IR 05000285/1989011
| ML20247G342 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/23/1989 |
| From: | Baer R, Nicholas J, Ricketson L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20247G340 | List: |
| References | |
| 50-285-89-11, NUDOCS 8904040202 | |
| Download: ML20247G342 (11) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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NRC Inspection Report:
50-285/89-11 Operating Licer.3e:
OPR-40
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Docket:
50-285
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Licensee:
Omaha Public Power District (OPPD)-
1623 Harney Street'
Omaha,. Nebraska 68102 Facility Name:
Fort Calhoun' Station (FCS)
Inspection At:
Inspection Conducted:
February 27 through March 3, 1989 Inspectors:
h d4&@
>ZN
% Y B.)it'e's Nichol Senior Radiation Specialist
.Date f
Facil ad ological Protection Section
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' B V7 L. T.
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diation Specialist Date Facili i@4olog tal Protection Section Approved:
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3 88 R
E'. Baer, Chiet, Tacilities Radiological Date Protection Section Inspection Summary Inspection Conducted February 27 through March 3, 1989 (Report 50-285/89-11)
Areas Inspected:
Routine, unannounced inspection of the licensee's liquid and gaseous radioactive waste management programs.
Results: The NRC inspectors determined that liquid and gas releases were conducted in accordance with the licensee's procedures and that quantities of
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l radionuclides released in the effluents were within the limits specified in l
the Radiological Effluent Technical Specification (TS).
Offsite doses had been calculated and were within the TS.
Sampling and analysis had been performed in compliance with TS and Quality Assurance audits and surveillance were technically comprehensive.
No violations or deviations were identified.
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DETAILS 1.
Persons Contacted OPPD
- K. J. Morris, Division Manager, Nuclear Operations
- W. G. Gates, Manager, Fort Calhoun Station
- G. R. Peterson, Assistant Manager, Fort Calhoun Station
- J. P. Bobba, Supervisor, Radiation Protection M. A. Breuer, Acting Radwaste Coordinator C. J. Brunnert, Supervisor, Operations Quality Assurance (QA)
- T. R. Dukarski, Chemistry Laboratory Coordinator
- J. J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs
- F. F. Franco, Manager, Emergency Preparedness
- S. K. Gambhir, Division Manager, Production Engineering
- J. K. Gasper, Manager, Nuclear Training
- J. M. Glantz, Senior Chemistry Technician
- D. J. Matthews, Supervisor, Station Licensing
- G. L. Roach, Supervisor, Radiation Protection Services
- B. A. Schmidt, Acting Plant Chemist
- C, F. Simmons, Station Licensing Engineer l
NRC
- P. H. Harrell, Senior Resident Inspector, FCS
- T. Reis, Resident Inspector, FCS
- Denotes those present during the exit interview on March 3,1989.
2.
Inspector Observations The following are observations the NRC inspectors discussed with the licensee during the exit interview on March 3, 1989.
These observations are not violations, deviations, unresolved items, or open items.
These observations were identified for licensee consideration for program improvement, but the observations have no specific regulatory
.l requirements.
The following observations are identified in paragraph 3 of
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this report.
The licensee stated that these observations would be
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evaluated, a.
Monitor Tank Release Permits - The licensee was no longer requiring a supervisory review and approval signature on the liquid radwaste effluent release permits prior to submitting the release permits to the control room for performance of the liquid discharge (see paragraph 3).
b.
Liquid Radwaste Ef fluent Release Data Review - The licensee's Plant Chemist had not completed a review of liquid radwaste effluent release reports in a timely manner following the completion of the liquid releases (see paragraph 3).
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3.
Liquids and Liquid Wastes (84750, 84523, 84723)
The NRC inspectors reviewed the licensee's liquid radioactive waste effluent program including:
liquid radwaste system construction and installation, liquid radwaste sampling, procedures for liquid radwaste and effluent systems, reactor coolant and secondary water quality, and audits and surveillance to determine agreement with commitments in Chapters 4, 9, 11, and 12 of the Updated Safety Analysis Report (USAR) and the requirements in Sections 2.1, 2.9, 2.20, 3.12, 5.5, and 5.8 of the Technical Specifications (TS).
