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| {{Adams | | {{Adams |
| | number = ML20203P182 | | | number = ML20212E228 |
| | issue date = 10/15/1986 | | | issue date = 12/24/1986 |
| | title = Partially Withheld Insp Rept 50-188/86-02 on 860909-10. Violation Noted:Failure to Perform Semiannual Calibr of Listed Portable Survey Instruments & Written Instruction Not in Effect for Spectroscopy Sys | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-188/86-02 |
| | author name = Murray B, Wise R | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Faw R |
| | addressee affiliation = | | | addressee affiliation = KANSAS STATE UNIV., MANHATTAN, KS |
| | docket = 05000188 | | | docket = 05000188 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-188-86-02, 50-188-86-2, NUDOCS 8610270093 | | | document report number = NUDOCS 8701050278 |
| | package number = ML20203P177 | | | title reference date = 11-17-1986 |
| | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO EDUCATIONAL INSTITUTION, OUTGOING CORRESPONDENCE |
| | page count = 8 | | | page count = 1 |
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| I APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
| | ., 4 DEC 2 41986 in Reply Refer To: |
| . REGION IV NRC Inspection Report: 50-188/86-02 License: R-88 Docket: 50-188 Licensee: Kansas State University (KSU)
| | Docket: 50-188/86-02 Kansas State University Department of Nuclear Engineering ATTN: Dr. R. E. Faw, Director Nuclear Reactor Facility Manhattan, Kansas 66505 Gentlemen: |
| Department of Nuclear Engineering Manhattan, Kansas 66505 Facility Name: Kansas State University Inspection At: Manhattan, Kansas Inspection Conducted: September 9-10, 1986 Inspector: <^="''-"= | | Thank you for your letter of November 17, 1986, in response to our letter |
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| /0//f/~ M Russell Wise, Radiation Specialist, Facilities Date Radiological Protection Section f
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| Approved: jd)tATgf BaineMurray(,Lhief,F)cilitiesRadiologicalDate
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| Protection Section /
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| Inspection Summar Inspection Conducted September 9-10, 1986 (Report 50-188/86-02)
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| Areas Inspected: Routine, unannounced inspection of the licensee's program including: (1) radiation protection, (2) emergency preparedness, (3) material accountability, and (4) physical securit Results- Within the areas inspected, three violations were identified (see paragraphs 3.a. 3.d, and 3.e).
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| FM.Af OVAL CF THE PAGES M ARKEO " SAFEGUARDS I pECONTROLS THE REMAINDER OF THIS DOCUMEN ,
| | and Notice of Violation dated October 20, 1986. We have reviewed your reply l and find it responsive to the concerns raised in our Notice of Violation. We l will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintai,ed. |
| 8610270093 861020 PDR ADOCK 05000188 G PDR
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| | Sincerely, ORIGINAL SIGNED BY: |
| . DETAILS Persons Contacted
| | J. E. Gagliardo, Chief Reactor Projects Branch cc: |
| *N. D. Eckhoff, Department Head, Nuclear Engineering
| | Kansas Radiation Control Program bec to DMB (IE06) |
| *R. E. Faw, Director, Nuclear Reactor Facility (NRF)
| | bcc distrib. by RIV: |
| *J. F. Higginbotham, Reactor Supervisor
| | RPB Resident Inspector R. D. Martin, RA R&SPB Section Chief (RPB/B) D. Weiss, LFMB (AR-2015) |
| *F. L. Ferguson, General Manager, Physical Facilities
| | RIV File DRSP RSB MIS SYSTEM RSTS Operator Inspector Section Chief W. L. Fisher R. L. Bangart J. J. Dosa, NRR, Project Manager RIV:FRP C:FRPS C:R&SPB CRPB [ |
| *J. Lambert, Radiation Safety Of ficer
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| *G. Simonis, Professor
| | Wi se/j t BMurqay WLFisher JEGaghfrdo p to/ 86 y /gb/86 lg/jd/86 4,/Dj/86 |
| *J. Daniels, Reactor Operator
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| * J. Whitfield, Reactor Operator R. Tout, M.D., Director, Student Health Center C. A. Beckom, Chief, KSU Police G. D. Westcott, Industrial Hygienist E. M. Hupe, Administrative Officer, Physical Facilities
| | e701050278 861224 PDR O |
| * Denotes those present during the exit briefin . Inspector Observation The following are observations the NRC inspectors discussed with the licensee during the exit meeting on [[Exit meeting date::September 10, 1986]]. These observations are neither violations nor unresolved items. These items were recommended for licensee consideration for program improvement, but they have no specific regulatory requiremen Documentation of Instrumentation Calibration / Response Tests - Records of portable survey instrument calibrations and alarm setpoint tests did not indicate what calibration source was used or who had performed the calibratio (See paragraph 3.a.) Calibration of Area Monitor - The area radiation monitor which actuates the evacuation alarm is not currently calibrated above 100 mR/ (See paragraph 3.b.) Personnel Monitoring - Personnel monitoring devices were not approved by National Voluntary Laboratory Accreditation for Personnel i Dosimetry (NVLAP). (See paragraph 3.d.) Neutron Surveys - Neutron radiation levels had not been establishe (See paragraph 3.f.)
| | ADOCK 05000188 PDR |
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| ' CFR Part 19.12 Training - Documentation of radiation worker
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| 10 CFR 19.1 (See paragraph 3.g.)
