IR 05000445/1993024
| ML20045H273 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/09/1993 |
| From: | Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20045H268 | List: |
| References | |
| 50-445-93-24, 50-446-93-24, NUDOCS 9307200036 | |
| Download: ML20045H273 (16) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMM': TION
REGION IV
inspection Report:
50-445/93-24 50-446/93-24 Operating Licenses: NPF-87 NPF-89 Licensee: TV Electric Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Facility Name:
Comanche Peak Steam Electric Station, Units 1 and 2 Inspection At:
Glen Rose, Texas Inspection Conducted:
June 14-18, 1993 Inspector:
J. B. Nicholas, Ph.D., Senior Radiation Specialist Facilities inspection Programs Section f
n Approved:
[ fii (/ M76 7 Wk Blaine Murray,' Chief,,f 'cilities Inspection Datd Programs Section Inspection Summary
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Areas Inspected (Units 1 and 2):
Routine, announced inspection of the startup of the Unit 2 liquid and gaseous radioactive effluent waste program.
Results:
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The Unit 2 startup test of the reactor coolant system and secondary
coolant system was completed through 75 percent power, and the test a
results were evaluated and approved as required (Section 1.1).
The Unit 2 startup radiochemistry and water chemistry control programs
were being properly implemented (Section 1.1).
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Good radiochemistry and secondary water chemistry programs were e
established and implemented. Water chemistry control procedures were l
written and approved (Section 1.1).
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9307200036 930713 PDR ADOCK 05000445 l
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-2-The Unit 2 primary coolant. and secondary water quality was maintained
and met Technical Specification requirements (Section 2.1).
The Unit 2 radioactive waste effluent management program was implemented
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in accordance with Technical Specification and Offsite Dose Calculation Manual requirements (Section 2.1).
An excellent program was established and implemented to frequently
compare the installed effluent radiation monitor readings to the analyzed gross gamma radioactivity concentration in liquid-and gaseous radioactive waste effluent releases (Section 3.1).
Excellent radioactive gaseous and liquid radioactive waste effluent
management programs were implemented to ensure compliance with the Offsite Dose Calculation Manual requirements and Technical Specification limits (Section 4.1).
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Excellent procedures had been established and implemented for conducting
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the radioactive waste effluent management programs (Section 4.1).
An excellent program was established and implemented to routinely check l
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normally nonradioactive process and effluent streams for unanticipated l
radioactivity (Section 5.1).
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Comprehensive audit and surveillance programs were established and
implemented to review and evaluate the radioactive waste effluent
program activities (Section 6.1).
The Unit 2 liquid radioactive waste processing system construction was
completed.
Preoperational testing was completed on the Unit 2 liquid
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waste processing system and associated equipment.(Section 7.1).
Unit 2 primary and secondary water sampling systems were installed,
tested, and operational.
The process instrumentation was installed, tested, calibrated, and operational.
Sampling procedures to operate the various water system sampling panels were written and -approved for both Units 1 and 2 (Section 7.1).
The Unit 2 turbine building floor drain monitor and the Unit 2 station.
- service water system monitors were installed, tested, calibrated, and operational (Section 7.1).
Radwaste systems procedures were written and approved which included
instructions for the processing of liquid radioactive waste generated from the operation of both Units 1 and 2 (Section 7.1).
The gaseous radioactive waste effluent processing system was common to
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both Units 1 and 2 and was installed and operational.
Sampling procedures were written and approved to obtain representative samples during normal operation (Section 8.1).
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Construction and preoperational testing of the Unit 2 plant systems
affecting water chemistry were completed. All Unit 2 plant systems affecting water chemistry were operational (Section 9).
Semiannual Radioactive Effluent Release Reports included the required
information, were timely submitted, and their format followed regulatory
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guidance (Section 10.1).
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Attachment:
Attachment - Persons Contacted and Exit Meeting
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DETAILS
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1 CHEMICAL AND RADI0 CHEMICAL TESTS (84521)
Performance and evaluations of the startup radiochemical and chemical tests for Unit 2 were reviewed to determine agreement with commitments in the Updated Safety Analysis Report.
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Discussion The inspector reviewed the radiochemical and chemical results of the startup test of the Unit 2 reactor coolant system and secondary coolant system, as detailed in Procedure ISU-006B, Revision 0.
