IR 05000416/1987030
| ML20236U120 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/23/1987 |
| From: | Kahle J, Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20236U107 | List: |
| References | |
| 50-416-87-30, NUDOCS 8712020295 | |
| Download: ML20236U120 (6) | |
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UNITED STATES ps arcoq'o NUCLEAR REGULATORY COMMISSION
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[n REGION 11 y
,j 101 MARIETTA STREET, N.W.
's ATLANTA, GEORGI A 30323
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NOV 2 41987
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Report No.: 50-416/87-30 Licensee:
System Energy Resources, Inc.
Jackson, MS 39205 Docket No.: 50-416 License No.:
NPF-29 Facility Name: Grand Gulf Nuclear Station Inspection Conducted:
November 2-6, 1987
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Inspector:
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Date Signed R.Marqton Approved by:
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11/13/17 y( B. Kahle, Section Chief Dhte S'igned
[Div ion of Radiation Safety and Safeguards
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SlJMMARY Scope: This routine, unannounced inspection involved onsite and in-office inspection in the areas of liquid and gaseous effluent releases.
Results: Of the areas inspected, no violations or deviations were identified.
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8712O2029S 871124 PDR ADOCK 05000416 l
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l REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J.
E. Cross, Site Director
- R. Hutchinson, General Manager
- J. P. Dimmette, Jr., Manager - Plant Maintenance
- J. L. Robertson, Plant Licensing Superintendent
- W. R. Magee, Jr., Manager - Relay & Communications
- S. Feith, Director, Quality Programs
- J. G. Cesare, Director, Licensing
- K. Beatty, Training Superintendent
- F.
W. Titus, Director, NPE
- J. H. Mueller, Mechanical Superintendent
- G. O. Smith, Plant Chemist
- M. Lloyd, Nuclear Plant Systems Analyst
- P. M. Different, Plant Licensing Engineer J. M. Lassetter, HP/ Chemistry Specialist R. N. Buckley, Environmental Specialist J. P. Hinman, Engineer, Nuclear Plant Engineering D. F. Mahoney, Quality Programs Engineer R. Brinkman, Radiological Engineer B. Edwards, Mechanical Maintenance Engineer NRC Resident Inspectors
- R. C. Butcher, SRI J. Mathis, RI
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 6,1987, with those persons indicated in paragraph 1 above.
The licensee acknowledged the inspector's comments.
The licensee did not identify as-
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I proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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Audits (80721,84723,84724,84725)
Technical Specification 6.5.2.8 specifies the requirements for the audits I
that are to be performed under the cognizance of the Safety Review l
Committee.
The inspector reviewed the audits conducted since the last inspection. The following audits were included:
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- MAR 87/0020, Radioactive Gasenus Effluent Monitoring, conducted June 24 - July 17, 1987...This audit was identified as a limited scope audit to verify the written program and implementation of Regulatory Guide 4.15 policies regarding radioactive gaseous effluents.
Compliance was also evaluated to the criteria of Regulatory Guide -1.21 and the requirements of Technical Specification (T.S.) 3/4.11.2.1
MNRE 87/01, Radiological Environmental Monitoring, conducted January 26 - February 18, 1987.
This audit evaluated the program to the criteria of Reg Guide 4.15, and the requirements of 10 CFR 20, 10 CFR 71, 49 CFR 172, and 49 CFR 173. The audit included positive findings and a resume for the Technical Specialist on the Audit Team.
The audits appeared to be thorough and in depth.
Most of the findings were resolved during the audit period.
A licensee representative stated that an audit of the Liquid Radwaste Treatment System was in process and included evaluation to the requirements of Section 1.3 of the Offsite Dose Calculation Manual (0DCM).
No violations or deviations were identified.
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RadioactiveLiquidWaste(84723)
Technical Specification 3/4.11.1 establishes upper limits for concentrations of radioactive materials in liquid effluents.
The inspector selectively reviewed Liquid Radwaste Discharge Permits for the period July - September 1987.
Each permit was in six parts:
(1) Pre-Release Processing; (2') Pre-Release Analysis (including effluent monitor alarm setpoint f
calculation);
(3) Monitor Setpoint Calibration;
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(4) Release Authorization; I
(5) Release; and (6) Post-Release Analysis.
I The inspector determined from review of the permits and discussion with j
cognizant licensee personnel that the releases appeared to be conducted in J
accordance with Technical Specifications and implementing procedures and
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instructions.
The inspector also reviewed the results of the Radwaste l
Release Monthly Composite Analysis.
i No violations or deviations were identified.
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Radioactive Gaseous Waste (84724)
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Technical Specification 3/4.11.2 establishes. upper limitsfor-concentrations of radioactive materials in gaseous effluents.
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h inspector selectively reviewed Gaseous Radwaste Daily Logs for the period J i-from March 1987 through November 2,1987 for releases from the Radwaste
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Vent, Containment Vent, Turbine Bu'lding Vent, Fuel Handling. Area Vent, l
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and Standby Gas Treatment ' System..The records included'both annual and
'l quarterly neble gas beta and accrued gamma.. doses, maximum dose rates for j
both total body and skin, and showed comparison to annud limits.
