IR 05000416/1993006
| ML20044G088 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/19/1993 |
| From: | Decker T, Mcneill N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20044G086 | List: |
| References | |
| 50-416-93-06, 50-416-93-6, NUDOCS 9306020021 | |
| Download: ML20044G088 (10) | |
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"I UtelTED STATES
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o WUCLEAR REGULATORY CONNISslON g
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E 101 MARIETTA STREET N.W.
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ATLANTA CEORGIA 30323
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MAY 2 0 1993 Report No.:
50-416/93-06 Licensee:
Entergy Operations, Inc.
Jackson, MS 39205 Docket No.:
50-416 License No.: NPF-29 Facility Name: Grand Gulf Inspection Conducted: April 19-23, 1993
Inspector:b nw [ Z h
Io 5f!95 N. G. McNeill, Radiation Specia st Dste Signed
/heA Esh9fS3 Approved byL /
nud A T. R. Decker, Chief Date Signed
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Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch i
Division of Radiation Safety and Safeguards
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SUMMARY Scope:
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This routine, announced inspection was conducted in the areas of organization
of the Chemistry Department and the Radwaste Shipping Unit; the Clean Laboratory Count Room; liquid radiological effluent processing and monitoring; effluent monitoring instrumentation; the radiological environmental monitoring
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program (REMP); and the Meteorological Monitoring Program.
Results:
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The structure of the licensee's Chemistry Department and Radioactive Waste Group satisfied the requirements of the Technical Specifications (TSs)
(Paragraph 2).
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Chemistry parameters were maintained within TS limits (Paragraph 3).
The licensee had established a good Training and Qualification program I
(Paragraph 4)
The licensee demonstrated proficiency in the calibration and maintenance.of effluent monitoring instrumentation (Paragraph 5).
The Annual Environmental Operating Report for 1992 was presented in a timely manner and covered all areas as specified in the TS (Paragraph 6).
9306020021 930520 PDR ADDCK 05000416 Q
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The licensee's Semiannual Radioactive Effluent Release report for 1992 was
. reviewed and the totals for effluent releases were found to be within TS limits. (Paragraph 7).
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i The licensee had performed Audits and acted on those findings as specified in i
the TSs (Paragraph 8).
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In-place filter testing was observed by the inspector and found to follow i
licensee procedures and industry guidelines (Paragraph 9).
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Previous inspection items were reviewed and closed (Paragraph 10).
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REPORT DETAILS
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1.
Persons Contacted Licensee Employees
- J. Antoine, Chemistry Supervisor (Technical Support)
- W. Brice, Licensing Specialist
- W. Cottle, Vice President of Operations
- D. Coulter, Technical Supervisor, Radiological Controls
- D. Crawley, Environmental Specialist
- L. Daughtery, Superintendent, Plant Licensing
- R. Dubey, Principal Mechanical Engineer
- C. Dugger, Manager of Operations
- C Ellsaesser, Assistant Manager of Operations
- R. Fuller, Senior Engineer
- W. Garner, Supervisor, Q P J. Hurley, Health Physics Training 5pecialist
- C. Hutchinson, Plant General Manager
- D. Jackson, Chemistry Supervisor
- E. James, Radiochemist
- T. Love, Quality Specialist
- M. Larson, TSH/ Auditor
- M. Meisner, Director, Nuclear Licensing
- K. O'Neal, Chemistry Shift Supervisor
- R. Patterson, Assistant to the General Manager
- J. Roberts, Manager, Plant Maintenance
- R. Ruffin, Specialist, Licensing
- T. Tankersley, Superintendent, Radiological Control
- T. Williamson, Superintendent, Chemistry Other licensee employees contacted included maintenance personnel, technicians, and administrative personnel.
Nuclear Regulatory Commission
- R. Bernhard, Senior Resident Inspector
- Attended exit interview Acronyms and Initialisms used throughout this report are listed in the last paragraph.
2.
Organization (84750 and 86750)
Technical Specification (TS) 6.2 describes the licensee's onsite facility organization. The inspectors reviewed the licensee's organization, staffing levels, and lines of authority as they related to the Chemistry Department and Radioactive Waste Group to verify compliance with the TS..