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| | Department of Nuclear Engineering ICAlqSAS Ward Hall N |
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| | November 17, 1986 U.S. Nuclear Regulatory Commission Region IV Attn: J. E. Gagliardo, Chief Reactor Projects Branch 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 Re: License R-88 Docket 50-188 |
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| , Emergency Equipment - A high range instrument was not available in an
| | ==Dear Sirs:== |
| ; emergency ki (See paragraph 4.)
| | This is in response to your letter of 20 October 1986 and its attendant notice of violation. Our response is enclosed. |
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| REMOVAL OF THE PAGES MARKED " "
| | Sincerely, et<f f hin V Richard E. Faw, Director KSU Nuclear Reactor Facility REF/cs Enclosure |
| DECONTROLS THE REMAINDER OF THIS DOCUMEN . . _ . - . - _ . , _ _ _ . . _ . . . . - _ _ . . . , _ -
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| | RESPONSE TO NOTICE OF VIOLATION |
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| | Kansas State University (KSU) Docket: 50-188/86-02 TRICA MkII Reactor License: R-88 A. Failure to Perform Survey Instrument Calibration Reason for Violation This violation is admitted. The reasons are as follows: The Reactor Facility maintains and calibrates instruments for general use in the Nuclear Engineering Department. On some occasions, these general-purpose instruments are in use outside the Reactor Facility at the time of reactor-instrument calibratior.. Record keeping procedures hase been deficient in identification of those occasions. |
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| | Cprrective Steos Taken New record keeping procedures have been implemented. A master log of calibration dates has been instituted to supplement calibration logs for each instrument. |
| , Key Control - Documentation of personnel authorized access to the NRF was not curren (See paragraph 8.) Radiation Protection The licensee's radiation protection program was inspected to determine compliance with the requirements of Technical Specifications (TS) F and H; 10 CFR Parts 19 and 20; the KSU Emergency Plan; and the recommendations of NRC Regulatory Guide (RG) The NRC inspector reviewed records, interviewed personnel, made observations, and performed independent survey Radiation Measuring Instrumentation The NRC inspector reviewed calibration records for portable radiation survey instrumentation for 1983, 1984, 1985, and 1986. It was noted that calibration standards utilized for calibration and the' person who was performing the survey instrument calibration was not recorded on the data sheet. The licensee stated at the exit briefing on September 10, 1986, that this observation would be reviewe The NRC inspector noted that calibration of portable survey instrumentation was required to be performed in accordance with Section 10.5 of the KSV Emergency Plan, dated October 14, 1982, which
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| ; states, in part, that portable survey instruments will be calibrated i
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| semiannuall It was noted from the review of calibration records that the following five portable radiation monitoring instruments had been used to determine radiation levels, but had not been calibrated semiannuall Eberline Model E-120, Serial Number (S/N) 915, June 1984 -
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| July 1985 i
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| Eberline Model E-120,.S/N 940, January - December 1985
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| ; Eberline Model E-500B, S/N 968, January - December 1985
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| Eberline Model E-500B, S/N 1021, January - September 1985 Eberline Model E-510, S/N 153, July 1985 - June 1986 The feilure to calibrate radiation monitoring instruments semiannually as required is an apparent violation of Secticn 10.5 of the KSU Emergency Pla (188-8602-01) Area Radiation Monitors (ARMS)
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| The NRC inspector reviewed the licensee's calibration programs for ARMS which are required to be function tested daily during operations, response tested quarterly, and calibrated annuall REMOVAL OF THE PAGES MARKED " "
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| DECONTROLS THE REMAINDER OF THIS DOCUMEN __ . _ _ - .
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| | Corrective Steos to be Taken At the time of the next calibration, those instruments not required for reactor surveillance are to be sequestered in their own storage location. |
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| | All instruments are to be tagged with identification of their use (reactor or non-reactor) and the calibration expiration date. |
| , The NRC inspector noted that documentation regarding calibration of the ARM consists of a label placed on the readout panel of the instrument: no other documentation was utilized to indicate what sources were used, who performed the calibration, or the ranges of operation at which the instrument was calibrate The NRC inspector noted that an area radiation monitor identified in Section 8.3.1 of the KSU Emargency Plan, which actuates the ,
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| evacuation alarm at an exposure rate of 5 R/h, is only calibrated at an upper radiation level of 100 mR/h The NRC inspector discussed the need to calibrate instrumentation over the ranges of operation addressed in the Emergency Pla Continuous Air Monitor (CAM)
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| The NRC inspector reviewed the licensee's program for monitoring airborne concentrations within the reactor bay to determine compliance with Sections F and H of the TS and Section 8.3.1 of the Emergency Pla Section 8.3.1 of the Emergency Plan states that the CAM is sensitive to radioiodine and alarms at maximum permissible air concentrations of Iodine-131 in restricted areas. The licensee stated that the instrument is calibrated with a Technetium-99 source, but tha.t no direct comparison results were available from the calibration results to indicate the instruments' response to Iodine-131 level The NRC inspector informed the licensee that Iodine-131 concentration might be difficult to verify because of the masking effect of the noble gases that are produced in the reactor bay during operation The NRC inspector noted that the calibration of the CAM is documented only on the current calibration label placed on the readout meter of the' instrument; no other documentation was utilized to indicate what sources were used, who performed the calibration, or what ranges of operation the instrument was calibrate d. Personnel Monitoring The NRC inspector reviewed the NRF personnel radiation exposure records for 1983, 1984, 1985, and 198 The personnel monitoring devices are provided by the KSU radiation safety department. Two separate badges are utilized at KSU, a beta gamma badge for researchers and a neutron gamma badge for NRF staf The NRC inspectors noted that the licensee had not conducted testing of dosimeters as recommended in ANSI N13.11-198 The NRC inspector noted that the licensee had not developed written calibration and operating procedures for use of the TLD monitoring l system which is utilized for determining personnel exposures at KSU.
