IR 05000313/1989014
| ML20246P299 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/02/1989 |
| From: | Baer R, Nicholas J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20246P265 | List: |
| References | |
| 50-313-89-14, 50-368-89-14, NUDOCS 8905220142 | |
| Download: ML20246P299 (15) | |
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APPENDIX B
.U.S.
NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-313/89-14 Operating Licenses:
DPR-51 50-368/89-14 NPF-6 Dockets:
50-313 50-368 Licensee:
Arkansas Power & Light Company (AP&L)
P.O. Box 551 Little Rock, Arkansas 72203
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Facility Name:
Inspection At:
AN0 Site, Russellville, Pope County, Arkansas
Inspection Conducted:
April 3-7,1989 Inspector:
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Jy/B. Nicholas, SeniortRadiation Specialist Date f4cilities Radiological Protection Section Approved:
R' E. Baer, Chief, Facilities Radiological Date Protection Section Inspection Summary Inspection Conducted April 3-7, 1989 (Report 50-313/89-14; 50-368/89-14)
Areas Inspected:
Routine, unannounced inspection of the licensee's liquid and gaseous radioactive waste management programs.
Results:
The NRC inspector determined that the licensee was implementing the radioactive waste effluent program (RWEP) in accordance with the Radiological Effluent Technical Specifications (RETS) and Offsite Dose Calculation Manual.(0DCM).
The quantities of radionuclides released in the radi n ctive waste effluents were within the limits specified in the RETS.
Offsit i doses had been calculated using methods specified in the ODCM and were within Technical Specification (TS) limits.
The licensee's ventilation systems had been tested in accordance with TS requirements.
Quality Assurance (QA)
surveillance and audits had been performed as required and were technically comprehensive.
The licensee had submitted their Semiannual Effluent Release Reports as per TS requirements.
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Within the areas inspected, two violations were identified:
(A) failure to
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maintain proper radiation monitor alarm setpoint and (B) radioactive liquid
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effluent release exceeding TS limits (see paragraphs'5 and 6).
No deviations 3"
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, were identi.fied.
One previously identified open item and one deviation were
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closed in paragraph 2.
Two Licensee Event Reports (LER) were closed in
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. paragraph 3.
One new open-item is discussed in paragraph 7.
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DETAILS 1.
Persons Contacted AP&L
- E. C. Ewing, General Manager, Plant Support S. M. Quennoz, Plant General Manager G. W. Bartlett, Surveillance Test Coordinator S. L. Capehart, Instrumentation and Control Maintenance Engineer
- M. E. Frala, Supervisor, Nuclear Chemistry
- H. T. Greene, Superintendent, QA L. W. Humphrey, General Manager, Nuclear Quality'
- D. B. Lomax, Supervisor, Licensing'
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A. B. McGregor, Superintendent, Engineering. Services
- S. J. McWilliams, Manager, Maintenance
- P. L. Michalk, Licensing Specialist
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D. J. Wagner, QA Engineer
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- H. D. Young, Engineering Technician, Engineering Services
- Denotes those individuals present"during the exit interview conducted on April 7, 1989.
2.
Followup on Previously Identified Inspection Findings (92701, 92702)
(Closed) Open Item (313/8818-01; 368/8818-01):
Semiannual Effluent Release Reports - This item was previously discussed in NRC Inspection Report 50-313/88-18; 50-368/88-18 and involved the erroneous reporting of radwaste shipped offsite during the second half of 1987 and the first half of 1988.
The licensee has prepared revisions to the two semiannual reports to include shipments of non-compactable dry active waste and spent fuel.
The revisions also correct the volume and curie content of the radioactive waste shipments.
The NRC inspector reviewed the revisions to the two semiannual effluent release reports and verified that the reported radwaste shipment data included all radwaste types shipped offsite during the two semiannual periods.
(Closed) Deviation (313/8827-01; 368/8827-01):
Organization and l
Responsibilities - This deviation was identified in NRC Inspection Report 50-313/88-27; 50-368/88-27 and involved the reporting chain for the radioactive waste superintendent.
