IR 05000445/1992054
| ML20128B520 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/27/1993 |
| From: | Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20128B447 | List: |
| References | |
| 50-445-92-54, 50-446-92-54, NUDOCS 9302030086 | |
| Download: ML20128B520 (21) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Inspection Report:
50-445/92-54 50-446/92-54 Operating License:
NPf-87 Construction Permit:
CPPR-127 Licensee: 1U Electric Skyway Tower 400 North Olive Street, L.D. 81 Dallas, Texas 75201 facility Name:
Comanche Peak Steam Electric Station, Units 1 and 2 Inspection At: Glen Rose, Texas inspection Conducted: December 14-23, 1992 Inspectors:
J. B. Nicholas, Ph.D., Senior Radiation Specialist facilities inspection Programs Section L. W11 born, Radiation Specialist facilities Inspection ProgramsSection I $ @y [li.l _es in_sp_ecilon 07f[)
R Approved:
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ato rray, Programs Section in_spection Summary.
Areas inspected:
Routine, announced inspection of the Units 1 and 2 programs for liquid and gaseous radioactive waste management, the radiological environmental monitoring program, solid radioactive waste systems, and plant systems affecting water chemistry.
Results (Unit 1):
The radioactive waste effluent management program was well implemented
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(Section 1.2).
Good procedures has been established for the radioactive waste
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management program (Section 1.2).
9302030006 930129 PDR ADOCK 03000445 O
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-2-Semiannual radiological effluent release reports were timely and thnir
format followed regulatory guidance (Section 1.2).
Comprehensive audit and surveillance programs had been established and
implemented to review and evaluate the radiological environmental monitoring program activities (Section 2.2).
The 1991 Annual Radiological Environmental Operating Report was well
prepared and timely submitted (Section 3.2).
Results (Unit 211 The site's radiological environmental monitoring program was being
conducted in compliance with Technical Specification and Construction Permit CPPR-127 requirements (Section 4.2).
The radiological environmental monitoring program was being documented
in accordance with the Offsite Dose Calculation Manual and approved procedures (Section 4.2).
Responsibilities and authorities for the implementation of the
radiological environmental monitoring prngram were assigned to specific organizations (Section 4.2).
The liquid radioactive waste processing system construction was
completed.
Preoperational testing of the liouid waste processing system was completed (Section 5.5).
Construction of the primary and secondary water sampling systems was
completed, and the sample panels and sample lines were flushed, tested, and verified during hot functional testing (Section 5.5).
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Liquid process instrumentation had been installed, tested, and function
checked (Section 5.5).
Sampling procedures to operate the various water system sampling panels
were written and approved (Section 5.5).
The post accident sampling system reactor coolant and containment air
sample modules were tested operational during hot functional testing (Section 5.5).
Procedures concerning the operation of the liquid, gaseous, and solid
radwaste systems had been written and approved (Section 5.5).
Most of the liquid process and effluent radiation monitors for the
liquid radioactive waste system were common to both Units 1 and 2.
The Unit 2 turbine building sump monitor and the Unit 2 station service water system monitors were installed, and preoper-tional testing and calibration had been completed (Section 5.5).
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-3-The gaseous and solid radioactive waste effluent processing systems were
common to both Units 1 and 2 and were installed and operational. No preoperational tests were planned for the common components during the Unit 2 startup (Section 6.6).
All gaseous radioactive waste effluent monitors were common to both
Units 1 and 2, and they were calibrated and operational (Section 6.6).
the solid radioactive waste processing systems were common to both
Units 1 and 2. 'No preoperational tests were planned fer the common components during Unit 2 startup (Section 7.2).
Radwaste systems procedures were written and approved and included
instructions for processing Unit 2 spent resins (Section 7.2).
Goed water chemistry and radiochemistry programs had been established
(Section 8.3).
Chemistry staff had been supplemented with qualified contract personnel
to support Unit 2 startup and operation (Section 8.3).
Vater chemistry control procedures had been written and ap3 roved.
The j
'Jnit 2 preoperational water chemistry control program was aeing properly implemented (Section 8.3).
l Construction of the Unit 2 plant systems affecting water chemistry was
completed.
Preoperational testing had been completed on the various systems (Section 9.9).
Summary of Inspection Findings:
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Three Mile Island Action Plan Item II.F.1.2.8 was closed (Section 10.1).
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I Attachment:
l Attachment - Persons Contacted and Exit Meeting l
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-4-DETAILS 1 UNIT 1 RADI0 ACTIVE WASTE SYSTEMS (84750)
The Unit I liquid and gaseous radioactive waste management programs were reviewed to determine agreement with commitments in Chapters 1 and 11 of the Updated Safety Analysis Report and the recommendations of Regulatory Guide 1.21, and compliance with Technical Specifications 3/4.11.1,3/4.11.2, 6.8, and 6.9.1.4.
1.1 Discussion
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1.1.1 Changes Licensee representatives stated that there was one major change in the equipment and facilities dealing with the liquid and gaseous radioactive waste systems since the previous NRC inspection of this area conducted in May 1992.
Construction was completed on two 30,000 gallon liquid waste holdup tanks
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located outside, next to the f"el building.
The Design Modification 89-168 was closed on November 7, 1992.
A Licensing Document Change Request was prepared to include the two new plant effluent tanks, X-01 and X-02, in the next amendment to the Updated Safety Analysis Report.
1.1.2 Effluents The radioactive waste management program consisted of a consolidated effort by radwaste operations, radiation protection, and chemistry departments.
These groups functioned well together.
The inspectors reviewed selected components of the liquid and gaseous waste systems and confirmed that the components and systems were as described in the Updated Safety Analysis Report.
Selected radiation protection, radwaste, and chemistry procedures were reviewed, and it was determined that the procedures provided good guidance to individuals implementing the liquid and gaseous radioactive waste tffluent programs.