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| l REMOVAL OF THE PAGES MARKED TION" " SAFEGUARD DECONTROLS THE REMAINDER OF THIS DOCUME
| | Date of Full Compliance All instruments are now in calibration. The next round of calibration will take place in Decerber 1986 and January 1987. |
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| . | | B. Failure to Develon Written Procedures Reason for Violation |
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| | The absence of certain written procedures is not admitted. That these prccedures have not been approved by the Reactor er Safeguards Committee is admitted. Vendor-supplied instruction manuals for the systems in question are followed in their use. Such manuals have not been submitted to the Reactor Safeguards Connittee for its endorsement. |
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| | Corrective Steps to be Taken , |
| TS, Section H, Administrative Requirements, paragraph 1, states
| | Operating procedures incorporating, by reference, vendor's instruction manuals will be prepared and submitted to the Reactor Safeguards Committee for endorsement. |
| " written instructions, approved by the Reactor Safeguards Committee, shall be in effect for, but not limited to:" specific areas noted in Section H. The failure to develop written procedures for calibration and operation of the TLD personnel monitoring system is an apparent violation of TS, Section H.1. (188/8602-02)
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| The NRC inspector noted that the licensee had not participated in the NVLAP program. The NRC inspector discussed with the licensee the forthcoming 10 CFR Part 20 requirement that personnel monitoring devices will need to be NVLAP accredite The NRC inspector noted that self reading dosimeters (SRD) are calibrated semiannually with a radioactive sourc However, the licensee does not routinely, prior to calibration, perform testing on SRDs to determine leakage. The NRC inspector discussed with the licensee the recommendations of NRC RG 8.4 concerning testing and calibration of SRD. The licensee stated at the exit briefing on September 10, 1986, that the NRC inspector's observation would be reviewe e. Environmental Surveillance / Radioactive Releases The NRC inspector reviewed records of analysis on sump drain liquid which is performed with a gamma spectroscopy syste The NRC inspector noted that the licensee had not developed written calibration and operating procedures for use of the gamma spectroscopy system which is routinely used to analyze sump drain water prior to release to unrestricted area TS, Section H, Administrative Requirements, paragraph 1, states
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| " written instructions, approved by the Reactor Safeguards Committee, shall be in effect for, but not limited to:" specific areas noted in Section H. The failure to establish written procedures for calibration and operation of the gamma spectroscopy system is an apparent violation of TS, Section H.1. (188/8602-02)
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| Records indicated that all beta gamma radioactivity concentrations were below 10 CFR 20 limits. However, liquid effluent is not monitored for alpha activity. The NRC inspector noted that the Americium / Beryllium neutron startup source located in the reactor pool was not being routinely wipe tested for leakage and the potential exists for the release of alpha activity into unrestricted area CFR Part 20.201(b) states "each licensee shall make or cause to be made such surveys as: (1) may be necessary for the licensee to comply with the regulations in this part, and (2) are reasonable under the circumstances to evaluate the extent of radiation hazards REMOVAL OF THE PAGES MARKED " "
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| DECONTROLS THE REMAINDER OF THIS DOCUMEN _ ___ . _
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| that may be present." The failure to analyze liquid effluents for alpha activity is an apparent violation of 10 CFR 20.201(b).
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| (188/8602-03)
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| The licensee stated that gaseous effluents are not routinely released and that the normal pathway would be through an exhaust duct which has been sealed and the fan switch disconnected to prevent operatio Air intake to the reactor bay is from the outside with exhaust to the reactor bay area. The licensee stated that elevated airborne concentrations are present in the reactor bay atmosphere during operations; however, no analyses have been performed to determine the concentration The failure to analyze reactor bay atmosphere to determine if airborne concentrations exceeded 10 CFR 20 limits is an apparent violation of 10 CFR 20.201(b). (188/8602-03) Surveys The NRC inspector reviewed radiation and contamination survey records regarding surveys performed by the NRF staff to determine compliance with the requirements of 10 CFR Part 20 and the recommendations of industry standard ANSI /ANS-15.11-197 The NRC inspector noted that smears taken routinely to determine levels of contamination were analyzed on the radiation safety department's liquid scintillation counte The NRC inspector noted that procedures had not been developed by the licensee for calibration and operation of the liquid scintillation counte TS, Section H, Administrative Requirements, paragraph 1, states,
| | C. Failure to Survey Reason for Violation Failure to evaluate liquid effluents for alpha-particle activity is admitted. |
| " written instructions, approved by the Reactor Safeguards Committee, shall be in effect for, but not limited to:" specific areas noted in Section The failure to establish written procedures for calibration and operation of the liquid scintillation counter is an apparent violation of TS, Section (188/8602-02)
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| The NRC inspector performed independent contamination and direct radiation dose rate surveys in the NR The smears taken by the NRC inspector were analyzed on NRC Region IV laboratory counting instrumentation, with all results less than or equal to minimum detectable activities. Tne direct radiation survey results revealed no areas of radiation levels in excess of 10 CFR'20 limit The licensee's survey program had not included an evaluation of neutron levels with the reactor operating at full power. The NRC inspector stated that neutron radiation levels are not usually considered to be a problem at TRIGA facilities; however, surveys REMOVAL OF THE PAGES MARKED " "
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| DECONTROLS THE REMAINDER OF THIS DOCUMEN .
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| | Failure to monitor adequately airborne activity in the reactor bay atmosphere is not admitted. The potential for fuel-element cladding failure and for escape of noble gas and iodine radionuclides was addressed in the Hazards Summary Report for the Kansas State University TRIGA Mk II Reactor and in the safety analysis submitted to the Atomic Energy Commission in application for operation of the reactor at 250 kWt. |
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| should be performed to establish that no significant neutron radiation levels exist. The licensee stated at the exit brief!ng on September 10, 1986, that the NRC inspector's observation would be reviewe Radiation Worker Training Personnel qualifications and training were reviewed and discussed with the licensee to determine compliance with the requirements of 10 CFR Part 19.12 and the recommendations of RGs 8.13 and 8.2 The NRC inspector noted that the licensee required all workers to attend radiation protection trainin However, documentation was not available that all topics required by 10 CFR 19.12 had been covere The licensee stated that the topics required by 10 CFR 19.12 were covered in training sessions, but they were not aware that documentation to that extent would be required, and that
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| documentation on all future training conducted in this area would be complete .'
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| to her and her co workers concerning the recommendations in NRC RG 8.1 . Emergency Planning and Preparedness The NRC inspector reviewed the implementation of the KSV Emergency | |
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| Plan (EP) approved by the NRC on August 13. 1984, to determine compliance with 10 CFR 50.54(r).