The NRC inspectors reviewed the licensee's implementation of the Radiological Effluent Technical Specifications (RETS) and Offsite Dose Calculation Manual (0DCM) to ensure agreement with analysis sensitivities, reporting limits, analytical results, sampling requirements, surveillance tests, radioactive waste effluent program (RWEP) operating procedures, offsite dose results from liquid effluents, and functional checks and calibrations of equipment associated with the radioactive liquid waste processing system.
Selected documents and records listed in Attachment 1 to this report were reviewed.
The NRC inspectors reviewed current approved revisions of FCS standing orders and procedures governing the release of liquid radioactive waste.
These liquid effluent release procedures provide for the following:
sampling of radioactive waste; chemical and radionuclides analyses prior to release; calculation of effluent release rates and projected offsite radionuclides concentrations and offsite doses prior to release; verification of effluent radiation monitor setpoints and testing of effluent isolation valves prior to release; recording effluent dilution parameters during releases; and verifying discharge flow rates and effluent volume discharged.
Selected documents listed in Attachment 1 to this report were reviewed.
The NRC inspectors reviewed a representative number of liquid release permits for the period January through December 1988.
It was determined that processing, sampling and analysis, and approval and performance of the releases were conducted in accordance with FCS procedures.
Quantities of radioactive nuclides released in the liquid effluents were within the limits specified in the RETS.
Offsite doses had been calculated according to the ODCM and were within the TS limits.
During the review of the liquid release permits, the NRC inspectors observed that the Chemistry / Radiation Protection Supervisor or Plant Chemist no longer was i
l required to approve and sign the liquid effluent release permit prior to its submittal to the control room and shift supervisor for performance of the discharge of liquid radioactive waste to the river.
The only required
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signature was that of the chemistry technician who performed the chemistry I
analyses and prepared the release permit.
This appeared to be a reduction i'
in station management oversight of the release of radioactive waste
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materials beyond the site boundary.
The NRC inspectors discussed this observation with the licensee's representatives during the exit interview on March 3, 1989, expressing the concern that the deletion of the supervisory approval signature on the liquid effluent releases may be a
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reduction of safety precautions involving release of radioactive material
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to the environment.
The licensee agreed to evaluate the necessity of supervisory approval of the liquid effluent release permits prior to submittal to the shif t supervisor for initiation of the releases.
The NRC inspectors also observed that liquid effluent releases (88090-88149) had received a final review, but they were signed by an alternate for the Plant Chemist and the remaining liquid effluent releases for 1988 (88150-88201) and all liquid effluent releases performed during January through. February 1989 had not been reviewed and signed by the Plant Chemist at the time of the inspection.
This appeared to the NRC inspectors as another example of lack of management oversight in conducting the RWEP.
The NRC inspectors determined that a contract had been awarded to the Duratek Company to process the station's liquid radwaste.
The Duratek Enhanced Volume Reduction Processing System replaces the station's radwaste denineralizers and waste evaporator for processing liquid radwaste.
The NRC inspectors reviewed procedures and selected reactor coolant and secondary water chemistry analyses records for the period January through December 1988.
The records reviewed indicated that all required sampling and analyses were performed at the frequencies required by the TS and the analyses results met TS requirements.
The NRC inspectors reviewed selected QA audit and surveillance reports of QA activities performed during 1987 and 1988 in the areas of radioactive waste effluent releases.
The reports were reviewed for scope and thoroughness of program evaluation and timely followup of identified deficiencies.
The NRC inspector determined that QA surveillance had been performed in accordance with FCS procedures.
The NRC inspectors reviewed the Safety Audit and Review Committee Audit No. 8-88, " Radiological Effluent Program," performed during the period October 31 through November 10, 1988, and found the audit plan to be technically comprehensive.
It was noted that 10 Deficiency Reports and
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8 Quality Reports were issued as a result of the audit.
The NRC inspectors reviewed the licensee's responses and corrective actions to these audit findings and found two Deficiency Reports closed and four Quality Reports closed at the time of the inspection. The remaining audit findings were in the progress of being resolved and had been assigned completion dates prior to July 1,1989.