The test was performed over the time period February 1 through May 26, 1993, which included Unit 2 fuel load through 75 percent power testing.
The test results established chemistry base levels and water quality of the primary and secondary coolant systems during precritical tests and also demonstrated the licensee's ability to control water quality during plant heatup and operation at temperature from initial criticality through power ascension to 75 percent power. The test results were found acceptable, and the test program met requirements. The test results were evaluated and approved by the licensee as required.
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The inspector 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 licensee had established an effective and well documented program for controlling the i
quality of primary coolant water and secondary water.
The water chemistry control program included written and approved management policies and procedures to implement the policies. The inspector's 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 startup water chemistry control program was implemented in accordance with approved procedures.
1.2 Conclusions The Unit 2 startup test of the reactor coolant system and secondary coolant system was completed through 75 percent power, and the test results were evaluated and approved as required. The Unit 2 startup radiochemistry and water chemistry control programs were being implemented according to procedures.
The radiochemistry and secondary water chemistry programs were established and implemented in accordance with requirements. Water chemistry control procedures were written and approved.
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-5-2 TECHNICAL SPECIFICATIONS (84521)
The Unit 2 primary coolant and secondary water quality and radioactive waste effluents were reviewed to determine compliance with Technical Specification and Offsite Dose Calculation Manual requirements.
2.1 Discussion The inspector reviewed applicable primary coolant water chemistry control' and secondary water chemistry control procedures used for the chemistry control of
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the primary and secondary water systems. Chemistry controls were based on industry standards and Electric Power Research Institute guidelines for pressurized water reactors. Action levels for out-of-specification chemistry parameters were established and strictly enforced.
Corrective actions were initiated in a timely manner to restore out-of-specification chemistry parameters to normal operating limits. The inspector reviewed radiochemistry and water chemistry data trends for the Unit 2 primary and secondary coolant systems for the time period March through May 1993.
Proper chemistry controls of the plant systems were implemented and met Technical Specification requirements.
Selected liquid and gaseous radioactive waste effluent batch and continuous release permits were reviewed.
The required sampling, testing, approvals, and release controls were performed in accordance with Technical Specification and Offsite Dose Calculation Manual requirements.
2.2 Conclusions The Unit 2 primary coolant and secondary water quality was maintained'and met Technical Specification requirements. The Unit 2 radioactive waste effluent program was implemented in accordance with Technical Specification and Offsite Dose Calculation Manual requirements.
3 COMPARISONS OF EFFLUENT MONITOR READINGS AGAINST KNOWN EFFLUENT CONCENTRATIONS (84521)
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The Unit 2 testing program for comparison of effluent monitor readings against a
known effluent radionuclide activity concentrations as determined by laboratory analysis was reviewed to determine agreement with recommendations in Regulatory Guides 1.21, 1.68, 1.97, and 4.15.
3.1 Discussion The inspector reviewed the licensee's program for comparing the effluent radiation monitor readings to the analyzed effluent radionuclide activity concentrations.
The Radiation Protection Instruction RPI-704, " Pre-Release
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Processing of Radioactive Effluent Releases," Revision 3, April 7,1993,
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required that for every batch liquid or gaseous radioactive waste effluent release the latest 10-minute or hourly trend printout, as appropriate, for the applicable effluent radiation monitor be obtained and included in each radioactive waste effluent batch release package to support the required comparisons between the radionuclide analysis results of grab samples and the
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I-6-radiation monitor readings during the release performed during the-post-release processing of each batch radioactive waste effluent release permit. This program was designed to establish a relationship between the radiation monitor readings and radionuclide concentrations for effluent releases. The inspector reviewed the batch liquid release log maintained by radiation protection personnel responsible for reviewing the closed radioactive waste effluent release permits and specifically noted the i
comparisons of the effluent radiation monitor readings to the sample gross gamma activity for each batch radioactive waste liquid effluent release performed during the time period January through April 1993.
The inspector verified, by direct observation and through discussions with radiation protection personnel, that a satisfactory test and comparison program for radiation effluent monitors was established and implemented and met the recommendations !n Regulatory Guides 1.21, 1.68, 1.97, and 4.15 for frequent tests and comparisons of installed effluent radiation monitors by laboratory analyses of samples from effluent streams to verify their response and ' channel calibration.
