IR 05000271/1987013
| ML20237J021 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/14/1987 |
| From: | Davidson B, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20237J020 | List: |
| References | |
| 50-271-87-13, NUDOCS 8708250266 | |
| Download: ML20237J021 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION-REGION I Report No. 50-271/87-13 Docket No. 50-271 License No.,DPR-28 Priority --
Category C
Licensee: Vermont Yankee Nuclear Power Corporation RD 5, Box 169 Brattleboro, Vermont 05301 Facility Name: Vermont Yankee Inspection At: Vernon, Vermont Inspectors:
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Barry S avidson Radiation Specialist dat'e fh
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Approved by:
t alter-J. Pasciak, Chief ~
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Effluents Radiation Protection Section Inspection Summary: Inspection on July 13-1_7, 1987 (Report No. 50-271/87-13)
Areas Inspected:
Routine, unannounced inspection of the licensee's radioactive effluents control program, liquids and liquid wastes, gaseous waste system, process radiation monitoring system, and auditing activities.
Results:
No violations or deviations were noted in the areas reviewed. The licensee is effectively implementing its radioactive effluents control program.
R708250266 B70818 PDR ADOCK 05000271 Q
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DETAILS 1.0 Persons Contacted During this inspection, the following personnel were contacted:
1.1 Licensee Personnel
_Mr. R. Grippardi, Quality Assurance
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Ms. E. Keegan, Environmental Coordinator
- Mr. R. Leach, Radiation Protection Supervisor Mr. S. McAvoy, Chemistry Specialist
- Mr. J. Pelletier, Plant Manager Ms. L. Savard, Chemistry Specialist
- Mr. S. Skibniowsky, Chemistry Supervisor 1.2 NRC Personnel
- J. McDonalo, NRC RII
- W. Raymond, NRC RI
- Attended the exit interview on July 16, 1987.
2.0 Previously Identified Items 2.1 (Closed) Severity V Non-Compliance (50-271/84-07-02)
Failure to perform filter tests on train B of the Standby Gas treatment System (SGTS). The inspector reviewed the records of SGTS filter and charcoal methyl iodide removal tests from 1985 to date and noted that they were performed in a timely manner.
In addition, the inspector noted that a master surveillance schedule system, which included this surveillance, was used.
It provided the licensee the means to preclude a missed surveillance.
This item is closed.
2.2 (0 pen)
Inspector Follow-up Item (50-271/84-07-03).
Implement a laboratory QA/QC program to include Reg. Guide 4.15.
The inspector noted that a draft revision to procedure AP6000 " Chemistry Laboratory Quality Control Program", Revision 7, was in its final stage of review prior to issuance.
2.3 (Closed)
Inspector Follow-Up Item (50-271/85-17-01)
Disagreement between procedure 0.P. 4511 and Offsite Dose Calculation Manual (0DCM) se.tpoint methodology.
Procedure 0.P.
4511, " Source Calibration of Process Radioactive Monitoring System "
(PRMS) now includes setpoint methodologies described in the ODCM.
This item is closed.
2.4 (0 pen)
Inspector Follow-up Item (50-271/85-17-02)
Procedure 0.P. 4510 does not include instructions to review environmental sampling locations for placement of sample stations
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where the highest ground-level deposition occurs.
The technical
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- specifications require annual review of meteorological data and placement of sampling locations inareas of highest deposition.
The licensee has submitted correspondence to NRR to change Technical Specifications so as to eliminate the need for relocating environmental sampling to highest deposition locations.
The licensee requested that the locations remain unchanged because of the importance of having comparable historical data and small differences between actual locations and those otherwise required by Technical Specifications as currently written.
2.5 (Closed) Inspector Follow-Up Item (50-271/85-17-03)
Procedures to implement a land use census were not implemented.
Procedure 0.P. 4510. " Environmental Radiation Surveillance",
Revision 12, implements the surveillance requirements of Technical Specification 3.9/4.9 to conduct a land use census. This item is closed.
2.6 (Closed) Inspector Follow-up Item (50-271/86-23-01) Calibration errors in calibration of one liter gas Marinelli geometry. A 26%
bias had been introduced by the use of an incorrect volume in ('
calculating concentration and by the use of a liquid radioactive standard with a 30% efficiency error for low energy photons in lieu of a gas or low density foam standard.