The licensee's Updated Safety Analysis
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Report (USAR) for Units 1 and 2 had the radioactive waste superintendent
reporting to the health physics superintendent who was no longer l
responsible for radioactive waste operations.
The current organization, j
which has been in effect since August 1986, indicates that the radioactive l
waste superintendent reports cirectly to the manager of technical support.
i The licensee has removed the organization charts from the TS and the i
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current revision 6 of the USAR for Units 1 and 2 reflects the present organization.
The NRC inspector verified that the current organization is described in the licensee's QA Manual for Operations.
3.
Followup on Licensee Event-Reports (LER) (92700)
(Closed) LER (368/88-014):
Control Room Ventilation Radiation Monitor -
Setpoint - The event described in the LER involved the increasing of the j
alarm / trip setpoint on the Unit 2 control room ventilation radiation monitor to a value greater than two times background.
This increase in the monitor alarm / trip setpoint resulted in a failure to maintain the setpoint in accordance with the TS required value of less than or equal to two times background. This failure to maintain the requ red monitor alarm / trip setpoint is discussed in paragraph 5 of this report and is the subject of a Notice of Violation issued with this report.
(368/8914-01)
(Closed)-LER (313/88-007):
Radioactive Liquid Effluent Releases Exceeding Technical Specification Limit - The event described in the LER involved
,the release of radioactive liquid effluent at a concentration which exceeded the TS release limits.
This event was a repeat of.a'similar release that occurred in 1986.
The failure to meet release rate limits while discharging radioactive liquid effluents is discussed in paragraph 6 of this report and is the subject of a Notice of Violation issued with this report.
(313/8914-02)
4.
Open Items Identified During This Inspection An open item is a matter that requires further review and evaluation by the NRC inspector or licensee.
Open items are used to document, track, and ensure adequate followcp on matters of concern to the NRC inspector.
The following open item was identified:
Open Item Title Paragraph
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313/8914-03; Semiannual Effluent
368/8914-03 Release Report Dose-Data Format
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Radiation Monitoring Instrumentation 5.
The NRC inspector reviewed the licensee's process radiation monitoring instrumentation for agreement with the requirements in Section 3/4.3.3, Table 3.3-6 in the ANO Unit 2 TS.
TS 3/4.3.3.1, Table 3.3-6, Item 2.b, dealing with the'ANO Unit 2 control
. room ventilation intake duct process monitor, requires that the alarm / trip
)setpoint for this monitor, in all modes of plant operation, be set and maintained at a value of less than or equal to two times background.
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a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within-4 hours or declare the channel inoperable.
With the number of channels
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operable less than required by the minimum channels operable requirement, within I hour initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
In LER 368/88-14, dated October 6, 1988, the licensee identified to the NRC the facts surrounding and the subsequent evaluation of the failure to maintain the proper alarm /setpoint on the ANO Unit 2 control room ventilation process monitor or declare the monitor inoperable and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode.
The ANO Unit 2 control room ventilation system radiation monitor, 2 F.ITS-8750-1, is a process monitor used to measure radioactivity in the control room inlet air and initiates automatic isolation of the control room from outside air when the monitor's alarm / actuation setpoint is reached.
The background activity measured by the monitor is generally 250 cpm to 300 cpm.
The alarm / actuation setpoint is required by TS 3.3.3.1 to be set at less than or equal to twice the background level and is commonly set at 500 cpm.
ANO Unit 2 operations personnel records the control room ventilation monitor reading twice per shift and verifies daily that the setpoint is maintained as required by TS 3.3.3.1.
The setpoint is also checked and verified during the performance of a monthly channel function surveillance test.
The Shift Administrative Assistant (SAA) performs a daily calculation to establish an " average" monitor background reading to verify that the control room ventilation i
l radiation monitor setpoint is maintained at the required value.
If the setpoint is greater than two times the average daily background value, a job order is issued and the monitor setpoint is adjusted to mai.nt'ain the setpoint at a value less than or equal to twice the background readi'ng.