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| The NRC inspector reviesed assignment of responsibilities, emergency facilities, and equipment (first aid and medical facilities, communications, and radiation and contamination protection equipment).
| | In the Safety Evaluation by the Division of Reactor Licensing. Docket l |
| | 50-188, " Kansas State University Increase in Power Level " signed by D.J. |
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| The NRC inspector discussed with the KSV Student Health Center Director their roles and responsibilities in the event of a reactor accident at the NR The NRC inspector reviewed the placement and inventories of the emergency equipmen The NRC inspector noted that the inventory of the l cabinet located in the basement of Ward Hall indicated that two survey | | Skovholt on 26 June 68, it was stated by the AEC that: |
| ; instruments, one high range and one low range instrument, would be
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| ! available for use. At the time of the inspection, only the low range l instrument was available for use. The licensee stated that the high range instrument was out-of service. The NRC inspector discussed with the licensee the need to provide a supplemental instrument to the kit to provide for adequate inventory. The NRC inspector noted that the actual
| | . The applicant's analysis, with which we agree, indicates that such an accident [ loss of pool coolant water af ter prolonged high-power operation] would not cause damage to the fuel or result in the release of fission products. However, even if the cladding of a fuel element were to fail, permitting fission products to escape, the applicant's calcualtions, and our analysts indicate that doses to personnel within the building and in unrestricted areas outside the building would remain within acceptable limits." |
| ; number and type of instruments and equipment are not specifically l identified in the KSV EP.
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| | In view of this finding, attempts have not been made to identify specific noble gas radionuclides in the reactor building atmosphere. Instead, radiation exposure rates are monitored throughout the reactor building in recognition that significant noble gas releases would thus be detected. |
| The licensee had conducted emergency exercises on August 16, 1984, and
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| , August 7, 1986. The critiques of emergency exercises were on file and had l been reviewed by the Reactor Safeguards Committee (RSC) as required by the l KSV emergency plan.
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| (' | | Emergency Procedure No. 6 has been implemented in order that such l exposure rates could be translated conservatively into radionuclide l concentrations for use in accident assessment. ) |
| REMOVAL OF THE PAGES MARKED " "
| | In order to monitor lor potential fission product relee.se of long duration, a number of surveillance actions are taken: (1) Activity held |
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| | on pool-cleanup demineralizer resin is monitored each operating day. |
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| _ | | Unusual increase in ac tivity would provide an early qualitative warning of the presence of fission products in primary coolant. (2) Primary coolant is sampled monthly and analyzed for gross activity using a liquid scintillation system. If any activity were found, gansna-ray spectral analysis would be performed. This would provide a quantitative measure of fission product activity in primary coolant. (3) During reactor use, operation of a continuous air monitor is required. Except for periods of maintenance, the monitor is operated continuously (24-h per day). The monitor is set to alarm at radiation indication very conservatively 131 representative of I maximum permissible concentration in unrestricted areas. The potential for argon-41 release into the reactor building was also addressed in the Hazards Analysis Report and found not to present a significant risk. Notwithstanding this finding, the use of air as the |
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| The NRC inspector reviewed the biennial EP reviews conducted and approved by the RSC, and the annual requalification training required for the NRF staf The NRC inspector noted that documentation of annual qualification training was lacking as to specific subject matte l No violations or deviations were identifie I 5. Nuclear Materials Safeguards
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| The NRC inspector reviewed the nuclear materials inventory program to determine compliance with License Conditions 2.B and The NRC inspector reviewed the accountability procedures and practice records and material status reports for the period January 1,1983, through September 1, 1986. The procedures, practices, and records were found to be well-implemented. Responsibilities and response requirements were defined clearly and understoo No violations or deviations were identified.
| | driver gas for the pneumatic transfer system has been discontinued, with its use replaced by that of helium. The highly unlikely, but potential venting of air from the rotary specimen rack has also been investigated. |
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| | That event would certainly be detected, yet concentrations and potential personnel exposures would be within acceptable 10CFR20 limits. |
| 6. Physical Security The material discussed here contains Safeguards Information as defined by 10 CFR 73.21 and is reported in Attachment to this report.
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| . 7. Exit Briefing The NRC inspector met with the licensee's representatives identified in paragraph 1 of this report at the conclusion of the inspection on September 10, 198 The NRC inspector summarized the scope and inspection findings. | | Corrective Stens to be Taken A procedure for alpha monitoring of Reactor Facility liquid effluents is under preparation. No effluents will be released without such monitoring. |
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| | Aside from fuel material, whose presence would be indicated by fission-product activity, the only source of measurable artificial alpha activity in reactor effluents would be the Am/Be source used for reactor start-up. This source is encapsulated in stainless steel and contained within an aluminum housing. We are contemplating either seeking a method of direct determination of source leakage or appealing for relief from this :aonitoring requiren.ent under the provisions of 10CFR20.501. |
| !- DECONTROLS THE REMAINDER OF THIS DOCUMENT.