No violations or deviations were identified.
4.
Gaseous Waste System (84750, 84524, 84724)
The NRC inspectors reviewed the licensee's gaseous radioactive waste effluent program including:
gaseous waste system construction and installation, gaseous radwaste sampling, procedures for gaseous waste and effluent systems, and air cleaning systems to determine agreement with commitments in Chapters 6, 9, and 11 of the USAR and the requirements in Sections 2.9, 3.6, 3.12, and 5.8 of the TS.
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The NRC inspectors reviewed the licensee's' implementation of the RETS and ODCM to ensure agreement with analysis sensitivities, reporting limits, analytical results, sampling requirements, surveillance tests, RWEP operating procedures, offsite dose results from gaseous effluents, and functional checks and calibrations of equipment associated with the radioactive gaseous waste processing system.
Selected documents and records listed in Attachment 1 to this report were reviewed.
The NRC inspectors reviewed current approved revisions of FCS standing orders and procedures governing the release of gaseous radioactive waste.
These gaseous effluent release procedures provide for:
the sampling of gaseous radioactive waste; radionuclides analysis prior to release; calculation of effluent release rate, projected offsite radionuclides concentrations, and offsite doses prior to release; verification of gaseous effluent radiation monitor setpoints and testing of effluent isolation valves prior to release; recording of meteorological conditions during releases; and verifying discharge flow rates and effluent volume discharged.
Selected documents and records listed in Attachment 1 to'this report were reviewed.
The NRC inspectors reviewed selected gaseous waste release data and permits which included plant stack continuous releases and batch releases from waste gas decay tanks and containment for the period January through December 1988.
It was determined that the gaseous waste releases were being performed according to FCS procedures and the quantities of gaseous radioactive nuclides released were within the limits specified in the RETS.
Offsite doses had been calculated according to the 00CM and were within the TS limits.
The NRC inspectors reviewed the licensee's analyses results to determine compliance with the requirements of TS 2.9.1(2) and 3.12.1(2) and Table 3-12.
The NRC inspectors determined that no design changes had been made to the gaseous radwaste management system since the previous NRC inspection in December 1987.
The NRC inspectors reviewed the instrument operability checks of the hydrogen and oxygen monitors on the gaseous waste system. These monitors are to monitor the in-service gas decay tank during the transfer of waste
gases to the gas decay tank to ensure that the hydrogen and oxygen concentrations are maintained below an explosive mixture. The hydrogen
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and oxygen monitors have been out-of service since June 10, 1988.
Due to this monitor inoperability, the licensee has been required by TS to take grab samples from the in-service gas decay tank during transfer of waste gases and analyze these samples for oxygen and hydrogen concentration.
The NRC inspectors reviewed the results of these analyzes and verified that the TS requirements were being met.
The NRC inspectors reviewed the licensee's procedures, surveillance tests, and selected records and test results for maintenance and testing of air cleaning systems which contain high efficiency particulate air (HEPA)
filters and activated charcoal adsoruers.
The NRC inspectors verified that the licensee's procedures and surveillance tests provided for the l
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required periodic functional checking of ventilation system components, evaluation of HEPA and activated charcoal adsorbers, tracking of system operating hours, and replacement and in place filter testing of filter systems.
The NRC inspectors reviewed selected records and test results for the period January through December 1988 for the control room, containment building, safety injection pump room, spent fuel pool area, and auxiliary Iuilding air cleaning systems.
The in place filter testing and activated charcoal laboratory tests had been performed by approved and Q' audited contractors and all test results were verified to be within TS limits.
Selected documents and surveillance tests listed in Attachment 1 to this report were reviewed.
The NRC inspectors determined that the licensee was using a contractor to perform in place filter testing and a second contractor laboratory to perform charcoal adsorber enalyses on station ventilation systems as required by TS.
The licensee had performed a QA program audit on each of the contractors performing the in place filter testing and laboratory analyses on the station ventilation systems and had placed the contractors
.on the FCS routine supplier's list.
No violations or deviations were identified.