On August 11, 1988, during the performance of the, monitor monthly channel
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functional test, the indicated monitor background radiation level had I
increased causing the monitor to repeatedly actuate at the 500 cpm setpoint.
The Shift Supervisor directed the' maintenance technician to reset the monitor setpoint to 700 cpm and document the change on the i
placard mounted on the panel located below the mopitor readout.
The Shift Supervisor also notified the SAA of the setpoint change.
However, the SAA failed to note the setpoint change on the control room process monitor log and inform the oncoming relief SAA of the setpoint change.
On August 22, 1988, the ANO Unit 2 control room ventilation system radiation monitor's high alarm actuated the control room emergency ventilation system.
In response to the alarm, the SAA noted that the setpoint value on the placard below the monitor readout was 700 cpm and not 500 cpm as logged on the process monitor log.
Further review of the ANO Unit 2 process monitor logs, for the time period between August 11, 1988, through August 22, 1988, revealed that within a few hours after increasing the radiation monitor setpoint on August 11, 1988, the monitor background readings had decreased and returned to a normal range of approximately 200 cpm to 300 cpm. When this occurred, the existing setpoint of 700 cpm became greater than that allowed by the TS and should
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have been decreased to the required setting.
However, personnel taking
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. the usual 500 cpm setting; and, therefore no action was taken to correct
or change the setpoint.
/ ' As a result of this event, it was determined that the ANO Unit 2' control-room! ventilation radiation monitor was operated with an alarm /setpoint
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beyond.the allowable 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and without placing the control room emergency ventilation system in the recirculation mode.
The. failure to maintain the proper alarm /setpoint on the ANO Unit 2 control room ventilation process monitor or declare the monitor inoperable and' maintain f
operation of~the control room emergency ventilation system in the recirculation mode.is a violation of TS 3/4.3.3.1, Table 3.3-6, Item 2.b.
(368/8914-01)
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As a result of this event, the licensee took the following corrective actions:
Issued a job order for maintenance personnel to check and readjrst the monitor setpoint as necessary to maintain TS compliance.
The monitor setpoint was reset to 500 cpm on August 22, 1988, based on the indicated monitor background radiation level.
Pr5'edures which govern maintaining the monitor setpoints were res; sed to provide additional instructions and procedural controls to the SAAs and maintenance technicians, for ensuring that the setpoint is maintained within the TS limit and properly recorded.
The licensee's corrective actions were reviewed by the NRC inspector on April 4, 1989, and determined to be adequate to correct the violation and prevent a recurrence.
A review of selected ANO Unit 2 process monitor logs verified that the control room ventilation system radiation monitor alarm /setpoint was being maintained in compliance with TS requirements.
Therefore, it will not be required that the licensee respond to this violation in writing.
No deviations were identified.
6.
Radioactive Liquid and Gaseous Waste Systems (84750)
The NRC inspector reviewed the licensee's liquid and gaseous radioactive I
waste effluent programs including:
waste sampling, process and effluent monitors, procedures for radioactive waste and ef fluent systems, air cleaning systems, and audits and surveillance to determine adherence to i
commitments in Chapters 9, 11, and 17 in the Units 1 and 2 USAR and the I
requirements in Sections 3.5.6, 3.5.7, 3.9, 3.13, 3.15, 3.22, 3.25.1,
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3.25.2, 4.10, 4.11, 4.17, 4.25, 4.29.1, 4.29.2, 6.5.2.8, 6.8, and 6.14 of the Unit 1 TS and Sections 3/4.3.3.9, 3/4.3.3.10, 3/4.7.6, 3/4.9.4, l
3/4. 9.11, 3/4.11.1, 3/4.1L 2, 6. 5. 2.8, 6.8, and 6.14 of the Unit 2 TS.
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The NRC inspector reviewed the licensee's implementation of the.RETS and ODCM to ensure agreement with analysis sensitivities, reporting limits, analytical results, sampling requirements, surveillance tests, RWEP operating procedures, offsite dose results from effluents, and functional checks and calibrations of equipment associated with the RWEP.