I 3.2 Conclusions The licensee had established and implemented an excellent program to i
frequently compare the installed effluent radiation monitor readings to the l
analyzed effluent gross gamma radioactivity concentration in liquid and l
gaseous radioactive waste effluent releases which met the recommendations in
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Regulatory Guides 1.21, 1.68, 1.97, and 4.15.
4 WASTE SYSTEMS (84521)
The Unit 2 gaseous and liquid radioactive waste management programs including radioactive waste effluent processing, storage, and release systems 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, 6.8.1, and 6.8.3.e; and the Offsite Dose Calculation Manual Sections 3.0 ard 4.0; and Tables 4.11-1 and 4.11-2.
4.1 Discussion l
The radioactive waste management program consisted of a consolidated effart by q
the radwaste operations, radiation protection, and chemistry departments.
These groups functioned well together.
The inspector reviewed selected components of the liquid and gaseous radioactive waste systems and confirmed, by direct observation, that the components and systems were as described in the Updated Safety Analysis Report.
Selected radiation protection, radwaste operations, and chemistry procedures governing the release of liquid and gaseous radioactive waste effluents were reviewed.
From this review it was determined that the procedures provided excellent guidance to individuals implementing the liquid and gaseous radioactive waste effluent programs.
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-7-The inspector reviewed the radioactive waste liquid and gaseous release permit programs and verified, by direct. observation and discussions with licensee personnel, that required sampling and analyses were performed prior to each radioactive waste effluent release, that the radioactive waste effluent'
release permits were properly reviewed by the appropriate licensee personnel, that the proper valve lineups were performed and verified, that the proper effluent radiation monitor setpoints were selected and verified, and that Technical Specification and Offsite Dose Calculation Manual radioactivity limits and offsite dose limits were not exceeded.
The inspector accompanied and observed chemistry personnel collect and analyze a radioactive waste liquid sample from Liquid Holdup Monitor Tank 2 on June 16, 1993.
A radiation protection technician was observed as he prepared the batch liquid radioactive waste effluent release permit.
The. inspector accompanied and observed two radwaste operators perform the initial release permit valve lineup and independent verification, the radiation effluent monitor setpoint verification, and performance of the radioactive waste batch liquid release.
Upon completion of the radioactive waste batch liquid effluent release, the inspector observed a radiation protection technician perform the post-release calculations and closeout of the release permit. All aspects of the radioactive waste batch liquid effluent release were performed in accordance with approved procedures.
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4.2 Conclusions The radioactive gaseous and liquid radioactive waste effluent management programs were well implemented to ensure compliance with the Offsite Dose
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Calculation Manual requirements and Technical Specification limits.
Excellent procedures had been established and implemented for conducting the radioactive waste effluent management programs.
5 NONRADI0 ACTIVE PROCESS AND EFFLUENT STREAMS (84521)
The Unit 2 prcgram for checking normally nonradioactive process and effluent streams was reviewed.
5.1 Discussien The inspector reviewed the licensee's program for monitoring normally
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nonradioactive process and effluent streams for unanticipated radioactivity.
The inspector reviewed Form CHM-ll2-1, " Control of Contamination of
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Nonradioactive Systems Log," for Unit 2 over the time period January through May'1993, which documented the routine monthly sampling and analyses of the specified nonradioactive systems and verified, by direct observation, that the
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required sampling and gamma isotopic analyses were performed.
Selected analysis results from the Unit 2 monthly surveillance tests for 1993 for the station service water system, condensate storage tank, component cooling water system, auxiliary steam condensate system, and steam generator blowdown system were reviewed and indicated no detectable radioactivity in the samples collected.
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-8-5.2 Conclusion The licensee had established and implemented an excellent program to routinely check normally nonradioactive process and effluent streams for unanticipated radioactivity.
6 QUALITY ASSURANCE PROGRAM (84750)
The inspector reviewed the quality assurance audit and surveillance programs of the radioactive waste effluent programs 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.
6.1 Discussion The inspector reviewed the 1992 quality assurance audit report of the radiological effluent and environmental monitoring programs (QAA-92-122) which was conducted during the time period August 20 through September 3, 1992.
The quality assurance audit program included an audit notification memorandum, audit plan, audit checklist, and audit report. The audit was performed by qualified personnel and a technical specialist who were knowledgeable in radiological effluent monitoring program activities.