The inspectors reviewed the radioactive waste liquid and gaseous release permit program and determined that proper sampling and analyses were performed prior to each effluent release, that the effluent release permits were properly reviewed by the appropriate licensee personnel, that the proper radiation monitor setpoints were selected and verified, and that Technical Specification radioactivity limits, and offsite dose limits were not exceeded.
The inspectors reviewed the Semiannual Radioactive Effluent Release Report filed since the previous NRC inspection of this area and noted that there had been two abnormal gaseous releases during the period of January 1 through June 30, 1992.
Station problem reports were filed on these two releases.
Corrective actions were iroplemented, and no Technical Specifications were exceede _
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-5-The 1991 Semiannual Radioactive Effiuent Release Reports documented that the licensee released 460 curies of tritium in the form of liquid effluent.
The original Table llA-1 of the Updated Safety Analysis Report listed the expected annual liquid tritium release at 80 curies for the two unit operation.
The licensee created a Radioactive Waste and Water Treatment Systems Task force in the latter part of 1991 to evaluate this situation.
The inspectors interviewed representatives of the task force regarding their findings and conclusions.
Task force representatives stated that the original tritium values for liquid waste effluents stated in the original final Safety Analysis Report were unreasonably low.
They referenced liquid effluent tritium release values at two other similar pressurized water reactors in Region IV which they had contacted for information to support this conclusion.
The task force submitted its findings and proposed amendments to Chapters 9, 10, 11, and 15 of the Updated Safety Analysis Report to the station operations review committee for its approval.
Amendment 85 to the Updated Safety Analysis Report, which incorporated the task force's findings and recommendations, was issued on May 29, 1992, and reflected the current plant design and operating practices.
The inspectors reviewed the task force's findings and recommendations based on the plant's design and current operation of the radioactive wastn and water treatment systems and the task force's effluent release and dose calculations and determined that the methodologies and results were satisfactory.
lable llA-1 of the Updated Safety Analysis Report was updated (Amendment 85) and currently states an expected annual liquid tritium release of 2,500 curies for the two unit operation.
Based on the liquid ef fluent isotopic release values reported in the 1992 Semiannual Radioactive Effluent Release Reports, the current plant radioactive waste effluent operation meets the expected annual isotopic release quantities.
1.1.3 Instrumentation The inspectors met with Instruments and Controls personnel who were responsible for the calibration of the radioactive waste effluent radiation monitors.
The inspectors reviewed calibration records for selected monitors and determined that the monitors had been properly calibrated.
The inspectors also observed selected monitors in operation in the plant and did not identify any deviations from the Updated Safety Analysis Report or circumstances 3hich
would prevent the monitors from functioning as designed.
1.2 Conclusions The radioactive effluent management program was well implemented to ensure compliance with the Offsite Dose Calculation Manual requirements and Technical Specification limits.
Good procedures had been established for the radioactive waste effluent management program.
Semiannual Radioactive Effluent Release Reports were timely and their format followed regulatory guidance.
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-6-2 UNIT 1 RADIOLOGICAL ENVIRONMENTAL M'NITORING PROGRAM QUALITY ASSURANCE PROGRAM (84750)
The inspectors reviewed the quality assurance audit and surveillance programs of the radiological environmenta? monitoring program to determine agreement with the commitments in Chapters 13.4 and 17.2 of the Updated Safety Analysis Report and compliance with the requirements in Technical Specification 6.5.2.8.
2.1 Discussion The inspectors reviewed the licensee's 1992 quality assurance audit report of the station's radiological effluent and environmental monitoring programs (QAA-92-122).
The quality assurance audit program included an audit notification memorandum, audit plan, audit checklist, and audit report including a list of audit findings.
The audit was performed by qualified personnel who were knowledgeable in radiological effluent and environmental monitoring program activities. The 1992 quality assurance audit was conducted in agreement with Updated Safety Analysis Report commitments and met Technical Specification requirements.
The inspectors noted that the Independent Safety Engineering Group had been assigned the responsibilities for the administration and implementation of the licensee's operating surveillance program. The ins)ectors reviewed the Field Note Sheet ISEG-FN-92-98 dated March 31, 1992, whic1 documented the Independent Safety Engineering Group's surveillance of the radiological environmental sam)1ing operation.
The inspectors determined that the surveillance of tie radiological environmental sampling operation had been conducted in sufficient depth to satisfy the Updated Safety Analysis Report commitments and meet the lechnical Specification requirements.
2.2 Conclusion Comprehensive audit and surveillance programs had been established and implemented to review and evaluate the radiological environmental monitoring program activities.
3 UNIT 1 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORTS (84750)
The inspectors reviewed the 1991 Annual Radiological Environmental Operating Report to determine compliance with requirements in Technical Specification 6.9.1.3.
3.1 Discussion The 1991 Annual Radiological Environmental Operating Report included the required information consistent with the objectives outlined in the Offsite Dose Calculatien Manual and met the Technical Specification requirements.
The 1991 Annual Radiological Environmental Operating Report analytical results, when compared to the preoperational environmental analytical results, indicated that the plant's operation during 1991 caused no increase in meastrable levels of radiation or radioactive materials in the environment,
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-7-except for the measurable tritium concentration in the surface water samples collected from the Squaw Creek Reservoir sample locations, which resulted in detectabir levels far below the required reporting levels for radioactivity isotopic concentcations in environmental samples. The radiological environmental sample analytical reported results, except for the tritium results from the Squaw treek Reservoir samples, were either below the analytical measurement detection limits or were indicative of natural terrestrial and cosmic ray radiation levels.
None of the radiological analytical results exceeded any notification levels.
