IR 05000369/1987013
| ML20214T575 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/28/1987 |
| From: | Adamovitz S, Gloersen W, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20214T555 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 50-369-87-13, 50-370-87-13, IEIN-86-042, IEIN-86-076, IEIN-86-42, IEIN-86-76, NUDOCS 8706100324 | |
| Preceding documents: |
|
| Download: ML20214T575 (13) | |
Text
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>S RES UNITED STATES r
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o NUCLEAR REGULATORY COMMISSION '
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Report Nos.:
50-369/87-13 and 50-370/87-13
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Licensee: Duke Power Company l
422 South Church Street
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Charlotte, NC 28242
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Docket Nos.
50-369 and 50-370 License Nos:
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Facility Name: McGuire Nuclear Station
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j Inspection Conducted:
May 11-15, 1987
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g Inspector: h Q.
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! 'Ghersdn Dat6 Signed
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//Sh7 S. S. Adamovitz j
Date gned'
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j Approved by:, 2) b t%.[w M/4 <, 2 7. / 997
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R 8. Kahle, Sec4. ton Chief Date/ Signed'
j Division of Radiation Safety and Safeguards
SUMMARY
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Scope: This routine, unannounced inspection involved an examination onsite in i
i the areas of previously-identified enforcement items, inspector followup items,
TMI itemt, liquid and gaseous radwaste.
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Results: One unresolved item was identified.
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G706100324 070601
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PDR ADOCK 05000369
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- D. J. Rains, Superintendent of Maintenance (Acting Plant Manager)
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- B. H. Hamilton, Superintendent of Technical Services
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- E. O. McCraw, Compliance Engineer
- S. E. LeRoy, Licensing, General Office
- J.
Foster, Station Health Physicist
- W. M. Funderburke, Station Chemist
- N. G. Atherton, Compliance
- R. A. Johanson, Test Engineer
- W. F. Byrum, Sciences Supervisor, Health Physics R. S. Jones, Subunit Supervisor, Radiological Projects D. L. Cline, Radwaste Chemistry Coordinator H. Sloan, Production Health Physicist M. E. Bridges, General Supervisor, Power Chemistry R. M. Pope, Assistant Shift Supervisor
- G. E. Singletary, Nuclear Production Engineer T. D. Henrickson, Chemistry Supervisor NRC Resident Inspectors
- W. Orders
- S. Guenther
- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on May 15, 1987, with
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those persons indicated in Paragraph 1 above. The inspector described the
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areas inspected and discussed in detail the inspection findings listed below. During the exit meeting a verbal commitment was made to address
the concerns regarding the sampling and analysis requirements of NUREG-0737, item II.F.1, Attachment 2 (see Paragraphs 3 and 9).
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licensee did not identify as proprietary any of the material provided to or reviewed by the inspectors during this inspection.
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3.
Unresolved Items j
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Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviations. One new unresolved item was identified during this inspection and is discussed in Paragraph 9.
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4 The unresolved item was concerned with TMI/NUREG-0737, Item II.F.1, Attachment 2, Sampling and Analysis of Plant Effluents.
During the exit meeting and during a telephone conversation on May 19, 1987, it was confirmed that the licensee will submit within 90 days from the transmittal date of this inspection report to the NRC Region II office a response to the concerns regarding the sampling and analysis requirements specified in NUREG-0737, Item II.F. 1, Attachment 2.
4.
Licensee Actions on Previously Identified Enforcement Matters (92702)
i (Closed) Violation, 50-370/84-07-06:
Reactor Coolant PASS did not meet i
NUREG-0737 Criteria.
The inspectors reviewed the modifications that were
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made on the PASS for both Units 1 and 2.
Modifications were performed first on Unit 1 as documented in a letter from H. B. Tucker (DPCo) to J. P. O'Reilly (NRC) dated November 2, 1984.
The applicable Unit 1 modifications were incorporated into the Unit 2 PASS during the latter part of 1985 when the system was considered operable.
Overall the licensee has demonstrated that the PASS was capable of collecting and analyzing representative reactor coolant samples (except for oxygen, which is recommended by NUREG-0737 and not a requirement).
This item is considered closed.