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inspector's review of the Release Logs and discussions.mith cognizant licensee representatives-appeared to show that the program was conducted within Technical Specification and procedural limits.
l No violations or deviations were identified.
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Procedures (84723, 84724)
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l Technical Specification 6.8.1 requires in part, that written procedures.
- 1 shall be established, implemented and maintained covering the following'
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The applicable procedures recomended in Appendi:e "A" of Regulatory Guide 1.33, Revision 2, February 1978; Surveillance and test activities of safety related pquipment;
- Process Control' Program. implement'ation;
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Offsite Dose Calculation. Manual impipmentation; and
Quality' Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, February
.1978.
The inspector reviewed selected procedures and instructions in the Chemistry / Health Physics area and Maintenance procedures applicable to effluent filter and adsorber testing.
The procedures ' appeared to be arlequate to meet the requirements of the Technical Specifications.
No violations or deviations were identified.
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Radioactive Effluent Monitoring Instrumentation (84723,' 84/24)
Technical Specifications 3/4.3.7.1 establishes the min 1mym operability and surveillance for radioactive liquid and gaseous process and effluent stream monitoring instrumentation.
Surveillance of counting room coenting equipment is specified in appropriate procedures.
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The inspector reviewed a selection of calibration records for plant i
effluent monitors. The records showed that the Maintenance Instrument and l
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- t Control Group calibrated tne. Containment Ventilation Accident Range j
Monitor on October 14,1987i,tna Accident Range Monitors for both trains
of the Standby Gas Treatment System on December 9,1986; the Fuel Handling l
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. Area Gaseous Monitor was calibrater. in Na/ and July,1987; the Containment
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Building Ventilation Gaseous Monitor wah calibrated on July 10, 1987; and j-the Ofdgas Post Treatment Exhaust Gaseous Isotopic Monitor was calibrated
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The inspector examir.3d calibration records for count room instrumentation, l
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Spectroscopy systema, one Packari Tricarb Liquid Scintillation system, and
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two VC11T Gas Proportional systsas. i licensee representative stated that l
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another Hriie Gamma Spec systempas ma?ntained in the Chemistry Hot Lab.
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Records showed that the lab countingsystems were in current calibration, j
A visual display was maintained at e'n% Gamma Spec system showing the i
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No violations er deviations wert ' identified c
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l Air Cleanirg Systems (b724)
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The ' ins.)ector 'rev/ewed records of HEPA, filter ano adsorber leak testing on effluerit clennup Nystems.
The records 'showed that a vendor tested the following systaas in March 1987:
Radwaste su:1 ding Exhaust (HEPA> inly)
Radwaste Storage Tanks Ventitetion;
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ContainmentdoolingSystem;
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StandbyGasTreatmentSyptems;
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- lurdine Building Charcou and filter Trairit; and
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\\h Offgas Treatment Syster..s (HEPA 011y).'
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No violations or deviations were identified
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10. ' Post Accident Sarpiing System (PASS) (84723, 84724)
- The inspector discussed the PASS with a cognizant licensee representative.
The licensee representative stated that no changes had taken place in the
PAS 3 since the last inspection in this area, but several changes were i
planned during the upraing outage.
The licensee representative stated
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that inline ch t) ride Mysis (Coonnt) and Hydrogen analysis (Containment and drywell atmosphee) suculd be eleted, e well as the gas stripper
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(coolant) and radiclogicci analyzers.
Tasa parameters will be evaluated 3j ~ laboratory analysit of grab samples.
A new containment and drywell
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ifitmosp31ere sample control N oel'will be installed.
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No violations or deviations were identified.
11. TI-2500/22 (25022)
l The purpose of this Temporary Instruction is to provide for collection of licensee environmental TLD measurement results from monitoring locations collocated with NRC TLD monitoring locations.
This information was
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obtained by the inspector.
Tnerefore, Inspector Followup Item (IFI)
50-416/T2500/22, collection of collocated TLD measurement results, is j
closed.
12. Semiannual Radioactive Effluent Release Reports (84723, 84724)
Technical Specification 6.9.1.8 requires that routine radioactive release J
reports covering the operation of the unit during the previous 6 months of
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operation shall be submitted within 60 days after January 1 and July 1 of q
each year.
Technical Specification 6.9.1.9 requires that the radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June.1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Technical Specification includes further requirements regarding the content and format of the report.
i The inspector reviewed the report for the period January 1 - June 30, 1987.
The report was transmitted within the 60 day period after June 30 and included all elements specified in Appendix B to Regulatory Guide 1.21 and the Technical Specification.
l The inspector reviewed the releases for the semiannual period and compared them to releases from previous years.
Results were generally consistent until the report for the first half of this calendar year, which showed an upward trend.
A licensee representative stated that he believed this was due to a fuel leak which was detected during the period.
No violations or deviations were identified.
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