3.2 Conclusion The 1991 Annual Radiological Environmental Operathg Report was well prepared and timely submitted.
4 Unit 2 RADIOLOGICAL ENVIRONMENTAt. MONITORING PROGRAM (80210)
The inspectors reviewed the Unit 2 radiological environmental monitoring program to determine compliance with requirements in the Offsite Dose Calculation Manual and Technical Specification 6.8.3.f.
4.1 Discussion The Comanche Peak Steam Electric Station is a multi-unit site.
The radiological environmental monitoring program requirements are common to both units, and the radiological environmental monitoring program is considered a site function encompassing both units. Unit I received a low-power operating license on february 8,1990, and achieved initial criticality on April 3, 1990.
A full-power license for Unit I was issued on April 17, 1990, and commercial operation was declared on August 13, 1990. Unit 2 was issued Construction Permit CPPR-127 on December 19, 1974, and Unit 2 construction is currently near completion.
By a letter dated February 3,1992, as supplemented on March 16, 1992, the Texas Utilities Electric Company filed a request for an extension of the construction completion date specified in Construction Permit CPPR-127, The inspectors reviewed an Order (TAC No. M71899) issued by the NRC on July 28, 1992, which extended the construction completion date specified in Construction Permit CPPR-127 to August 1, 1995.
To differentiate between background radiation levels and any increases in radiation levels resulting from the operation of the plant, radiological surveys of the plant's environs were divided into preoperational and operational phases.
Preoperational phase radiological environmental measurements were conducted from 1981 to 1989, and the operational phase has been conducted since.
The operational phase environmental data, when compared to the preoperational phase data, assists in performing an evaluation of the radiological impact the plant's operation has on the surrounding environment.
The most recent NRC inspection of the site's radiological environmental monitoring program was conducted during the period November 18-22, 1991, and was documented in NRC Inspection Report 50-445/91-66; 50-446/91-66. The inspectors did not identify any problems of regulatory significance that had the potential to cause or contribute to an occurrence which could be related
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-8-to an adverse environmental impact during the time period between Nevember 1991 and December 1992.
4.2 Conclusions The site's radiological environmental monitoring program was being conducted in compliance with icchnical Specification and Construction Permit CPPR-127 requirements.
The radiological environmental monitoring program was being documented in accordance with the Offsite Dose Calculation Manual and approved procedures.
Responsibilities and authorities for the implementation of the radiological environmental monitoring program were assigned to specif;c organizations.
5 UNIT 2 LIQUIDS AND LIQUID WASTES (84523)
Tne inspectors reviewed the Unit 2 liquid radioactive waste effluent program to determine whether the components and the installation of the liquid waste processing system were as described in Chapter 11 of the Updated Safety Analysis Report; whether preoperational tests had been com)leted on the liquid radioactive waste systems to verify operability; whether t1e radioactive waste effluent and process monitoring program ras adequate and conformed to the Updated Safety Analysis Report description; and whether preoperational,
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startup, and operational procedures had been written and approved.
5.1 Liauid Waste System Construction and Installation
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The liquid radioactive waste effluent system was mostly common to both Units 1 and 2 and installed in the plant's common auxiliary building.
Floor drain tank No. 2 was installed in the Unit 2 safegaardt building with adequate shielding.
All drain systems from the Unit 2 safeguards building and Unit 2 containment were connected to floor drain tank No. 2..The Unit 2 interconnecting pipe " spool" was installed connecting floor drain tank No. 2 to the common liquid waste processing system which made the entire liquid radioactive waste ef fluent system operational. - Preoperational
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Test 2CP-PT-41-01, " Liquid Waste Processing Channel
'B'," Revision 0, was completed on November 20, 1992, and all components associated with the performance of the test met-the design requirements.
The preoperational testing included the verification of the floor drain tank No. 2 volume and the determination of the floor drain tank No. 2 recirculation time to provide a representative sample of the floor drain tank contents.
There were no outstanding items associated with the completion of the test.
At the time of the inspection, the test results were being reviewed and comments resolved, and the final test results had not been approved by the Joint Test Group. The Unit 2 reactor coolant drain tank was installed and system flushing was completed. Preoperational Test 2CP-PT-41-02, " Reactor Coolant Drain Tank,"
Revision F, was completed on August 20, 1992, and all components associated with the performance of the test met the design requiroments.
There were no outstanding items associated with the completion of the test. -The final test results were approved by the Joint Test-Group on October 28, 1992.
Preoperational Test 2CP-PT-23-01, " Radioactive Vents and Drains," Revit. ion 0, P
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-g-was completed on December 20, 1992, and all components associated with the performance of the test-met the design requirements, the preoperational test demonstrated the capability of the radioactive portior, of the Unit 2 vents and drains system to collect and separate potential radioactive liquid wastes and also demonstrated the capability of the Unit 2 containment vents and drains to detect unidentified leakage and high atmospheric moisture content.
There were no outstanding items associated with the completion of the test. 'At the time of the inspection, the test results were being reviewed and comments resolved, and the final test results had not been approved by the Joint Test Group.
5.2 Liauid Samplina The inspectors inspected the Unit 2 primary sampling area. The primary
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sampling system brings sampics from the reactor coolant system-and auxiliary water systems to a common location on the Unit 2 grab sample hood assembly, CP2-PSMEPS-01, located in the Unit 2 safeguards building. Grab sample provisions had been provided for both pressurizect and nonpressurized samples of the various primary water systems.
The Unit 2 grab sample hood assembly-and associated process instrumentation were installed, and construction was completed. All sample lines were flushed and verified during hot functional testing, and the process instrumentation had been installed, tested, and function checked.
The inspectors inspected the Unit 2 Steam Generator Blowdown Sample Panel CP2-PSMEPS-03.
The Unit 2 steam generator blowdown sample panel construction was complete.
All sample lines were flushed and verified during hot functional testing. All major equipment and process instrumentation were installed, and the conductivity instruments and sodium analyzers had been tested and function checked and left in wet standby condition.
