IR 05000400/1987003
| ML20210V320 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/05/1987 |
| From: | Kahle J, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210V311 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-400-87-03, 50-400-87-3, NUDOCS 8702180748 | |
| Download: ML20210V320 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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FEB 0 91987 Report No.: 50-400/87-03 Licensee: Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Docket No.: 50-400 License No.: NPF-53 Facility Name: Shearon Harris Inspection Cond d: Januarq3-14,1987 Inspector: //
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. Kahle, Section Chief Date Signed 1sion of Radiation Safety and Safeguards SUMMARY Scope:
This routine announced inspection was in the areas of preoperational inspection of radioactive liquid and gaseous effluent treatment systems, radiological effluent monitoring and post accident sampling systems.
Results:
No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. L. Willis, Plant General Manager
- A. Poland, Project Specialist
- G. Nathan, Project Specialist
- G. L. Forehand, Director, Quality Assurance
- A. L. Klemp, Quality Assurance Project Specialist
- L. J. Woods, Startup Supervisor
- 0. Hudson, Senior Engineer, Regulatory Compliance
- J. R. Sipp, Manager, Engineering B. Stevenson, Project Engineer
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J. Pierce, Project Specialist
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S. Beaver, Project Specialist Other licensee employees contacted included engineers, technicians, and
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office personnel.
Other Organizations L. Aspray, Multi-Amp Services, Inc.
W. Blevins, Westinghouse NRC Resident Inspector
- S. P. Burris
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on January 14, 1987, with those persons indicatett in Paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
No dissenting comments were received fror. the licensee.
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Preoperational functional and leak tests for 21 ESF and non-ESF ventilation treatment systems were reviewed and found adequate.
Status of the post-accident sampling system was reviewed and found acceptable for full power operation, subject to an evaluation which will be performed after full power is achieved.
The licensee did not identify as proprietary any of the material provided to
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or reviewed by the inspector during this inspection.
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3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Post Accident Sampling System (PASS) (NUREG-0737, Item II.B.3)
The inspector reviewed the licensee's actions taken to correct a problem identified earlier during functional testing of the PASS (50-400/86-79-03).
At that time, a sampling valve was identified as having an under-size bore, which resulted in excessive dilution of liquid samples.
The valve was replaced with a valve having a larger bore and a corresponding larger sample volume.
The inspector reviewed the licensee's corrective actions, and examined the PASS sampling panel.
The licensee's corrective actions appeared to be satisfactory.
At the time of this inspection, licensee personnel were conducting tests to verify the sample volumes and dilutions resulting from the modified valve.
On the basis of this inspection, and on the inspections of the PASS previously made and reported in 50-400/86-79, 86-54 and 86-44, the inspector determined that the Shearon Harris Post Accident Sampling System, as established in NUREG-0737, Item II.B.3, was installed, tested and inspected, and found to be in full conformance to the established criteria and is, therefore, considered operable.
The PASS will be further evaluated after Shearon Harris, Unit 1, has been operated at full power for at least 30 consecutive days immediately prior to the evaluation, as provided in 50-400/86-79-05 (IFI).
(0 pen) 86-79-05 - Evaluate PASS operation and performance after reactor has operated at least 30 consecutive days at full power.
This plant had not exceeded 5% power at the time of the inspection.
This item remains open.
(Closed) NUREG-0737, Item II.B.3, Post Accident Sampling System.
Per above discussion.
(Closed) 86-79-03 (IFI) - Review installation of modified metering valve with larger bore in liquid PASS (NUREG-0737,Section II.B.3); installation to be completed prior to exceeding 5% power.
The modified valve was installed January 7,1987.
The inspector reviewed the installation of the modified valve assembly and the preoperational test procedure.
The results appeared to be sastifactory.
The PASS will be further evaluated after full power is reached as previously noted in 50-400/86-79-05.
IFI 86-79-03 is considered closed.
No violations or deviations were identified.
5.
