IR 05000395/1987035

Insp Rept 50-395/87-35 on 871207-11.No Violations or Deviations Noted.Major Areas Inspected:Liquid & Gaseous Effluents & Gathering of Data on Collocated Licensee & NRC Environ TLDs

ML20149E183
Person / Time
Site:	Summer
Issue date:	01/06/1988
From:	Kahle J, Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20149E170	List: IR 05000395/1987035 ML20149E168
References
50-395-87-35, NUDOCS 8802100371
Download: ML20149E183 (7)

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RUCLEAR REGULATORY COMMisslON

[ o REGION 11 g ,j 101 MARIETTA STREET, *I 's ATL ANTA, G EORGI A 30323

9 * * * * * ,o IAki i 210Q4 Report No.: 50-395/87-35 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.: '50-395 License No.: NPF-12 Facility Name: Summer Inspection Conducted: December 7 - } 1, 1987 Inspector: , [.

R. R. Mar'sto '

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/!I Date Signed Approved by: . (ald '

_ //L N e D4 te / Signed J.B.Kay'ca,SectionChief~

Radiolog Effluents and Chemistry Division o Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection was conducted in the areas of liquid and gaseous effluents and gathering of data on collocated licensee and NRC environmental TLD Results: No violations or deviations were identified.

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REPORT DETAILS Persons Contacted Licensee Employees

• F. Bacon, Associate Manager, Chemistry

• W. Baehr, Manager, Corporate Health Physics and Environmental Progrh, G. Baker, Maintenance Engineer

• D. Blanks, Licensing Engineer

• L. Blue, Manager, Support Services 0. Bradham, Director Nuclear Plant Operations

• M. Browne, Group Manager, Technical and Support Services

• J. Cox, Associate Manager, Health Physics A. Cribb, Jr. , Plant Chemist G. Guy, Radwaste Coordinator

• Higgins, Associate Manager, Regulatory Compliance V. Prawdzik, Instrumentation and Control Coordinator J. Sowell, Health Physics Supervisor

• R. Sweat, QA Surveillance Specialist

• Williams, Group Manager, Nuclear Regulatory and Developmental Services NRC Resident Inspectors

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R. Prevatte, Senior Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on December 11, 1987, '

with those persons indicated in paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the license The inspector stated that Violation 395/87-21-01 (described in paragraph 3) was closed and IFI T2500/22 (described in paragraph 11) was i close j l

The licensee did not identify as proprietary any of the materi:als provided

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to or reviewed by the inspectors during this inspection. Licensee Action on Previous Enforcement Matters (Closed) Violation 395/87-21-01; Failure to verify the volume of the geometry used to determine airborne radioactivity concentrations which resulted in inaccurate ganna spectroscopy measurements, i

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During the confirmatory measurements inspection -(87-21), the inspector noted that the licensee used 1000 ml as the volume for the "one liter gas marinelli" used in gamma spectroscopy. In response to this violation, the licensee comitted by letter dated September 1987, to verify the volumes (and had already done so) of the 25 ml and 1000 ml gaseous geometries. A further comitment was made to revise the applicable sampling procedures (HPP-808 and HPP-810) to include the requirements that actual volumes of gaseous volumes be determine The inspector reviewed documentation showing that the above volumes were verified to be 26 ml and 1260 m1, respectively, and that the one liter liquid marinelli (used for grab samples of gases) was approximately 1200 ml. Audits (80721, 84723, 84724, 84725)

Technical Specification 6.5.2.8 requires audits of the radiological environmental monitoring program at least once per 12 months; the Offsite Dose Calculation Manual (0DCM) and implementing procedures at least once each 24 months; the Process Control Program (PCP) and implementing proce-dures at least once each 24 months; and the conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 month The inspector reviewed the following audits and surveillances: 03-RMB-87-R, "Mechanical Filter Changeout and Leak Testing of the Duratek EVR System," conducted November 17, 1987; II-AEC-87-X, "Station Procurement,"

conducted September 4-11, 1987 (this audit documented circumstances leading to receipt, installation, and operation of a Portable Radwaste Ion Exchange system provided by Duratek Corporation); and II-5-87-R,

