ML18325A146
| ML18325A146 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 11/07/2018 |
| From: | Roy B US Dept of Interior, Geological Survey (USGS) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 4-2017-027, 4-2018-005, IA-18-038 | |
| Download: ML18325A146 (93) | |
Text
{{#Wiki_filter:EUSGS science for a changing world Department of the Interior US Geological Survey Box 25046 MS-97 4 Denver CO, 80225 November 7, 2018 Re: Docket 50-27 4 License R-113 U.S. Nuclear Regulatory Commission Document Control Desk Washington DC 20555 Re: Response to Apparent Violations Associated with NRC Investigation Reports 4-2017-027 and 4-2018-005; IA-18-038 Please find attached information as requested during the pre-decisional enforcement conference (PEC) of October 25, 2018. The attachments include operator requalification trainings of November 2, 2017; December 21, 2017; and May 8, 2018. One additional training of July 2, 2018, is also included because I had mentioned during the PEC that we had held one additional_documented training. Also included are the Reactor Operations Committee (ROC) agendas and minutes from the meetings of October 20, 2017 and April 27, 2018. Because both reactor operation requalification trainings of 2017 were held late in the calendar year, I only included the agenda and minutes from the fall 2017 ROC meeting. Additionally, please find attached the startup checklists and logbook records from the month of September 2016. Sincerely, ~a~'l=<~ Brycen Roy Copy to: Louise Lund Director, Division of Licensing Projects, Office of Nuclear Reactor Regulation Mr. Anthony Mendiola Branch Chief NRR/DLP/PROB 12 D20 Reactor Operations Committee
Operator Requalification Training November 2, 2017 Brycen Roy, SRO Tim DeBey, SRO Chris Farwell, SRO Signature Clayton Manning, SRO Led by: (PJ9 s* n Brycen Roy, Reactor Supervisor Discussion/training topics:
- MWh calculation for days where we run at multiple powers
- Higher-t_han-normal perimeter dose rate (specifically, 11 151 Door Gate" environmental dosimeter) o Presented information received from Cynthia and Clayton on material movement within neighboring laboratories
- SER content arid how to proceed from facility standpoint o Presented information assembled by Chris on power peaking in reactor.core
- Non-expiring licenses
- Changes to Procedure 7 Procedure for Control Rod Measurement, Inspection, or Replacement
Operator Requalification Training December 21, 2017 Bryceh Roy; SRO Sign:;gre Chris Farwell, SRO Ck; Signature 6:.~ Clayton Manning, SRO ~~
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s"lr,at;e / Led by: Bryceri Roy, Reactor Supervisor Discussion/training topics:
- SER content and how to proceed from facility standpoint o Presented information contained in SER-in referen~e to phone call with NRC PM
- BRR DTS SOP (read by each staff ahead of training meeting)
- ProjectPlan, U.S. Geological Survey TRIGA Facility Fuel Shipment (read by each staff ahead of training meeting)
- Proposed scheaule from Doug Morrell (read by each staff ahead of training meeting)
- Discu?sion of cooling system operation in cold weather
- Discussion of glove use while handling potentially contaminated samples
Operator Requalification Training 5/8/2018 Brycen Roy, SRO Sign~;; (} Chris Farwefl, ,SRO Cck':' 1~,.- {..~--{!
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Signature Clayton Manning, SRO Siailire Led by: Brycen Roy, Reactor Su_pervisor Discussion/training ~opics primarily consisted of ROC meeting follow-up discussion and actio.n items for future review (Draft Audit Report on hand as supplemental document):
- Watchdog SCRAMS
- EnvironnientalTLDs (exposure report versus logbook)
- Pool water radioactivity and CAM filter (Genie reports)
- BRR/DTS shipping records
- 10 CFR 110 for exporting radioactive materials
- Mat!:!rial Leak Testing requirements
* "Back" table contaniinaticin
- Ar-41 measuring/reporting o Add note for step change from July 2017 to August 2017 o Change to system?
- Tracer production and handling o Better do_se rate measurements on unload (an extra 10 seconds above the CT@ 100 R/hr = "'1 mr extra personnel dose) o Added procedure?
o RPP change? o Discussion of fume hood misuses and limitations o Clayton summary of air sam piing data
- Fuel inspection plan, especially aluminum fuel o Have tool made o Rotate all ele_ments?
o "Rotate*11 tuel in core?
- SAR updates
Self-reported shipping violation training 7/2/2018 Brycen Roy Chris Farwell 1/2/ 1f Clayton Manning Led by: Brye.en Roy, Reactor Supervisor Training on self-reported violations of 06/18. The violations occurred in two related areas for shipping Br-82 tracer material and were self-reported to both NRC and DOT.
- 1. Br-80m should have been included along with Br-82 on the majority of shipping labels.
- 2. Additionally, when calculating the total quantity allowed to be transported in a Type A package of the mixture qf Br-Som.and Br-82 as per "Appendix A to Part 71-Determination of Al and A2" IV(b), there were rare occasions in the past 3 years where the sum was greater than 1.
Training included our proposal to request the use of a different A2 value for Br-80m.
Proposed Agenda for the October 20, 2017 USGS Reactor Operations Committee Meeting
- 1. Introduction of Cynthia Duffield and TBA as current and future USGS RSO
- 2. Review of minutes from 3/27/17 meeting.
- 3. Review of quarterly reports.
- 4. Old Business - fuel procurement efforts
- 5. NRC Correspondence - inspection results
- communication with NRC PM about TS/neutronics/TH
- 6. Plans and Procedures: Procedures for review:
#6. Procedure for Loading and Unloading Irradiation Facilities (proposed changes)
#7. Procedure for Control Rod Measurement, Inspection, or Replacement (proposed changes) -
#12. Procedure for Changing Demineralizer Resin (no changes)
#15. Pocket Dosimeter Drift Check Procedure (no changes)
#16. Pocket Dosimeter Calibration Procedure (no changes)
#23. Receipt of Radioactive Material Shipments (proposed changes)
Proposed revisions to emergency plan and emergency procedures Proposed revisions to security plan New & revised Exp Auth?
- 7. New Business. - ROC membership
- USGS re-organization
- 8. Audit of Operating Records.
- 9. Summary and Discussion.
- 10. Facility Inspection.
- 11. Adjourn.
