ML20214N723
| ML20214N723 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/15/1987 |
| From: | Murray B, Nicholas J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20214N711 | List: |
| References | |
| 50-458-87-11, NUDOCS 8706030031 | |
| Download: ML20214N723 (7) | |
See also: IR 05000458/1987011
Text
{{#Wiki_filter:s . . - APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION REGION IV ' NRC Ir spection Report: 50-458/87-11 License: NPF-47 Docket: 50-458 Licensee: Gulf States Utilities (GSU) P. O. Box 220 St. Francisville, Louisiville 70775 Facility Name: River Bend Station (RBS) Inspection At: River Bend Station, St. Francisville, Louisiana Inspection Conducted: April 13-17, 1987 Inspector: d4 [[/ldZd_ 8/87 m J. B. Nicholas', Senior Radiation Specialist Date ' gg/LFacilities Radiological Protection Section Approyed: f/ fio )llUs$lLTV) $f/$fhl '~ B.~ MUrr'ay, ~ Chief, Fac lities Radiological D' ate' Protection Section Inspection Summary Inspection Conducted April 13-17, 1987 (Report 50-458/87-11) Areas Inspected: Routine, unannounced inspection of the licensee's liquid and gaseous radioactive waste management programs, including organization and management controls, training and qualifications, radioactive waste effluent releases, records and reports of radioactive effluents, radioactive waste effluent release procedures, effluert monitoring instrumentation, air. cleaning systems, reactor coolant and secondary water quality, quality control of analytical measurements, and quality assurance (QA) program. Results: Within the areas inspected, one violation was identified (failure to use ODCM parameters to project liquid radwaste doses, paragraph 6). No deviations were identified. " 8706030031 870529 PDR ADOCK 05000458 G PDR ,
- . .- - - . . - .- , a s.... 2 DETAILS 1. Persons Contacted
GSU . l
- J. C. Deddens, Senior Vice President, RBS Nuclear Group
- T. F. Plunkett, Plant Manager
- D. L. Andrews, Director, Nuclear Training
- E. M. Cargill, Supervisor,. Radiological Programs
- J. W. Cook, Lead Environmental Analyst, Licensing
J. D. Davis, Senior QA Engineer
- R. G. Easlick, Supervisor, Radwaste
W. F. Eisele, Radiological Health Supervisor P. E. Franklin, Radwaste Operator
- K
J. Giadrosich, Supervisor, Operations Quality Control (QC)
- E. R. Grant,- Director, Nuclear Licensing
- R. W. Helmick, Director, Projects
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- K
C. Hodges, Chemistry Supervisor
- R. E. Horn, Nuclear Training Coordinator, Technical
' D. G. Looney, Radwaste Foreman
- I. M. Malik, Supervisor, Quality Systems
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- C. L. Nash, Supervisor, Technical Support
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- W. H. Odell, Manager, Administration
- E. R. Oswood, Lead Senior QA Engineer
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- R. R. Smith, Licensing Engineer
J. E. Spivey, QA Engineer '
Others I
- D. D. Chamberlain, NRC Senior Resident Inspector
- W. B. Jones, NRC Resident Inspector
4
- Denotes those present during the exit interview on April 16, 1987.
2. Followup on Previous Inspection Findings (Closed) Violation (458/8601-01): Failure to Use Offsite Dose Calculation Manual (0DCM) Alarm Setpoints - This violation was discussed in NRC. Inspection Report 50-458/86-01 and involved the use of an incorrect setpoint in the Main Plant Exhaust Radiation Monitor IRMS-RE126. The setpoint established by Stone and Webster. Engineering Corporation calculated on the design basis rather than the more conservative 0DCM methodologies was inadvertently loaded into the RM-80 data base'during'the
performance of Surveillance Test Procedure ~(STP)-511-4231 on January 16, 1986. The NRC inspector reviewed the licensee's corrective actions regarding this violation. The NRC inspector verified that the licensee- had issued Plant Engineering Procedure (PEP)-0028, "DRMS RM-80 Data Base 4 Management," which establishes the acceptable data base for all radiation !
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__. , n. . 3 monitor setpoints. The licensee had revised applicable STP's to reference PEP-0028 as the source document for the RM-80 data base. This violation is considered closed. (Closed) Deviation (458/8601-02): Failure to Maintain Emergency Response Equipment - This deviation was discussed in NRC Inspection Report 50-458/86-01 and involved the licensee's failure to maintain emergency equipment and supplies in the main control room, operations support center, and emergency operations facility as committed to in the Final Safety Analysis Report (FSAR). The NRC inspector reviewed the licensee's corrective actions contained in their May 2, 1986, response and verified that emergency kit deficiencies had been corrected; FSAR, Chapter 13.3, Appendix E, equipment inventory lists and Emergency Implementing Procedure (EIP)-2-103, Revision 2, dated October 1, 1986, equipment inventory lists were in agreement; and that emergency kit inventories were being performed within 48 hours following an emergency drill or exercise. This deviation is considered closed. 3. Followup on Licensee Event Report (Closed) Licensee Event Report (458/87-001): Missed Technical . Specification Sample Collection on Main Plant Exhaust Radiation Monitor and Fuel Building Exhaust Radiation Monitor - This item involved the isolation of the particulate and iodine samplers (Main Plant Exhaust Radiation Monitor, RMS-RE125 and Fuel Building Exhaust Radiation Monitor, RMS-RE5A) for greater than 8 hours without an alternate means of stack sampling and monitoring in-service. Auxiliary sampling equipment for particulates and iodines was not placed in-service within the 8 hour time period allowed by the Technical Specification action statement to supplement the continuous monitoring requirement. The cause for the missed alternate sampling was due to operations failing to notify the chemistry department prior to changing the monitor samples alignments. The NRC inspector reviewed the licensee's corrective actions, including: (1) an " operator aid" which is attached to the front of each digital radiation monitoring system monitor next to the sample selection function switch in the main control room, and (2) a memorandum issued by the operations supervisor to all operations section personnel stating the requirement to notify the chemistry department prior to changing any radiation monitor sample alignments. The NRC inspector verified .that the " operator aids" were posted on the front of each radiation monitor next to the sample function switch in the main control room. This item is . considered closed. 4. Inspector Observations The'following is an observation the NRC inspector discussed with the licensee during the exit interview on April 16, 1987. This observation is not a violation, deviation, unresolved item, or open item. The observation was identified for licensee consideration for program improvement, but the observation has no specific regulatory requirement. The licensae stated that the observation would be reviewed. - L
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s 4- Liquid Effluent Isolation Valve Testing - The licensee k liquid effluent release procedures-do not require the testing of liquid effluent isolation- l- valves before each release by initiating an isolation signal through the. ', ' l.- alarm / trip setpoint of the controllinc/ radiation monitor. m .f s 5. Program Areas Inspected i The following program areas were inspected. 'Unless otherwise noted, the f inspection was completed and revealed no vjolations, deviatiqns, unresolved items, or open items. Notations after a specific inspection itervare used to identify the following: I = item not-inspected or only partially inspected; V = violation; D = deviation; U = unresolved item; . and G = open item.