The inspectors inspected the various Unit 2 secondary chemistry sampling areas.
The rampling areas included the secondary water support systems, condenser, and condensate polishing system. Grab sample provisions had been provided for all sample types on each of the sampling' panels so as to perform water quality laboratory analyses for the control of the secondary water.
chemistry. The various Unit 2 secondary water' sampling panels and associated process instrumentation were installed and construction,was completed. L All sample lines were flushed and verified.
The process instrumentation including silica, sodium, hydrazine, dissolved oxygen, conductivity, and Ph analyzers had been installed at the various Unit 2 secondary water sampling panels and had been tested and function checked and left in wet standby condition.
The licensee had developed sampling procedures to operate the sampling panels-for the various water systems, and the procedures were common for Units 1 and 2 operation. The licensee's approved procedures were reviewed during previous NRC inspections and provided the necessary information required for obtaining a representative sample from the various sample points.
Preoperational Test 2CP-PT-59-02, " Process Sampling System,"_ Revision 0, was completed on October 10, 1992, and all components associated with the performance of the test met the design requi-ements.
The preoperational test demonstrated that the process sampling systems provided samples for analysis
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within the design requirements for flow rates, temperature, and pressure.
The sample line delay times for the reactor coolant hot legs were within acceptable design limits. There were no outstanding items associated with this test. The final test results were approved by the Joint Test Group on November 10, 1992.
The inspectors reviewed the status of the Unit 2 post accident sampling system.
The post accident sampling system remote operating modules for the reactor coolant sample (CP2-PSMEPS-8A, CP2-PSMEPS-88, and CP2-PSMEPS-8C) were installed and had been tested during hot functional testing.
The post accident sampling system containment air sample module, CP2-PSMEPS-06; the post accident sampling system reactor coolant sample module, CP2-PSMEPS-04; and the post accident sampling system reactor coolant system flush module were installed.
The post accident sampling system components were operational and had been tested during hot functional testing.
The Preoperational Test 2CP-PT-59-01, " Post Accident Sampling System," Revision 0, was performed during the time period July 3 through November 16, 1992. On November 16, 1992, the preoperational test was declared complete except for the performance of Section 7.10 (Containment Air Gas Sampling Demonstration) and all other steps applicable to the performance of Section 7.10.
Section 7.10 testing was waiting final disposition of Design Change Authorization 103769 on the post accident sampling system panel heat tracing of the containment air gas sample line.
The inspectors reviewed the analytical results of the two reactor coolant samples collected during hot functional testing using the post accident sampling system and the comparison of these results to the analytical results of samples collected from the normal reactor coolant system sample point.
The analytical results comparison showed excellent agreement for the lithium and boron analyses performed. Therefore, the post accident sampling system operability for collecting a reactor coolant sample was demonstrated satisfactorily. Due to the delay in installing the heat tracing on the containment air gas sample line, no sample collection testing had been performed on the containment air post accident sampling system. The verification of the containment air post accident sampling system operability was scheduled to be completed prior to fuel lead. At the time of the inspection, the test results were being reviewed and comments resolved.
The final test results had not been approved by the Joint Test Group.
5.3 Liouid Process and Effluent Monitors The inspectors determined that most of the liquid process and effluent radiation monitors for the liquid radioactive waste system were common to both Units 1 and 2 and that they were installed, tested, calibrated, and operational in the common auxiliary building. The liquid process and effluent radiation monitors solely in Unit 2 included the turbine building sump monitor, 2RE-5100, and the station service water system monitors, 2RE-4269 and 2RE-4270. The inspectors verified that these radiation monitors were installed and had been turned over to Unit 2 startup for preoperational testing and calibration.
Preoperational Test 2CP-PT-70-01, " Radiation Monitoring System," was deleted and replaced with individual procedures for testing the individual radiation monitors.
Preoperational Test XCP-EE-30,
" Functional Test and Channel Calibration of Station Service Water System Effluent Liquid Process Radiation Monitors," Revision 2, was completed on
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The final test results had not been approved by the _ Joint Test Group.
The primary calibrations of 2RE-4269 (Service Water Train A) and 2RE-4270 (Service Water Train B) radiation monitors were performed on October 10, 1992, in conjunction with the performance of the preoperational test. The primary calibrations were performed in accordance with Procedure INC-2099.
The inspectors reviewed the primary calibration results and preoperational test results of the two service water radiation monitors dnd found them to be satisfactory and documented in'accordance with approved procedures. The Unit 2 service water system radiation monitors were tied into the Unit 2 control room computer.
Preoperational Test XCP-EE-35, " Functional Test and Channel Calibration of the Turbine Building Floor Drains Liquid Process Radiation Monitor," Revision 0, was completed on December 21, 1992.
At the time of the inspection, the test results were in the process of initial review and comment, and the comments were being resolved. -The final test results had not been approved by the Joint Test Group.
The primary calibration of 2RE-5100 (Turbine Building Floor Drain) radiation monitor was performed on November 20, 1991.
The primary calibration was performed in accordance with Procedure INC-2099.
The inspectors reviewed the primary calibration results and preoperational test results of the turbine building-floor drain radiation monitor and found them to be satisfactory and documented in accordance with approved procedures.
5.4 Programs. Plans, and Procedures for the Liauid Waste ~ and Effluent Systems The liquid radioactive waste effluent system was mostly common to both Units 1 and 2 and had an established program and approved implementing procedures which were reviewed during previous NRC inspections of Unit 1 operation. The inspectors noted that Radwaste Systems Procedure RWS-103, " Drain Channel B,"
Revision 6, included instructions for the recirculation of floor drain tank No. 2, and the transferring of its contents to floor drain tank-No. 3 in the common auxiliary building in order to incorporate floor drain tank No. 2 into the normal operation of the radioactive liquid waste effluent system.
