IR 05000369/1981011
| ML20004D188 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/27/1981 |
| From: | Hosey C, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20004D186 | List: |
| References | |
| 50-369-81-11, 50-370-81-04, 50-370-81-4, NUDOCS 8106080558 | |
| Download: ML20004D188 (9) | |
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o UNITED STATES l-
~ ' 'h, NUCLEAR REGULATORY COMMISSION
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o 101 MARIETTA ST.. N.W.. SUITE 3100 ATLANTA, GEORGIA 30303
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Report Nos. 50-369/81-11 and 50-370/81-04 1.icensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Docket Nos. 50-369 and 50-370 License Nos. NPF-9 and CPPR-84 Inspection at McGuire site near Cornelius, NC d!a7!@/
Inspector:
s G. L. Troup 7
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Date Signed f
Approved by:
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Technic /et Acting C. 'M. flo ection Chief Date Signed al Inspectic Branch Engineering and Tec, ical Inspection Division SUMMARY Inspected on April 6-10, 1981 Areas Inspected This routine, unannounced inspection involved 36 inspector-hours onsite in the i
areas of radioactive waste management and radiation protection including effluent control, ALARA considerations, preoperational test results review, review of previously identified items and review of the Unit 1 startup chemistry control.
I Results Of the areas inspected, no violations or deviations were identified.
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r REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. L. McConnell, Superintendent of Technical Services
- 0. J. Rains, Superintendent of Maintenance
- W. M. Sample, Projects and Licensing Engineer
- T. J. Keane, Station Health Physicist R. P. Michael, Station Chemist
- R. M. Propst, Radwaste Chemistry Coordinator L. R. Kimray, Chemistry Coordinator W. E. Smith, Maintenance Supervisor A. Duckworth, Chemistry Supervisor J. W. Foster, Health Physics Coordinator G. F. Terrell, Health Physics Coordinator
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P. G. Huntley, Health Physics Supervisor R. F. Cole, Health Physics Supervisor G. E. Singletary, Associate Engineer A. F. Batts, Assistant Engineer
- 0. B. Lampke, Associate Engineer D. Motes, Junior Engineer T. Parker, Training Supervisor Other licensee employees contacted included 2 technicians.
NRC ' -ident Inspector
- M. J. Graham
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 10, 1981 with those persons indicated in paragraph 1 above.
Regarding the previously l
identified items on stack sample probe evaluation, installation of the stack j
flow monitor and evaluation of the charcoal adsorber residence times, the inspector emphasized that these are Technical Specification or license
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requirements which must be met prior to criticality; this was acknowledged by Mr. McConnell. The inspector also emphasized that the composite sampler had not yet been installed on the containment ventilation unit condensate
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drain tank (CVUCDT) discharge. As this sampler is required by the Technical Specifications, until the installation is complete, action is necessary to i
preclude automatic discharges. This was acknowledged by Mr. McConnell who stated that administrative controls such as locks or tags, would be used to prevent discharges until the sampler is installed.
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3.
Licensee Action on Previous Inspection Findings
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Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Preoperational Test Results a.
The inspector reviewed eleven completed preoperational test p ocedures.
The review included verification of proper review and approval of changes, review and approval of the completed test, identification and correction of identified deficiencies, completed results and retest as appropriate after deficiency correction or modification. No discrep-ancies were noted.
b.
Test procedures reviewed were:
(1) 0/A/1450/01, "Preoperational Filter Test for Control Room Area Outside Air Pressure Filter Trains 1 and 2"
(2) 0/A/1450/02, "Preoperational Filter Test for Auxiliary Building Filtered Exhaust Filter Trains 1 and 2" (3)
1/A/1450/03, " Containment Purge and Ventilation System Functional
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Test" (4)
1/A/1450/04, " Auxiliary Building Ventilation System Functional Test" (5) 0/A/1450/05, " Control Room Area Ventilation System Functional
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Test" l
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(6)
1/A/1450/06, " Annulus Ventilation System Functional Test"
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(7)
1/A/1450/12, " Containment Air Release and Addition Functional Test" (8)
1/A/1450/17, " Annulus Ventilation Filter Inplace Filter Test"
(9)
1/B/1500/08, " Equipment Decontamination System Functional Test" (10) 0/B/1500/11, "Radwaste Solidification Preoperational Test" (11)
1/B/1600/01-A, " Process Radiation Monitoring System Functional Test"
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c.