(Closed) Deviation, 50-370/85-32-01: VA filter testing not performed per ESAR Section 9.4.2.3 and Regulatory Guide 1.52.
The inspectors reviewed the formal response written by the licensee in response to the deviation cited above.
The licensee conducted air-flow distribution tests in accordance with ANSI N510-1980 under the NRC/RII Confirmation of Action letter dated October 23, 1985, with results transmitted to the NRC in a letter from H. B. Tucker dated October 28, 1985. In a conference call on November 1,1985, the NRC indicated that the review of the test results were complete and acceptable. The licensee indicated that the FSAR would be updated to reflect system te: ting in the next annual update. This item is considered closed.
(Closed) Deviation, 50-369/85-39-01 and 50-370/85-40-01:
Failure to conduct the air-aerosol uniformity mixing tests as required by FSAR Commitments for the Control Room ventilation systems.
The inspectors reviewed the licensee's supplemental response to the deviation as documented in a letter dated March 27, 1986, frcm H. B. Tucker to the NRC.
The supplemental response indicated that additional preoperational tests will be required only in the event of system modification.
The response described how Nuclear Station modifications are initiated, approved, and implemented. Post modification testing was also described, which is the phase where appropriate FSAR commitments are identified and the tests devised to demonstrate compliance with applicable standards. The licensee indicated that the administrative controls involving the review of modifications by personnel familiar with the FSAR commitments and applicable codes would avoid future deviations involving the ventilation system preoperational testing.
The inspectors had no further questions.
This item is considered closed.
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(Closed) Violation, 50-369, 370/86-32-01: Failure to follow MNS operating procedures for radiological effluent sample analyses prior to realignment from radiological to nonradiological discharge pathways.
The inspectors reviewed McGuire Action Item Completion Packages 1601-032 AI (completed January 19,1987)
and 1601-032 FI (completed February 3, 1987).
Corrective actions included counseling of all involved personnel and modifying the procedure OP/B/6400/01A, Condenser Circulating Water and Low Level Intake, to require Health Physics permission prior to system realignment.
The inspectors verified that the procedural modifications had been completed for Units 1 and 2, and reviewed selected completed work sheets for HP sign-off verification.
This item is considered closed.
(Closed)
Violation, 50-369, 370/86-32-02:
Failure to complete 10 CFR 50.59 review to properly evaluate functional changes to a MNS auxiliary building laboratory.
Duke Power denied that an initial 10 CFR 50.59 review was required for a laboratory name change but acknowledged that a 10 CFR 50.59 review was not completed once radioactive contamination was discovered in a nonradiological system.
Subsequent licensee investigations identified the source of the contamination as a laboratory sink in Room 954. The inspectors reviewed McGuire Action Item Completion Packages 1601-032 BI (completed January 28, 1987) and
1601-032 GI (completion due date May 13, 1987) and verified licensee corrective actions. The licensee had performed an audit of the floor and sink drain system and identified 9 additional drains which empty to the i
waste treatment (WT) system or into the groundwater sump system.
The inspectors with cognizant licensee representatives toured selected laboratories and plant areas and verified that the sink drain in Room 954
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had been rendered inoperable and that signs prohibiting the dumping of radioactive material had been posted near the appropriate drains.
The procedure PT/0/B/4700/13, Radwaste Chemistry Monthly Inspection for System Leakage and Cleanliness (for) NUREG-0578 Compliance, Rev. 7, May 8,1987,
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had been revised to include surveillance of the 9 additional drains, and the monthly surveillance had been initiated for May 1987. The inspectors reviewed the subsequent 50.59 review of the incident, McGuire Nuclear i
Station Safety Evaluation of Potential Uncontrolled Release of Sewage Sludge, November 20, 1986, and verified Section 3.5.5 of the Chemistry Manual had been revised to require a 50.59 report if radioactive material was found in a non-radioactive system.
This item is considered closed.
(Closed) Violation 50-369, 370/86-32-03:
Inadequate surveys for release
of radioactive effluents through the MNS domestic wastewater (WT) system.
l The inspectors reviewed McGuire Action Item Completion Package 1601-032 CI l
(completed January 12, 1987) and verified that Section 3.5.5 of the McGuire Nuclear Station Chemistry Manual, Rev.