Selected documents and records listed in Attachment 1 to this report were reviewed.
The NRC inspector reviewed current approved revisions of ANO procedures governing the release of liquid and gaseous radioactive waste.
These effluent release procedures provide for the following:
sampling of radioactive waste; radionuclides analysis prior to release; calculation.of effluent release rate, effluent adiation monitor setpoints, projected offsite radionuclides concentrations, end offsite doses prior to release; verification of effluent radiation nonitor setpoints and testing of effluent isolation valves prior to release; and verifying discharge flow rates and effluent volume discharged.
The NRC inspector reviewed selected liquid and gaseous release permits
.I which included batch liquid effluent releases from the various waste tanks, unit vent continuous gaseous releases, and batch releases from waste. gas-decay tanks and containment from botn Units 1 and 2 for the period January 1988 through December 1988.
It was determined that processing, sampling and analysis, and approval of the releases were conducted in accordance with ANO procedures.
Offsite doses had been calculated according to the ODCM and were within TS limits.
Effluent radiation monitor setpoints were calculated in accordance with the ODCM.
Quantities of radionuclides released in the liquid and gaseous effluents were within the limits specified in the RETS except for a liquid effluent release made on September 5, 1988, and is the subject of LER 313/88-007.
TS 3.25.1.1 states that the concentration of radioactive material released to the discharge canal shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
In LER 313/88-007, dated October 5, 1988,.the licensee identified to the NRC the facts surrounding and the subsequent evaluation of the release of radioactive liquid effluent at a release rate which exceeded the TS concentration limits.
Du'.'ing the review of completed documentation for a radioactive liquid effluent release performed on September 5, 1988, the licensee determined that the radioactive effluent concentration during the release exceeded the TS limit.
A review of previous liquid effluent releases,for Units 1 and'2 identified that a Unit 1 radioactive liquid effluent release performed on September 22, 1986, had also exceeded the TS limit.
The operators performing the releases failed to perform the f
releases in accordance'with the approved procedure.
This resulted in a higher than specified discharge rate of the radioactive liquid effluent into the discharge canal exceeding the discharge concentration TS limit.
l Prior to a radioactive liquid effluent release, a Liquid Radioactive Waste
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Pre-Release Permit is developed by the radiochemistry section based upon j
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the analysis-of a sample from the waste storage tank.
An acceptable discharge flow rate from the waste storage tank (release rate) is i
calculated so that upon dilution of the concentrated liquid waste by the
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circulating water flow in the discharge canal, the instantaneous concentration of radioactive material discharged to the unrestricted area is within the limits of 10 CFR Part 20, Appendix B, Table II, Column 2.
The release permit provides operations with the release rate to be used to discharge the waste storage tank.
Acceptable release rates.are specified in the pre-release report for each of the possible dilution flows, which are dependent on the number of circulating water pumps in operation at the time of the release.
Prior to performing each batch liquid effluent release, station procedures require the release rate from the waste storage tank be set according to the' number of operating cirt ulating water pumps.
The majority of radioactive liquid releases are of fJch low radioactivity levels that the maximum available release ratt of approximately 80 gpm is used.
The radioactive liquid effluent concentration value is determined based upon the Maximum Permissible Concentration (MPC) values specified by 10 CFR Part 20, Appendix 8, Table II, Column 2.
The ratio between the concentration of each radionuclides in the waste storage tank sample and its MPC is calculated and summed.
The sum of these ratios for each radionuclides in the waste storage tank sample may not exceed the limiting value of 1.
On September 22, 1986, three circulating water pumps were operating during the release and a calculated corresponding release rate of 33.8 gpm should have been used as specified by the pre-release report.
On September 5, 1988, only two circulating water pumps were operating during the release and a calculated corresponding release rate of 35.0 gpm should have been used as specified by the pre-release report.
However, during each release, a release rate of approximately 80 gpm was used.