5.
Reports of Radioactive Effluents (84750)
The NRC inspectors reviewed the licensee's reports concerning radwaste systems and effluent releases for compliance with the requirements of 10 CFR Part 50.36(a)(2) and Section 5.9.4.a of the TS.
The NRC inspectors reviewed the semiannual effluent release reports for the periods July 1 through December 31, 1987; January 1 through June 30, 1988; and July 1 through December 31, 1988.
These reports were written in the format described 'in NRC Regulatory Guide 1.21 and contained the
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information required by TS.
No violations or deviations were identified.
6.
Exit Interview (30703)
The NRC inspectors met with the NRC resident inspectors and the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on March 3, 1989.
The NRC inspectors summarized the scope and findings of the inspection and discussed the NRC inspectors' observations. The licensee representatives stated at the exit interview that they would evaluate the NRC inspectors' observations and concerns and take necessary corrective action to implement program improvements.
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ATTACHMENT 1 Fort Calhoun Nuclear Station NRC Inspection Report:
50-285/89-11 Documents Reviewed Title Revision Date 1.
Standing Orders (50)
SO G-5, Fort Calhoun Station Plant
11/16/88 Review Committee SO G-23, Surveillance Test Program
12/28/88 SO T-2, Waste Liquid Release
01/06/89 S0 T-3, Waste Ga: Release
07/21/88 50 T-5, Primary Chemistry Summary Report
07/21/88 SO T-7, Secondary Chemistry Summary Report
07/18/88 S0 T-12, Containment Purge Release
07/18/88 2.
Chemistry Manual Procedures (CMP)
CMP-2.0, Sample Collection
12/09/88 CMP-2.1, Grab Sampling
01/07/88 CMP-2.2, Waste Gas Sampling System
11/23/87 CMP-3, Composite Sampling Procedure
03/02/87 CMP-2.6, Gaseous Effluent Sampling
10/01/88 CMP-4.4, Waste Liquid Release Permit
11/02/88 CMP-4.5, Containment Purge / Vent Release Permit 10 11/02/88 CMP-4.6, Waste Gas Release Permit
11/02/88 CMP-6.0, Offsite Dose Calculation Manual
09/10/38
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Chemistry Record Forms FC-211, Waste Liquid Release Permit
12/13/88 FC-212, Containment Purge Release Permit
12/13/88 FC-213, Waste Gas Release Permit
01/26/89 FC-214, Reactor Coolant Summary Report
02/06/89 FC-215, Secondary Chemistry Summary Report
02/12/88 FC-240, RM-060 Iodine Cartridge Weekly Log
04/27/88 FC-261, Condenser Air Ejector Release Summary
09/10/88 FC-287, Steam Generator Release Summary
09/10/88 FC-293, Continuous Stack Release Summary
10/02/86 FC-302, Waste Gas Release Summary - Containment 4 02/04/86 FC-303, Waste Gas Decay Tank Summary
08/04/88 FC-339, Monitor Tank Releases Monthly Composite 7 10/13/88 Data Sheet FC-341, Steam Generator Blowdown and Secondary
10/13/88 Releases Monthly Composite Data Sheet FC-364, Non-Routine Analysi s Report
02/23/85 FC-417, Instrument Check Panel No. AI-110
03/18/86 FC-421, Quarterly Cumulative Dose Contributions 1 02/13/88 from Radioactive Effluents 4.
Operating Instruction (OI)
OI WDL-1, Collection and Transfer of Liquid
01/26/89 Waste 01-WOL-2, Waste Disposal Liquid Normal
12/15/88 Operation Process 01-WDL-3, Liquid Waste Disposal
11/16/88 OI-WDG-1, Waste Gas System Normal Operations
01/14/89 01-WDG-2, Waste Gas Release
08/30/88
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OI-WDG-3, Waste Gas Sampling System (AI-110)
12/15/88 Operation 01-VA-1, Heating, Cooling, and Ventilation -
01/31/89 Normal Operation Containment 5.