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The licensee's Chemistry Department consisted of thirty-five full time personnel, directed by the Chemistry Superintendent who reported to the'
i Manager of Operations. There were two vacancies in the full time i
positions at the time of this inspection. The Chemistry Superintendent, j
the Operations Supervisor, and Technical Support Supervisor had been in l
their. positions for between three and a half to four years. The eleven
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radiochemists directed by the Operations Supervisor were either ANSI-
qualified or pursuing their qualifications. The licensee's Radiation Control Organization consisted of a staff of fifty-five personnel when at full strength, and was directed by the Radiation Control
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Superintendent who reported to the Manager of Operations.
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t One significant change which had occurred was the incorporation of the
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Environmental group into the Chemistry Department. This system
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consolidation resulted in the removal of the Environmental staff from
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Entergy Operations Incorporated in Jackson, MS to the Grand Gulf Nuclear i
Station. This consolidation is expected to result in more responsiveness i
to GGNS needs and does not represent any apparent problem with
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fulfilling requirements of the TSs in either the Chemistry or
4 Environmental areas.
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The inspector concluded that the licensee's Chemistry Department and
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Radwaste Unit satisfied the requirements of the TSs and personnel were j
capable of effectively discharging their duties as related to j
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chemistry / effluents and Radioactive Waste Management.
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No violations or deviations were noted.
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3.
Chemistry Parameters (84750)
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TS 3/4.4.4 specifies the chemistry control requirements for the reactor
coolant system. TS 3/4.4.5 specifies the radiochemistry requirements for i
the reactor coolant system. TSs 4.4.4 and 4.4.5 state the surveillance
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requirements for chemistry and radiochemistry parameters respectively.
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Table 3.4.4-1 states the requirements for chlorides, conductivity, and pH relative to plant operational conditions, j
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The inspector reviewed Quarterly Chemistry Reports for the third and
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fourth quarters of 1992 and the first quarter of 1993 to verify I
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compliance and assess quality. The Quarterly Chemistry Reports
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described and graphed trends in Reactor Water, Primary Water, Reactor
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Water Clean up Systems, Condensate Demineralizer Effluent, Condensate l
Pump Discharge, and Final Feedwater parameters, as well as those of i'
specified auxiliary systems.
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Reactor water conductivity averaged 0.156 uS/cm, chlorides averaged less j
than.31 ppb and pH averaged 7.5 to 7.9.
All these values were well j
within the TSs outlined above. These parameters were maintained within
limits over the three quarters reviewed with few exceptions. Where l
limits were exceeded, the parameters were brought back into
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acceptable values in a timely manner and resolution to _the causes and i
effects associated with exceeding any limit were reviewed thoroughly.
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The inspector concluded that the Plant Water Chemistry was maintained
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well within TS requirements.
No violations or deviations were noted.
4.
Training and Qualifications (84750 and 86750)
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TS 6.3 states that each member of the unit shall meet or exceed the
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minimum qualifications of ANSI N18.1-1971 for comparable positions.
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The inspector inspected the training records of several personnel in the l
Radiation Control and the Chemistry Departments. Qualification Records
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as well as actual test scores and On-the-Job documentation for the l
personnel were reviewed. The records and testing for procedural
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competency appeared thorough and comprehensive.
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There had been no significant changes to the structure or operation of i
the Training Program since the time of the last inspection.
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The review indicated that plant personnel involved in the operations that were examined during the inspection were adequately trained and that the Training program was meeting the requirements of the TS.
No violations or deviations were noted.
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Effluent Monitoring Instrumentation (84750)
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TSs 3.3.7.11 and 3.3.7.12 identify the surveillance and calibration
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requirements for liquid and gaseous effluent monitors.
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The inspector reviewed Limiting Condition of Operation (LCO) reports
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relative to gaseous effluent monitors. The licensee had experienced j
quite a few problems with these type monitors over the last year. These
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monitors are General Electric particulate / Iodine and noble gas
monitoring stations utilized in such release point areas as: the j
Radwaste Building Vent (RWBV), the Containment Building Vent (CBV),
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Turbine Building Vent (TBV), and the Fuel Handling Building Vent (FHBV).
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Two additional GE skids were installed in the Stand By Gas Treatment i
(SBGT), A and B trains, as post-TMI items.
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The nature of the problems relative to the aonitors was primarily
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. related to failure of flow elements and sensitivity to beta radiation
during routine calibrations (low and high failures). The problem with l
the flow elements appeared to have been addressed with Minor Change
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Package (MPC) 90-1050 which installed new flow transmitters on the I
units in question. The other LCOs were concerned 'with routine
maintenance on the monitors.