REACTOR OPERATIONS COMMITTEE MEETING MINUTES October 20, 2017 ATTENDANCE Sean O'Kelly Associate Lab Director at the Advanced Test Reactor Idaho National Labs Idaho Falls, ID Committee Chairman Cynthia Duffield USGS Radiation Safety Officer, USGS Exofficio Member Michael Cosca Research Geologist, USGS Committee Member Shannon Mahan Research Geologist, USGS Committee Member Brycen Roy Reactor Supervisor, USGS Exofficio Member, Committee Secretary Vito Nuccio, Reactor Administrator, USGS, non-member (present for -30 min) Tim DeBey, Senior Reactor Operator, non-member Chris Farwell, Senior Reactor Operator, non-member Clayton Manning, Senior Reactor Operator, non-member Kirk Stueve, ATR Safety Oversight and Review Committee Chairman, non-member
Agenda Introduction of new personnel Review minutes of.previous meeting Review quarterly and annual reports Old Business NRC correspondence New Business Review and Audit of Procedures and Plans Audit of Operating Records Summary and Discussion Facility Inspection Adjourn The meeting was called to order at 0800. Start of New Business The Reactor Administrator had other obligations and could only attend the first portion of the meeting, so some of the new business was discussed at the beginning of the meeting. The Reactor Administrator reported good news on the budget for the reactor. The Energy and Minerals, and Environmental Health mission area, where the reactor sits, was the only mission area to have a proposed increase to its budget. The budget still has to go to the Senate and House. It was reported that there are sufficient funds in the fuel working capital fund to pay for a shipment of lightly-used fuel. It was noted that the USGS budget is under a continuing resolution (CR), but that the CR will not affect the working capital fund and fuel purchase. The Reactor Administrator reported the USGS will be going through a reorganization. The reorganization should not affect the reactor because the reactor sits in a mission area and is not associated with a region. Introduction of USGS RSC Cynthia Duffield had introduced herself as the USGS RSO prior to the meeting. It was discussed that she was the interim RSO until a permanent RSO could be hired. She noted that the new USGS RSO is set to start work on October 30, 2017, and should be officially named on the USGS broad scope license within 90 days of that date. Review of Previous Minutes The minutes of the March 27, 2017, meeting were reviewed. The minutes were approved as written. Review of Quarterly and Annual Reports The health physics (HP) and operations reports for the 1st, 2nd, and 3rd quarters of 2017 were reviewed. 1
Shannon asked how power loss to the building affected the reactor if the reactor was being operated. There was a discussion of the reactor's backup power and the procedure to SCRAM the reactor if there is a building power outage. Sean noted the replacement of trim pots in the NM-1000 and asked whether there were problems with the instrument. It was discussed that the trim pots need replaced periodically, but there are no major issues. Sean noted a high accumulated dose on the "151 Door Gate" environmental dosimeter. The Reactor Supervisor discussed the occupancy factor for the reactor facility perimeter. He also mentioned that because of the location of the dosimeter it was possible that the high dose rate was coming from a neighboring laboratory. After the prior discussions, the Committee voted to approve the quarterly reports as written. Old Business The Reactor Supervisor discussed the fuel acquisition efforts. It was discussed that USGS has contracts in place with Fluor Idaho, Battelle Energy Alliance (BEA-the DOE contractor that manages the BRR cask), and Secured Transportation Services (STS) for obtaining "lightly-used" fuel from the DOE storage facility at INL. The receipt of the fuel shipment is tentatively schedule for the first quarter of 2018. The shipment would be 19 lightly-used elements. Based on the list sent by Fluor Idaho, these elements appear to very lightly used, with an average burn up of -2.5%. Sean noted that it would be advisable to make preparations to use higher weight percent fuel for whenever the TRIGA International facility comes back online. These preparations would include a license amendment. NRC Correspondence The NRC performed its annual compliance inspection during the week of April 10, 2017. There were no findings of significance identified. The Reactor Supervisor noted that there had been a violation due to a faulty NP-1000 cable self-reported in 2016. This violation was issued as a "non-cited" violation as part of the 2017 compliance inspection. The Reactor Supervisor had a brief discussion on the proposed rules to move to non-expiring licenses for NRG-licensed research reactor facilities. The Reactor Supervisor discussed a conversation he had with the NRC project manager (PM). The phone conversation was initiated by the Reactor Supervisor when he called the PM to discuss how the licensing should be handled when lightly-used fuel was received at the USGS facility. When the fuel is offloaded from the transport truck, it would not be considered in transport. However, the process will take some time to move the fuel from the transport cask to the reactor room and the area outside the reactor room is not covered under the reactor license. During this conversation, the PM brought up the Safety Evaluation Report (SER) received from the NRC in October 2016 as part of the relicensing package. The SER summarizes the findings of a safety review conducted by 2
the staff of the NRC. The PM noted that within the SER the NRC confirmatory calculations indicated that the USGS's proposed limiting core condition (LCC) would reach flow stability limits below the power levels provided in the USGS's thermal-hydraulic (T-H) analysis. To quote the SER, "The NRC staff was unable to validate the licensee's T-H results for the LCC, and performed an independent T-H analysis which verified the acceptability of the USGS OCC. As indicated in Table 2.9, the USGS OCC reaches the flow stability limits at the given Hot Channel Rod Powers versus Reactor Pool Water Temperature. Based on the information above, the NRC staff concludes that the T-H analyses for the GSTR OCC is acceptable." In this case, OCC is operating core condition. The Reactor Supervisor notes that essentially the NRC states in the SER that the OCC is the most limiting core condition that they have approved, even though the NRC issued USGS a renewed license with technical specifications (TS) that reflect limits equal to the actual LCC as described throughout the relicensing process. After discussion of this issue with the Committee, Sean's final recommendation was that the Reactor Supervisor needs to work with the NRC to clarify the NRC's position on the apparent discrepancy between the SER and license/TS to ensure that the USGS reactor stays in good standing with the NRC. This could mean only loading new fuel up to the maximum OCC and working on licensing changes to allow operation up to the LCC. Review of Procedures The Committee reviewed six operating procedures the emergency plan, and the emergency procedures. The details of these reviews are given below. The Committee voted to approve all documents with changes noted below.
- 6. Procedure for Loading and Unloading Irradiation Facilities: Changed to add TS requirements into the procedure.
- 7. Procedure for Control Rod Measurement, Inspection, or Replacement: Changed the process description to reflect the upcoming modification in limit switch configuration.
- 12. Procedure for Changing Demineralizer Resin: (Not changed)
- 15. Pocket Dosimeter Drift Check Procedure (Not changed)
- 16. Pocket Dosimeter Calibration Procedure (Not changed)
- 23. Receipt of Radioactive Material Shipments: Clarified the wording for when swipes and surveys are required for the various shipment types.
Emergency Plan: Various changes were proposed to the Emergency Plan including clarification that "Health Physicist" (HP) specifically refers to the reactor's HP, clarification of who the DOE RAP team is and what their mission is, changing the classification of unusual event and alert conditions to match ANSI/ANS-15.16-2015, and a few additional clerical changes. Emergency Procedures: A few changes were proposed to the Emergency Procedures including clarification that the DOE contractor is the DOE RAP team, clarifying which staff personnel are responsible for emergencies in the Reactor Supervisor's absence, and correction of an old Technical Specification reference. 3
Physical Security Plan (PSP): Changes were proposed to the PSP to allow for a temporary controlled-access area during the time that the lightly-used fuel is received and moved into the reactor room. The Committee voted that the changes to the PSP do not reduce the effectiveness of the plan. Conclusion of New Business There was more discussion of the USGS RSO including a discussion of the relationship between the USGS reactor license and Reactor Supervisor and the USGS broad scope license and USGS RSO. Sean requested an addition to the New Business section of the agenda, a discussion of ageing management at the reactor facility. The Reactor Supervisor noted that the facility has an extensive collection of backup components such as DAC and CSC components and backup auxiliary items such as a backup NM-1000 and discrete components and spare rod drives. Additionally, it was noted that the AFRRI reactor was upgrading many of their systems and had verbally committed to give the USGS reactor whatever spare parts they desired. Chris noted that Randy Hyde would be available to provide programming support for the console. Audit of Facility Records The Committee audited the facility records, and those results are included in a separate Audit Report. Summary and Discussion The Committee made general comments that the reactor staff should be commended for their quality work. Even some of the nitpicky errors that were noted in the past were being minimized or eliminated. Additionally, it was noted that the USGS reactor is very busy and some university reactors would be jealous of the workload. The reactor staff should be commended for their high level of customer service. Adjourn The Committee adjourned at 1114. Tour Committee members toured the reactor facility. No problems were identified. Brycen Roy, Secretary 4
Proposed Agenda for the April 27, 2018 USGS Reactor Operations Committee Meeting
- 2. Review of minutes from 10/20/17 meeting.
- 3. Review of quarterly reports, annual report, annual audit, and experiment classifications (C-60, C-61, 0-28, 0-29, 0-30).
