IR 05000267/1981028
| ML20041B326 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/10/1982 |
| From: | Brown G, Holley W, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20041B211 | List: |
| References | |
| 50-267-81-28, NUDOCS 8202230531 | |
| Download: ML20041B326 (9) | |
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V. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-267/81-28 License: DPR-34 Docket:
50-267 Licensee:
Public Service Company of Colorado (PSCo)
P. O. Box 840 Denver, Colorado 80201 Facility:
Ft. St. Vrain Nuclear Generating Station (FSV)
Location: Platteville, C0 j
Inspection Conducted:
December 7-11, 1981 Inspectors:
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W' L. Hol
,11adia~ tion Spe alist D&tif
$/14 tam e M BD2-Blaine Murray, Chief, cility Radiation Date /
Protection Section Approved by:
M 2/hd2.
Glen D. Brown, Chief, iechnical Inspection Date Branch
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Inspection Summary Inspection conducted during December 7-11,1981-(Report 50-267/81-28).
Areas Inspected: Routine unannounced inspection of the licensee's radwaste program including:
liquid and gaseous radioactive effluent releases; records and reports of radioactive effluents; effluent control instrumentation; procedures for controlling the release of effluents; testing of air cleaning systems; reactor coolant quality; licensee audits of radiochemistry-activities; radiochemistry organization; health physic organization; and solid radioactive waste. The inspection involved 64 onsite hours.by two inspectors.
Results: One violation was identified during the inspection:
(Failure to use titanium sponge, see paragraph 5.b).
Three open items are discussed in paragraphs 7, 9.b, and 13. One unresolved item is discussed in paragraph 9.a.
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DETAILS 1.
Persons Contacted a.
Public Service Company of Colorado (PSCo)
- M. L. Block, Superintendent of Operations
- T. J. Borst, Radiation Protection Manager
- W. L. Franek, Nuclear Site Engineering Manager
- J. W. Gahm, Quality Assurance Manager J. Glass, Acting Scheduling and Stores Supervisor M. Lombard, Design Engineer
- L. M. McBride, Technical / Administrative Sr vices Manager V. McGaffic, Chief Radiochemist M. Prochownick, Radiochemist D. Miller, Radiochemist R. Reiss, Quality Assurance Engineer
- T. Schleiger, Health Physics Supervisor
- L. W. Singleton, Quality Assurance Operations Superintendent D. Warembourg, Nuclear Production Manager W. Woodard, Plant Health Physicist b.
Other Personnel
- M. Dickerson, NRC Resident Inspector
- G. Plumlee III, NRC Resident Inspector
- Denotes those present during the exit interview.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item 78-15/01: An unresolved item regarding the use of the reactor building sump as part of the radwaste system was discussed in Report 50-267/78-15. A position on this item has not been received from NRR. This item remains open.
3.
Open and Unresolved Items Identified During This Inspection (0 pen) Open Item (50-267/81-28/01):
Gaseous Iodine / Particulate and Liquid Monitors (monitors RT-7324-1&2 and RT-6212, and 6213, respectively).
The licensee has not developed a comprehensive calibration and testing program that satisfies the recommendations of ANSI-N323-1978.
See Section 7 of this report.
(0 pen) Open Item (50-267/81-28/02):
Control Room Filter and Technical ISupport Center Filters. The licensee has not included these systems t n a routine surveillance program.
See Section 9.b for additional i
Wetails.
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(0 pen) Open Item (50-267/81-28/03):
Lic uid Waste System.
Several liquid waste discharges during 1980-81 exceedec release limits.
Proposed modifications of the liquid radwaste system to correct these problems have not been completed.
See Section 13 for additional details.
(Unrcsolved) Unresolved Item (50-267/81-28/01), Reactor Building Exhaust Filters:
Documentation was not available to determine if filters had been tested to meet the requirements of the Technical Specifications. See Section 9.a for additional details.
4.