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The licens9 had made plans to change out the GM tubes on the monitors
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and had in tact already received the replacement tubes on site. The
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tubes were to be installed on the monitors in June-July of 1993. The
inspector notified that the installation and subsequent performance of
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the new tubes would be tracked as Inspector Follow-Up Item (IFI)
50-416/93-06-01.
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6.
Annual Environmental Operating Report (84750)
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i TS 3.12 states the requirements for the licensee's radiological i
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environmental monitoring program. The program is implemented through Environmental Surveillance Program Administrative Procedures 5.1 to 5.8,
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and Procedures SP-R-1 through SP-R-13. The inspector accompanied
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Environmental Specialists on a typical weekly sample collection tour of the environmental sampling stations to verify compliance and evaluate
quality. The sample points were located as specified in the requirements, and the air samplers were in current calibration. The inspector and specialist examined air samplers, vegetation sampling
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plots, TLD stations, liquid effluent outfalls, rain gauges, and two cisterns. The air sample stations were changed out in accordance with
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the above-referenced procedures and the personnel were familiar with i
both the equipment and the collection of the data.
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The Monthly Grand Gulf Radiological Environmental Monitoring Program (REMP) Report included all analyses performed on environmental samples for the year through die current month. The results included results for
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duplicate samples analyzed for quality control purposes. In general, all
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results were in the lower limit of detection levels.
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From a review of the licensee's environmental report, observation of the technicians in the field, and general review of the Radiological l
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Environmental Monitoring Plan, the inspector concluded.that the Radiological Environmental Technical Specification (RETS) requirements were being fulfilled and that plant operations had negligible impact on
the surrounding environment.
Furthermore, any activity which may have
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been present as a result of plant operations did not represent a l
significant contribution to the exposure of the members of the public.
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7.
Semiannual Effluent Report (84750)
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TS 6.9.1.8 states the requirements for the Semiannual Radiological Effluent Report including timeliness, content, and format.
The inspector reviewed the reports issued for the first and second halves of calendar year 1992 to determine compliance and reviewed data j
from previous reports to evaluate trends in liquid and gaseous releases.
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The effluent information presented in the following table was obtained from current and previous effluent reports.
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EFFLUENT RELEASE SUMMARY FOR GRAND GULF NUCLEAR STATION Activity Released (Curies)
1990 1991 1992 i
i Gaseous Effluents:
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Fission and Activation 1.36E+2 3.17E+1 2.12E+2
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Iodines and Particulates 2.52E-3 1.09E-3-2.14E-l*
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Tritium 3.32E+0 5.57E+0 8.87E+0
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Liquid Effluents:
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f Fission and Activation 6.45E-1 8.77E-1 1.20E-1 l
Products Tritium 1.88E+1 2.16E+1 2.30E+1
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Inoperable Effluent
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Monitoring Instruments i
for Greater Than 30 days
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Unplanned Releases Liquid
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- During fuel Cycle 5 there were three fuel bundles that had pinhole f
leaks. Analysis by General Electric on the Siemens Fuel identified the-
leakers. Since new fuel was loaded for the current Fuel Cycle 6 no i
elevated 1-131 levels have been detected. ' Iodine levels have returned l
to the pre-1992 levels.
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I The licensee's program to control and quantify radioactive effluent was j
effective. The quantities of radioactive material released due to plant
operations in 1992 resulted in negligible calculated offsite doses.
j There were no unplanned radioactive releases that required reporting to
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the NRC in 1992 or in 1993 to date.
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No violations or deviations were identified.
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Audits (84750 and 86750)
l Technical Specification (TS) 6.5.2.8 requires that audits of unit activities be performed under the cognizance of the Safety Review committee (SRC) in the following areas: (1) the radiological i
environmental monitoring program and the results thereof at least Once
per 12 months; (2) the 0FFSITE DOSE CALCULATION MANUAL and implementing
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procedures at least once per 24 months; (3) the PROCESS CONTROL PROGRAM
and implementing procedures for SOLIDIFICATION of wet radioactive wastes j
at least once per 24 months; and (4) the performance of activities
required by the Quality Assurance Program to meet the criteria of
Regulatory Guide 4.15, February 1979, at once per 12 months.
j The inspector reviewed the following audit reports:
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QSA-92/0038, Quality Assurance for Radiological Monitoring i
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Programs - Effluent Streams and the Environment j
QSA-92/0457, Low-level Radioactive Waste and NRC approved
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Packaging and Shipping Program
QSA-92/0025, Qualification, Certification and Training
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QSA-92/0001, Control of Measuring and Test Equipment
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-t The above audits assessed the adequacy and effectiveness of the quality
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assurance program for radiological effluent monitoring and shipping and j
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transportation of radioactive materials and radwaste. The audits covered the applicable areas specified in TS 6.5.2.8.