Radwaste Systems Procedure RWS-108, " Vents and Drains," Revision 0, was written and approved to provide comprehensive instructions for effluent discharges from all of the Units 1 and 2 discharge points including the turbine building sumps in each unit, t
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5.5 Conclusions The Unit 2 liquid radioactive waste processing system construction was completed, and the various components were installed as described in the L
Updated Safety Analysis Report.
Preoperational testing was completed on the i
Unit 2 liquid waste processing system and associated equipment.
l The primary and secondary water sampling systems were installed, and all sample lines were flushed and verified. The process instrumentation had been
L installed, tested, and function checked.
Sampling procedures to operate the various water system sampling panels were written and approved for both
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Preoperational tests were performed during hot functional testing to test the Unit 2 water sampling systems.
The post accident sampling system reactor coolant and containment air sample modules were installed and tested. A preoperational test was performed during _
hot functional testing.
Most of the liquid process and effluent radiation monitors for the liquid radioactive waste system were common to both Units 1 and 2.
The Unit 2 turbine building floor drain monitor and the Unit 2 station service water system monitors were installed, tested, and calibrated.
Preoperational tests were performed to test the Unit 2 radiation monitoring system.
A radwaste systems procedure was written and approved, which included instructions for the processing of liquid radioactive waste generated from the operation of both Units 1 and 2.
6 UNIT 2 GASEOUS WASTE SYSTEM (84524)
The inspectors reviewed the Unit 2 gaseous radioactive waste effluent program to determine whether the gaseous waste system was installed as described in Chapter 11 of the Updated Safety Analysis Report; whether preoperational tests had been performed on the gaseous waste systems to verify operability; whether the gaseous radioactive waste effluent and process monitoring program was adequate and conformed to the Updated Safety Analysis Report description; and whether preoperational, startup, and operational procedures had been written and approved.
6.1 Gaseous Waste System Construction and Installation The gaseous radioactive waste effluent processing system including the waste gas compressors, waste gas decay tanks, and hydrogen recombiners was
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completely common to both Units 1 P.nd 2 and was installed and operational in the common auxiliary building except for the piping required to connect the gas spaces from the Unit 2 volume control tank, reactor coolant drain tank, and the primary process sampling system to the common suction header of the waste gas compressors.
The gas spaces and piping in Unit 2 required to connect the Unit 2 volume control tank, reactor coolant drain tank, and the primary process sampling system to the common suction header were tested during the performance of Preoperational Test 2CP-PT-23-01, " Radioactive Vents and Drains," Revision 0, which was completed on December 20, 1992.
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l gaseous waste system piping cross-ties-between Unit 1 and Unit 2 were completed with the removal of the blind flanges and the installation of the
flanged " spool pieces" in the appropriate piping, and the unit separation L
" locked closed" valve tags removed, i
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The gaseous radioactive waste effluent sampling system for normal operation was comoon to both Units 1 and 2 and was installed and operational in the common auxDiary building.
This sampling system was inspected during previous NRC inspectiocs of Unit 1 operation and was found to be satisfactory.
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-13-Sampling procedures were written, approved, and implemented to obtain representative samples from the gaseous radioactive waste effluent processing system during normal operation.
6.3 Test Program for the Gaseous Waste System All the major components of the gaseous radioactive waste effluent processing system were installed and operational in the common auxiliary building.
These components were inspected during previous NRC inspections of Unit 1 operation.
No preoperational tests were planned or performed on these common components during the startup of Unit 2.
Piping in the Unit 2 safeguards building required to connect the gas spaces of the various Unit 2 systems to the common suction header of the waste gas compressors was tested in conjunction with the specific individual system tests prior to system connection to the common waste gas header in the auxiliary building. Most of this piping-preoperational testing was included in the performance of the Preoperational-Test 2CP-PT-23-01, " Radioactive Vents and Drains."
6.4 Process and Effluent Monitors All gaseous radioactive waste effluent monitors were common to both Units'1 and 2 and were installed, tested, calibrat 1, and operational in the common auxiliary building.
These monitors were spected during previous NRC inspections of Unit 1 operation.
6.5 Programs Plans, and Procedures for the Gaseous Waste and Effluent Systems The gaseous radioactive waste effluent system was common to both Units 1 and 2 and had an established program and approved implementing procedures which were reviewed during previous NRC in pections of Unit 1 operation. The inspectors noted that Radwaste Systems Procedure RWS-201, " Gaseous Waste Processing System," Revision 5, included instructions for processing gaseous radioactive waste generated from both Units 1 and 2.
6.6 Conclusions The gaseous radioactive waste effluent processing system was. common to both Units 1 and 2 and was installed and operational.
Sampling procedures were written and approved to obtain representative samples during normal operation.
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processing system were common, installed, and operational,- no preoperational tests were planned or performed on the common components during the Unit 2 startup. Unit 2 safeguards building piping. required to connect the gas spaces
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of the various Unit 2 systems to.the common suction header of the waste gas compressors was tested.
All gaseous radioactive waste effluent monitors were common to both Units 1 and 2, and they were calibrated and operational.
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_]4 A radwaste-systems procedure was written and approved, and it included instructions for the processing of gaseous radioactive waste generated from the operation of both Units I and 2.
7 UNIT 2 SOLID WASTES (84522)
The inspectors reviewed the Unit 2 solid radioactive waste management program to determine hether the solid waste systems were installed as described in Chapter 11 of the Updated Safety Analysis Report.
7.1 Discussion The solid radioactive waste management systems were common to both Units 1 and 2, and all major components were installed and operational in the common
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auxiliary building. These systems were inspected during previous NRC operational inspections of Unit I and were found to be satisfactory.
It was determined that there were no radioactive pathways from Unit 2 to the common solid radioactive waste management systems.