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| ! | | Date of Full Compliance March 1, 1987 |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6761999-10-26026 October 1999
Informs That Effective 991026,SW Holmes Will Be NRC Inspector for Kansas State Univ Nuclear Reactor Facility
ML20138H3711999-10-25025 October 1999
Ack Receipt of ,Enclosing Rev to Kansas State Univ Triga Mk II Nuclear Reactor Emergency Plan Dtd March 1999. Based on Determination That Changes to Not Decrease Effectiveness of Plan,No NRC Approval Required
ML20217A4521999-10-0404 October 1999
Forwards Proprietary Special Nuclear Matl Status Forms 741, 742 & 742C for Period 990401 to 990930 for Kansas State Univ Triga Mark II Nuclear Reactor Facility,Under Licenses R-88 & 38-C011-01.Proprietary Encls Withheld
ML20216G6111999-09-24024 September 1999
Forwards Insp Rept 50-188/99-201 on 990830-0902.No Safety Concerns or Noncompliance to NRC Requirements Identified
ML20210C2761999-07-14014 July 1999
Informs That Reactor Safeguards Committee Held Meeting to Evaluate Operation Under Plan,To Rept on Progress to Hire Permanent Replacement for Brendan & to Consider Whether Adjustments in Plan Were Appropriate
ML20209C3471999-07-0101 July 1999
Informs That B Ryan Served as Reactor Supervisor & Facility Manager.Ryan Has Resigned Effective 990701,to Accept Position at Wolfcreek Npp.Until Replacement Found, Temporary Listed Changes Will Be Made
ML20196A2521999-06-11011 June 1999
Discusses Initial Exam Conducted Wk of 990517.Findings Discussed with Staff & Identified in Encl Rept.Without Encl
ML20204H0281999-03-22022 March 1999
Discusses Arrangements Made for Administration of Operator Licensing Exams at Kansas State Univ Scheduled for Week of 990517 & Requests Licensee Furnish One Set of Reference Matl Listed in Encl 1
ML20202C3711999-01-15015 January 1999
Informs of Change to Kansas State Univ Sar,Per Recent Telcon.Several Modifications to Reactor Own Ventilation Have Been Undertaken,In Order to Meet Intent of SAR
ML20198K8021998-12-21021 December 1998
Forwards Amend 12 to License R-88 & Safety Evaluation.Amend Designates Dept Head of Mechanical & Nuclear Engineering Dept as Chairman of Reactor Safeguards Committee in TS H.2
ML20155C5111998-10-28028 October 1998
Forwards Amend 11 to License R-88 & Safety Evaluation.Amend Deletes License Condition 3.E,which Required That Physical Security Plan Be Maintained
ML20154G1231998-10-0404 October 1998
Submits Listed Changes for Kansas State Univ Triga Mark II Nuclear Reactor for Period of 971001-980930,per 10CFR50.59(b)
ML20237B4551998-08-13013 August 1998
Forwards New Copy of Kansas State Univ Triga Mark II Physical Security Plan W/Changes Highlighted,As follow-up to 980619 Submittal.Elimination of Licensee Physical Security Plan as Licensed Document,Requested.Encl Withheld
ML20249B8421998-06-19019 June 1998
Forwards Revised Proprietary Copy of Physical Security Plan for Kansas State Univ Triga Mark II Nuclear Reactor.Current Changes Editorial in Nature.Proprietary Encl Withheld
ML20247M7161998-05-20020 May 1998
Informs That HV Rectanus,SOP-70187,no Longer Performs Duties of Licensed SRO at Kansas State Univ
ML20248L7751998-03-10010 March 1998
Transmits Four RO Candidates & 1 SRO Candidate for Operator License Certificates for Kansas State Univ
ML20203H7841998-02-25025 February 1998
Forwards Results of Operator Initial Exam Conducted at Kansas State Univ on 980209-11.W/o Encl
ML20199E8021997-11-12012 November 1997
Responds to Telcon Between W Eresian & BC Ryan Re Arrangements for Administration of Operator Licensing Exams at Kansas State Univ.Exams Scheduled for Week of 980209
ML20217H9151997-10-13013 October 1997
Informs That J Monzon No Longer Performs Duties of Licensed Reactor Operator at Kansas State Univ
ML20138H5741997-05-0202 May 1997
Forwards Insp Rept 50-188/97-01 on 970407-11.No Violations Noted
ML20134A3221997-01-24024 January 1997
Informs That BC Ryan Replaced R Faw as Official Representative for Facility.New Address as Submitted
ML20134M6491996-11-21021 November 1996
Ack Receipt of from R Faw,Which Transmitted Changes to Emergency Plan for Kansas State Univ Triga Mk II Nuclear Reactor Facility,Submitted Under Provisions of 10CFR50.54(q)
ML20134F1281996-10-30030 October 1996
Forwards Amend 10 to License R-88 & Safety Evaluation.Amend Revises Titles of Members of Reactor Safeguards Committee Due to Merger of Dept of Nuclear Engineering & Mechanical Engineering at Univ
ML20128H6391996-10-0707 October 1996
Forwards Results of Operation Initial Exam Conducted at Kansas State Univ on 960924-25.W/o Encl
ML20128H4871996-10-0707 October 1996
Forwards Results of Operator Initial Exam Conducted at Kansas State Univ on 960924-25.W/o Encl
ML20129H1571996-10-0101 October 1996
Submits Changes Re Facility,Procedures & Tests and Experiments for Oct 1995-Sept 1996
ML20116J9931996-08-0606 August 1996
Re-affirms Intention of Ks State Univ to Apply for Extension of Operating License for 250-kW Pulsing Triga Reactor
ML20093E8541995-10-0909 October 1995
Advises That No Changes in Facility,Procedures & Test & Experiments Made During Oct 1994-Sept 1995
ML20086A0771995-06-19019 June 1995
Advises NRC That Licensee Existing Control of Access to Radiation Beams Adequate to Protect Individuals from over- Exposure & to Assure Compliance w/10CFR20.1601
ML20070N3861994-04-21021 April 1994
Informs That on 940420,intrusion Alarm Sys for Facility Failed Due to Failure of Electrical Relay in Alarm Unit at Police Dept.Relay Replaced,Unit Returned to Service & Functional Performance Test Conducted
ML20059H1611993-11-0202 November 1993
Informs That Listed Ref Matl Requested Prior to Administration of Operator Licensing Exams Scheduled for Wk of 930411 at Kansas State Univ Reactor
ML20059M4191993-09-17017 September 1993
Responds to Submitted on Behalf of Constituent Kansas State Univ Re Commission Recent Decision to Assess Annual Fees to Nonprofit Educational Institutions Holding NRC Licenses or Other Approvals
