IR 05000271/1979010
| ML19260A693 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/11/1979 |
| From: | Stohr J, Thonus L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19260A679 | List: |
| References | |
| 50-271-79-10, NUDOCS 7912030096 | |
| Download: ML19260A693 (7) | |
Text
.
.
.
U. S. NUCLEAR REGULATORY COMMISSION
,
0FFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-271/79-10 Docket No.
50-271 License No.
DPR-28 Priority
--
Category C
Licensee:
Vermont Yankee Nuclear Power Corporation 20 Turnpike Road Westborough, Massachusetts Facility Name:
Vermont Yankee Nuclear Station Inspection At:
Vernon, Vermont Inspection Conducted:
July 10-13,1979 f!/o!71 Inspectors:
h
.
L. H. Thonus, Radiation Specialist date date Approved by:
/
f J..#.
Stohr, Chief, Radistf on date Support Section, FF&MS Branch Inspection Summary:
Inspection on July 10-13, 1979 (Recort No. 50-271/79-10)
Areas Ir.spected:
Routine, unannounced inspection by a regional based inspec-tor of Radioactive Waste Systems including licensee action on previous inspec-tion findings and IE circulars, effluent releases, records and reports, effluent control ir.strumentation, procedures, testing of air cleaning systems, reactor coolant water quality, solid radioactive waste and tours of the radiation con-trol area.
Upon initial arrival at approximately 8:50 p.m. on July 10, 1979 a tour was conducted of the radiation control area to observe radiation safety practices and control of higt radiation areas.
The inspection involved 29 inspector-hours onsite by one NRC regional based inspector.
Results:
Of the ten areas inspected one item of non _mpliance (infraction-failure to sample within required frequency paragraph 4) was found in one area.
1466 136 Region I Form 167 (August 1979)
.
.
DETAILS 1.
Persons Contacted
- Mr. R. W. Burke, Engineering Support Supervisor
- Mr. D. C. Girroir, Tecnnical Assistant Mr. D. E. LaBarge, Shift Supervisor Mr. J. T. McCarthy, Chemistry and Health Physics Assistant Mr. D. W. Mohler, Chemistry and Health Physics Assistant
- Mr. W. P. Murphy, Assistant Plant Superintendent Mr. M. E. Prystupa, Chemist Mr. W. T. Penniman, Security Supervisor Mr. D. S. Tolin, Chemistry and Health Physics Assistant
- Mr. G. D. Weyman, Chemistry and Health Physics Supervisor The inspector also interviewed several other licensee and contractor per-sonnel during the course of the inspection.
These employees included personnel from chemistry and health physics, operations, and security.
- Denotes those present at the exit interview.
2.
License Actions on Previous Inspection Findings (Closed) Noncompliance (271/78-26-02):
Failure to control high radiation areas.
This item was previously reviewed in inspection report (271/79-04).
The licensee's installation of the self-closing door mechanisms is now comnlete.
Checklists used by auxiliary operators on their rounds were retiewed; they require checks of locked high radiation area doors.
No discrepancies were noted in the checklists examined by the inspector.
The inspector had no further questions.
3.
Licensee Action on IE Circulars (0 pen) 79-09:
Regulator diaphragm failure in certain types of self-contained breathing apparatus (SC8A).
The licensee performed a check of regulator diaphragms and which did not identify any ruptures or pinhole leaks.
A procedure change has been initiated which will require periodic examinations of the diaphragms.
The revised procedure will be reviewed in a subsequent inspection.
The licensee utilizes SCBA's in the pressure-demand mode such that any leaks would reduce service time but would not reduce the protection factor.
1466 137
.
.
4.
Effluent Release, Monitoring, and Analyses a.
Liquid Releases The licensee has made no liquid effluent releases since the last routine radioactive waste management inspection conducted in May, 1978.
The licensee's radioactive liquid transfer log was reviewed for the period April, 1978 thru July, 1979.
Technical Specification (TS) 3.8.8 limits the activity (except tri-tium and dissolved gases) which can be stored in the two waste sam-ple tanks, floor drain sample tank and waste surge tank to 3.2.Ci.
TS 4.8.B requires that these tanks be sampled and analyzed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each addition to the tanks.
The licensee's tank analy-ses for the periods October thru November, 1978, March, 1978 and May thru July, 1979 indicated that the activity limits and surveil-lance requirements had been met.
b.
Airborne Efflueny Technical Specificatian (TS) 3 1.C.1 limits gross activity released from the plant; TS 3.8.C.2 lin<..s the radiciodine release rate, and TS 3.8.C.3 limits the release of particulates.