The audit team evaluated the implementation of the radioactive effluent and environmental monitoring programs. The evaluation included reviews of the gaseous and liquid effluent release permits, training of personnel, and compliance with the surveillance requirements of the Offsite Dose Calculation Manual.
The 1992 quality assurance audit was conducted in agreement with Updated Safety Analysis Report commitments and met Technical Specification requirements.
The inspector noted that the Independent Safety Engineering Group had been assigned the responsibilities for the administration and implementation of the operating quality assurance surveillance program.
The inspector reviewed the following Field Note Sheets: ISEG-FN-92-237, " Liquid Effluent Release," dated September 15, 1992; ISEG-FN-92-244, " Liquid Effluent Waste Discharge," dated September 20, 1992; ISEG-FN-92-325, " Radiation Protection Counting Room,"
dated December 29, 1992; and ISEG-FN-93-242, " Wastewater Discharge Permit,"
dated April 27, 1993, which documented the Independent Safety Engineering
Group's surveillances of the radioactive waste effluent program since the l
previous NRC inspection of this area. The inspector determined that the l
operating quality assurance surveillances of the radioactive waste effluent
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programs were thorough and technically comprehensive and were conducted in j
sufficient depth to evaluate the licensee's compliance with Technical Specification and Offsite Dose Calculation Manual requirements.
6.2 Conclusion Comprehensive audit and surveillance programs had been established and implemented to review and evaluate the radioactive waste effluent program I
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7 UNIT 2 LIQUIDS AND LIQUID WASTES (84521)
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The inspector reviewed the Unit 2 liquid radioactive waste effluent program to
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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 completed on the liquid radioactive waste systems to verify operability, whether the radioactive waste
effluent and process monitoring program was adequate and conformed to the
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Updated Safety Analysis Report description, and whether operational procedures had been written and approved.
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7.1 Discussion 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 safeguards 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 l
interconnecting pipe " spool" was installed connecting floor drain tank No. 2 l
to the common liquid waste processing system which made the entire liquid
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radioactive waste effluent system operational.
Preoperational Test 2CP-PT-41-01, " Liquid Waste Processing Channel
'B'," Revision 0, was completed on November 20, 1992, and all components associated with the
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performance of the test met the design requirements. The preoperational
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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-
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representative sample of the floor drain tank contents.
There were no outstanding items associated with the completion of the test. The final test results were approved by the Joint Test Group on December 22, 1992.
The Unit 2 reactor coolant drain tank was installed and operational.
i Preoperational Test 2CP-PT-41-02, " Reactor Coolant Drain Tank," Revision 1, was completed on August 20, 1992, and all components associated with the l
performance of the test met the design requirements.
There were no l
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," Revision 0, 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 portion 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. The final test results were approved by the Joint Test Group on January 15, 1993.
The inspector inspected the Unit 2 primary sampling area. The primary sampling system brings samples 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 were provided for both pressurized and nonpressurized samples of the various primary water systems.
The Unit 2 grab sample hood assembly and associated process instrumentation were installed, tested, calibrated, and
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i-10-operational. The inspector inspected the Unit 2 Steam Generator Blowdown i
Sample Panel CP2-PSMEPS-03.
The Unit 2 steam generator blowdown sample panel I
and associated process instrumentation were installed, tested, calibrated, and operational.
The inspector inspected the various Unit 2 secondary chemistry sampling areas.
The sampling 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
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instrumentation including silica, sodium, hydrazine, dissolved oxygen, l
conductivity, and Ph analyzers were installed at the various Unit 2 secondary I
water sampling panels and were tested, calibrated, and operational.
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The licensee had developed sampling procedures to operate the sampling panels
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for the various water systems, and the procedures were common for Units 1 and 2 operation.
Selected approved procedures were reviewed and found to provide the necessary information required for obtaining a representative sample from the various sample points.
l Preoperational Test 2CP-PT-59-02, " Process Sampling System," Revision 0, was i
completed on October 10, 1992, and all components associated with the performance of the test met the design requirements. The preoperational test demonstrated that the process sampling systems provided samples for analysis i
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 inspector determined that most of the liquid process and effluent radiation monitors for the liquid radioactive waste system were common to both 4I 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
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The inspector verified that these radiation monitors were installed and operational.