ML20056G6471993-08-27027 August 1993
Responds to Re NRC Assessment of Annual Fees to Kansas State Univ,Manhattan,Ks
ML20056G6621993-08-23023 August 1993
Expresses Thanks for Extension of Deadlines for Payment of 1993 Annual Fees Announced in NRC Delineating Options Available to non-profit Licenses Re Biling for 1993 Annual Fees
ML20059M4521993-08-17017 August 1993
Urges NRC Approval of Kansas State Univ Request for Exemption from Payment of Licensing Fees,Per 10CFR171.11(b)
ML20056G6651993-08-10010 August 1993
Urges NRC to Favorably Consider Kansas State Univ Appeal for Exemption from Licensing Fees
ML20029D5991993-08-0404 August 1993
Endorses 930727 Request for Individual Exemption from Payment of Annual Fees for Triga Mark II Reactor
ML20046D3531993-08-0404 August 1993
Requests Exemption from Payment of Annual Fees for Triga Mark II Reactor
ML20056D2691993-08-0303 August 1993
Forwards Rev to Physical Security Plan for Univ Triga Mark II Reactor Facility.Withheld Per 10CFR2.790
ML20029D5971993-08-0202 August 1993
Endorses 930727 Request for Individual Exemption from Payment of Annual Fees for Triga Mark II Reactor
ML20046D3501993-08-0202 August 1993
Endorses 930727 Request for Exemption from Payment of Annual Fees for FY93 for Listed Reasons,W/Regard to Invoice AT-0464-93
ML20046D3551993-07-27027 July 1993
Requests Individual Exemption from Payment of Annual Fees for FY93,per 10CFR171.11(b)
ML20029D5931993-07-27027 July 1993
Requests Individual Exemption from Payment of Annual Fees for Kansas State Univ Triga Mark II Nuclear Reactor
ML20045G5861993-07-0606 July 1993
Forwards Response to 930616 Ltr Re Violations Noted in Insp Rept 50-188/93-01 on 930524-28.Encls Withheld
ML20056C3581993-05-0707 May 1993
Forwards Requalification Exam Rept 50-188/OL-93-01 on 930428-29
ML20128G2041993-02-0808 February 1993
Accepts Changes to 920918 Ks State Univ Research Reactor Emergency Plan,Rev 2.Plan Maintains Compliance w/10CFR50, App E
ML20127J6521993-01-13013 January 1993
Forwards Emergency Plan,Reflecting Items Stricken from Newest Rev as Advised by Univ Reactor Safeguards Committee. Memo Sent to Facility Director Outlining Mods Suggested by Newest Rev of EPA Protective Action Guides Also Encl
ML20099F5501992-08-0606 August 1992
Advises That J Kirkland Replaces M Burger as Reactor Supervisor for Ks State Univ Triga Reactor Facility, Effective 920818
ML20081L0241991-06-18018 June 1991
Advises That Effective 910618,MJ Burger Will Replace Dj Whitfill as Reactor Supervisor for Univ Reactor
ML20073E7331991-04-11011 April 1991
Forwards Proposed Rev to Physical Security Plan,Reflecting Change in Type of Intrusion Alarm.Rev Withheld
1999-09-24
[Table view]
Category:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARML20245L0361989-04-19019 April 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-188/89-01
ML20247D1031989-03-21021 March 1989
Forwards Insp Rept 50-188/89-01 on 890206-09.Violation Noted
IR 05000188/19880011988-06-0303 June 1988
Ack Receipt of Informing NRC of Steps Taken to Correct Violations & Deviations Noted in Insp Rept 50-188/88-01.Addl Clarification Warranted as Discussed During 880526 Telcon Re Listed Deviation
ML20154E2811988-05-11011 May 1988
Informs of Failure to Observe Conditions of Senior Operator License 2158-6 Under 10CFR55.53(e) & (F) as Noted in Insp Rept 50-188/88-01 on 880308-10
ML20151R2781988-04-19019 April 1988
Forwards Insp Rept 50-188/88-01 on 880308-10 & Notices of Violation & Deviation
ML20236F6511987-10-26026 October 1987
Informs That J Pellet Replacing R Cooley as Section Chief of Operators Licensing Section in Div of Reactors Safety, Effective 871025
ML20215D5331987-06-11011 June 1987
Informs of Recent Reorganization of Nrr.T Michaels Designated as Facility Project Manager
ML20210A5901987-04-29029 April 1987
Forwards Automatic Sprinkler Corp of America 861201 Part 21 Rept Re 6 Inch Model C Valve & Mercury Check Device,For Info.W/O Encl
ML20211E8891987-02-17017 February 1987
Forwards Ga Technologies,Inc 860918 Part 21 Rept Re Triga Reactors from Vendor.Info Provided for Evaluation of Potential Defect Re Reactor for Appropriate Corrective Action
IR 05000188/19860021986-12-24024 December 1986
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-188/86-02
ML20203P1761986-10-20020 October 1986
Forwards Insp Rept 50-188/86-02 on 860909-10 & Notice of Violation
ML20210U6141986-05-30030 May 1986
Forwards Insp Rept 50-188/86-01 on 860430-0501.No Violations or Deviations Noted
ML20154R4181986-03-26026 March 1986
Advises of NRR Reorganization.Telephone Number of J Dosa Changed.D Tondi New Section Leader for Nonpower Reactors & Safeguards Licensing Section.Correspondence Should Be Addressed to Nrc,Attention Document Control Desk
ML20054L3881982-06-16016 June 1982
Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl
ML20148U1731981-02-17017 February 1981
Forwards Revised NRC Region 4 Organization Chart,Effective 810227
ML20148G6391978-10-31031 October 1978
Responds to Re Dr Eckoff'S Training & Authorizes Him to Perform Licensed Duties
ML20137G4721971-06-23023 June 1971
Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form
1989-04-19
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217P6761999-10-26026 October 1999
Informs That Effective 991026,SW Holmes Will Be NRC Inspector for Kansas State Univ Nuclear Reactor Facility
ML20138H3711999-10-25025 October 1999
Ack Receipt of ,Enclosing Rev to Kansas State Univ Triga Mk II Nuclear Reactor Emergency Plan Dtd March 1999. Based on Determination That Changes to Not Decrease Effectiveness of Plan,No NRC Approval Required
ML20216G6111999-09-24024 September 1999
Forwards Insp Rept 50-188/99-201 on 990830-0902.No Safety Concerns or Noncompliance to NRC Requirements Identified
ML20196A2521999-06-11011 June 1999
Discusses Initial Exam Conducted Wk of 990517.Findings Discussed with Staff & Identified in Encl Rept.Without Encl
ML20204H0281999-03-22022 March 1999