Radioactive Gaseous Treatment System (84524)
The inspector reviewed the preoperational functional and leak tests conducted by licensee contractors on twenty-one ESF and non-ESF HEPA filter and charcoal adsorber systems.
All ESF systems checked out satisfactorily in accordance with ANSI N510-1980 criteria.
Two non-ESF systems were found
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to have excessive bypass leakage resulting from inadequate seating of bypass dampers.
In each case, the damper was replaced with a blank-off plate and the bypass duct was permanently sealed.
One non-ESF in-containment recirculating cleanup filter system was found to have 0.09% bypass leakage (acceptance criteria for effluent systems is 0.05% per ANSI N510-1980).
Since this system is not an effluent system, the licensee performed an evaluation which indicated that no Technical Specification criteria would be exceeded if the system were to be accepted "as is;" the inspector concurred in the licensee's evaluation.
The inspector reviewed the qualification documentation for the contractor personnel who conducted the leak testing of the HEPA filter and charcoal adsorber systems noted above.
The qualification of the test personnel were in accordance with the qualification criteria of ANSI N510-1980.
No violations or deviations were identified.
6.
Radioactive Gaseous Effluent Monitoring (84524)
The inspector reviewed licensee actions taken toward correction of a condensation problem associated with the turbine building exhaust stack monitor.
As noted in 50-400/86-79-06 (IFI) condensation of moisture in the gaseous effluent monitor and sampling system had been previously identified.
The licensee installed heat tracing designed to raise gas temperature inside the sampling line to a level of approximately 110 F to prevent condensation.
Upon checking system operation, it was found that operating temperatures had exceeded 130 F and had damaged the detection element of the mass-flow meter; this was attributed to incorrect placement of the thermocouple used to control the heat tracing temperature.
At the time of this inspection, licensee personnel were planning to relocate the thermocouple to a point in the line closer to the monitor and were going to replace the flow measurement device.
(0 pen) 86-79-06 (IFI) - Review Turbine Building effluent air monitoring system after plant startup to determine if moisture condensation problem corrective measures prove adequate.
As noted in the above discussion, the moisture condensation problem has nut been resolved.
This item remains open.
(Closed) 86-54-01 (Unresolved Item) - Review results of contractor test of transmission of containment atmosphere particulate aerosols through sampling line to demonstrate compliance with guidance of ANSI N13.1-1974.
The sample line addressed in this item was replaced subsequent to Inspection 86-54 by a new larger diameter sampling line with only two isolation valves in series instead of six; a different model isolation valve with a larger effective inner diameter than the original was used in the new line.
The replacement line was described in 50-400/86-79.
The sample transmission problem was resolved by replacement of the line with a satisfactorily designed sample line.
This item is considered closed.
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(Closed) 86-79-04 (IFI) - Review modifications to wide-range gaseous effluent monitoring particulate / iodine sample skids to provide straight-through sample flow for normal operation.
The inspector reviewed the alignment of electrically operated solenoid valves controlling the path of flow of three sample valves on each unit.
It was noted that these solenoids had been re-wired such that the selected normal flow path was straight-through, eliminating one sharp right-angle bend in the normal sampling path.
This item is considered closed.
(Closed) 86-79-01 (IFI) - Verify that thirteen exceptions to the preoperational test of the containment hydrogen monitor system, including replacement or repair of a flow sensor and circuit board provision for twelve computer points have been cleared and that the system is fully operational prior to exceeding 5% of full power.
Licensee personnel replaced a flow sensor and installed a modified circuit board which permitted the plant computer to read valve position indications for twelve valves in the hydrogen monitoring system.
The inspector reviewed the completed preoperational test records and determined that they had been completed satisfactorily and were submitted to the Joint Test Group (JTG)
for final approval on January 9, 1987.
This item is considered closed.
(Closed) 86-79-02 (IFI) - Review results of flow rate and particulate sampling efficiency tests to be conducted on the containment atmosphere sampling system used for detecting primary coolant leakage in containment.