4, January 9, 1987, i
required tritium, gross beta, and gamma isotopic analyses of the WT system samples.
The inspectors also reviewed " Liquid Sample Counting Results" for January-May 1987 and determined that the analyses of the WT system samples had been completed as required.
This item is considered closed.
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(Closed)
Violation 50-369, 370/86-32-08:
Inadequate 1985 annual radiological monitoring reports.
This item dealt with the failure to include a comparison of the results of the radiological environmental
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surveillance data for the 1985 reporting period with preoperational studies. The inspectors reviewed the McGuire Nuclear Station 1986 Annual Radiological Environmental Operating Report and noted a marked improvement. The report provided information on trends and anomalous data and environmental isotopic results were graphed for calendar year 1979 to 1986. The report also discussed doses from environmental measurements and compared them to doses from plant releases.
This item is considered closed.
(0 pen) Violation 50-369, 370/87-01-01: Failure to conduct adequate Fe-55 analyses for liquid effluent release measurements.
The inspectors reviewed McGuire Action Item Completion Packages 1701-0011 and 2701-0011 (completed March 5, 1987).
The licensee had utilized a contract laboratory to perform the Fe-55 analyses and subsequent to the violation, a second contract laboratory was evaluated by Duke Power. The inspectors
reviewed an internal company memo to C. A. Robinson, QA Manager, Vendors Division prepared by M. Greir, Nuclear Production Engineer, Subject:
Technical Review of SAIC's Fe-55 Analysis, dated February 24, 1987.
In addition to the onsite audit, the vendor lab had successfully analysed two
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sets of blind spikes, totalling six separate samples for Fe-55.
McGuire initiated the use of this second laboratory March 10, 1987, for all Fe-55 analyses. This item will remain open pending acceptable Fe-55 analysis of the next NRC confirmatory measurements spiked sample.
5.
Audits (84723, 84724)
Technical Specification (TS) 6.5.2.9 states audits of unit activities shall be performed under the cognizance of the Nuclear Safety Review Board (NSRB) encompassing conformance of unit operation to provisions contained within the TSs and applicable license conditions at least once per 12 months; the Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; the Offsite Dose Calculation Manual and implementing procedure at least once per 24 months; and the performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
The inspectors reviewed the following audit reports:
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Surveillance Report, Topic:
Health Physics, Waste Disposal, MC-86-64, November 14-December 9, 1986 b.
Surveillance Report, Topic:
Health Physics, Waste Disposal, MC-85-60, October 1-10, 1985 c.
Departmental Audit, NP-87-05 (MC), Health Physics, Environmental l
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Monitoring, and Radwaste, February 23, 1987-March 23, 1987 l
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The inspectors noted that the radwaste program, environmental program and health physics were audited against applicable sections of the Technical Specifications, station directives, applicable ANSI standards and regulatory guides. Any deficient or unresolved items identified in the audits were tracked by Regulatory Compliance and acted upon in a timely manner.
No violations or deviations were identified.
6.
Effluents (84723, 84724)
a.
Reports Technical Specification 6.9.1.7 requires the licensee to submit, within 60 days of January 1 and July 1 of each year, routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation. The reports shall include a summary of the quantities of radioactive materials released from the unit as outlined in Regulatory Guide 1.21.
Additionally, the reports that are submitted 60 days after January 1 of each year shall include an assessment of radiation doses from primary effluent
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pathways and direct radiation for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations.
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The inspectors reviewed the Semiannual Radiological Effluent Release Reports for the periods January 1,1986-June 30, 1986, and July 1, 1986-December 31, 1986. The review included an examination of the liquid and gaseous effluent release data as well as dose estimate data.
Selected data from these reports and previous reports are presented in Table 1.
The inspectors noted that quantities of radionuclides released and the annual dose estimates did not follow any significant trends from 1984 to 1986.
The gaseous releases at the McGuire Station were slightly below the 1985 gaseous release average which was based on data collected from 14 operating PWRs in
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Region II. The liquid releases at McGuire did not vary significantly from the 1985 Region II liquid release average.
Additionally, the inspectors noted that the reporting requirements for the Semiannual Effluent Release Report as specified by the technical specifications and the applicable portions of Regulatory Guide 1.21 were met.