Scope of Inspection The purpose of this inspection was to review the licensee's radwaste program for the period October 1,1978 through December 1,1981.
5.
Radioactive Effluent Releases a.
Liquid The inspectors examined the liquid effluent release program to determine compliance with items 4.8.2 ano 5.8.2 of the Technical Specifications.
No violations or deviations were identified.
b.
Gaseous The inspectors examined the gaseous effluent release program to determine compliance with items 4.8.1 and 5.8.1 of the Technical Specifications.
The inspectors determined that the titanium sponge in the helium purification system had been out of service since April,1980.
Technical Specification LC0 4.8.1.c states, " Plant equipment in the helium purification system (the high temperature filter adsorber, the low temperature absorber and the titanium sponge), in the gaseous waste system (vacuum tank, liquid drain tank, filters, compressor, surge tanks and reactor building filters), and analytical and monitoring instrumentation shall be utilized to keep releases of radioactive materials to unrestricted areas as low as practicable and to assure surveillance of radioactive gaseous waste produced during normal reactor operations and expected operational occurrences."
Failure to have the titanium sponge in service during operations is considered a violation against Technical Specification LC0 4.8.1.c.
This is a Severity Level V violation.
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6.
Records and Reports of Radioactive Effluents The inspectors reviewed records and reports required by 10 CFR 50.36a(a)(2). The licensee's semiannual reports conform to the format
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recommended in Regulatory Guide 1.21.
No violations or deviations were identified.
7.
Effluent Control Instrumentation The inspectors examined records and procedures regarding calibration results, response tests, operational checks, and alarm set-points for the
.various liquid and gaseous effluent monitors to determine compliance with items 4.8.1, 4.8.2, 5.8.1, and 5.8.2 of the Technical Specifications.
The licensee had developed a good program for calibration of_the noble gas monitors (RT-6314-2,RT-7324-1,andRT-7324-2). This program consisted of a quarterly full scale calibration with various known gas concentrations.
However, a similar comprehensive program had not been established for the gaseous iodine / particulate (RT-7325-1) and (RT-7325-2) and the liquid monitors (RT-6212 and RT-6213). The iodine / particulate and liquid monitors were full scale source calibrated as a part of the pre-operational testing program in 1973.
Since 1973, the iodine / particulate and liquid monitors calibration procedures have only included response testing with solid reference sources. _ Problems associated with adjusting the alarm-set points were discussed in Inspection Report 50-267/78-15.
Test results indicated that the iodine / particulate monitors were not tested over the full range of the instrument. The effluent monitors have a full scale read-out of about E+06 counts per minute (cpm). However, the information appearing on surveillance results forms SR 5.8.1 cd-Q, Radioactive Gaseous Effluent System Calibration and SR 5.8.2 c-Q, Radioactive Liquid Activity Monitor Calibration indicated 'that the gaseous iodine / particulate were calibrated / response tested with radioactive sources for a high scale reference point at about E+05 cpm and the liquid monitor tested at about 1.2 E+05 cpm. These data indicate v
that calibration / response test reference points were only established for less than 50% of full scale read-out. ANSI-N323-1978, Radiation Protection Instrumentation Test and Calibration recommends that radiation oetection instrumentation be calibrated at approximately 20%
and 80% of full scale.
The licensee acknowledged that discrepancies existed between the calibration program established for the noble gas monitors versus the program in use for the iodine / particulate and liquid monitors. The
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licensee stated during the exit interview on December 11, 1981, that a calibration program would be developed that satisfies the recommendations of ANSI-N323-1978.
This item is considered open (81-28/01).
No violations or deviations were identified.
8.