Ir. RII Report 50-369/81-02, paragraph 5.c, open item 81-02-01 was idsntified concerning the residence time evaluation for charcoal adsorbers.
The three test procedures for filter testing reviewed during this inspection were also revised to delete the residence time determination. The inspector discussed this with licensee representa-tives and was informed that Design Engineering was performing the residence time evaluation, but the evaluation was not complete. The inspector informed the licensee management representatives that the residence time evaluation was part of the acceptance tests required by ASNI N510-1975 and satisfactory performance was required to demonstrate operability. The inspector stated that this-item remained open pending the completion of the residence time evaluation.
6.
Radioactive Effluent Control a.
(Closed) Flow Recorder on Effluent Line (369/79-12-11)
This item was originally discussed in RII Report No. 50-369/79-12, paragraph 10.e, and dealt with the need to install a flow recorder on the liquid ef fluent line to determine the volume of waste released.
The flow recorder has been installed.
A licensee representative informed the inspector that modifications to the recorder to provide adequate scale range have been completed and the recorder is func-tional. The inspector had no further questions.
b.
(Closed) Liquid Waste Monitor Too Close to Isolation Valve (369/79-12-12) and (Closed) VCUDT Monitor Too Clos 9 to Isolation Valve (369/
79-27-01)
These two items relate to a condition where the automatic isolation valve on the effluent line is too close to the in-line monitor to close in time to prevent the release of waste which is greater than the release specification. A modification was made so that valve IWM46, which is downstream of the two isolation valves, will trip shut on a high radiation signal from any of three monitors.
This valve is downstream a sufficient distance to prevent the release of out-of-specification waste. After reviewing the work request to verify the
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trip function and observing the valve installation, the inspector stated that he had no further questions and that these two items were closed.
c.
(0 pen) Design Basis of Stack Sampling Probe (369/78-41-02)
This item was originally discussed in RII Report No. 50-369/78-41, paragraph 6 and dealt with the design basis and verification of the stack sampling probe. As stated in the report, a licensee represent-
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ative made the commitment to perform a velocity profile at the stack to
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confirm the design basis of the probe.
A licensee representative informed the inspector that verification measurements (flow traverse)
were being planned but had not been accomplished. Condition 2.c.(1).b requires that this test be completed prior to initial criticality.
This was acknowledged by licensee management representatives.
d.
(0 pen) Effluent Flow Rate Monitor on the Unit Vent (369/79-12-13)
This item was originally discussed in RII Report No. 50-369/79-12, paragrpah 10.g dealt with the need to install a flow rate monitor on the unit vent to' measure the volume of air released so that plaat effluents can be determined.
Condition 2.c.(14).d of the operating license requires that the flow rate monitor be installed and operable prior to initial criticality. A licensee representative informet the inspector that the monitor was scheduled to be installed following the completion of ' hot" testing.
Procedure TH/1/B/9500/02, " Unit Vent /
Waste Effluent Flow Data Collection" was prepared and issued to provide an alternate method of determining stack flow until the flow rate monitor is installed.
7.
ALARA Considerations a.
In RII Report Nos. 50-369/78-14 and 50-369/79-12 seve-(1 concerns were identified relating to arrangement of demineralizers and associated piping and other identified problems related to reducing occupational exposures.