Surveillance Tests (ST)
ST-CHEM-1, Chemical and Radiological Sampling
11/11/88 ST-WG-2, F.2, Waste Gas Hydrogen and Oxygen
10/17/88 Monitor Cross Comparisons ST-WG-2, F.3, Waste Gas Hydrogen and Oxygen
10/17/88 Mcnitor Calibration ST-CRV-1, F.1, Control Room Filter Circuit
05/16/87 Operation ST-CRV-1, F.2, Control Room Ventilation Damper 13 12/21/88 Operation ST-CRV-1, F.3, Control Room Ventilation
12/21/88 Positive Pressure Check ST-FIL-1, F.1, Containment HEPA Filter Banks
09/24/88 VA-5A and VA-5B Inspection ST-FIL-1, F.2, Containment Charcoal Filter
09/24/88 Banks VA-6A and VA-6B Inspection ST-FIL-1, F.3, Containment Filter Train
09/24/88 Pressure Drop ST-FIL-2, F.1, Safety Iniection Pump Room
10/20/88 Charcoal Filter Freon Test of the Adsorbers VA-26A and VA-26B ST-FIL-2, F.2, Control Room HEPA Filter DOP
09/27/88 Test VA-64 ST-FIL-2, F.3, Control Room Charcoal Filter
09/27/88 Freon Test VA-64 i
ST-FIL-2, F.4, Spent Fuel Pool Arec Charcoal
09/27/88 Filter Freon Test VA-66 ST-FIL-2, F.5, Pressure Drop Across Control Draft 10/10/88 Room Filter Banks VA-64 l
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ST-IR-1, F.1, Safety Injection Pump Room
09/30/88 Charcoal Filters (VA-26A and VA-268) Elemental Iodine Removal Efficiency Test ST-IR-1, F.2, Spent Fuel Pool Area Charcoal
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Filter (VA-66) Elementa1 Iodine
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l Removal Efficiency Test ST-IR-1, F.3, Containment Charcoal Filters
09/30/88 (VA-6A and VA-68) Methyl Iodide Removal Efficiency Test ST-IR-1, F.4, Control Room Charcoal Filter
09/30/88 (VA-64) Iodine Removal Efficiency Test ST-VA-1, F.1, Containment Air Cooling and
03/06/85 Filtering System ST VA-1, F.2, Containment Air Cooling and
01/02/89 Filtering System Filter Circuit Operation ST-VA-1, F.3, Containment Air Cooling and
12/20/88 Filtering System Fan and Remotely Operated 0amper Check ST-VA-1, F.4, Containment Air rooling and
12/20/88 Filtering System Flow Determination ST-VA-1, F.5, Containment Air Cooling and
01/02/89 Filtering System ST-VA-4, F.1, Auxiliary Building Air
03/06/85 Filtering Unit Operation s
ST-VA-4, F.2, Safety Injection Pump Room
12/15/88 Filter Circuit Operation ST-VA-4, F.3, Spent Fuel Pool Area Filter
10/10/88 Circuit Operation ST-VA-4, F.6, Measurement of Control Room
10/10/86 Filter Unit Air Flow ST-VA-4, F.7, Measurement of Safety Injection
10/10/88 Pump Room Filter Unit Air Flow ST-VA-4, F.8, Measurement of Spent Fuel Pool
10/10/88 Area Filter Unit Air Flow
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Quality Assurance (QA) Surveillance and Audits QA Surveillance Report (QASR), S-30, Liquid tiiluent Releases (July 1987, April 1988)
QASR, S-12, Waste Gas Releases (August 1987, March 1988)
l QASR, S-39, Containment Purge Releases (July 1987, May 1988)
Safety Audit Review Committee Audit Report No. 8-88, Radiological Effluent Program, conducted October 31, '.988 - November 10,1988 QA Vendor Audit Report No. 87-10, Nuclear Consulting Services, conducted April 28-29, 1987 QA Vendor Au.it Report No. 88-23, NCS Corporation, conducted
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September 15-16, 1988 7.
Fort Calhoun Station Semiannual Effluent Release Reports July 1, 1987, through December 31, 1987 January 1, 1988, through June 30, 1988 July 1, 1988, through December 31, 1988
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