The inspectors also noted that values represented by zero were defined in the semiannual reports as below the minimum detectable limits of the McGuire counting systems, b.
Monitors The inspectors reviewed the calibration, testing, and checking procedures of the containment airborne monitors EMF-38 (containment particulate low and high range) and EMF-39 (containment gas low and high range). This review included how these monitors were tested in
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accordance with their function as part of the Engineered Safety Features actuation system instrumentation for containment purge and exhaust isolation. During each refueling outage, the EMF monitors are calibrated; the signal providing the alarm and automatic termination of release is checked; and the testing of the dampers which would terminate the release is performed.
The instrument and engineering group calibrated the monitors and checked the signal from the EMF monitor to the electrical relay, while the performance group tested the system from the relay to the actuation of the damper. It should be noted that these containment isolation dampers are normally maintained in a closed position during modes one through four.
No violations or deviations were identified.
7.
Information Notices (92717)
l The inspectors reviewed and discussed with licensee representatives IE i
Information Notices (IEN) 86-42, " Improper Maintenance of Radiation l
Monitoring Systems," and IEN 86-76, " Problems Noted in Control Room Emergency Ventilation Systems."
The inspectors noted that both Information Notices had been received, distributed to the applicable engineering group, and that appropriate actions had been taken.
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a No violations or deviations were identified.
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8.
Licensee Event Reports (92700)
The inspectors reviewed the following Licensee Event Reports (LER):
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50-369/LER 83-44, Inoperability of Containment Atmosphere Gaseous Radioactivity Monitor EMF-39L Due to Detector Voltage Approximately 250 Volts Lower than the Previous Calibration
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50-369/LER 85-16, Temperature Compensation Chart Not Included in Hydrogen Analyzer Operation Emergency Procedure
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50-369/LER 87-06, The Control Area Ventilation and Chilled Water
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System Train B Chiller Tripped While Train A was Inoperable Due to Personnel Error The inspectors determined that for the nonroutine events noted above, the licensee had taken the corrective actions as stated in the written reports of the events and that the responses to the events were adequate. The inspectors noted that the immediate corrective action for LER 85-16 included the incorporation of temperature compensation charts and the steps used to obtain a temperature reading for the hydrogen analyzer in the applicable emergency procedures.
The planned corrective actions included the installation of heat tracing on the Units 1 and 2 hydrogen analyzer sample lines. The inspectors reviewed the station modification documents (NSM-MG-1-395 (Unit 1) and NSM-MG-2-298 (Unit 2)) and noted that
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the planned completion date for installing the heat tracing was June 1, 1987. The inspectors considered the LERs noted above to be closed.
No violations or deviations were identified.
9.
TMI/NUREG-0737 Items (25544)
a.
NUREG-0737 Item II.F.1, Attachment 1, described the high-range noble gas monitoring system that is required to detect and measure concentrations of noble gas fission products in plant gaseous effluents during and following an accident.
These monitors provide the plant operator and emergency planning agencies with information
on plant releases of noble gases during and following an accident. A
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review of this particular system had been previously documented in IE Report Nos. 50-369/84-16 and 50-370/84-13.
The inspectors noted that the high range noble gas monitor was manufactured by General Atomics and was designated by the licensee as 1,2-EMF-36(HH).
The EMF monitors were located in the unit vents approximately 30 feet below the unit vent isokinetic sample line penetration.
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detector monitors the unit vent effluent activity for noble gas by means of an ionization detector which had a range of 10 -10' R/hr.
Since the EMF-36(HH) monitor read out directly as roengtens per hour, the licensee utilized a chart to convert from roengtens per hour to microcuries per cubic centimeter, which considered the radionuclide spectrum distribution as a function of time after shutdown.
Additionally the inspectors reviewed the calibration procedure IP/0/A/3005/10, Radiation Monitoring System High Range Area Channel Calibration, March 13, 1986, Revision 3 for the EMF-36(HH) package.
Based on the review performed during this inspection and the inspection documented in 50-369/84-16 and 50-370/84-13, it appeared that the systems met the criteria of NUREG-0737 Table II.F.1-1 for the required range to monitor noble gaseous effluents auring accident conditions.
b.