"Radioactive Waste," conducted February 16 to March 9, 198 The inspector also discussed Audit Il-20-87-M, "Environmental Monitoring and TLD Processing, conducted October 21 to November 10, 1987, with cognizant licensee representatives. This audit report had not yet been issue The inspector's review of the contents of the audit packages indicated that the audits were thorough and in depth. Responses to findings and corrective actions appeared to be appropriate and timel No violations or deviations were identified. Changes to Equipment and Procedures (84723, 84724)

Technical Specification 6.15.1.1 requires that major changes to radio-active liquid and gaseous waste treatment systems shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the Plant Safety Review Comittee. Technical Specification 6.8.1 requires that the l' ansee establish, implement, and maintain written procedures concerning those subjects recomended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978; Process Control Program; Offsite Dose Calculation Manual; and effluent and a

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environmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 197 Licensee representatives stated that no changes had been made in organiza-tion pertaining to the radwaste program since the previous inspectio Licensee representatives stated that a Duratek demineralization system had been installed to clean up part of the liquid radwaste stream. The installation was temporary, with the t ave to a permanent location ,

dependent on preliminary operational findings. Licensee representatives stated that the system would be operated by plant personnel and operated in accordance with plant procedures adapted from vendor procedures. The inspector examined the unit installation during a tour of the plan Licensee representatives stated that a new ganina spec. unit had been installed, replacing an older uni The inspector selectively reviewed several procedures which had been revised since the previous inspection. The procedures were Health Physics and Chemistry procedures pertaining to effluent sampling and analysis, and operation and calibration of the equipment used in these processes; Surveillance Test Procedures in the 360.xxx series, used for calibration and test of effluent monitors and flow measurement instruments, Surveillance Test Procedures in the 554.xxx and 555.xxx series which describe HEPA filter and charcoal adsorber tests on the Control Room Emergency Air Cleanup System and effluent pathway cleanup system No violations or deviations were identified. Semi-Annual Report (84723, 84724)

Technical Specification 6.9.1.8 requires the licensee to submit routine radioactive effluent release reports within 60 days after January 1 and July 1 of each yea Technical Specification 6.9.1.9 requires that the radioactive effluent release reports inc~iude 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 fonnat of Appendix B thereo The inspector reviewed the semi-annual radiological effluent report dated August 24, 1987, and concerning the period from January 1 through June 30, 1987. The report appeared to comply with the Technical Specifications in format and content. No significant trends were noted. One abnormal liquid release was reported as occurring in February 1987. Approximately 4.7 microcuries were released, primarily Co-58 and Co-6 The leak was apparently confined to soil in the protected are The licensee performed calculations assuming a worst case release to the Broad l Rive The calculations showed a negligible dose to a maximum exposed l individual at the exclusion boundary, i

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On the basis of the report discussed above and the inspector's review of selected liquid gaseous effluent release permits, the effluents were within the limits of Technical Specifications and 10 CFR Part 50, Appendix I design objective ,

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No violations or deviations were identifie . Radioactive Liquid Waste (84723)

Technical Specification 3.11.1.1 establishes the limits for concentrations of radioactive materials in liquid effluent Technical Specification 3.11.1.2 requires the licensee to limit the dose or dose commitment to an individual from radioactive materials in liquid effluent releases, i The inspector reviewed liquid radwaste release permits for the period from April 1 through November 30, 1987. The releases and calculations appeared to have been done in accordance with the, Technical Specifications and the ODC The records indicated that concentration and dose limits had not been exceede No violations or deviations were identified.