- 4. Old Business - fuel procurement efforts
- 5. NRC Correspondence
- conversation with PM regarding use of new fuel
- non-routine inspection during fuel receipt (inspection report)
- 6. Plans and Procedures: Procedures for review:
#3. Control Rod Calibration Procedure (proposed changes)
#4. Procedure for Fuel Loading and Unloading (proposed changes)
#8. Procedure for Measurement of Fuel Elements (proposed changes)
#9. Procedure for Locating a Fuel Element Cladding Failure (proposed changes)
#11. Procedure for Cleaning the Reactor Tank (proposed changes)
#13. Procedure for Use of Leak Testing Device (proposed changes)
#14. Procedure for Overhead Crane Operation (proposed changes)
#17. Procedure for Determining Argon-41 Release (proposed changes)
Radiation Protection Program (proposed changes)
- 7. New Business.
- Facility staffing
- ROC membership
- Aluminum fuel
- Historical records
- 8. Audit of Operating Records.
- 9. Summary and Discussion.
- 10. Facility Inspection.
- 11. Adjourn.
REACTOR OPERATIONS COMMITTEE MEETING MINUTES April 27, 2018 ATTENDANCE Sean O'Kelly Associate Lab Director at the Advanced Test Reactor Idaho National Lab Idaho Falls, ID Committee Chairman Thomas Johnson Associate Professor Colorado State University Fort Collins, CO Committee Member Thomas Newton Deputy Director and Chief, Reactor Operations and Engineering NIST Center for Neutron Research Gaithersburg, MD Committee Member Michael Cosca (left -10 AM, after voting on all items requiring Committee vote) Research Geologist, USGS Committee Member Shannon Mahan Research Geologist, USGS Committee Member Brycen Roy Reactor Supervisor, USGS Exofficio Member, Committee Secretary Chris Farwell, Senior Reactor Operator, non-member, present off and on Clayton Manning, Senior Reactor Operator, non-member, present off and on ___J
Agenda Review minutes of previous meeting Review quarterly and annual reports, annual audit, and experiment classifications Old Business NRC correspondence Plans and Procedures Review New Business Audit of Operating Records Summary and Discussion Facility Inspection Adjourn The meeting was called to order at 0802. Start of New Business The Reactor Supervisor noted that the Reactor Administrator would not be able to attend the meeting and had not designated another USGS management official to attend in his place. It was discussed that nothing had changed since the previous meeting in terms of the USGS reorganization and budget. It was still assumed that the GSTR would stay within its same reporting chain and would continue to receive appropriate funding. Review of Previous Minutes The minutes of the October 20, 2017, meeting were reviewed. The minutes were approved as written. NRC Correspondence part 1 - non-routine inspection and inspection report The Reactor Supervisor discussed the NRC being onsite for the receipt of lightly-used fuel from INL. Three personnel from NRC were present: Craig Bassett, inspector; Beth Reed, security specialist; Anthony "Tony" Mendiola, Chief Research and Test Reactors Oversight Branch. According to Tony Mendiola, the NRC was there to conduct a non-routine inspection to ensure that the GSTR was appropriately prepared for the receipt of lightly-used fuel from the standpoint of staff, procedures, and security. Once the fuel was onsite, Tony stated that NRC personnel would switch from regulator to observer. However, the Reactor Supervisor commented that Craig Bassett and Beth Reed both continued to perform inspections while the GSTR staff was busy dealing with the fuel receipt. The Reactor Supervisor had not received a physical copy of the non-routine inspection report, but he had gotten a digital copy off ADAMS. The GSTR received a Technical Specification Violation of Minor Safety Significance. The Reactor Supervisor summarized the finding for the Committee. The Ar-41 sampling pipe on the roof had been broken during a very severe hail storm on May 8, 2017. The broken pipe was discovered during the May 2017 monthly maintenance and repaired on June 7, 2017. The GSTR Technical Specifications allows for calculations to be performed to determine the total amount of Ar-41 released as a function of operating hours, but these calculations failed to be performed during the period when the pipe was broken and likely affecting the 1
measurement of Ar-41 release. Although these calculations were not completed at the time, follow-up calculations indicated that no release above the regulatory limit occurred. Therefore, according to the non-routine inspection report, although the issue was detected and corrected, it constituted a violation of minor significance. Review of Quarterly and Annual Reports, Annual Audit, and Experiment Classifications The Committee reviewed the health physics (HP) and operations reports for the 4th quarter of 2017 and 1st quarter of 2018; the 2017 annual report; and the 2017 annual audit. Tom Newton asked why the reported release of Ar-41 was lower for August compared to July when the MWh operated was higher in August compared to July. The Reactor Supervisor reported that a calibration of the Ar-41 monitor was performed in July and that a more accurate method for determining the reactor flux was used. The GSTR staff took a "grab" sample from the normal exhaust in a Marinelli beaker and used HPGe results for Ar-41 concentration from this "grab" sample to calculate the flux in the central thimble. In the past, the typical central thimble flux value was used and scaled from -900 kWt to the equivalent operating power during an Ar-41 calibration. The ROC Chairman asked whether the GSTR was going to notify NRC about the reason for the step change in reported Ar-41 release. The Reactor Supervisor said that they had no plans to specifically notify the NRC. After further discussion on the issue of precisely identifying the release of Ar-41, the Chairman said that the GSTR should benchmark their process against the processes of other RTRs. The ROC Chairman questioned contamination discovered on the back table in the reactor room during routine monthly swipes and surveys. He said that some type of disposable cover or a cover that could be frisked separated and potentially decontaminated should be used instead of potentially contaminating the table during central thimble sample changes. The ROC Chairman asked about the visitor dosimetry data reported in the annual audit. There was a note that the maximum recorded dose was 13 mrem but that the individual's dose could be the result of electronic interference due to a nearby cell phone. There was some discussion about proper handling of tour groups and whether certain members of the group should be allowed to remain on a tour if they did not listen to GSTR staff instruction regarding cell phone use. It was determined that the Reactor Supervisor would move forward with two potential solutions: 1) require cell phones be turned off or left elsewhere during tours and 2) work with Tom Johnson to determine whether there was a different electronic dosimeter that could be used and was less sensitive to cellular frequencies. After the prior discussions, the Committee voted to approve the quarterly reports (pending the receipt of water sample data), annual report, and annual audit with minor changes. 2