NUREG-0737 Item II.F.1, Attachment 2 described the sampling and analysis requirements of high-range radiciodine and particulate effluents in gaseous effluent streams.
The purpose for this capability was to determine the quantitative release of radiciodines and particulates for dose calculation and assessment.
NUREG-0737, II.F.1, Attachment 2, states that the licensee shall provide continuous sampling of plant gaseous effluent for postaccident releases of radioactive iodines and particulates to meet the requirements of Table II.F.1-2.
The inspectors reviewed the licensee's system for sampling and analysis or measurement of high-range radiotodine and particulate effluents against the sampling requirements outlined in Table II.F.1-2 of NUREG-0737. The sampling
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requirements were as follows:
(1) representative sampling per
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ANSI N13.1-1969; (2) entrained moisture in effluent stream should not degrade the adsorber; (3) continuous collection of the sample whenever exhaust flow occurs; and (4) provisions for limiting occupational dose to personnel incorporated in sampling systems, in
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sample handling and transport, and in analysis of samples.
NUREG-0737 stated that this requirement should not be construed to prohibit design and development of radioiodine and particulate monitors to provide online sampling and analysis for the accident condition.
It appeared that the licensee's system for sampling and analysis of radioiodines and particulate effluents in gaseous effluent streams failed to meet several of the sampling requirements listed in Table II.F.1-2.
For example, the inspectors noted the lack of heat tracing on approximately 70 feet of the 3/4 inch diameter exposed sample delivery lines.
Non-heated sample delivery lines could result in entrained moisture in the effluent stream which could degrade the adsorbers used for radiciodine collection.
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noted that the licensee had identified the need for heat tracing of these sample delivery lines as documented in station modification packages MG-1-1623 (Unit 1) and MG-2-0588 (Unit 2) dated January 18, 1985 and April 29, 1985, respectively. However, tt :se modifications have been delayed until the 1988 refueling out Jes.
Additionally, it appeared that the licensee's system was no, designed for the continuous collection of samples wherever exhaust ficw occurs.
This concern is outlined below.
The licensee used Procedure HP/0/B/1009/06, Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions, September 9,1986, for the sampling and analysis of radiciodines and
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particulates. The procedure specified the following three conditions as to when a gaseous effluent sample was to be collected: (1) if the (contact) dose rate at the gas supply line and the iodine cartridge of the EMF monitor are less than or equal to 3 R/hr, collect a gas, particulate, and iodine sample by connecting a particulate filter, silver zeolite cartridge, 100 cc gas bomb, vacuum gauge, flow meter, and vacuum pump to the normal technical specification sampling line supply (note: this sampling assembly would be placed, unshielded, on a mobile laboratory cart); (2) if the dose rate at the gas supply line is greater than 3 R/hr and the dose rate at the fodine cartridge is between 3 R/hr and 15 R/hr, then determine the gas concentration (uCi/ml) from a correlation graph of R/hr versus uCi/mi and collect the iodine sampling by removing the silver zeolite cartridge from the iodine EMF sampling holder (Note:
the cartridges are removed while the EMF is turned off manually); and (3) if the iodine cartridge dose rate is greater than 15 R/hr, no sample shall be taken and the iodine concentration will not be determined by this procedure (Note:
the licensee stated that the post accident gas sampling system can be used for a containment sample). As noted above, it appeared that the licensee cannot provide for the continuous sampling of plant gaseous effluent for post accident releases of radioactive iodines and particulates, especially in situations where the contact dose rates on the_ gas supply line and the iodine cartridge to the Unit Vent EMF are greater than 3 R/hr.
Additionally, the licensee's sampling system for iodines and particulates does not provide shielding for limiting the occupational dose to personnel. Personnel exposures are
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controlled by prescribing dose rate limitations as to when particular
samples are collected.
The inspectors informed cognizant licensee representatives that the concerns regarding the licensee's ability to meet the sampling requirements of Table II.F.1-2 would be considered an unresolved item (50-369/87-13-01 and 50-370/87-13-01). During a telephone conversation on May 19, 1987, the licensee agreed to submit a response to the NRC Region II office within 90 days after the transmittal date of this inspection report that would address the sampling requirements of Table II.F.1-2 in NUREG-0737 and how the sampling system meets those requirements.