In response to a meeting held on January 5,1979, between NRC officials and Duke Power Company a letter, dat ed March 21, 1979, from Duke Power Company to Region II delineated responses to specific concerns relating to ALARA censiderations of the demineralizer arrange-ment and associated piping.
Several of the items were previously reviewed and discussed in RII Report Nos. 50-369/80-02, paragraph 3, 50-369/80-21, paragraph 5 and 50-369/80-34, paragraph 5.
b.
The inspector reviewed the corrective actions stated in the Duke Power Company letter, discussed changes' made or being made with the cognizant supervisors and toured the various areas to observe the status of the changes. The following is a summary of the previously identified ALARA considerations.
(1) (0 pen) Spent Resin Sluice Pump (79-12-03)
Shielding has not been installed around the sluice pump to reduce radiation levels for maintenance of valves in the pump room.
A licensee representative informed the inspector-that the shield design was still under evaluation.
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(2) (0 pen) Surveillance Requirements for Snubbers (80-21-01)
aeseral mechanical snubbers, which were installed as replacements for hydraulic snubbers, are located in potential high radiation areas. Periodic surveillance of these snubbers would result in high personnel exposures. The licensee submitted a list of these snubbers to NRR and requested an exemption from the periodic surveillance requi ements. The Technical Specifications have not been issued for raschanical snubbers.
This item remains open pending the issuance of the Technical Specification surveillance requirements.
8.
Bulletins and Circulars a.
Circular 78-03, " Packaging Greater than Type A Quantities of Low Specific Activity Radioactive Material for Transport". Health Physics procedure HP/0/B/1004/02, " Shipment of Radioactive Waste" was revised to include provisions for the subject materials. The inspector had no further questions.
b.
Circular 79-21, "Preventioa of Unplanned Releases af Radioactivity".
A> 2 result of this Circular, a meeting was held by the licensee in May 1980 to identify possible pathways and corrective actions.
The inspector discussed the status of the corrections and observed that selected items had been completed. This Circular is closed.for record purposes.
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c.
Circular 80-14, " Radioactive Centamination of P? ant Demineralized Water System and Resultant Internal Contamination of Personnel".
As dis-cussed in RII Report No. 50-369/80-27, paragraph 8.c, the licensee was unable to procure backfiow preventers of the proper size and material and was considering administrative controls.
The inspector observed that various connections on the YM system (Makeup Demineralized Water)
had been labelled with "nonpotable water" labels. A licensee repre-sentative stated that machanical devices were still being investigated but the labeling of the connection should provide sufficirint warning to individuals.
The inspector had no further questions and informed licensee management that open item 80-27-03 was closed for record purpose.
9.
Radioac ive Waste Procedures (Closed) Radioactive Waste Discharge P, ocedures (369/80-12-04)
a.
This item was originally discussed in RII Report No. 50-369/80-12, paragraph 13, and dealt with the inspector's review of procedures to impelment the Technical Specifications. The inspector reviewed proce-dures HP/0/B/1003/02, " Procedure for Liquid Waste Release" and HP/0/
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B/1003/03, " Radioactive Gaseous Waste Release" and discussed various aspects with licensee representatives.
The inspector had no further questions.
b.
(0 pen) Waste Solidification Procedures (369/80-12-05)
l This item was originally discussed in RII Report No. 50-369/80-12,
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paragraph 14, and dealt with the status of the implementing procedures
for the waste solidification program.
A licensee representative l
informed the inspector that enemistry procedure CP/0/B/8600/13,
"Radwaste Chemistry Procedure for Solidification and Preparation for
Shipment" had completed the cross-disciplinary review and was being
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routed for approval. This item remains open.
10.
Changes to the FSAR Three items were previously identified concerning information in the FSAR which did not adequately describe the plant as constructed. Amendment 41 to
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the FSAR included revisions which addressed these items. After reviewing Amendment 41, the inspector informed licensee management that he had no
further questions and the three items were closed.
The three previously j
identified items were:
a.