This resulted in the release of approximately 8000 gallons of radioactive liquid waste at an instantaneous concentration value of 1.07 on September 22, 1986, and approximately 200 gall.,o-of radioactive liquid waste at an instantaneous concentration value c i 03 on September 5, 1988.
The failure to perfoi'
the radioactive liquid waste discharges in such a mar,ner as not to exceed the instantaneous concentration MPC value of 1 is a violation of TS 3.25.1.1.
(313/8914-02)
As a result of this event, the licensee took the following corrective actions:
The operators involved in the September 5, 1988, release have been disciplined on the requirement to strictly follow the requirements of plant procedure implementation.
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Operations personnel for ANO Units 1 and 2 have been made aware of
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the event and the necessity of reviewing the pre-release report and
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establishing and maintaining the correct release rate for the current-station operating conditions prior to and during radioactive liquid releases.
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Procedures' governing radioactive liquid effluent releases have'been'
changed to provide clarifications that will. reduce the possibility of.
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future procedural errors of this type.
'The. licensee's corrective actions were reviewed by the NRC inspector on
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April 4,'1989, and determined to be adequate to correct the; violation and prevent'a recurrence.
Therefore, it will not be required that the.
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license'e respond to this ' violation in writing, t
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- The NRC_ inspector determined that the contract awardedzto Duratek Company.
to process liquid.radwaste had been expanded to include the processing of waste from both Units 1.and 2.
The current contract is in effect through December 31, 1990.
The Duratek' Enhanced Volume Reduction Processing
' System replaces various radwaste filters, demineralizers, and tanks in the two units.
No major design changes were noted in the gaseous radioactive waste systems.
The NRC inspector reviewed functional checks, source checks, calibrations,
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and setpoint-procedures and records for process and radioactive waste effluent monitors which indicated that the frequency of monitor checks and calibrations met TS; requirements.
The monitor calibrations and setpoint determinations were verified to have been performed according to procedures.
The NRCfinspector reviewed the licensee's procedures, surveillance tests, and' selected records and test results'for: maintenance and testing of air cleaning systems which contain highLefficiency particulate air (HEPA)
filters and activated charcoal adsorbers.
The NRC inspector. verified that the licensee's procedures and surveillance tests,provided for the required periodic functional checking of ventilation sfstem' components, evaluation of HEPA filters and activated charcoal adsorbersi and replacement and
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in place filter testing _of filter systems.
The NRC inspector reviewed selected records and test results-for the period January 1987 through
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March 1989 for the Unit 1 penetration room.ventila. tion system, fuel
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handling arsa ventilation system, reactor building purge' filtration i
system, and control room emergency air conditioning. and isolation system
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and the Unit 2 fuel handling area ventilation system *," containment building
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purgeandexhaustsystem,andcontrolioomemergency+ air'conditioningand air filtration system.
The in place"filtert testirig and
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laboratory. tests had been performed ~ by a, contractor < usin{ activated charcoal g approved procedures.and all test results were verified'to be within TS limits.
Th'e
'licenseehadperformedaQAaudit,onfhecontractorperformingthetesting on the station ventilation systems and had placed the contractor on the
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ANO qualified vendors list.
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s The NRC inspector reviewed audit and surveillance schedules for 1988 and 1989 and the qualifications of QA aud,itors.
Surveillance and audit
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m reports of QA activities performed during the period January 1988 through March 1989 in the area of RWEP were reviewed for scope, thoroughness of
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program evaluation, and timely followup of identified deficiencies.
The i
NRC inspector also reviewed the audit report of the contractor used to
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perform the testing on the station. ventilation systems.
The NRC inspector
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determined that the QA surveillance and audits had been performed in i
accordance with ANO QA procedures and schedules and had not identified any i
significant problems.
The documents which were reviewed are listed in-Attachment 1 to this report.
No deviations were identified.
7., Reports of Radioactive Effluents
.J4750)
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, iThe NRC inspector reviewed th' iicensee's reports concerning radwaste s
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' systems and effluent releases to determine compliance with the requirements of 10 CFR Part 50.36(a)(2) and Section 6.12.2.6 of the Unit-1 TS and Section 6.9.3 of the Unit 2 TS.