URI:
50-369, 370/87-13-01, Review the radioiodine and particulate sampling requirements of Table II.F.1-2 and. determine whether the four criteria for sampling considerations are met.
10. Equipment Staging Building Heating, Ventilating, Air Conditioning and Radiation Monitoring System (927058)
The inspectors briefly reviewed Equipment Staging Building, heating, Ventilating and Air Conditioning system with cognizant licensee representatives and discussed certain aspects of the system with the site Resident Inspectors. The Equipment Staging Building was a new facility which has not yet become operational. At the time of this inspection, the Office of Nuclear Reactor Regulation was evaluating the plan for this new facility to determine if any applicable licensing issues would be involved.
The purpose of the Equipment Staging Building Heating, Ventilation, and Air Conditioning system was to prevent an unmonitored release of radioactivity from the building, to provide air filtration, and to maintain suitable building temperature.
The ventilation system consists, in part, of a filter unit containing prefilters, HEPA filters and cooling coils; a centrifugal fan to recirculate building air; a vane-axial fan for building exhaust, an air-cooled reciprocating chiller; and an electric duct and unit heaters. The radiation monitoring system consisted of particulate filter and charcoal cartridge sampling assembly and an EMF monitor (beta scintillator). The EMF monitor provided for a high radiation alarm only with a local readout and a remote readout in the Control Room. The building exhaust fan would continue to operate when radioactivity is detected so that'the total release could be determined by the EMF monitoring sampling system (2 EMF 59).
This system was not intended to mitigate the consequences of an accidental release of radioactivity inside containment.
To ensure that an accidental release would not occur with the equipment hatch open, administrative controls of the reactor building equipment hatch would have to be maintained in accordance with the plant Technical Specifications.
No violations or deviations were identified.
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11 Review of Radioactive Resin Released From the Unit 2 Polishing Demineralizer Backwash Tank (84723)
The inspectors reviewed McGuire Nuclear Station Incident Investigation Report No. M87-018-0 and discussed the incident with cognizant licensee personnel. The event occurred on March 17, 1987, when condensate polisher spent resin was backwashed into a backwash tank with the tank's drain valve open. The resin spilled onto the floor and approximately 17 cubic feet of resin went into the floor drain.
The floor drain leads to the Building Sump and the resin was then automatically pumped into the Initial Holdup Pond (IHP).
Sufficient resin was collected from the floor to quantify the radioactive isotopes.
Licensee calculations determined Technical Specification 3.11.1.5 concerning the addition of radioactive materials to the pond was not exceeded. The inspectors reviewed the gamma isotopic results and work papers from the procedure HP/0/B/1003/10, Used Backwash Resin Transfer to Initial Holdup Pond or WC Settling Pond A or B, May 22, 1986.
The licensee identified personnel error and inadequate administrative controls governing Chemistry controlled equipment as causes of the tank drain valve being left open. Chemistry personnel verified the resin was contained in the IHP by sampling the influent and effluent lines of the IHP.
Licensee corrective actions included initiating a procedure to document equipment removal from service under chemistry control and compiling a Station Problem Report to evaluate methods to prevent recurrence of this type of accident. At the time of this inspection, the Station Problem Report had not been completed. The inspectors informed licensee personnel the evaluation of operational problems concerning the March 1987 spent resin spill would be considered an inspector followup item.
IFI:
50-369, 370/87-13-02, Evaluation of operational problems concerning the March 1987 spent resin spill.
12.
Licensee Action on Previously-Identified Inspector Followup Items and Unresolved Items (927018)
(Closed) URI 50-369/84-07-04: Licensee must perform an exposure review of the PASS Panel due to a design change.
The inspectors reviewed a post-accident personnel dose calculation as documented in a memo dated August 3,
1984 (MDPE-84-503) and determined that the response was adequate.
Additionally, the licensee had established administrative controls in HP/1/B/1009/15, Nuclear Post-Accident Containment Air-Sampling System Operating Procedure, so that stay times in the sample panel area would be limited to approximately six minutes. This item is considered closed.
(Closed) URI 50-370/84-07-05:
Obtain data to determine operability of containment atmosphere PASS panel.