The Committee reviewed experiment authorizations C-60, C-61, 0-28, 0-29, and 0-30 for appropriate classification. A misspelling of aluminum was noted in 0-30. The classifications of the experiments were approved by Committee vote. Old Business The Reactor Supervisor discussed the receipt of lightly-used fuel from INL. Photographs of the process-com pliments of Tom Johnson-we re shown to the Committee describing the process for setting up the BRR cask and moving TRIGA fuel elements one at a time into the reactor pool using the dry transfer cask. The GSTR received a shipment of 19 TRIGA fuel elements. The Reactor Supervisor also discussed that one of the TRIGA fuel elements was received as damaged. It had a bulge on the lower weld which would not allow it to go into the go/no-go gauge. This element rs considered damaged as per the GSTR Technical Specifications and will remain in storage, out of service. The Chairman asked about the funding mechanism for the fuel receipt efforts. The Reactor Supervisor said that the project came in under the projected maximum cost and that the remaining money in the working capital fund was able to be re-prioritized to replace the secondary cooling tank. Start of New Business Aluminum fuel While on the topic of fuel, the Reactor Supervisor felt it was appropriate to discuss the aluminum fuel topic from New Business. He told the Committee that the reactor staff had conducted required quinquennial fuel inspections after the lightly-used fuel from INL was received. During these fuel inspections, 5 aluminum fuel elements failed inspection due to bowing (would not go fully into the go/no-go gauge). He continued that these 5 elements were part of the earliest aluminum fuel used in the GSTR and had been in the F-ring their whole lifetime in the GSTR core. When the damaged elements were discovered, the fuel of the same era as the damaged fuel and also having spent their whole time in the F-ring were moved to the G-ring, and the lowest-burned aluminum elements from the G-ring were moved to the F-ring. He then stated that the company who had been contracted to assist with the setup of the BRR cask and moving the lightly-used fuel into the reactor pool (Secured Transportation Services) had told him that rotating the aluminum fuel within its core location could minimize or prevent future bowing. After presenting all information on the aluminum fuel, the Reactor Supervisor asked for input from the Committee on how to handle aluminum fuel and inspections moving forward. After discussion, The Chairman recommended that the GSTR staff develop a plan and procedure for rotating aluminum fuel and inspecting the fuel at more frequent intervals than quinquennially. The Reactor Supervisor would present this _information at the next ROC meeting. NRC Correspondence part 2 - follow-up with NRC PM regarding OCC/LCC and Non-routine inspection report inspector follow-up item The Reactor Supervisor discussed a follow-up conversation with the GSTR's NRC project manager (PM). The phone conversation was initiated by the Reactor Supervisor to clear up a previous conversation and get additional information. From the minutes of the fall 2017 ROC meeting: 3
"After discussion of this issue with the Committee, Sean's final recommendation was that the Reactor Supervisor needs to work with the NRC to clarify the NRC's position on the apparent discrepancy between the SER and license/TS to ensure that the USGS reactor stays in good standing with the NRC. This could mean only loading new fuel up to the maximum OCC and working on licensing changes to allow operation up to the LCC." An email received from the NRC PM 8/10/17 states " ... you will find the results of the NRC thermal-hydraulic (T-H) analysis in Section 2.6 of the USGS License Renewal Safety Evaluation Report (SER), issued October 17, 2016. As was discussed during the NRC staff's review of the USGS license renewal, we could not accept the T-H analysis for the Limiting Core Configuration (LCC) when both our Contractor's and NRC staffs confirmatory calculations showed the minimum DNBR limit/stability limit exceeded the guidance in NUREG-1537. This conclusion is documented in the SER. However, the NRC SER T-H analysis may be useful in your review as Table 2.9 provides the Stability Limit versus Bulk Pool and Core Inlet Temperatures." This information was summarized for the Committee. The follow-up conversation with the NRC PM was similar in content to the email of 8/10/17. The conversation concluding with the NRC PM telling the Reactor Supervisor that the GSTR staff could perform MCNP modeling for new core configurations, and as long as the modeling showed a maximum peak rod of less than 17.5 kWt as per Table 2.9 of the SER, then the NRC would find the core configuration acceptable. After these discussions with the Committee, the Committee still finds the situation not acceptable. The GSTR SAR still does not align with the NRC SER, and the license and Technical Specifications were written to align with the SAR. Because the SER shows that the NRC did not accept the T-H analysis for the LCC, any fuel shuffle reviewed in accordance with the requirements of 10CFR50.59 and compared to core configurations described in the GSTR SAR could indicate an unreviewed condition. The Committee's recommendation is to continue to work on an appropriate outcome to this situation by obtaining written confirmation from NRC or to modify the GSTR SAR to match Table 2.9 of the SER. The final topic of discussion in NRC correspondence comes from the NRC non-routine inspection report. The report states that "the licensee was informed that the issue of determining whether or not a bioassay program was needed at the facility would be considered an inspector follow-up item (IFI). The Reactor Supervisor discussed that the NRC questioned whether or not there had been an evaluation of the need for a bioassay program at the facility. To the knowledge of the Reactor Supervisor, no specific evaluation had been conducted. At this point, the facility is using a portable air sampler to sample the air directly outside the fume hood during all tracer transfers. All data to this point indicates that a bioassay program is not necessary. Tom Johnson indicated that if the NRC was very picky about the analysis, they may require a breathing zone air sampler. The Reactor Supervisor indicated he would look into using a breathing zone air sampler for future analyses. 4
Review of Procedures The Committee reviewed eight operating procedures and the Radiation Protection Program. The details of these reviews are given below. The Committee voted to approve all documents with changes noted below. There was a discussion on Procedure
- 14 for Crane Operation and the crane in general. It was noted by the Committee that it could be helpful to have a checklist of topics for the training program within the procedure.
- 3. Control Rod Calibration Procedure. Changed TS requirements from general language to exact TS language. *
- 4. Procedure for Fuel Loading and Unloading. Changed to add language for new fuel handling tool. Added exact TS language for when an operator is required at the console during fuel movement. Removed requirement for posting during fuel movement.