Procedures for Controlling the Release of Effluents The following Surveillance Reports and Release Permits were reviewed during this inspection:
Surveillance Reports:
SR 5.2.11-W, Primary Reactor Coolant Radioactivity Analysis SR 5.2.12-W, Primary Reactor Coolant Chemical Analysis SR 5.3.7-W, Secondary Coolant Activity SR 5.4.9-W, Area and Miscellaneous Process Radiation Monitors Functional Test SR 5.5.3a-SA, Reactor Building Exhaust Filters SR 5.5.3abc-A, Reactor Building Exhaust Filters SR 5.5.3de-SA, Reactor Building Exhaust Filters - Charcoal Filter Samples SR 5.8.labc-M, Radioactive Gaseous Effluent System Test SR 5.8.1cd-Q, Radioactive Gaseous Effluent System Calibration SR 5.8.le-A, Radioactive Gaseous Effluent Flow Recorders Calibration SR 5.8.1f-W, Radioactive Gaseous Effluent Vent Iodine / Particulate Filter Analysis SR 5.8.2a-A, Radioactive Liquid Effluent System SR 5.8.2bc-M, Radioactive Liquid Effluent System Instrumentation SR 5.8.2c-Q, Radioactive Liquid Effluent Activity Monitor Calibration Liquid Release Permits (January 1 - November 30,1981)
Form (c)372-02-2535
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Gaseous Release Pennits (January 1 - November 30,1981)
Form (c) 372-02-25366 The licensee's release permits indicate that the following items are verified as part of releases made from the various hold-up tanks:
-Compliance with Technical Specifications-Total activity released-Total volume released-Duration of release-Response test of effluent monitors-Dilution flow rate-Maximum allowable release rate-Effluent monitor set-point-Total activity released-Authorization signatures No violations or deviations were identified.
9.
Testing of Air-Cleaning Systems a.
Technical Specification Systems The inspectors were unable to determine from the review surveillance results SR 5.5.3a-SA, Reactor Building Exhaust Filters - Charcoal Filter Samples if the requirements of Technical Specification SR 5.5.3(d) were satisfied.
Specification SR 5.5.3.d states, " Flow distribution across the HEPA and charcoal filter will be tested with initial operation of the system and following any structural modification to the filter housings. Air distribution shall be demonstrated within 20% across the HEPA and charcoal filter when tested in accordance with ANSI-N510-1975."
The licensee stated that testing had been completed in accordance with SR 5.5.3(d), but the documentation regarding these tests could not be located during this inspection. This item is considered unresolved pending review of the test results.
(81-28/01),
b.
Non-Technical Specification Items Discussions with the licensee revealed that the control room filter system (F-7502, F-7503, F-7504, and C-7506) was not included in a routine surveillance testing program. This filter system is designed to be activated in the event of a high alarm from certain stack effluent monitors and provide proper atmospheric conditions for
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personnel in the control room during a radioactive release. The licensee was unable to locate documentation that would indicate that the system had been tested in order to meet the design objectives appearing in the FSAR. The licensee stated during the exit interview on December 11, 1981, that testing requirements for the control room and the Technical Support Cer.ter would be evaluated in order to satisfy the recommendations of Regulatory Guides 1.52 and 1.140.
This item is considered open (81-28/04).
10.
Reactor Coolant Quality The inspectors examined analyses results of reactor coolant to determine compliance with the Technical Specifications 4.2.8, 4.3.8, 5.2.11, 5.2.12, and 5.3.7.
No violations or deviations were identified.
11.
Radioactive Solid Waste The inspectois determined that no radioactive waste has been shipped off-site since issuance of the OL in 1973.
12. Audits The inspectors examined audits conducted by the licensee's QA Department of radwaste and radiochemistry activities for the period October 1, 1978-November 1, 1981. The following audits were reviewed:
QAA-601-79-1, Water Chemistry and Radiochemistry, August 27, 1979 QA-81-007, Radioactive Gas Waste Systems Operability, December 30, 1980 QAMN-P3-5, Quality Assurance Monitoring Checklist Radioactive Liquid Waste System Operability, April 6, 1981 QAA-601-81-01, Water Chemistry and Radiochemistry, July 16, 1981 QAA-1501-81-01, Radioactive Solid Waste Disposal, September 3, 1981 This audit reports indicated that timely corrective action was completed for those deficiencies identified in the reports.