The inspector reviewed licensee contractor special reports on calculated particulate and iodine-131 aerosol transmission through the containment atmosphere sampling line.
Results were consistent with measurements made at other comparable facilities.
This item is considered closed.
(0 pen) 86-70 07 Review results of iodine aerosol sample loss
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test / evaluation through post-accident containment atmosphere sampling line shared with hydrogen sampling system.
The licensee indicated that a contractor review of the sample line was expected to be completed approximately March 30, 1987.
This item remains open.
(Closed) 86-79-08 - Review applicant data on flow tests of Stack 5A and Plant Vent Stack.
The inspector reviewed flow tests on stacks SA and Plant Vent and a report on sampling errors prepared by a licensee contractor.
The material was found to be satisfactory.
Predicted sampling errors were less than 25% at the 95% confidence level.
This item is considered closed.
No violations or deviations were identified.
7.
NUREG-0660, Items II.F.1.2.A (Noble Gas Monitor) and II.F.1.2.B (Iodone/ Particulate Sampling) (also Module 84524)
The inspector reviewed various aspects of the II.F.1 monitors during this inspection and in the following inspections:
85-44 (November 5-8, 1985), Paragraph 4, "NUREG-0737 Items"
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86-37 (May 5-8,1986), Paragraph 6, " Liquid and Gaseous Radioactive Effluent Monitoring" 86-54 (June 23-27, 1986), Paragraph 3, " Process and Ef fluent Monitoring Instrumentation" 86-79 (September 29-October 3, 1986, October 15-17, 1986, and October 27-28, 1986), Paragraph 6, " Radioactive Liquid and Gaseous Process and Effluent Monitoring and Sampling" The licensee has provided state-of-the-art monitoring and sampling equipment for detecting and measuring concentrations of gaseous and particulate aerosols in plant effluent streams under both normal operational and emergency conditions.
The equipment was manufactured by General Atomics (GA) and provides for monitoring of noble gas activity concentrations of from 10 7 pCi/cm3 to 105 pCi/cm3 and for monitoring iodine and particulate concentrations of 10 7 pCi/cm3 to 102 pCi/cm3, as specified in NUREG-0737.
Extended range coverage for noble gas monitoring is provided through combinations of alternate sampling paths, alternate volumetric sample
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collection rates, and alternate detectors.
Noble gas activity at normal or low concentrations is monitored by a beta sensitive plastic scintillation detector in accordance with Regulatory Guide 1.21 guidelines.
Noble gas activity at medium and high ranges is diverted through a separate path and monitored by a solid-state cadmium-telluride beta detector in accordance with NUREG-0737 and 0660.
Low range particulate aerosols are collected on a moving filter and detected by a beta-sensitive plastic scintillation detector.
Low range iodine aerosols in gaseous or vapor form are filtered through the moving filter media and pass downstream to either an activated charcoal cartridge or a silver zeolite cartridge where the iodone is adsorbed from the airstream and the deposited iodine is detected by a sodium-iodide thallium-activated gamma scintillation detector.
When iodine and particulate aerosol concentrations reach the point where the low-range instrumentation range is exceeded, high voltage to the detectors is turned off.
Under these conditions, a separate sampling device, located near the sample conditioning skid, is used to collect samples.
To evaluate high-level samples, the sampling head, which is encased in a lead shield, is removed from the system using quick-disconnect fittings, and taken to a sample processing and analysis facility.
The inspector reviewed the preoperational and functional tests of the monitoring and sampling system, reviewed the equipment installations, and reviewed the sample intake points within the effluent release points, the sample transport lines, and the sample conditioner unit (which is used to maintain isokinetic sampling rates.
The equipment appeared to be adequate,
. appropriate tests had been made and documented, calibration had been oerformed satisfactorily, and operating and maintenance procedures had been prepared and appreved.
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On the basis of the foregoing discussion and on the basis of prior inspection activities as discussed in the reference inspection reports, Items II.F.1.2.A and II.F.1.2.B are considered closed.
No violations or deviations were identified.
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