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The'NRC ; inspector reviewed the semiannual effluent release reports for the
a periods' January 1 through June 30, 1988, and July 1 through December 31, ' '
1988.
These reports were written in the format described in NRC
" Regulatory' Guide 1.21 and contained the information required by TS.
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. was noted that the first report filed each year contained a summary 0f
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radiation doses due to radiological effluents during the previous calendar
, year calculated'in accordance with the methodology specified in the ODCM.
However, th_e data was not presented in such a manner as to easily
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determine compliance with TS requirements.
The licensee had not provided
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'a ;echnical explanation or summary of the @' a in the semiannual reports in a format which provided a direct correlation to TS requirements.
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item was discussed with the licensee during the exit interview an April 7,
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The licensee agreed to evaluate the NRC inspector's concern and
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take the necessary action to improve the radiation dose data presentation
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in the semiannual effluent release reports.
This is considered to be open item (313/8914-03; 368/8914-03) pending completion of the licensee's evaluation.
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No violations or deviations were identified.
l 8.
Exit Interview (30703)
The NRC inspector met with the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on April 7, 1989.
The NRC
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inspector summarized the scope and findings of the inspection and I
discussed the details of the violations and open item.
The licensee representatives stated at the exit interview that they would evaluate the NRC inspector's concern expressed as an open item and take necessary
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action to implement documentation improvements.
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ATTACHMENT 1 Arkansas Nuclear One NRC Inspection Report:
50-313/89-14 and 50-368/89-14 Documents Reviewed Title Revision Date 1.
Administrative Procedure 1042.003, Radiochemistry Routine Surveillance
01/13/88 Schedule and Tech. Spec. Surveillance Reporting 2.
Chemistry / Radiochemistry Procedures 1604.001, Gross Alpha Measurement
06/25/88 1604.002, Gross Beta and Gamma Spectroscopy
04/13/87 Sample Preparation 1604.003, Tritium Sample Preparation
02/14/89
1604.004, Liquid Scintillation Counting For
02/14/89 Gross Beta and Tritium Measurements 1604.009, Radiostrontium Determination
03/07/89 1604.014, Reactor Building Purge Analysis 10-01/30/86 1604.015, Analysis of Unit Vent and Condenser
06/18/88 Vacuum Pump 1604.016, Analysis of Gaseous Waste Decay Tanks.
01/30/86 1604.017, Analysis of Liquid Waste
12/23/87 1607.007, Sampling the Laundry Drain Tanks
04/15/87 s
1607.008, Sampling the Filtered Waste Monitor
10/24/88 Tank (T-21 A/B)
1607.009, Sampling the Treated Waste Monitor
~7 04/15/87 l
Tanks (T-16 A/B)
1607.010, Samp1:..s of the ANO Unit 1 Vent
'07/20/88 l
1607.014, Reactor Building Purge Sampling
01/14/87 Procedure l
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1607.018, Sampling the Unit 1 Waste Gas Decay
01/14/87
. Tanks and Surge Tank
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1607.023, Sampling the Unit 1 Neutralizing Tank
02/27/86 1607.024,' Unit 1 Dirty Waste Drain Tank
01/13/88 (T-20 A/B) Sampling Procedure i
2607.008, Unit 2 Waste Tank (2T-20 A/B)
06/08/87 Sampling Procedure 2607.009, Sampling the Unit 2 Waste Condensate
10/02/87
2607.010, Sampling the Unit 2 Vents
01/14/87 2607.014, Reactor Building Purge Sampling
01/14/87 Procedure 2607.016, Sampling the Unit 2 Holdup Tanks
03/16/85 (2T-12A, B, C, and D)
2607.018, Sampling the Waste Gas Decay Tanks,
01/14/87 Surge Tank, and Volume Control Tank Gas Space on Unit 2 2607.026, Sampling the Regenerative Waste Tanks
03/07/85 (2T-92A, B, and C)
3.