Discusses Arrangements Made for Administration of Operator Licensing Exams at Kansas State Univ Scheduled for Week of 990517 & Requests Licensee Furnish One Set of Reference Matl Listed in Encl 1
ML20198K8021998-12-21021 December 1998
Forwards Amend 12 to License R-88 & Safety Evaluation.Amend Designates Dept Head of Mechanical & Nuclear Engineering Dept as Chairman of Reactor Safeguards Committee in TS H.2
ML20155C5111998-10-28028 October 1998
Forwards Amend 11 to License R-88 & Safety Evaluation.Amend Deletes License Condition 3.E,which Required That Physical Security Plan Be Maintained
ML20248L7751998-03-10010 March 1998
Transmits Four RO Candidates & 1 SRO Candidate for Operator License Certificates for Kansas State Univ
ML20203H7841998-02-25025 February 1998
Forwards Results of Operator Initial Exam Conducted at Kansas State Univ on 980209-11.W/o Encl
ML20199E8021997-11-12012 November 1997
Responds to Telcon Between W Eresian & BC Ryan Re Arrangements for Administration of Operator Licensing Exams at Kansas State Univ.Exams Scheduled for Week of 980209
ML20138H5741997-05-0202 May 1997
Forwards Insp Rept 50-188/97-01 on 970407-11.No Violations Noted
ML20134M6491996-11-21021 November 1996
Ack Receipt of from R Faw,Which Transmitted Changes to Emergency Plan for Kansas State Univ Triga Mk II Nuclear Reactor Facility,Submitted Under Provisions of 10CFR50.54(q)
ML20134F1281996-10-30030 October 1996
Forwards Amend 10 to License R-88 & Safety Evaluation.Amend Revises Titles of Members of Reactor Safeguards Committee Due to Merger of Dept of Nuclear Engineering & Mechanical Engineering at Univ
ML20128H6391996-10-0707 October 1996
Forwards Results of Operation Initial Exam Conducted at Kansas State Univ on 960924-25.W/o Encl
ML20128H4871996-10-0707 October 1996
Forwards Results of Operator Initial Exam Conducted at Kansas State Univ on 960924-25.W/o Encl
ML20059H1611993-11-0202 November 1993
Informs That Listed Ref Matl Requested Prior to Administration of Operator Licensing Exams Scheduled for Wk of 930411 at Kansas State Univ Reactor
ML20059M4191993-09-17017 September 1993
Responds to Submitted on Behalf of Constituent Kansas State Univ Re Commission Recent Decision to Assess Annual Fees to Nonprofit Educational Institutions Holding NRC Licenses or Other Approvals
ML20056G6471993-08-27027 August 1993
Responds to Re NRC Assessment of Annual Fees to Kansas State Univ,Manhattan,Ks
ML20056C3581993-05-0707 May 1993
Forwards Requalification Exam Rept 50-188/OL-93-01 on 930428-29
ML20128G2041993-02-0808 February 1993
Accepts Changes to 920918 Ks State Univ Research Reactor Emergency Plan,Rev 2.Plan Maintains Compliance w/10CFR50, App E
ML20245D3611989-04-21021 April 1989
Forwards Rept Re Component Failure on Triga Mk II for Comments as to Whether Problem Generic in Nature & If Advisory Should Be Issued
ML20245L0361989-04-19019 April 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-188/89-01
ML20247D1031989-03-21021 March 1989
Forwards Insp Rept 50-188/89-01 on 890206-09.Violation Noted
IR 05000188/19880011988-06-0303 June 1988
Ack Receipt of Informing NRC of Steps Taken to Correct Violations & Deviations Noted in Insp Rept 50-188/88-01.Addl Clarification Warranted as Discussed During 880526 Telcon Re Listed Deviation
ML20154E2811988-05-11011 May 1988
Informs of Failure to Observe Conditions of Senior Operator License 2158-6 Under 10CFR55.53(e) & (F) as Noted in Insp Rept 50-188/88-01 on 880308-10
ML20151R2781988-04-19019 April 1988
Forwards Insp Rept 50-188/88-01 on 880308-10 & Notices of Violation & Deviation
ML20150D8641988-03-18018 March 1988
Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup
ML20236F6511987-10-26026 October 1987
Informs That J Pellet Replacing R Cooley as Section Chief of Operators Licensing Section in Div of Reactors Safety, Effective 871025
ML20215D5331987-06-11011 June 1987
Informs of Recent Reorganization of Nrr.T Michaels Designated as Facility Project Manager
ML20210A5901987-04-29029 April 1987
Forwards Automatic Sprinkler Corp of America 861201 Part 21 Rept Re 6 Inch Model C Valve & Mercury Check Device,For Info.W/O Encl
ML20211E8891987-02-17017 February 1987
Forwards Ga Technologies,Inc 860918 Part 21 Rept Re Triga Reactors from Vendor.Info Provided for Evaluation of Potential Defect Re Reactor for Appropriate Corrective Action
IR 05000188/19860021986-12-24024 December 1986
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-188/86-02
ML20203P1761986-10-20020 October 1986
Forwards Insp Rept 50-188/86-02 on 860909-10 & Notice of Violation
ML20210U6141986-05-30030 May 1986
Forwards Insp Rept 50-188/86-01 on 860430-0501.No Violations or Deviations Noted
ML20154R4181986-03-26026 March 1986
Advises of NRR Reorganization.Telephone Number of J Dosa Changed.D Tondi New Section Leader for Nonpower Reactors & Safeguards Licensing Section.Correspondence Should Be Addressed to Nrc,Attention Document Control Desk
ML20054L3881982-06-16016 June 1982
Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl
ML20148U1731981-02-17017 February 1981
Forwards Revised NRC Region 4 Organization Chart,Effective 810227
ML20149K1911980-05-0707 May 1980
Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility
ML20148G6391978-10-31031 October 1978
Responds to Re Dr Eckoff'S Training & Authorizes Him to Perform Licensed Duties
ML20137G4721971-06-23023 June 1971
Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form
1999-09-24
[Table view] |
Text
. _ _ _ _ _ _ . _ _ . . _ _ _ _ _ . _ -_ _ _ _ _ _ _ _ _ _ . - - _ _ _ _ _ _ _ _ - _ _ - _ _ -____
., 4 DEC 2 41986 in Reply Refer To:
Docket: 50-188/86-02 Kansas State University Department of Nuclear Engineering ATTN: Dr. R. E. Faw, Director Nuclear Reactor Facility Manhattan, Kansas 66505 Gentlemen:
Thank you for your letter of November 17, 1986, in response to our letter
and Notice of Violation dated October 20, 1986. We have reviewed your reply l and find it responsive to the concerns raised in our Notice of Violation. We l will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintai,ed.