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 i
Test and Channel Calibration of Station Service Water System Effluent Liquid j
Process Radiation Monitors," Revision 2, was completed on October 11, 1992, j
and all components associated with the performance of the test met the design
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requirements. The final test results were approved by the Joint Test Group on l
January 13, 1993. The primary calibrations of 2RE-4269 (Service Water i
Train A) and 2RE-4270 (Service Water Train B) radiation monitors were l
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 inspector reviewed the primary calibration
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results and preoperational test results of the two service water radiation monitors and found them to be satisfactory and documented in accordance with
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-11-approved procedures.
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. The final test results were approved by the Joint Test Group on January 13, 1993.
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 inspector 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.
The inspector noted that Radwaste Systems Procedure RWS-103, " Drain Channel B," Revision 6, October 23, 1992, 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, June 23, 1992, was written and approved to
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provide comprehensive instructions for effluent discharges from all of the l
l Units 1 and 2 discharge points including the turbine building sumps in each unit.
7.2 Conclusions The Unit 2 liquid radioactive waste processing system construction was completed, anc the various components were installed as described in the Updated Safety Analysis Report.
Preoperational testing was completed on the Unit 2 liquid waste processing system and associated equipment.
Unit 2 primary and secondary water sampling systems were installed, tested, and operational.
The process instrumentation was installed, tested, calibrated, and operational.
Sampling procedures to operate the various water system sampling panels were written and approved for 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, calibrated, and operational.
Radwaste systems procedures were written and approved which included instructions for the processing of liquid radioactive waste generated from the operation of both Units 1 and 2.
l 8 UNIT 2 GASEOUS WASTE SYSTEM (84521)
The inspector reviewed tne 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 were 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 operational procedures had been written and approved.
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-12-8.1 Discussion The gaseous radioactive waste effluent processing system including the waste gas compressors, waste gas decay tanks, and hydrogen recombiners was completely common to both Units 1 and 2 and was installed and operational in the common auxiliary building. 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, "Radioactie/e Vents and Drains," Revision 0, which was completed on December 20, 1992. All gaaeous waste system piping cross-ties between Unit 1 and Unit 2 were completed and the gaseous waste system was operational.
The gaseous radioactive waste effluent system had an established program and approved implementing procedures. The inspector noted that Radwaste Systems Procedure RWS-201, " Gaseous Waste Processing System," Revision 5, October 20, 1992, included instructions for processing gaseous radioactive waste generated from both Units 1 and 2.
8.2 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.
9 UNIT 2 PLANT SYSTEMS AFFECTING PLANT WATER CHEMISTRY (84521)
The inspector 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 volume control system, boron thermal regeneration system, and reactor coolant system.
9.1 Condensate System The inspector reviewed the status of the Unit 2 condensate system. The system was tested and operational.
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 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, 1992.
9.2 Condensate Polishing System The inspector reviewed the status of the Unit 2 condensate polishing system.
The condensate polishing system contained five water polishing vessels.
The system was tested and operational.
Preoperational Acceptance Test 2CP-AT-25-01, " Condensate Polishing Performance," Revision 0, was
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-13-l 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 J
resin transfer to the Unit 2 phase separator was performed, and the waste liquid from the phase separator was discharged to the Low Volume Waste Pond.
'l 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.
J 9.3 Feedwater S_ystem i
The inspector reviewed the status of the Unit 2 feedwater system. The j
feedwater system was tested and operational.
The two feedwater pumps had been u
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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
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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. There were no outstanding items associated with the completion of the test.
The final test results were approved by the Joint Test Group on December 14, 1992.
9.4 Auxiliar_y feedwater S_ystem The inspector reviewed the status of the Unit 2 auxiliary feedwater system.
The auxiliary feedwater system, including the condensate storage tank, was tested and operational.
Preoperational Test 2CP-PT-37-01, " Auxiliary Feedwater System," Ruision 0, was completed on Octcber 21, 1992. All components associated with the performance of the test met 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
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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.
There were no outstanding items associated with the completion of the test.
The final test results were approved by the Joint Test Group on December 10, 1992.
Preoperational Test 2CP-PT-37-03, " Auxiliary Feedwater Turbine Driven Pump,"
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Revision 0, was completed on October 24, 1992, and all components associated
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-14-with the performance o' the test met the design requirements. There were no outstanding items associated with the completion of the test. The final test results were approved b/ the Joint Test Group on December 22, 1992.
l 9.5 Service Water' System lhe inspector reviewed the status of the Unit 2 service water system.