Operations Procedures 1104.014, Dirty Liquid Waste and Drain
04/30/87 Processing 1104.015, Laundry Waste Processing
05/21/87 1104.020, Clean Waste System Operation
01/27/88 1104.022, Gaseous Radwaste System
12/05/87 1104.033, Reactor Building Ventilation
03/11/88 2104.010, Unit 2 Waste Gas Analyzer Operation
02/17/88 2104.014, Liquid Waste Systems Operation
11/17/87 2104.022, Gaseous Radwaste System
03/11/88
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Surveillance Procedures
- 1092.081, In-Place Leak Testing of. Ventilation'
CL 03/22/88; Systems.Containing.HEPA and Carbon Filters 1802.001, Interrogation of Tech. Spec.
07/21/84 Surveillance Limitations, Safety-Related Ventilation Systems 1304.026, Process Radiation Mcnitoring System
05/29/86 Quarterly Calibration 1304.027, Unit 1 Process Radiation Monitoring
03/11/88 System Calibration 1304.077, Channel Test of GERMS for Radwaste
09/04/87 Area Rx-9825 1304.131, Liquid Radwaste Instrument
08/21/87 Calibration 1304.132, Unit 1 Gaseous Radwaste
06/24/88 Instrumentation Calibration 1304.138, Calibration of GERMS for Radwaste
08/05/87 Area.Rx-9825 1305.001, Radiation Monitoring System Check and
01/15/88 Test 2304.006, Gaseous Process Radiation Monitoring
01/20/88 System Calibration 2304.016, Process Radiation Monitoring System
08/21/87 Test 2304.027, Liquid Process Radiation Monitoring
07/06/88 System Calibration 2304.028, Area Radiation Monitoring System
01/27/88 Calibration 2304.059, Area Radiation Monitoring System
09/12/85 Monthly Test 2304.133, Containment High Range Radiation
11/27/d7 Monitor 2304.137, Calibration of GERMS for Containment
12/16/88 Purge 2Rx-9820
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2304.138,- Calibration of. GERMS for Radwaste
08/05/87 Area 2Rx-9825 2304.139, Calibration of GERMS for Fuel
08/05/87
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Handling Area 2Rx-9830 2304.142, Calibration of GERMS for Aux.'
08/05/87 Building Ext. 2Rx-9845 2304.148, High Range Containment Radiation
02/20/E5 Monitor Test t
'2304.149, Channel Test of GERMS for Containment
03/04/88 Purge 2Rx-9820
2304.150, Channel Test of GERMS for Radwaste
09/04/87 Area 2Rx-9825 2304.151, Channel Test of GERMS for Radwaste
03/04/88 Area 2Rx-9830 2304.154, Channel Test of GERMS for Auxiliary
03/04/88 Building 2Rx-9845 2304.155, Channel Test of GERMS for Low Level
03/04/88-Radwaste' Storage 8uilding 2Rx-9850
- 2304.156, Calibration of GERMS for Low Level
11/23/87 Radwaste Storage Building 2Rv-9850 5.
. Quality Assurance (QA) Surveillance and Audits
.1987-1989 Nuclear Quality Audit Schedule, Revision 1, 07/25/88
.QA Surveillance Report 88-140, " Unit 1 Liquid Radwaste Instrumentation
' Calibration," dated July 5, 1988
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,
QA Surveillance Report 88-147, "Radwaste Annunciators," dated July 21-22, 1988
'QA Surveillance Report 88-175, " Unit 2 Waste Gas Analyzer (2C382A)
Operation," dated August 17, 1988 QA Surveillance Report 88-251, " Unit 1 Process Monitor Test Check," dated November 9,:1988 i
QA Audit Report, QAP-28-88, "ANO Environmental Monitoring Program,"
performed March 1, 1988 - May 25, 1988 QA Vendor CASE Audit Report, " Nuclear Containment Systems," dated December 5, 1986
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AN0 Semiannual Effluent Release Reports January 1 through June 30, 1988 July 1 through December 31, 1988 l
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