Radwaste Systems Procedures RWS-302, " Nuclear Steam Support System Spent Resin Handling System," Revision 4, and RWS-304, " Steam Generator Blowdown Spent Resin Handling System," Revision 1, included instructions for processing Unit 2 spent resins.
7.2 Conclusions i
The solid radioactive waste processing systems were common to both Units 1 and 2.
No preoperational tests were planned for the common components during Unit 2 startup.
Radwaste systems procedures were written and approved and included
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8 UNIT 2 REACTOR WATER CHEMISTRY C9NTROL AND CHEMICAL ANALYSIS (79501)
The inspectors reviewed the Unit 2 water chemistry control program to determine the licensee's capability to control and make chemical measurements necessary to maintain the chemical quality of Unit 2's process water. The water chemistry control program was common to both Units 1 and 2.
This program was inspected during previous Unit 1 NRC operational inspections and found to be satisfactory.
8.1 Establishment of a Water Chemistry Control Program The inspectors had previously reviewed the Unit 1 operational water chemistry control program and had determined that the licensee had established an effective and well documented program for controlling the quality of primary coolant water and secnndary water. The water chemistry control program included written and approved management policies and procedures to implement the p'olicies. These management policies and procedures assigned the authority and responsibilities to implement and maintain the Units 1 and 2 water-chemistry control program to the chemistry department. To support Unit 2 startup and operation, the licensee had increased the chemistry staff by
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-15-hiring two contract staff chemists, 12 contract chemistry technicians, and two contract clerical staff.
The increased chemistry department staffing appeared adequate to support Unit 2 startup and operations.
8.2 Implementation of the Water Chemistry Control Program The inspectors' review of the plant's water chemistry control program indicated that the licensee had approved administrative procedures, surveillance procedures, chemistry control procedures,- instrument calibration -
and quality control procedures, and analytical procedures. A review of selected procedures indicated that the licensee had sufficient programmatic procedures to meet Updated Safety Analysis Report commitments and Technical Specification requirements.
The Unit 2 preoperational and startu) water chemistry control program was being implemented in accordance wit 1 existing
procedures.
8.3 Conclusions The secondary water chemistry and radiochemistry programs were established and implemented in accordance with NRC requirements.
The chemistry staff was supplemented with qualified contract personnel to support Unit 2 startup and operation. Water chemistry control. procedures were written and approved for both Units 1 and 2.
The Unit 2 startup water' chemistry control program was being implemented according to procedures.
9 UNIT 2 PLANT SYSTEMS AFFECTING PLANT WATER CiiEMISTRY (79502)
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The inspectors reviewed the status of the construction, installation, preoperational testing, and startup of the Unit 2's primary, secondary, and auxiliary water systems.
The review included the condensate system, condensate polishing system, feedwater system, auxiliary feedwater system, service water system, chemical and vclume control system, boron thermal regeneration system, and reactor coolant system.
9.1 Condensate System The inspectors reviewed the status of the Unit 2 condensate system. The system had been cleaned and flushed, and the system was in operation to support flushing operations of other Unit 2 water systems.
Preoperational Acceptance Test 2CP-AT-19-01, " Condensate System," Revision 0, was completed on October 15, 1992. The test procedure demonstrated the operability of the two condensate pumps, the hotwell-level control valve, the gland steam condenser flow valve, and the low pressure heater bypass valve.
The Design
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Change Authorization 103427 dealing with the failure of the condensate pumps to deliver the designed -flow was evaluated and dispositioned by the startup engineers to use the condensate pumps as tested.
The test results for the associated components were found to be acceptable and met design requirements.
There were no outstanding items associated with the completion of the test.
The final test results were approved by the Joint Test Group on November 2, 199..
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-16-9.2 Condensate Polishino Syst_em The inspectors reviewed the status cf the Unit 2 condensate polishing system.
The condensate polishing system contained five water 70lishing vessels. The system was cleaned, flushed, loaded with filters, and' tested during hot
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functional testing.
Preoperational Acceptance Test.2CP-AT-25-01, " Condensate Polishing Performance," Revision 0, was completed on August '10,1992. The test demonstrated a semiautomatic backwash recovery and precoated one vessel with Ecodex. During the test, one vessel precoat was backwashed off to Backwash Recovery Tank A, an automatic spent resin transfer to the Unit 2 phase seaarator was performed, and the waste liquid from the phase separator was discharged to the Low Volume Waste Pond. Two test deficiencies were closed.
There were no components or functions associated with the performance of this test which did not meet the design requirements.
There were no outstanding items associated with the completion of the test. The final test results were approved by the Joint Test Group on September 4,-1992.
9.3 Feedwater System The inspectors reviewed the status of the Unit 2 feedwater system.
The feedwater system was cleaned, flushed, and tested. The two feedwater pumps had been rebuilt.
Preoperational Acceptance Test 2CP-AT-28-01, "Feedwater System Test," was completed on August 22, 1992.
The test demonstrated the operability of Steam Generator Feedwater Pumps 2A and 2B in a recirculation mode of operation. There were no components or functions associated with the performance of this test which did not meet the design requirements.
There were no outstanding items associated with the completion of the~ test.
The final test results were approved by the Joint Test Group on October 4,1992.
Preoperational Test 2CP-PT-28-02, "Feedwater Isolation Valve Testing,"
Revision 0, was completed on October 22, 1992.
The test demonstrated the proper operation of the feedwater system valves. All components associated with the performance of this test met design requirements.
The final test results were approved by the Joint Test Group on December 14, 1992.
9.4 Auxiliary Feedwater System The inspectors reviewed the status of the Unit 2 auxiliary feedwater system.
The auxiliary feedwater system, including the condensate storage tank, was cleaned, flushed, and tested.
Preoperational Test 2CP-PT-37-01, " Auxiliary Feedwater System," Revision 0, was completed on October 21, 1992. All components associated with the performance of the test met the design requirements. The final test results were approved by the Joint Test Group on December 15, 1992.