- 8. Procedure for Measurement of Fuel Elements. Changed to make the different inspection setup descriptions more clear and accurate.
- 9. Procedure for Locating a Fuel Element Cladding Failure. Changed to add TS-defined language (should, shall, may).
- 11. Procedure for Cleaning the Reactor Tank. Language added to clarify what happens to material filtered out while cleaning the tank.
- 13. Procedure for Use of Leak Testing Device. Changed to add TS-defined language (should, shall, may).
- 14. Procedure for Overhead Crane Operation. Changed to add TS-defined language (should, shall, may).
- 17. Procedure for Determining Argon-41 Release. Changed to add clarity and allow flexibility during some portions of the calibration.
Radiation Protection Program. Changed to add information on portable air samplers to the Section 8.4.4 Airborne Radioactivity Monitoring. Conclusion of New Business Facility staffing The Reactor Supervisor stated that Tim DeBey had left the GSTR to work for the NRC, effective 12/9/2017. The facility intends to backfill the position but is waiting to hear back on a hiring waiver. ROC membership There was a discussion about the recent history of the RSO for the USGS Type A license of broad scope (USGS RSO). The Reactor Supervisor stated that it seemed likely at the time of the meeting that the current USGS RSO would be staying on as the RSO. It had seemed unlikely that would be true even the week prior to the meeting. The USGS RSO duty station would be relocated from Denver, Colorado, to Reston, Virginia. This affects the facility in that the USGS RSO is an ex-officio member of the ROC. Historical records To start the discussion of "historical records" the Reactor Supervisor asked whether the Committee thought that a correction to the annual report would need to be made in 5
response to the Technical Specification Violation of Minor Safety Significance from the non-routine inspection report. The Committee indicated that a memo to the record should be written indicating that there was no need for a correction to the annual report because the reported Ar-41 release and actual Ar-41 were so far from the limit that there was no safety significance. The Reactor Supervisor stated that a review of SCRAM count had been performed and that the actual SCRAM number reported in annual and quarterly reports was not correct. He asked the Committee whether a correction should be made to the number and, if so, how that correction should be documented. The Committee stated that the number could be changed as long as there was a note in the report acknowledging and justifying the change. Finally, the Reactor Supervisor stated that the facility had begun investigating the historical calculations of plutonium transmutation and it seemed likely that the inventory of plutonium reported to NMMSS was not accurate. He asked whether the Committee had any guidance on correcting the facility's inventory on plutonium. The Chairman said that he believe there was a specific form and to work with NMMSS to make the correction with appropriate justification. The Committee also said to be careful to ensure that the correction would be a one-time thing. Essentially, make certain the new process is sound so that another correction does not need to be made a short time into the future. Audit of Facility Records The Committee audited the facility records, and those results are included in a separate Audit Report. Summary and Discussion There was no summary and discussion of significance beyond what was included in the Audit Report. Adjourn The Committee adjourned at 1224. Tour Committee members toured the reactor facility. No problems were identified. Brycen Roy, Secretary 6
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5/16 Rev. 14 .~ USGS TAIGA REACTOR FACILITY START-UP CHECKL IST Date "I;; /j6 No. /9 'ff! Operator £2~. VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room &,/;£ in. H20. Reactor ~P to outside IP,17 in. H20. Vent system reset.,..1', Normal: Reactor ~p to control room &If in. H20. Supply system on~,~<=+ ---- Reactor ~p to outside tJ, /t; in. H20. Main exhaust on ~ t RADIATION MONITORING SYSTEMS RAM #1: Background t/1.r2.. mR/h Alarm setpoint S-z? mR/h (50) RAM #4: Background -ci,ere7 mR/h ~I arm setpoint \ r; mR/h ( 15) RAM #6: Background If'/ I> mR/h Alarm setpoint w mR/h (20) CAM:
Background:
2L ~f cpm Lo alarm: o;f cpm (5K) Hi alarm: /oi," cpm (1 OK) Airflow: ,'Et? cfm (5,+/-0.1) Calibration: J>~?:Z cpm (3600,:!:360) WATER SYSTEMS Demineralizer flow <1:5"' gpm (5 to 10) Sump level okay '2': Primarycooli ngon oi.'J:",t: lnlet:.z.1,z..- °C Outlet:-i.z,e °C Pressure: 13 psig(10-14) Secondary cooling on OS SL/ Inlet: 2.1 S psig (18 to 25), 1:l_°F Lo Pressure signals t:)K Outlet: !:z*-? psig (4 to 10), .1..L_°F Conductivity: Inlet ~-37 µSiem (<5.0) Outlet tfl,~f µS/cm AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure <30 psig (>50) Pulsing scheduled? Jv& Pulse rod functional check /{J {It Water level alarm enabled ~ REACTOR ROOM All rods down ~ Tank/Core integrity OK-%,.-~~ -- Dry tube ;;;: 0/ Central thimble C-Jff;l6'tJ I L~zy Susan ~npf't
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4/11 Rev - USGS TAIGA REACTOR START-UP CHECKLIST-page2 No.&'W "-" Pneumatic systems: Receiver Core Connected
~ Location Location or Plu'gged Bare [JV @f fJ Cd-lined f Other CONSOLE CHECKS (/
Prestart checks passed~{L§~---- Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 - L Percent 2 -1 Key switch .:Z. Hi Voltage 1_ _ __ Hi Voltage 2 / DAC Watchdog Z CSC Watchdog \L Manual_____ ~--- Rod 1= Pulse, Rod 2= Shim 1 , Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: . . Intercom check OK ~ Maximum NM1000reading '2f!8 W (>5 W) Source position /J~ Background / Y, Z mW (>5 mW) "-' ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse f Demineralizer prefilter itt> mr/hr Shim 1 .p Demineralizer tank s-S mr/hr Shim2 fl North Pb cave i,.\:. mr/hr Regulating 7 SW Pb cave I- \ mr/hr Above Rx tank t. \ mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 2 730 al,.~\) mr/hr (must be >250 mr/hr} Ludlum S/N /f:f'fl]/ !).'I,~ mr/hr Startup checks completed by _ _ ___,_,Q_. - = " , ~ : : 1 6 - S ' - - - - - - - - Time O6 ~?'.'.' Startup sheet reviewed by _ _,_*L==*.....)____________ Date '?/e:,/1G (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Date Cf/ljJ(R No. JJi$l VENTILATION SYSTEM (all LlPs must be >0.1) Emergency: Reactor LlP to control room cJ 23 in. H20. Reactor L\P to outside @,J.I in. H20. Vent system reset._..... "t"'"'e~"----- Normal: Reactor LlP to control room ~.?lO in. H 20. Supply system on--'--')'&."""l.5'----- Reactor LlP to outside c91 lq in. H20. Main exhaust on ye 5 RADIATION MONITORING SYSTEMS RAM #1: Background r9y I mR/h Alarm setpoint 'iO mR/h (50) RAM #4: Background (}, 0 mR/h Alarm setpoint l~ mR/h (15) RAM #6: Background /,) mR/h - Alarm setpoint . 'J...0 mR/h (20) CAM:
Background:
I?5{) cpm Lo alarm: 5K cpm (5K) Hi alarm: t()!c cpm (1 OK) Air flow: 5,Q cfm (5,+/-0.1) Calibration: ~sq, cpm (3600,+/-360) WATER SYSTEMS Demineralizer flow gr:)' gpm (5 to .10) Sump level okay_'Ye~e.=:.S_ _ Primary cooling on {)6lf'5' Inlet: "l }, 1 °C Outlet: ';I 'J..{) °C Pressure: J 3,0 psig (10-14) Secondary cooling on Qt..43 Inlet: 21.~ psig (18 to 25), 1..1__°F Lo Pressure signals otA<o Outlet: :5".) psig (4 to 10), l..2_°F Conductivity: Inlet c'?t'flf µSiem (<5.0) Outlet &, 'J. <1 µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure §X[) psig (>50) Pulsing scheduled?_Ni~o~-- Pulse rod functional check NIA Water level alarm enabled )'es REACTOR ROOM All rods down *y~...5 Tank/Core integrity OK Yt:0 Dry tube____,,~=!Y(>c.q.,.i....f,_._ _ __ Central thimble (-lfr; l-J~[8S' Lazy Susan L-l'f:2.l5'8':[h .#i Other &'~t111t1lier- """l~,,:l~-L~ Neutron radiography tube 5.-J.e '2f- 'Ctt1f Pump.tube Pl~td ip°k
4/11 Rev~ USGS TRIGA REACTOR START-UP CHECKLIST-page2 No. ~1'12 ,__,, Pneumatic systems: Receiver Core Connected IYlli2 Location Location or Plugged Bare rW Kq, *f Cd-lined f Other CONSOLE CHECKS Prestart checks passed---'-'0'-s_ _ __ Exceptions:. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a -rod from its down limit for each check. Percent 1 lf Percent 2 3 Key switch.~ Hi Voltage 1_--L..._ _ Hi Voltage 2 :2, DAC Watchdog f CSC Watchdog If Manual__ '3_ __ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK:
- Intercom check OK ~,i.~ Maximum NM1000 reading '~PY W (>5 W)
Source position 2::-1£: Background 2/,~ mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse IJ Demineralizer prefilter S-.?- mr/hr Shim 1 Demineralizer tank lf Id mr/hr le Shim2 ~ North Pb cave J.1~ mr/hr Regulating ?- SW Pb cave I, ~'5" mr/hr Above Rx tank <. l mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N ?.?°)0 _lt-'-'"!O.._____mrlh r (must be >250 mr/hr) Ludlum S/N 15~9 rO _4_?:()~_mr/hr Startup checks completed by-1,~~-~( ~ - - - - - - - - - Time 01-()() Startup sheet reviewed by * . 1':~ Date 9/c;;((~ (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Date q I 1p l 11.o No. 8'1~3 Operator_ _'K--';,L.-------- VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room 0.20 in. H2 0. Reactor ~p to outside 0,2-z. in. H20. Vent system reset_"'""¥__.J_ __ Normal: Reactor ~p to control room a.ls in. H20. Supply system on_~---- Reactor ~p to outside o.t(o in. H20. Main exhaust on If=( RADIATION MONITORING SYSTEMS RAM #1: Background_.....O_*o_ _ mR/h Alarm setpoint £~ mR/h (50) RAM #4: Background o.o mR/h Alarm setpoint.__l5' _ _ _ mR/h (15) RAM #6: Background o.o mR/h Alarm setpoint z.o mR/h (20) CAM:
Background:
/ra 2 cpm Lo alarm: sic- cpm (5K) Hi alarm: ml, cpm (10K)
Air flow: r, tJ cfm (5:+/-:0.1) Calibration: Y C :?/ cpm (3600.+/-360) WATER SYSTEMS Demineralizer flow 9,5 gpm (5 to 10) Sump level okay ~S: Primary cooling on Ovd% Inlet: -z2..2. °C Outlet:-z2,"l °C Pressure: I 13 psig (10-14) Secondary cooling on ~A,ois~ Inlet: '2-L,G" psig (18 to 25), ~ ° F Lo Pressure signals O!( Outlet: <o psig (4 to .10), .1:£_°F Conductivity: Inlet o,43 µSiem (<5.0) Outlet :o,z"I µSiem AUXILIARY SYSTEMS Lazy susan flush o ml/hr Pulse rod air pressure £,o psig (>50) Pulsing scheduled?_I"\_'->_ __ Pulse rod functional check N{A Water level alarm enabled 7s REACTOR ROOM All rods down r Tank/Core integrity OK 'Pf Dry tube~~C!..f'-'~.,J------ Central thimble 1 C.-"-'.tl!.h, ';j'nS Lazy Susan L. * \ ~'2SSS b :fk I Other g*' be.G ,._ , SI~ .(!- ~ , . air ,~ L-11-Z.l\1.I.I, '" 1£L/ Neutron radiography tube ~,c:>-n J. .+~1l- Pump tube ~ ?l"'-rtul .~
4/11 Re,* ' USGS TAIGA REACTOR START-UP CHECKL1ST-page2 No. 81~3 "--' Pneumatic systems: Receiver Core Connected JyQ§ Location Location or Plugged Bare \)N 1<1 t' Cd-lined NIA p Other CONSOLE CHECKS ~; Prestart checks passed __/-=ee-=,s.__ _ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 3 Percent 2 L{ Key switch Hi Voltage 1__~ - - - Hi Voltage 2 1.. DAC Watchdog CSC Watchdog LI_ Manual-'-2.._ __ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK 7/=~ Maximum NM1000 reading$: (I W (>5 W) Source position NE Background ({ 7 mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse // Demineralizer prefilter i,11 mr/hr Shim 1 9 Demineralizer tank 1.0 mr/hr Shim 2 9 North Pb cave 1,S mr/hr Regulating 7 SW Pb cave L. I mr/hr Above Rx tank l. \ mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N :2-1:'.1\) L\<;,ti mr/hr (rnust be >250 mr/hr) 2'~~-~~'-- Ludlum S/N6..... l.{1-1;:) mr/hr Startup checks completed by ---~.i..=. ..i,------- -- Time o'5~'b Startup sheet reviewed by . U e.fJ-PL r l l Date q 1?., 1l, (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 ~ USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Date q\,-\H.,o No. ~e>i-o4 Operator_ _ ~......° ' ; ) - - - - - - - VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room 0, 19 in. H2 0. Normal: Reactor ~p to outside O, '2-\ Reactor ~p to control room in. H2 0. t7..-? o in. H20. Vent system reset T Supply system on-~..,..,,.__ __ Reactor ~p to outside ~.. ?t? in. H20. Main exhaust on ~ RADIATION MONITORING SYSTEMS RAM #1: Background O, 1- mR/h Alarm setpoint So mR/h (50) RAM #4: Background._O_,o_ _ mR/h Alarm setpoint
- r mR/h (15)
RAM #6: Background l, 5 mR/h Alarm setpoint zO mR/h (20) CAM:
Background:
\-OS' cpm Lo alarm: S"lc. cpm (5K) Hi alarm: 10k: cpm (1 OK)
Air flow: o,t? cfm (5_+/-0.1) Calibration: 3!co cpm (3600.+/-360) ,,,,-,..\ WATER SYSTEMS Demineralizer flow ltJ gpm (5 to 10) Sump level okay p~cf Primary cooling on oS"S"b Inlet: / B.,°C Outlet: /7A/ °C Pressure: / ;J> psig (10-14) Secondary cooling on o s.ro Inlet: '21* C psig ( 18 to 25), G.:i °F Lo Pressure signals ok. Outlet: 6- psig (4 to 10), ~ ° F Conductivity: Inlet o,Lll µSiem (<5.0) Outlet O, 2~ µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure '60 psig (>50) Pulsing scheduled?_V\_o_ __ Pulse rod functional check N I[A Water level alarm enabled =JS REACTOR ROOM All rods down 14, Tank/Core integrity OK ~ Dry tube-=6=~;;,..,.c..9-r---,--__,,..-:--- Central thimble £"¥77 Lazy Susan L. /f<.17,5"i Jc/ Other~"'-J ~;J:2r~ Neutron radiography tube ~ttl.t.°'f"-ln11J... Pump tube p~,:a/
4/11 Rev" USGS TRIGA REACTOR START-UP CHECKLIST-page2 No.1,:1B4 -~ Pneumatic systems: Receiver Core Connected lYQ§ Location Location or Plugged Bare 1~ <<.'-\ '\) Cd-lined Other CONSOLE CHECKS Prestart checks passed_-l1f,-'5_ _ __ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 / Percent 2 2 Key switch 8 Hi Voltage 1___,'f,__ _ Hi Voltage 2
/ DAC Watchdog :Z CSC Watchdog Rod 1= Pulse, Rod 2=* Shim 1, Rod .3= Shim 2, Rod 4= Regulating 3 Manual Si'.'.
NEUTRON SOURCE RESPONSE CHECK: Intercom check OK 1f Maximum NM1000 reading *-;J.,'ls- W (>5 W) Source position r,..I e Background 2.L\, e mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse (! Demineralizer prefilter &, ,7.. mr/hr Shim 1 q Demineralizer tank 'i'L mr/hr Shim2 g North Pb cave 1,2.. mr/hr Regulating ---"-1--_ _ SW Pb cave \,~ mr/hr Above Rx tank L. \ mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N_1=-3"-"--?i~_ _ S-10 mr/hr (must be >250 mr/hr) Ludlum S/N \ S"'°\ ~':\'\ la,O\> mr/hr Startup checks co,mpleted by --------"-D~~~1 'f)-~'4.,<*
~ - - ~ - - - Time /& s-2 Startup sh~etreviewed by i)_fl,.__~7 Date 1/zi~
* * ~ (Senior Reactor Operator/Supervisor)
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5/16 Rev. 14 USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Date Wd?