78-41-01:
FSAR Statement Concerning Liquid Waste Release l
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80-1?-02:
Radioactive Liquid Waste System Addition t
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60-12-03: Actual Volume of Waste Monitor Tanks 11.
Radwaste Addition Facility (0 pen) Exhaust Monitor Sample Lines (80-21-02)
This item was originally discussed in RII Report No. 50-369/80-21, paragraph 7.b, and dealt with the unsatisfactory installation of sample lines due to numerous bends and long, horizontal runs.
A licensee representative informed the inspector that the sample line would be modified to relocate
the particulate / iodine filter holder ncar the sample point. This work has not been accomplished. This item remains open.
12. Other Previously Identified Items a.
(Closed) bproper Storage of HEPA Filters (369/79-12-01)
l This item was originally discussed-in RII Report No. 50-369/79-12, paragraph 6, and dealt with the improper storage of HEPA filters for
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use in safety related systems. The inspector toured storage areas in
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Warehouse No. 5 and observed the storage condition of the filters.
Filters were stored in the upright position and stacked no more than
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7 three high, as recommended in Appendix C of the Nuclear Air Cleaning Handbook (ERDA 76-21).
The inspector had no further questions. This item is closed.
b.
(ClosM) Repair of Continuous Air Monitors (369/80-02-05)
This item was originally discussed in RII Report No. 50-369/80-02, paragraph 9.b, and dealt with the incomplete status of two continuous air monitors. The monitors were repaired and calibrated by the vendor.
At the time of the inspection, the units were operable.
A licensee representative informed the inspector that additional work was.to be done on one unit but both units had been used and could be used as necessary.
c.
(Closed) Lapel Air Samplers This item was originally discussed in RII Report No. 50-369/80-02, (50-359/80-02-06), paragraph 9.b, and dealt with the procurement of lapel afr samplers for the assessment of airborne radioactive msterials.
A licensee representative informed the inspector that ten lapel air samplers had been received. The inspector observed one unit and discussed its use with the licensee representative. The inspector had no further questions.
d.
(Closed) Respiration Selection Procedure (369/80-02-08)
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This item was originally discussed in RII Report No. 50-369/80-02, paragraph 10.a, and dealt with revisions to the respirator selection procedare. The inspector reviewed the revision tc procedure HP/0/B/
1006/01 regarding respirator selection criteria; the inspector had no further questions.
e.
(Closed) Containment Air Monitor Installation (369/80-27-02)
This item was originally discussed in RII Report No. 50-369/80-27, paragraph 6.b, and dealt with the potential sampling problems with the containment air monitors due to long sample line runs. A licensee representative informed the inspector that action taken to reduce
i sample line losses included replacement of sample valves, increasing the size of the sample lines and rerouting of the sample lines to reduce the length of the runs and reduction of the number of bends.
The inspector observed the rerouted lines and noted that the flow path had been improved with the larger size piping and reduced number of bends. The inspector also reviwed Work Request 62704, which tested the flow rates and flow alarm setpoints for the monitors after rodifica-tion. The inspector had no further questions.
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13.
Startup Chemistry (Unit 1)
Technical Specifications 3.4.8 and 3.4.9 specify the limits for reactor coolant chemistry and specific activity, respectively.
Surveillance requirements are specified in Tables 4.4-3 and 4.4-4~
The inspector reviewed the primary plant chemistry records for February 20-26 and April 1-7 and verified that the required analyses were performed at the requisite frequency and the results were within the applicable limits for the mode of operation. The inspector had no further questions.
14.
Preoperational Inspection Program (Unit 2)
In conjunction with the exit interview to discuss the findings on Unit I the inspector discussed the preoperational inspection program applicable to Unit 2 for environmental monitoring, emergency planning, radiation protection and radioactive waste management. The inspector discussed the effect of shared systems programs and procedures on the reduced scope of the Unit 2 program.
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