The-service water system was tested and operational.
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
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this test that, after engineering evaluation of the test data, did not meet j
the design requirements. There were no outstanding items associated with the
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performance of this test. The final test results were approved by the Joint Test Group on December 1, 1992.
9.6 Chemical and Volume Control System i
i The inspector reviewed the status of the Unit 2 chemical and volume control system. The chemical and volume control system was tested and operational.
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
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system functioned according to the design requirements. All components associated with the performance of this test either met the design j
requirements or were deemed acceptable by engineering evaluations.
There were i
no outstanding items associated with the performance of this test.
The final test results were approved by the Joint Test Group 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, i
1992.
Preoperational Test 2CP-PT-49-03, " Chemical Control and Makeup," Revision 2,
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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 of this test that failed to meet the design requirements.
There were no outstanding items associated with the performance.of this test.
The final test results were approved by'the Joint Test Group on October 5, 1992.
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t-15-9.9 Conclusions
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Construction and preoperational testing of the Unit 2 plant systems affecting water chemistry were completed.
The preoperational test results were reviewed
and approved by the Joint Test Group. All Unit 2 plant systems affecting
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water chemistry were operational.
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10 REPORTS OF RADI0 ACTIVE EFFLUENTS (F?750)
The inspector reviewed the 1992 Semiannual Radioactive Effluent Helease Reports to determine compliance with the requirements of 10 CFR Part 50.36(a)(2), Technical Specification 6.9.14, and the Offsite Dose Calculation Manual.
10.1 Discussion
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The inspector reviewed the Semiannual Radioactive Effluent Release Reports for the time periods January 1 through June 30, 1992, and July 1 through December 31, 1992.
These reports were written in the format described'in NRC Regulatory Guide 1.21, Revision 1, June 1974, and contained the information required by the Technical Specifications and the Offsite Dose Calculation Manual.
During the time period January 1 through December 31, 1992, the licensee had performed 604 liquid batch releases and 63 gaseous batch releases.
The licensee reported five gaseous and one liquid abnormal / unplanned releases during the time period reviewed.
Forms were filed on the six abnormal / unplanned releases.
Corrective actions were implemented, and at no time were any dose or release radioactivity concentration limits
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exceeded. The inspector reviewed changes to the Offsite Dose Calculation
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Manual made during the time period reviewed and found the changes well documented in the appropriate Semiannual Radioactive Effluent Release Report as required by the Technical Specifications.
10.2 Conclusions The 1992 Seriannual Radioactive Effluent Release Reports included the required information consistent with the objectives outlined in the Offsite Dose Calculation Manual and met the Technical Specification requirements.
lhe 1992 Semiannual Radioactive Effluent Release Reports were well prepared, submitted timely, and their format followed regulatory guidance.
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ATTACHMENT 1 PERSONS CONTACTED 1.-1 Licensee Personnel
- J. M. Ayres, Quality Assurance Audits Manager
- D. M. Bozeman, Chemistry Manager
- S. E. Bradley, Radiation Protection Supervisor C. M. Carella, Chemistry Supervisor
- J. W. Donahue, Operations Manager
- J. M. Edwards, Radwaste Operations Supervisor T. L. Edwards, Radwaste Supervisor i
- L. T. Floyd, Staff Health Physicist
- J. H. Greene, Licensing Engineer
- W. G. Guldemand, Independent Safety Engineering Group Manager
- N. S. Harris, Licensing Engineer
- D. C. Kay, Technical Support Supervisor
- D. M. McAfee, Quality Assurance Manager G. B. Moore, Chemistry Supervisor R. L. Ramsour, Radiation Protection Technician G. A. Scroggin, Radwaste Operator D. L. Stearns, Independent Safety Engineering Group R. L. Theimer, Chemistry Supervisor
- J. E. Thompson, licensing Engineer 1.2 NRC Personnel W. B. Jones, Senior Resident Inspector, Unit 1
- D. N. Graves, Senior Resident Inspector, Unit 2 i
- Indicates those present at the exit meeting on June 18, 1993.
2 EXIT MEETING An exit meeting was conducted on June 18, 1993. During this meeting, the inspector reviewed the scope and findings of the inspection.
The licensee did not_ identify as proprietary any information provided to, or reviewed by, the inspector,