No violations or deviations were identified.
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13.
Reportable Occurrences (R0s)
The. inspectors reviewed R0s documented by the licensee regarding'radwaste
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activities during 1980-81. The following-R0s were reviewed:
80-52, September 25, 1980: Tritium concentrations exceeded Technical Specification 4.8.2(a) limits.
(150 gallon" dead. leg"indischargeline).
80-67, November 7,1980: Tritium concentrations exceeded Technical Specification 4.8.2(a) limits.
(Sensitivity of discharge flow valve
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inadequate for low flow rates)
81-13, February 3,1981: Tritium concentrations exceeded Technical Specifications 4.8.2(a) limits. (Inadequate discharge flow regulator)
81.34, April 29, 1981: Tritium concentrations exceeded Technical
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Specifications 4.8.2(a) limits.
(Inadequate blowdown dilution)
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81-36, May 12, 1981: Tritium concentrations exceeded Technical
Specification 4.8.2(a) limits.- (Inadequate blowdown dilution)
The licensee's documentation indicated that the above R0s resulted from a variety of problems associated with the liquid waste system. These-problems included " dead legs" in the discharge lines, sludge in the discharge. line, leaky valves, inadequate sensitivity for low flow rates,
and inadequate flow controls. The licensee had completed a review of the problems contributing to the R0s. The proposed corrective action was included in Design Change - Action Request (DC-AR) 113 and Change Notice
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(CN)1433. The inspector discussed the proposed corrective action with licensee personnel responsible for initiating and completing DC-AR-113 and
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CN-1433. The licensee stated that the proposed modifications should be i
completed early 1982. This item is considered open pending completion of l
DC-AR-113 and CN-1433.
14.
Plant Tour The inspectors toured the plant on December 8, 1981.
Particular attention was given to the radwaste system and effluent monitors. The inspectors observed the detector locations and their associated read-out instrumentation in the control room. The inspectors verified that the
.~ollowing monitors and recorders were in service and operating:
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RIS 2263, Reheat. Steam Condensate Monitor Recorder RIS 6212, Radioactive Liquid Waste Effluent Monitor Recorder
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RIS 6213, Radioactive Liquid Waste Effluent Monitor Recorder RIS 6314-1, Gas Waste Effluent Particulate and Iodine Monitor Recorder RIS 7324-1&2, Reactor Plant Ventilation Exhaust Gas Beta Monitor Recorder RIS 7325-1, Turbine Building Particulate and Iodine Monitor Recorder RIS 9301, Primary Coolant Beta Gas Monitor Recorder RIS 21251, Low Pressure Separator Drain Line Monitor Recorder RIS 46211, Waste Gas Compressor Cooling Water Monitor Recorder RT 7312, Beta Gas Radioactivity Building Monitor RT 7324-1&2, Reactor Plant Ventilation Exhaust Gas Beta Monitor RT 9302, Gas Beta Monitor RT 73437-1&2, Reactor Buildiag Vent Stack Monitor 15. Unresolved Items Unresolved Items are matter!, about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. The unresolved item disclosed during this (
inspection is discussed in paragraph 9.a.
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Exit Interview l
l At the conclusion of the inspection on December 11, 1981, the inspection l
findings were discussed with the individuals denoted in paragraph 1.
The
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inspector summarized the scope of the inspection and the inspection l
findings. The licensee made specific commitments regarding the following
items:
.A comprehensive caliscation and testing program will be established for the gaseous iodine / particulate (RT-7324-1 and 2) and the liquid monitors (RT-6212 and 6213) that will satisfy ANSI-N323-1978.
. A routine surveillance testing program for the control room and Technical Support Center filter systems would be developed to satisfy the recommendations of Regulatory Guides 1.52 and 1.140.
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