Technical Specifica-tions 4.8.C.1, 4.8.C.2, and 4.8.C.3 detail the monitoring and ana-lysis requirements of gross activity, radiciodines, and particulates respectively.
The inspector examined the release rates of gross activity radio-iodines, and particulates during the time periods September thru October, 1978 and March thru April, 1979.
No release rate limits were exceeded.
The release rate of radiciodine was greater than 4%
of the release limit during the third quarter of 1979 which required the licensee to take corrective actions (at 4% of limit) and submit a report (at 2% of limit) to the NRC (see paragraph 5).
Steam jet air ejector off gas samples and analyses were examined for the period June 1 thru July 12, 1979 (31 samples).
The samples and analyses are required weekly but are performed more frequently by the licensee.
Particulate and radioiodine sampling and analyses were reviewed for the period September thru October 1978, March thru April, 1979.
Raw data from several of the licensee's Ge(Li) gamma spectal analyses was reviewed.
TS 4.8.C.1.d requires that " samples of off gas effluents shall be taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and gamma radioactivity determined by gross or isotopic analysis."
1466 138
Review of the licensee's off gas effluent sampling for January 4 thru July 12, 1979 revealed that this was normally performed weekly.
Although on several occasions samples were taken more frequently and on two occasions the interval was 8 days.
Instances where the sampling interval exceeded 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> include January 11-19, January 19-26, April 12-19, April 19-26, April 26-May 3 and May 3-11, 1979.
The inspector identified the above as noncompliance with TS 4.8.C.1.d.
(271/79-10-01)
5.
Records and Reports of Radioactive Effluents Technical Specification 6.7.C requires thr licensee to submit Semi-annual Effluent Release Reports, and that the information within them shall be in accordance with Regulatory Guides (RG) 1.21 and 4.1.
The inspector exa-mined the Semi-Annual Effluent Release Reports for the calendar year 1978 (dated August 28, 1978 and March 19, 1979) to verify that they contain no anomalous results, were in conformance with the requirements of the regu-latory guides and were complete.
As noted in paragraph 4 above iodine releases were greater than 2% of Technical Specification (TS) 3.8.C.2.a limits, thus requiring a thirty day written report.
The report, dated April 11, 1979 contained the cause and corrective actions.
No items of noncompliance were ident*fied.
6.
Effluent Control Instrumentation Technical Specifications (TS) 4.9.A.1 and 4.9.8.1 require that the liquid and gaseous effluent monitors be calibrated quarterly.
TS 4.8.A and 4.8.C require that the liquid effluent monitor and stack gas monitors alarm prior to exceeding TS 3.8.A or 3.8.C discharge limits.
The inspector verified that the liquid efflent monitor had been calibrated for the first two quarters of 1979 in accordance with licensee procedure OP-4511.
Calibration data recorded on forms VYOPF-4511.06 and VYOPF-4511.07 was reviewed.
The calibrations of the stack gas monitors for the first two quarters of 1979 were also found to have been performed in accordance with OP-4511.
Data recorded on form VYOPF-4511.05 was reviewed.
The alarm setpoint for the stack monitors was found to be set conservatively relative to the TS 3.8.C limits.
No items of noncompliance were identified.
1466 139
.
o 7.
Procedures The inspector reviewed the following licensee operating procedures (0.P.)
and departmental procedures (D.P.):
0.P. 2150, " Advanced Off Gas System", Revision 8 0.P. 2151, " Liquid Radwaste", Revision 6 0.P. 2611, " Gaseous Radwaste", Revision 7 D.P. 2631, " Radiochemical Instrumentation", Revision 3 0.P. 4610, " Filter Testing", Revision 6 0.P. 4511, " Source Calibration of Process Radiation Monitoring System (PRMS)", Revision 8 The above operating procedures had been rev'?wed and approved by the Plant Operations Review Committee (PORC) ano the station superintendent in accordance with the licensee's Technical Specifications and Adminis-trative Procedures.
The above departmental procedure had been reviewed by the department head and station superintendent in accordance with Administrative Procedure 0001'.
The inspector made field observations to verify the licensee's compliance with procedures 0.P. 2611 and D.P. 2631.
No items of noncompliance were identified.
8.
Testing of Containment Air-Cleaning Systems Technical Specification 4.7.B requires that the Standby Gas Treatment System (SGTS) filters be tested at least once per 18 months and that charcoal filters be tested at least once per 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation (if this occurs sooner than 18 months).
Required tests include air dis-tribution, air flow, dioct3 1 pthalate (DOP) tests of High Efficiency Particulate Absolute (HEPA) filters, halogenated hydrocarbon (freon) tests of charcoal filters, and methy iodide tests of charcoal filters.