This problem has been corrected. The licensee purchased the low density foam standard and now uses the correct volume. This item is closed.
2.7 (Closed)
Inspector Follow-Up Item (50-271/86-23-02)
Stack gas sampling error. The layout of the stack gas sample pump and Marinelli, and the sequence of valving and pump operation resulted in negative pressure in the sarrple. A proceaure change was noted and the licensee demonstrated to the inspector's satisfaction that the change corrected the pressure problem. This item is closed.
3.0 Liquid Radioactive Waste Effluents Control Program The inspector reviewed the licensee's program for controlling liquid radioactive effluents. The licensee demonstrates an aggressive program of conserving water through the use of filtration and demineralization, and separation of resins from slurries through centrifuge system operation.
Planned discharges did not occur in the period reviewed (from 1985 to the present) and the licensee stated that liquid df scharges had not been made since 1982. The inspector noted that evaporative losses from the system comprise a minor addition (a few curies of tritium) to the gaseous waste source term. Thus the radioactivity associated with the liquid system is retained by resins and filters and disposed of as solid wastes.
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4.0 Gaseous Radioactive' Waste Effluents Control Program The primary source of gaseous radioactive effluents is the (off gas) air
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. ejector system. The system operates continuously and the source term is proportional to power. The facility's Augmented Off Gas (A0G) system incorporates hydrogen dilution and recombiners, moisture removal, particulate filtration and iodine adsorption.
Noble gases are reduced in holdup piping and adsorber beds.
Ultimately, the activities released are in proportion to condensor in-leakage and failed fuel.
In March 1987 the licensee observed elevated air ejector off-gas release rates which rose and leveled off at 11,600 uCi/second. The licensee will conduct refueling operations commencing in August and will remove the affected assembly at that time. The inspector reviewed the stack gas sample analyses and the monitoring information and noted that the A0G was operating to minimize these releases.
No violations or deviations were noted.
5.0 Standby Gas Treatment System (SGTS)
The inspector reviewed the records of tests of the SGTS surveillance requirements for flow, in-place filter tests, and iodine adsorption evaluations.
The tests are scheduled at the frequencies required by Technical Specifications. The records from 1985 to date indicated that the program was being implemented in accordance with prescribed requirements.
No problems were found.
6.0 Effluent Monitoring Instrumentation The inspector reviewed the effluent monitor calibrations and source check
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procedures. Setpoint methodologies from the Offsite Dose Calculation i
Manual (0DCM) were implemented.
Records of periodic functional checks were reviewed and found satisfactory. Redundart channels are checked daily by operations personne). Main steam line, liquid effluent monitor, air ejector offgas, control room annunciator and logic, and stack gas calibrations and functional tests were reviewed. No problems were noted.
The licensee stated it intends to pursue the use of foam standards in lieu of check sources for calibrating effluent radiation monitors.
These have an advantage in that more low energy photons are present with which to calibrate and that the geometry is more properly represented.
The inspector noted that the chemistry group was aware that its method to determine released quantities of noble gases relies on correlation data from an operating period when severe fuel failures occurred, and, titerefore may not represent the current mixture.
Consequently, determination of radionuclides concentrations in the offgas and monitoring of condensor in-leakage provide the bases for estimating release rates without measurable samples from the stack.
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7.0 Audits
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The inspector reviewed the licensee's program for conducting audits and surveillance.
Program audits are conducted by licensee personnel
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through the Yankee Atomic Electric Company. The Yankee Nuclear Services Department Quality Assurance staff on site conducts surveillance. The inspector reviewed the recent program audit,.VY87-02 and the two surveillance of program implementation. A yearly plan is established
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The audits and surveillance reviewed by the inspector had no significant findings, only recommendations to improve the programs.
No violations or deviations were found.
8.0 Exit Interview The inspector met with licensee representatives at the end of the inspection.on July 16, 1987. The inspector summarized the purpose and scope of the inspection as well at the inspection findings.
No written
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material was provided to the licensee by the inspector.
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