Inspection Procedure knspectionRequirements ' 83722 Organization and Management , _ Controls 02.01 Organization - I 02.02 Staffing - I , 02.03 Radiatio Protection Manager - I 02.04 Idantification and Correction of , , Program Weaknesses - I 02.05 Audits and Appraisal - I _ 83522- Organization and Management Controls i 02.01 Organization, Responsibilities, and Authorities - I - 02.02 Staffing - I 02.03 Identification.and Correction of Weaknesses.- I. 02.04 Audits and Appraisals - I 02.05 Communication to Employees - I 02.06 Documentation'and. Implementation - I 83723 Training and Qualifications 02.01 Adequacy of Training - I 02.02 Employee Knowledge - I 02.03 Transportation /Radwaste Training - I i .f'. 02.04 Qualification Requirements - I .. 02.05 New Employees -'I 02.06 INPO Accreditation - I .) 02.07 ' Audits and Appraisals - I' j 02.08 Training not Covered by INP0 - I l , . . S .} f* , l .y -
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5. ~ .83523 Training-and Qualifications ~ ' 02.01 Training an'd Qualification Program .I^ 02.02 Education and Experience 'I 02.03 Adequacy and Quality of Training - I 84723 Liquid Radioactive Wastes 02.01 Audits and. Appraisals- 02.02 Program Changes ~- V-(see' paragraph 6)- 02.03 Effluents 02.04 Instrumentation --I 84523 -Liquid Radioactive Waste 02.01 Construction and Installation of Liquid Waste-SystemL 02.02 Liquid Leakage, .0verflow, and Spillage 02.03 Sampling 02.04 Preoperational Test-Program 02.05 Completion ~of Preoperational Test Program 02.06 Installation, Calibration, and Testing of Process Monitors - I- 02.07 Procedures 02.08 Disposition of Low-Level Wastes 84724 Gaseous Radioactive Wastes 02.01 /udits and Appraisals 02.02- Program Changes 02.03 Effluents 02.04 Instrumentation - I 02.05 Air Cleaning Systems - I 84524 Gaseous Radioactive Waste 02.01 Construction and Installation of Gaseous Waste System 02 02 Sampling 02.03 Preoperational Test Program 02.04 Completion of Preoperational Test Program 02.05 Installation, -Calibration, and .Tc-sting of Process Monitors - I 02.06 Procedures ' -- . - . _
. _ _ - _ - _ _ _ , 8 * . e. 6 , 6. Violation
84723, Item 02.02 - Offsite Dose Calculation Manual (ODCM) Dose Calculations On April 15, 1987, the NRC inspector noted that the calculation methodology in.the ODCM for' projecting dose for radioactive liquid ~ effluents during a 31-day period had been changed to use the number of hours in the 31-day period during which releases were performed rather than whole days. The calculational methodology is more conservative ~and the results of the projected doses approaches the technical specification ~ limits of 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day- period much' sooner than the calculations using whole days of release. If these limits appear to be exceeded by the projected doses, the Technical Specification 3/4.11.1.3 requires that'the liquid radwaste treatment system be used to reduce the radioactive materials in the liquid radwaste - priorito their discharge. Further investigation showed that the calculational methed used in the Surveillance Test Procedure (STP)-511-8208, " Projection of Dose from Liquid Releases to Unrestricted' Areas," Revision 3, dated July 25, 1985, had not been changed to match the revised more conservative calculational methodology in the-0DCM. It was noted by comparison of the results of the two calculational methods since July 1986, when the ODCM method was revised, through March 1987, that the new calculational method resulted in the projected doses from liquid radioactive effluents to exceed the technical specification for total body in July 1986, and October 1986, and to exceed the dose limit organ in - . November 1986, and January 1987 as compared to the old method which indicated that the results were below the technical specification limits. ' The failure to project doses due to liquid releases to unrestrictedLareas , in accordance with methodologies and parameters in the ODCM is an apparent- violation of Technical Specification 3/4.11.1.3. (458/8711-01) ~ 7. Exit Interview- The NRC inspector met with the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on April 16, 1987. The NRC inspector summarized the scope of the . inspection and discussed the inspection findings, i- i - - - - , -,- g }}