The required tests had been performed twice during the current fuel cycle (approximately 12 months).
The inspector reviewed the test data for the most recent test of the system the results of which are contained in Table I below:
TABLE I SGTS TEST RESULTS Date Train Test Test Requirement Test Result 3/1/79 A
DOP 99% removal 99.9%
3/2/79 A
Freon 99% removal 99.9%
3/1/79 A
Air Dist.
Deviated <20%
Pass 1466 140
.
TABLE I SGTS TEST RESULTS (Continued)
Date Train Test Test Reauirement Test Result 3/1/79 A
Air Flow 1500 cfm 10%
1495
- 3/6/79 A
CH I 95% removal 99.8%
3/9/79 B
00P 99% removal 99.85%
3/9/79 B
Freon 99% removal 99.99%
3/9/79
Air Dist.
deviation <20%
Pass 3/9/79 B
Air Flow 1500 cfm 10%
1607
- 3/15/79
CH I 95% removal 99.9%
n performed @ 130 C, 95% relative humidity, 40 fpm flow, between 1.7 and 3 CH I 2.0 mg/m
As the table shows the filters passed the required tests.
The inspector reviewed a sample of the raw field data (i.e., inlet concentrations) from the tests to verify that the test conditions could produce valid results.
No items of noncompliance were identified.
9.
Tests of Reactor Coolant Water Quality Technical Specification (TS) 3.6.8.1 requires that the concentration of I-131 dose equivalent of radiciodine in the reactor coolant shall not exceed 1.1 micorcuries per gram.
TS 4.6.B.1 requires the licensee to sample and analyze the reactor coolant for I-131 and I-135 at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and sample and analyze for gamma emitters monthly.
The timing and results of the licensees of reactor toolant radiciodine analyses were reviewed for the periods October 13 thru November 14, 1978, February 26 thru March 17, 1979 and May 18 thru July 10, 1979.
Monthly analyses of gamma emitters were reviewed for the period October, 1978 thru February, 1979.
The samples were taken within the specified frequency and the results were within the technical specification limits.
Technical Specifications 3.6.B.2, 3 and 4 limit conductivity and chlorides during various steaming conditions.
Technical Specifications 4.6.B.2 and 3 require sampling for conductivity once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or once per 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> depending on steaming rate.
The inspector reviewed the Heensee's analyses of conductivity and chlorides for the period February 28 thru darch 16, 1979 to verify that they had been taken within the specified interval and that the results were within the technical specification limits.
The con-trol room read out and recent strip chart record of the continuous con-ductivity monitor were found to be in agreement with the licensees most recent grab sample analysis of conductivity.
The licensee routinely compares the continuous monitor readings with the grab sample analyses when they are performed.
Ten randomly selected comparisons from the time 1466 141
.
~
.
' period January 1979 thru July 1979 were examined.
In all the cases examined the grab sample and continuous monitor yeilded results within
.02 p mho/cm.
No items of noncompliance were identified.
10.
Solid Radioactive Waste Fifteen low level solid waste shipments made between January 2, 1979 and June 22, 1W 9 were reviewed against the requirements of 10 CFR 71, " Pack-aging of Radioactive Material For Transport and Transportation of Radio-active Material Under Certain Conditions"; procedure A.P. 0504, " Shipment and Receipt of Radioactive Material", Technical Specification 6.6.A.7,
" Records of Radioactive Shiprents"; and 49 CFR 170-179.
Fourteen of the shipments were 170 cu. ft. casks of ion exchange and filter media (i.e.,
resins).
The other shipment included 55 gal drums of baled waste and wooden boxes of non-baleable waste.
Ge(Li) gamma spectral analyses of the isotopic content of the shipments were examined.
Curie contents and radiation survey data from the containers and vehicle were within limits.
No items of noncompliance were identified.
11.
Plant Tours During the course of the inspection three tours of the radiation control area (RCA) were performed, one upon initial arrival during the second (4:00 p.m. to midnight) shift on July 10, 1979.
Posting, barricading and locking of high radiation areas were examined.
Work in the RCA was observed to verify that good raiation safety practices and Radiation Work Permit requirements were followed.
Independent radiation surveys were performed to verify selected licensee posting and surveys.
The qualifications of auxiliary operators to perform as personnel " qualified in radiation protection procedures" on the off shifts was reviewed.
No items of noncompliance were identified.
12.
Exit Interview The inspector met with licensee management representatives (denoted in paragraph 1) at the conclusion of the inspectionon July 13, 1979.
The inspector summarized the purpose and scope of the inspection and the inspection findings.
1466 142