. Radioactive Gaseous Waste (84724)

Technical Specification 3.11.2.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to: For noble gases: less than or equal to 500 mrem / year to the total body and less than an equal to 3000 mrem / year to the skin, and For radioiodines and for all radioactive materials in particulate fonn and radionuclides (other than noble gases) with half lives greater than eight days: less than or equal to 1500 mrem / year to any orga Technical Specification 3.11.2.2 requires that the air dose due to noble gases released in gaseous effluents to areas at or beyond the site boundary shall be limited to: During any calendar quarter: less than or equal to five mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and During any calendar year: less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiatio Technical Specification 3.11.2.3 requires that the dose to a member of the '

public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than eight days in gaseous

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effluents released from each reactor to areas at or beyond the site boundary shall be limited to: During any calendar quarter: less than or equal to 7.5 mrems to any organ, and During any calendar year: less than or equal to 15 mrems in any orga The inspector reviewed selected records for the period of January through November 1987 and determined that the calculated doses were within Technical Specification limit No violations or deviations were identified. Testing of Air Cleaning Filtration Systems (84724)

Technical Specifications 3/4.7.6 and 3/4.9.11 list the requirements for the Control Room Normal and Emergency Air Handling System and the Spent Fuel Pool Ventilation System, respectivel The inspector reviewed the results of leak testing of HEPA filters and charcoal adsorber beds conducted since the last inspection. The inspector verified that the surveilltnce requirements were me No violations or deviations were identified.

10. Effluent Radiological Monitoring and Analysis Instrumentation (84723, 84724)

Technical Specification Tables 4.3-8 and 4.3-9 provide surveillance for l liquid effluent and gaseous effluent monitoring instrumentation i respectivel The inspector reviewed selected completed Surveillance Test Procedures and verified that the surveillance tests had been performed at prescribed interval The inspector toured the plant, accompanied by a cognizant licensee representative. The inspector noted the installation, configuration, and cleanliness of the gaseous and liquid effluent monitor Licensee representatives stated that a gas calibration standard had been l received and gas calibrations had been performed on the gamma i spectroscopic systems since the last inspection (87-21). l The inspector reviewed the licensee's source certificate for the Mixed Gama Emitting Gas Standard and the Gas Transfer Accountability Certificate. The inspector also reviewed the calibration and weekly QC and background check records for the gama spec. systems for the period from July 1987 through November 198 !

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The inspector reviewed the following Health Physics Procedures:

HPP-812, Operation and Calibration of the ND-66/HP-9845 Ge(Li)

Spectroscopy System, and HPP-813, Quality Control of the ND-66/HP-9845 Ge(Li) Spectroscopy Syste The inspector determined that the systems had been operated, calibrated, and tested / checked in accordance with Technical Specifications and procedure No violations or deviations were identifie . Collocated Environmental TLDs (TI 2500/22)

The inspector discussed the environmental TLD program with licensee representatives and gathered the data specified in the instruction. The inspector also visited six sites where NRC and licensee environmental TLDs were collocate (Closed) IFI 395/T2500/22 is close No violations or deviations were identifie . Contaminated Sludge (84723)

The inspector discussed the licensee's proposed application of dewatered sludge from the sewage lagoon with licensee representative The inspector reviewed a letter from SCE&G to DHEC (State of South Carolina),

Subject: Virgil C. Summer Nuclear Station Land Application of Sludge, dated November 12, 1987. This letter was the cover for the application to the State for permission to spread the sludge on an area of licensee-owned i land and work it into the soi Licensee representatives stated that the sludge had been. removed from the lagoon and put in a lay down area. A 23-hour count showed detectable levels of Cobalt-60, Cesium-137, Cesium-134, and Uranium series. The licensee stated that the levels of the Cesiums and Uranium series was comparable to that in other environmental samples and was assumed to be ;

from previous atmospheric weapons tests and the Chernobyl inciden Pending approval from the State of South Carolina, the licensee plans to l spread the sludge in the soil in February 198 No violations of deviations were identifie !

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