Sincerely, ORIGINAL SIGNED BY:
J. E. Gagliardo, Chief Reactor Projects Branch cc:
Kansas Radiation Control Program bec to DMB (IE06)
bcc distrib. by RIV:
RPB Resident Inspector R. D. Martin, RA R&SPB Section Chief (RPB/B) D. Weiss, LFMB (AR-2015)
RIV File DRSP RSB MIS SYSTEM RSTS Operator Inspector Section Chief W. L. Fisher R. L. Bangart J. J. Dosa, NRR, Project Manager RIV:FRP C:FRPS C:R&SPB CRPB [
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November 17, 1986 U.S. Nuclear Regulatory Commission Region IV Attn: J. E. Gagliardo, Chief Reactor Projects Branch 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 Re: License R-88 Docket 50-188
Dear Sirs:
This is in response to your letter of 20 October 1986 and its attendant notice of violation. Our response is enclosed.
Sincerely, et<f f hin V Richard E. Faw, Director KSU Nuclear Reactor Facility REF/cs Enclosure
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RESPONSE TO NOTICE OF VIOLATION
.
Kansas State University (KSU) Docket: 50-188/86-02 TRICA MkII Reactor License: R-88 A. Failure to Perform Survey Instrument Calibration Reason for Violation This violation is admitted. The reasons are as follows: The Reactor Facility maintains and calibrates instruments for general use in the Nuclear Engineering Department. On some occasions, these general-purpose instruments are in use outside the Reactor Facility at the time of reactor-instrument calibratior.. Record keeping procedures hase been deficient in identification of those occasions.
Cprrective Steos Taken New record keeping procedures have been implemented. A master log of calibration dates has been instituted to supplement calibration logs for each instrument.
Corrective Steos to be Taken At the time of the next calibration, those instruments not required for reactor surveillance are to be sequestered in their own storage location.
All instruments are to be tagged with identification of their use (reactor or non-reactor) and the calibration expiration date.
Date of Full Compliance All instruments are now in calibration. The next round of calibration will take place in Decerber 1986 and January 1987.
B. Failure to Develon Written Procedures Reason for Violation
- .
The absence of certain written procedures is not admitted. That these prccedures have not been approved by the Reactor er Safeguards Committee is admitted. Vendor-supplied instruction manuals for the systems in question are followed in their use. Such manuals have not been submitted to the Reactor Safeguards Connittee for its endorsement.
Corrective Steps to be Taken ,
Operating procedures incorporating, by reference, vendor's instruction manuals will be prepared and submitted to the Reactor Safeguards Committee for endorsement.
Date of Full Compliance
. March 1. 1987. -
!
. -
_ - _ . .
, - , .
,
C. Failure to Survey Reason for Violation Failure to evaluate liquid effluents for alpha-particle activity is admitted.
Failure to monitor adequately airborne activity in the reactor bay atmosphere is not admitted. The potential for fuel-element cladding failure and for escape of noble gas and iodine radionuclides was addressed in the Hazards Summary Report for the Kansas State University TRIGA Mk II Reactor and in the safety analysis submitted to the Atomic Energy Commission in application for operation of the reactor at 250 kWt.
In the Safety Evaluation by the Division of Reactor Licensing. Docket l
50-188, " Kansas State University Increase in Power Level " signed by D.J.
Skovholt on 26 June 68, it was stated by the AEC that:
". .
. The applicant's analysis, with which we agree, indicates that such an accident [ loss of pool coolant water af ter prolonged high-power operation] would not cause damage to the fuel or result in the release of fission products. However, even if the cladding of a fuel element were to fail, permitting fission products to escape, the applicant's calcualtions, and our analysts indicate that doses to personnel within the building and in unrestricted areas outside the building would remain within acceptable limits."
[ italics added]
In view of this finding, attempts have not been made to identify specific noble gas radionuclides in the reactor building atmosphere. Instead, radiation exposure rates are monitored throughout the reactor building in recognition that significant noble gas releases would thus be detected.
Emergency Procedure No. 6 has been implemented in order that such l exposure rates could be translated conservatively into radionuclide l concentrations for use in accident assessment. )
In order to monitor lor potential fission product relee.se of long duration, a number of surveillance actions are taken: (1) Activity held
~
on pool-cleanup demineralizer resin is monitored each operating day.
Unusual increase in ac tivity would provide an early qualitative warning of the presence of fission products in primary coolant. (2) Primary coolant is sampled monthly and analyzed for gross activity using a liquid scintillation system. If any activity were found, gansna-ray spectral analysis would be performed. This would provide a quantitative measure of fission product activity in primary coolant. (3) During reactor use, operation of a continuous air monitor is required. Except for periods of maintenance, the monitor is operated continuously (24-h per day). The monitor is set to alarm at radiation indication very conservatively 131 representative of I maximum permissible concentration in unrestricted areas. The potential for argon-41 release into the reactor building was also addressed in the Hazards Analysis Report and found not to present a significant risk. Notwithstanding this finding, the use of air as the
_ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _
,
, . 3
driver gas for the pneumatic transfer system has been discontinued, with its use replaced by that of helium. The highly unlikely, but potential venting of air from the rotary specimen rack has also been investigated.
That event would certainly be detected, yet concentrations and potential personnel exposures would be within acceptable 10CFR20 limits.
Corrective Stens to be Taken A procedure for alpha monitoring of Reactor Facility liquid effluents is under preparation. No effluents will be released without such monitoring.
Aside from fuel material, whose presence would be indicated by fission-product activity, the only source of measurable artificial alpha activity in reactor effluents would be the Am/Be source used for reactor start-up. This source is encapsulated in stainless steel and contained within an aluminum housing. We are contemplating either seeking a method of direct determination of source leakage or appealing for relief from this :aonitoring requiren.ent under the provisions of 10CFR20.501.
Date of Full Compliance March 1, 1987
- .
l
.