The licensee performed additional testing on the Unit 2 post accident gas panel per McGuire testing procedure TH/2/B/9500/24 on July 24, 1984. A report was issued from the
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General office, File:
MC-215.00 Nuclear Station Post-accident Gas Sampling System Testing Report dated July 1984.
Sample results obtained
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11 from the' panel were compared with sample results from the normal sampling system which sampled the Unit 2 upper containment.
Total noble gas activities obtained from the post-accident gas (PAG) panel as compared to the normal sampling system indicated a relative standard deviation of approximately 15"4. Based on the test results, the inspectors determined that the PAG panel on Unit 2 could provide representative samples of the containment atmosphere. This item is considered closed.
(Closed) IFI 50-369, 370/86-32-04:
Comparison of NRC and licensee radiological analyses for WT, WC, and standby service water systems. The inspectors examined analytical results for samples split between-the NRC and the licensee.
No fission or activation products were detected by gamma spectroscopy in any of the splits.
Gamma isotopic analyses identified only natural products, and tritium results were less than the licensee's minimum detectable activity. This item is considered closed.
(Closed) URI 50-369, 370/86-32-05: Radiological evaluation of WT sanitary
waste shipped from MNS to a sanitary landfill for disposal. This item was concerned with the licensee's gamma spectroscopy counting methodology whereby a liquid geometry was used to quantify radioactive concentrations in sludge samples.
Discussions with cognizant licensee personnel indicated sludge samples were collected by dredging and then dewatered by filtering prior to gamma isotopic analyses. The sludge samples form for counting was typically a " wet" solid and not a slurry. Subsequent to the 86-32 inspection, the licensee had requested a contractor prepare a spiked sludge standard and had provided sludge to the contract lab.
The inspectors reviewed an internal memo to Jeff Foster and Bill Byrum, from P.
S. Wingo, Subject:
Sludge Geometry, File No.: OC, MC, CN, 778.20 dated December 12, 1986. The memo detailed that the contract laboratory had analyzed the density of the sludge.
The sludge's density was determined to be comparable to the NBS traceable resin standards currently used by McGuire's laboratory, and due to the difficulties in homogeneously spiking a sludge sample, use of resin standard was recommended.
The i
inspectors reviewed the contract lab's report and noted insignificant differences between the sludge's and resin's densities (1.18 grams /cc sludge compared to 1.15 grams /cc resin).
This item is considered closed.
(Closed) IFI 50-369, 370/86-32-07:
Review licensee procedures for systematic review of environmental data and identification of anomalous measurements.
The inspectors reviewed EP/0/B/2400/01, Preparation of Sample Analyses Reports and Unavailable Analysis Reports and the Review and Distribution of Analyses Data, Rev. 3, April 27,1986. A procedural change had been initiated November 14, 1986, to require timely review of all data and reports by a supervisor or a qualified reviewer. Anomalous
data and analytical results exceeding technical specification reporting levels were to be reported to the appropriate facility and the General Office. The inspectors discussed implementation of the procedural changes with cognizant licensee personnel.
This item is considered closed.
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Table 1 McGuire Nuclear Station Semiannual Effluent Release Summary, 1984-1986 Year 1984 1985 1986 No. Abnormal Releases a.
Liquid
0
b.
Gaseous
3
Liquid Waste Released (gallons)
5.44 E+6 1.54 E+7 2.10 E+7 Activity Released (Curies)
a.
Liquid 1.
Fission and Activation Products 3.02 E+0 1.24 E+0 1.55 E+0 2.
Tritium 6.47 E+2 8.04 E+2 9.16 E+2 3.
Gross Alpha
0
1
b.
Gaseous l
1.
Noble Gas 4.56 E+3 3.86 E+3 2.10 E+3 2.
Halogens 2.43 E-2 2.46 E-2 2.02 E-2 3.
Tritium 2.95 E+1 5.00 E+1 6.12 E+1 4.
Gross Alpha
0
Dose Estimate (mrem)
a.
Liquid Whole-body 1.82 E-1 1.76 E-1 2.80 E-1 b.
Gaseous 1.
Whole-body 3.96 E+0 1.47 E+0 7.58 E-1 2.
Skin 4.47 E+0 3.92 E+0 2.00 E+0
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