In general, the i
audits identified some program weaknesses and licensee management made
adequate cor.oiitments to correct the few deficiencies identified.
No violations or deviations were noted.
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In-Place Filter Testing (84750)
TS 4.6.6.3 states that the surveillance requirements for each standby l
gas treatment subsystem shall be operable to specific timetables and t
under various conditions.
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The inspector accompanied licensee personnel and a licensee vendor as i
they performed in-place filter testing on several systems throughout the i
pl ant. The procedures followed included.
06-ME-1T48-R-0005, In-Place Filter Testing of Standby Gas
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Treatment System - Safety Related
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06-ME-lZ51-R-0006, In-Place Filter Testing of Control Room
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Emergency Filtration System - Safety Related
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I 07-S-14-314, In-Place Testing of Containment Cooling System
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Charcoal Filter Trains - Non-Safety Related 07-S-14-313, In-Place Testing of Radwaste Building Exhaust. Filter
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Trains - Non-Safety Related
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The personnel involved appeared to have a thorough knowledge of the l
system and followed the procedures. The procedures appeared to cover the requirements of the systems and a review of calibration and maintenance.
records for the systems reviewed showed that the surveillance
requirements of the TSs were being achieved.
No violations or deviations were identified.
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10.
Preyious Inspection Items
a.
(Closed) VIO 50-416/92-24-01: Untimely Access to Emergency Response Telephone Number Concerning Radwaste Shipments.
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The original violation was cited for the licensee being unable to
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provide immediate information concerning a shipment of Radwaste while the shipment was enroute to the burial site. The inspector i
reviewed the licensee Closure Form.which addressed the violation.
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The corrective actions taken by the licensee entailed providing the Control Room with copies of all shipments and a briefing with the Shift Superintendent about those shipments. While no shipments
were in transit at the time of the inspection and the actual response could not be tested, the licensee's corrective actions i
were acceptable and close the violation. The licensee was informed that this would be an area of inspection in the future.
b.
(Closed) IFI 50-416/91-19-01:
Implementation of Administrative Controls for Labeling Requirements for the Containers of Dried Sewage Sludge.
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The inspector reviewed the following procedure.
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SP-R-14, Environmental Surveillance Program Section
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Procedure, Containerized Liquids, Soil, and Sludge Sample
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Collection
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r The procedure directly addresses the sampling, analysis, and
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subsequent labeling of not only tha sewage sludge type sample-but
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several other forms as well. The procrie appears to address-the issue identified in the IFI noted and therefore the item is
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closed.
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(Closed) IFI 50-416/92-17-01:
Evaluation of the Turbine Building i
roof hatch unmonitored pathway with respect to 10 CFR 20.201.
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The licensee had previously submitted to the NRC all the necessary l
information concerning this issue. The Regional office has asked
for a decision by NRR concerning whether this constitutes a
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generic issue at this and other Boiling Water Reactors (BWRS). The
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licensee sias also noted the fact that this issue is being reviewed by the NRC in their Semiannual Effluent Release Report (SERR). For i
these reasons the item is administratively closed and will l
subsequently be reviewed as further information is received.
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Exit Interview
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The inspection scope and results were summarized on April 23, 1993, with
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those persons indicated in Paragraph 1.
The inspector described the l
areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard. to documents i
and/or processes reviewed during the inspection. The licensee did not
identify any such documents or processes as proprietary.
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Acronyms and Initialisms I
AA - Atomic Absorption ANSI - American National Standards Institute, Inc.
cfm - cubic feet per minute CFR - Code of Federal Regulations
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Ci - curie
DOT - Department of Transportation FSAR - Final Safety Analysis Report GGNS - Grand Gulf Nuclear Station kg - kilogram LER - Licensee Event Report j
NRC - Nuclear Regulatory Commission i
ODCM - Off-site Dose Calculation Manual
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pCi - pico-Curie (1.0E-12 Ci)
QA - Quality Assurance REMP - Radiological Environmental Monitoring Program RETS - Radiological Environmental Technical Specification
SGTS - Standby Gas Treatment System i
TS - Technical Specification uS/cm - Micro Siemens
UV - ultraviolet
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VIO - Violation
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