- No. ~'?g>if Operator_~;...:;;,;.: ..,...).'--------
VENTILATION SYSTEM (all .6.Ps must be >0.1) Emergency: Reactor .6.P to control room o-t(R in. H20. Reactor .6.P to outside O* Zff) in. H2 0. Vent system reset._ _,_~=,es;_ __ Normal: Reactor .6.P to control room D, t"l- in. H2 0. Supply system on_y_.._es:..___ _ Reactor .6.P to outside o. 1.,,1,,, in. H20. Main exhaust on yg RADIATION MONITORING SYSTEMS cJftf RAM #1: Background___.(')_.,_ _ mR/h Alarm setpoint ~ 50 mR/h (50) RAM #4: Background c)*D mR/h Alarm setpoint~ ~5 mR/h (15) RAM #6: Background
- o* 1 mR/h Alarm setpoint'1l:rr2o mR/h (20)
CAM:
Background:
\21 t) cpm Lo alarm: 5l( cpm(5K) Hi alarm: tot<. cpm (10K)
Air flow: 6-, 0 cfm (5.:t.0.1) Calibration: 369')... cpm (3600.+/-360) WATER SYSTEMS Demineralizerflow 9-S gpm (5 to 10) Sump level okay--f'yµ--~- Primary cooling on o,'a> Inlet: ,<t.z. °C Outlet: 19- 0 °C Pressure: 13 psig (10-14) Secondary cooling on 91-z.c Inlet: ZG>*2 psig (18 to 25), ~ ° F Lo Pressure signals D"- Outlet: 2-s psig (4 to 10), J:!_°F Conductivity: Inlet o i.f3. µSiem (<5.0) Outlet o- z 8 µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure ~6 psig (>50) Pulsing _scheduled? __ Al_t_ _ Pulse rod functional check ;//.A Water level alarm enabled 'f&. REACTOR ROOM All rods down y.e.::::. Tank/Core integrity OK y..e.~
- Dry tube_~__,__-?:,-1---- --
Central thimble...;..~------- - Lazy Susanl- 141.Slr1"6 pos..i, Other ~*:;,,k s(AA ~ .,,*.~ Neutron radiography tube ;:s.i..t..c. orf -l.--.. Pump tube pLAMfed
4/11 Rev*" USGS TAIGA REACTOR START-UP CHECKLIST-page 2. No. fYtjs **-._,1* Pneumatic systems: Receiver Core Connected IYQ§ Location Location or Plugged Bare ::ucl ~i-1 1? Cd-lined Other CONSOLE CHECKS Prestart checks passed_ -+'f-=~- --- Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 f Percent 2 1 Key switch 3 Hi Voltage 1 LJ Hi Voltage 2 DAC Watchdog 1 CSC Watchdog 3- Manual ____1-~-- Rod 1= Pulse, Rod 2= Shim 1 , Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK \/.R'> Maximum NM1000 reading ?.2.. W (>5 W) Source position Nf Background -ZZ. ~ mW (>5 mW) -,/ ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse Demineralizer prefilter t.f. I mr/hr Shim 1 IC Demineralizer tank 3 tf mr/hr Shim 2 V North Pb cave ~2,(,.f.:""'-6:"" _ _ _ mr/hr Regulating _1_,___ SW Pb cave ___3~r)._;.; : . . ___ mr/hr Above Rx tank _<..;.L./___mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 3~ _'v~t.>,,:CO_ _mrlhr (must be >250 mr/hr) Ludlum S/N , ;;-P!.i'-1-l ft s~O.". .__ mrthr Startup checks completed by . . . ; , V / . / f f l . ~ ~ - - - - - - - - - Time f)f3 Startup sheet reviewed by Date C?J.u& * (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 ,-\ USGS TAIGA REACTOR FACILITY START-UP CHECKLIST Date q/,'l./11.? No. 0'1'50 Operator Adtrtu'!J VENTILATION SYSTEM (all L\Ps must be >0.1) Emergency: Reactor L\P to control room (}, 29 in. H20. Reactor L\P to outside &, ').~ in. H20. Vent system reset_)_~_$_ __ Normal: Reactor L\P to control room ,0.2.~ in. H20. Supply system on_'t{.l'----- Reactor L\P to outside_o_,2-y_ _ in. H20. Main exhaust on <f\ RADIATION MONITORING SYSTEMS RAM #1: Background o. t:> mR/h Alarm setpoint S<:i mR/h (50) RAM #4: Background o,o mR/h Alarm setpoint ts mR/h (15) RAM #6: Background o. o mR/h Alarm setpoint 2u mR/h (20) CAM:
Background:
cfW, cpm Lo alarm: 6't cpm (5K) Hi alarm: t6JK: cpm (10K) Airflow: 5.0 cfm (5_+/-0.1) Calibration: gf3b cpm (3600.+/-360) .~.., WATER SYSTEMS Demineralizer flow ci.5 gpm (5 to 10) Sump level okay Ye,5 Primary cooling on o1Zj lnlet:-zo~ °C Outlet: Zl, I °C Pressure: 1'3 psig (10-14) Secondary cooling on oS5'1 Inlet: Z\,S psig (18 to 25), fu:t..__°F Lo Pressure signals ok Outlet: S-5 psig (4 to 10), _kL°F Conductivity: Inlet o,'3'o µSiem (<5.0) Outlet o. :z<o µSiem AUXILIARY SYSTEMS Lazy susan flush a ml/hr Pulse rod air pressure 00 psig (>50) Pulsing scheduled?_(\_<:>~-- Pulse rod functional check N/ A Water level alarm enabled 3n REACTOR ROOM All rods down 7fS Tank/Core integrity OK_'f--- Dry tube 4~ Central thimble [-J../ {) lf:"J,f.i.s' Lazy Susan ~ Other g11 t-;,te,1 '1'4W' ro/1~5v4d'f~f:~ Neutron radiography tube 6rth,t,:- @-C Wt1 {L Pump tube Pl,s,ed . Il>tj'
4/11 Rev" USGS TRIGA REACTOR START-UP CHECKLIST-page2 Pneumatic systems: Receiver Core Connected I.yQg Location Location or Plugged Bare Dl'J l<g 1' Cd-lined Other CONSOLE CHECKS Prestart checks passed _ _..,.~-A=----- Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 3 Percent 2 ~ Key switch 1 Hi Voltage 1_ _.4_ __ Hi Voltage 2 J-. DAC Watchdog / CSC Watchdog ~ Manual __3___ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPQNSE CHECK: Intercom check OK rx Maximum NM1000 reading Q.i~ W (>5 W) Source position NE Background 2.\ ,'\ mW (>5 mW) *~ ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse _4__ Demineralizer prefilter '2,D mr/hr Shim 1 ~-- (o Demineralizer tank ,.~ mr/hr Shim 2 -lo- - North Pb cave '1, 1... mr/hr Regulating ___3:.___ SW Pb cave LL./ mr/hr Above Rx tank LI mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 1.:no l..\?..b mr/hr (must be >250 mr/hr) Ludlum S/N \ s '\ ~:t l ~'1.t) mr/hr Startup checks completed by .u.Jr=~=,,."'H------ ,,..,.------ Time e ifl{b Startup sheet reviewed by D-fs_ c: Date_........._.___
~ (Senior Reactor Operator/S
5/16 Rev. 14 , . __~. USGS TAIGA REACTOR FACILITY START-UP CHECKLIST Date 9 ( !'3(11, Operator~ VENTILATION SYSTEM (all LiPs must be >0.1)
. Emergency: Reactor LiP to *control room o,z~ in. H20.