Preoperational Test 2CP-PT-37-02, " Condensate Storage and Transfer System,"
Revision 1, was completed on June 3, 1992. The test demonstrated that the condensate transfer system operated satisfactorily to perform its design functions, and all test acceptance criteria were satisfied based on test data and engineering evaluations. All components associated with the performance of this test met design requirements. The' final test results were approved by the Joint Test Group on December 10, 199.
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-17-Preoperational Test 2CP PT-37 03, " Auxiliary Feedwater Turbine Driven Pump,"
Revision 0, was completed on Jctober 24, 1992, anc' all components associated with the performance of the test met the design requirements.
At the time of the inspection, the test re:"Its were in the precess of review and comment, and the comments were being i asolved.
The final test results had not been approved by the Joint Test Grcip.
9.5 Servic.e_ Water System The inspectors reviewed the status of the Unit 2 service water system.
The service water system was cleaned, flushed, and tested.
Chemistry was being maintained, and routine sampling and analyses were being performed.
Preoperational Test 2CP-PT-04-01, " Station Service Water," Revision 0, was completed on November 4, 1992.
The test demonstrated the automatic start functions of the station service water pumps, controls and interlocks of the pump discharge valves, automatic functions of the station diesel generator service water return valves, station service system flow balancing, station service water pumps start and rated flow requirements, and the station service water system pump 48-hour operation requirement. There were no associated components of this test, that after engineering evaluation of the test data, did not meet the design requirements.
There were no outstanding items associated with the performance of this test. The final test results were l
approved by the Joint Test Group on December 1, 1992.
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9.6 Chemical and Volume Control System The inspectors reviewed the status of the Unit 2 chemical and volume control system. The chemical and volume control system was cleaned, flushed, and tested.
Resin was installed in the three demineralizers, and the system g
supported hot functional testing, Preoperational Test 2CP-PT-49-01, " Charging and Letdown," Revision 1, was completed on October 12, 1992.
The test
demonstrated that the charging, letdown, and seal injection capabilities of the chemical and volume control system functioned according to the design I
requirements.
All components associated with the performance of this test either met the design requirements or were deemed acceptable by engineering i
evaluations.
There were no outstanding items associated with the performance of this test. The final test results were approved by the Joint Test Grnup on November 19, 1992.
Preoperational Test 2CP-PT-49-02, " Seal Water and Letdown Flow Performance,"
Revision 0, was completed on September 21, 1992.
Steps in Section 7.7 associated with the testing of the TCX-CSDMMB-01 differential pressure indicator were unable to be performed due to excessive contamination levels in the demineralizer.
These test activities will be performed by the Operations Performance and Test Group after the Unit 2 radiation control area lockdown.
The final test results were approved by the Joint Test Group on December 1, 1992.
Preoperational Test 2CP-PT-49-03, " Chemical Control and Makeup," Revision 2, was completed on August 12, 1992.
The test demonstrated the operations of the controls and interlocks associated with the reactor makeup boration and dilution system. There were no components identified during the performance l
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The final test results were approved by the Joint Test Group on October 5, 1992.
9.7--Boron Thermal Regeneration S_vstem
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The inspectors reviewed the status of the Unit 2 boron thermal regeneration system.
The boron thermal regeneration system was cleaned, flushed, and tested.
The five demineralizers were loaded with resin. _ Preoperational Test 2CP-PT-49-04, " Boron Thermal Regeneration System," Revision 0, was completed on October 6, 1992.
The boron thermal regeneration system steady-state and thermal performance testing could not be completed due to the Unit 2 boron thermal regeneration system demineralizer being contaminated.
Section 7.8, " Boron Thermal Regeneration System Steady-State Operation," and Section 7.9, " Boron Thermal Regeneration Systems Thermal Performance," were not completed due to time restrictions caused by the end of hot functional testing and due to the contaminated Unit 2 boron thermal regeneration system domineralizer.
The logic testing, pump performance testing, and boron thermal regeneration system chiller recirculation, testing were successfully performed.
It was recommended that Sections 7.8 and 7.9 of Preoperational Test 2CP-PT-49-04 be performed by the Operations Performance and Test Group and tracked by the Joint Test Group. The completed test results were approved by the Joint Test Group on November 10, 1992.
Preoperational Test 2CP-PT-49-06, " Boron Addition and Control," Revision 0, was completed on October 19,1992. - All system deficiency reports were closed.
All testing which could be performed with the present system configuration was completed and met all design requirements.
Boron addition and control flow testing was deleted from the preoperational test due to_ radioactive contamination of the common boric acid tanks. The uncompleted flow testing.
will be performed by the Operations Performance and Test Group and tracked by the Joint Test _ Group.
The completed test results were approved by the Joint Test Group on November 12, 1992.
9.8 Reactor Coolant System The inspectors reviewed the status of the Unit 2_ reactor coolant ' system. The reactor coolant system was cleaned, flushed, and tested during hot functional.
testing.
Preoperational Test 2CP-PT-55-01, " Reactor Coolant System Cold Hydrostatic Test," Revision 0, was completed on March-18, 1992. The reactor coolant system was maintained at 3112 pounds per square inch gauge (3112-3200)
for a minimum of 10 consecutive minutes. There were no. components identified during the performance of this test which did not meet the design requirements.
The completed test results were approved by the Joint Test Group on August 6, 1992.
Preoperational Test 2CP-PT-55-02, " Hot Fur.ctional Test," Revision 1, was completed on October 20, 1992.
The reactor coolant system was operated at full flow conditions for a minimum of 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> and a temperature of 515 degrees Fahrenheit for at least 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> of this operation. The test results met all acceptance criteria of this test. The final test results were.
approved by the Joint Test Group on October 22, 199,
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-19-9.9 Conclusions Construction of the Unit 2 plant systems affecting water chemistry was completed, and the systems reviewed were turned over to the Unit 2 startup engineers for preoperational testing. All-of the systems reviewed were cleaned, flushed, and tested.
Preoperational tests were performed on.the various systems.
The preoperational test results were reviewed and approved by the Joint Test Group.
10 REVIEW OF TEMPORARY INSTRUCTION 2515/065, "THREE MILE ISLAND ACTION PLAN REQUIREMENT FOLLOWUP" (2515/065)
i This temporary instruction provided inspection guidance for the items identified in the Three Mile Island Action Plan that required inspection followup.
(Closed) Three Mile Island Action Plan Item II.F.1.2.B:
Iodine / Particulate Sampling This item involved the licensee's capability for the sampling of airborne radioactive iodines and particulates at the plant gaseous effluent vent curing post accident releases. Tne inspectors reviewed Section II.F.1 and Chapter 11.5.2.6.3 (Amendment 85) of the Updated Safety Analysis Report and determined that the Wide Range Noble Gas Monitors installed in the plant vent stacks provided the capability to sample, detect, and measure: concentrations of radioactive iodines and.particulates in the plant gaseous effluents during and following an accident.
Wide Range Noble Gas Monitor Description: The inspectors reviewed
Procedure DBD-EE-023, " Radiation Monitoring System," Revision 3, dated November 13, 1991, and noted in paragraph 5.2.2.3 the description of the two plant vent stack Wide Range Noble Gas Monitors X-RE-5570 A and B.
The Wide Range Noble Gas Monitor System is a gaseous effluent monitoring
system composed of two identical monitors used for the detection of noble gas releases through the two plant vent stacks.
Radioactive iodine and particulate grab samples may also be obtained.
Radioactive iodine / particulate sampling procedures and training:
The
inspectors reviewed Procedures EPP-117, " Administrative Controls For Sampling Under Post Accident Conditions," Revision 5, dated. March 30, 1990; CHM-lll, " Post Accident Sampling Program," Revision 3, dated June 10,1992; CHM-521, " Gaseous Effluent Sampling Under Post Accident Conditions," Revision 1, dated November.6, 1987; and CLI-900, " Sampling, Handling, Preparation,-and Analysis of Post Accident or Highly Radioactive Samples," Revision 4, dated April 29, 1992. The inspectors determined that these procedures adequately addressed the sampling requirements for taking highly radioactive iodine / particulate samples from the plant gaseous effluents, containment environment, and gaseous waste system during and following an accident. The procedures also provided instruction on preparing, handling, and analyzing the collected samples.
The inspectors also reviewed the chemistry technician
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-20-specialty training courses and objectivas, qualification card, and on-the-job _ training requirements for the collection and handling of post accident samples from the plant vent stacks.
The inspectors determined that the post accident sampling training program was established for collecting radioactive iodine and particulate samples from plant gaseous effluents, and the training program was being implemented in accordance with approved procedures.
Radioactive iodine / particulate sampler operability:
The inspectors
venified that Procedures CHH-lll, " Post Accident Sampling Program," and CHM-521, " Gaseous Effluent Sampling Under Post Accident Conditions,"
included operational testing of the Wide Range Noble Gas Monitors to verify their capability to obtain radioactiva iodine / particulate samples of plant gaseous effluents.
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ATTACHMENT 1 PERSONS CONTACTED 1.1 Licensee Personnel
- D. M. Bozeman, Chemistry Manager
- R. W. Brady, Assistant Project Manager, Unit 2 C. M. Carella, Chemistry Supervisor K. E. Cooper, Staff Chemist, Unit 2
- J. M. Edwards, Radwaste Operations Supervisor T. L. Edwards, Radwaste Supervisor D. H. Evans, Staff Chemist, Unit 2 E. T. Floyd, Staff Health Physicist E. G. Good, Senior Engineer
- J. H. Greene, Licensing Engineer, Unit 2
- W. G. Guldemond, Independent Safety Engineering Group Manager S. W. Harrison, Project Eng;neer, Unit 2 C. Henton, Balance of Plant Startup Lead, Unit 2 T. A. Hope, Licensing Manager, Unit 2 C. D. Inbody, Senior Chemistry Technician D. A. Ischar Instruments and Controls Startup Test Engineer, Unit 2 D. C. Kay, Technical Support Supervisor G. K. Kirby, Instruments and Controls Supervisor D. C. Kross, Operations Manager, Unit 2 D. D. Mantz, Senior Radwaste Operator
- G. L. Merka, Licensing Engineer, Unit 2 M. A. Rubano, Nuclear Steam Supply Systems Startup Supervisor, Unit 2 R. E. Parsons, Instruments and Controls Startup Supervisor, Unit 2 C. W. Rau, Project Manager, Unit 2
- R. J. Prince, Radiation Protection Manager
- D. L. Ranstrom, Quality Assurance Supervisor, Unit 2 G. H. Ruszala, Radwaste Contractor
- J. E. Snyder, Startup Manager, Unit 2
- R. L. Theimer, Chemistry Supervisor, Unit 2
- R. D. Walker, Manager of Nuclear Regulatory Affairs
- C. H. Welch, Senior Quality Assurance Specialist L. A. Wojcik, Nuclear and Mechanical Analysis Supervisor 1.2 NRC Personnel W. B. Jones, Senior Resident Inspector, Unit 1 D. N. Graves, Senior Resident Inspector, Unit 2
- R. M. Latta, Resident Inspector, Unit 2
- Indicates those present at the exit meeting on December 23, 1992.
2 EXIT MEETING An exit meeting was conducted on December 23, 1992.
During this meeting, the lead inspector reviewed the scope and findings of the report.
The licensee did not identify as proprietary any information provided to, or review'ed by, the inspectors.
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