Reactor LiP to outside 0
- 22 in. H2 0. Vent system reset--~-µ_ __
Normal: Reactor LiP to control room o ,1q in. H20. Supply system on---',l~-.ei.___ _ Reactor LiP to outside ,p ,'21..- in. H20. Main exhaust on V' .s RADIATION MONITORING SYSTEMS RAM #1: Background {}, I mR/h Alarm setpoint 50 mR/h (50) RAM #4: Background O*~ mR/h Alarm setpoint l 5""" mR/h (15) RAM #6: Background 6, O mR/h Alarm setpoint io mR/h (20) CAM:
Background:
J3G{} cpm Lo alarm: 5/L cpm (5K) Hi alarm: tC)k cpm (10K) Air flow: 5~ Q cfm (5::!:,0.1) Calibration: '31.<,SS cpm (3600::!:,360) WATER SYSTEMS Demineralizer flow 10 gpm (5 to 10) Sump level okay_~..Jl,,,,,,L,.,-- Primary cooling on 00'5~ lnlet: tq,'1 °C Outlet:1.<J,{ °C Pressure: ts,5' psig (10-14) Secondary cooling on O'Ql:\4 Inlet: 21,f psig(18to25), ~ ° F Lo Pressure signals Ok Outlet: ~. 5' psig (4 to 10), 61:_°F Conductivity: Inlet fJ. "3 -=r µSiem (<5.0) Outlet @, l 5'" µSiem AUXILIARY SYSTEMS Lazy susan flush o ml/hr Pulse rod air pressure &tJ psig (>50) Pulsing scheduled? n10 Pulse rod functional check u(A Water level alarm enabled 1J=' REACTOR ROOM All rods down i CS Tank/Core integrity OK__._'@_~_ _ Dry tube__..e...... rnf""IF-'-~----- Central thimble C-ttf) tt2,58E( Lazy Susan fu1t0iy Other 8"f11/t,w11'bi s,*tft: at tw111~ Neutron radiography tube 5 ,rJe af 'rc,a,t Pump tube ~a<<'~--
~r. . . . . . I
4/11 Rev - USGS TAIGA REACTOR START-UP CHECKL1ST-page2 Pneumatic systems: Receiver Core Connected JyQ§ Location Location or Plugged Bare 'l)N 'R~ 1 Cd-lined ? Other CONSOLE CHECKS Prestart checks passed___.~"""" e,.5~--- Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 I..\' Percent 2 i Key switch :3 Hi Voltage 1_ _ __ Hi Voltage 2 3 DAC Watchdog 1 CSC Watchdog 1-t Manual.__ ~--- Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating _,I NEUTRON SOURCE RESPONSE CHECK: Intercom check OK Ye7 Maximum NM1000 reading 8.llo W (>5 W) Source position NE Background ~/,b mW (>5 mW) --" ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse 1 Demineralizer prefilter 1.. 50 mr/hr Shim 1 Demineralizer tank '5'°.S- mr/hr Shim2 8 . North Pb cave J\, f mr/hr Regulating ::;- SW Pb cave
-/, '00/
- - -mr/hr Above Rx tank
-G/- - -mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 'l]'?Jb
-t-f!y(}
- - -mr/hr (must be >250 mr/hr) Ludlum S/N It;°\
I
'61 \ -w;,{)- - -mr/hr
~-~-'4"""~"'""'~______
Startup checks completed by ...... -/ ___ Time (2 ~z,5' Startup sheet reviewed by n_A /
< Date %t?/,f; (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 ~\ USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Operator~ VENTILATION SYSTEM (all LiPs must be >0.1) Emergency: Reactor LiP to control room '()."2.~ in. H20. Reactor LiP to outside o. 2:i... in. H20. Vent system reset___Jf=-=1_ __ Normal: Reactor LiP to control room o, 1.4- in. H20. Supply system on'"""1f---- Reactor LiP to outside 0,2.4: in. H20. Main exhaust on :;jts" RADIATION MONITORING SYSTEMS RAM #1: Background ~,:)... mR/h Alarm setpoint____.5"..,,.0_ _ mR/h (50) RAM #4: Background O,D mR/h Alarm setpoint I mR/h (15) RAM #6: Background o, 5" mR/h Alarm setpoint ?f2 mR/h (20) CAM:
Background:
?.(Jf} cpm Lo alarm: 5j::. cpm (5K) Hi alarm: It) k cpm (1 OK)
Airflow: o,O cfm (5,+/-0.1) Calibration: 3S:':\:j cpm (3600,+/-360) WATER SYSTEMS Demineralizer flow* JO gpm (5 to 10) Sump level okay~Yt_~-- Primary cooling on Ola40 Inlet: /ti,?... °C Outlet: ltf,{r, °C Pressure: l~/;f psig (10-14) Secondary cooling on o~40 Inlet: 21,f psig (18 to 25), ~ ° F Lo Pressure signals 6k Outlet: 5, 'S psig (4 to 10), Ji:t__°F Conductivity~ Inlet 6,3-,... µSiem (<5.0) Outlet (9,?.i µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure ~Q psig (>50) Pulsing scheduled?_o ......o=---- Pulse rod functional check NI A Water level alarm enabled '(f REACTOR ROOM All rods down 1J Tank/C?re integrity OK_';f~r__ Dry tube ~ Central thimble C.-L\141.C.oit Yp'J\,,s-' Lazy Susan fD":f~ Other?.>' 1 -h..'2.e..u:i"'\t.- 1 -so.--r. 1 Neutron radiography tube S"'~ (I~ ~ Pump tube p\v..jjeA
4/11 USGS TRIGA REACTOR START-UP CHECKL1ST-page2 Pneumatic systems: Receiver Core Connected
~ Location Location or Plugged Bare J)N RI\ "V' Cd-lined Other CONSOLE CHECKS Prestart checks passed __ 1_)___
Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 4 Percent 2 ~ Key switch I Hi Voltage 1_3_ __ Hi Voltage 2 I DAC Watchdog )- CSC Watchdog 6 Manual_...... ~-- Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK 'ts Maximum NM1000 reading ta. o=t W (>5 W) Source position_=Mf::;..___ Background '2~ .I mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse _9_,___ Demineralizer prefilter 3.& mr/hr Shim1 _q__ Demineralizer tank 2I mr/hr Shim 2 3: North Pb cave @,3 mr/hr Regulating 1: SW Pb cave I 51 mr/hr
- Above Rx tank c. I mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 2::,.-;o i.trO mr/hr (must be >250 mr/hr) Ludlum S/N 15q ~-=r\ tf'i.i_ mr/hr Startup checks completed by-I-'~-, .....
-',/-/
_ _ _ _ _ _ _ _ _ _ Time Ofa5'6 Startup sheet reviewed by Da3..Az..- Date 94z/J~
~ (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 ~\ USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Operator $7 VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room 0,:2.), in. H20. Reactor ~p to outside (9/).f? in. H20. Vent system reset.~¥t"""5::;....__ _ Normal: Reactor ~p to control room 0 .z~ in. H20. Supply system on""""'"""rf-=---- Reactor ~P to outside a .'Z.4' in. H20. Main exhaust on z!S. RADIATION MONITORING SYSTEMS RAM #1: Background____.t0......,.2_ _ mR/h Alarm setpoint_5i_Q_ _ mR/h (50) RAM #4: Background o,b mR/h Alarm setpoint IJ mR/h (15) RAM #6: Background--"-o.-=l;,_ _ mR/h Alarm setpoint ?l) mR/h (20) CAM:
Background:
J'J.i(t? cpm Lo alarm: 6t cpm (SK) Hi alarm: IP/(, cpm (1 OK) Air flow: '5 .o cfm (5.+/-,0.1) Calibration: 31/qO cpm (3600+/-360) WATER SYSTEMS Demineralizer flow l (!J gpm (5 to 10) Sump level okay--'-']8""""5...__ Primary cooling on i,7:1[ Inlet: ,.(),6 °C Outlet: 1l,1 °C Pressure: 13,;5"" psig (1 b-14) Secondary cooling on ont Inlet: 2{,p psig (18 to 25), .il2__°F Lo Pressure signals o}<, Outlet: ,S- psig (4 to 10), /£L°F Conductivity: Inlet ,9,3 µSiem (<5.0) Outlet6),23 µSiem AUXILIARY SYSTEMS Lazy susan flush b ml/hr Pulse rod air pressure r?O psig (>50) Pulsing scheduled?___.o .......a...____ Pulse rod functional check fJ j,~ Water level alarm enabled '7/1 REACTOR ROOM All rods down ~ Tank/Core integrity OK # Dry tube ~19
- Central thimble ~-l.\l'*\:'J..le21 Lazy Susan_ 9 ~ ~ - - - Othere" blWl!V\ ....,c..kc::i M oC-~l(
Neutron radiography tube p o\o c\ -\-cm\<. Pump tube y\ 11 ~'i'eA-
4/11 Rev "' USGS TAIGA. REACTOR START-UP CHECKLIST-page 2 No. ~9~f\ '-" Pneumatic systems: Receiver Core Connected TuQ§ Location Location or Plugged Bare 1\tJ <R~. p Cd-lined Other CONSOLE CHECKS Prestart checks passed __ i_g_i__~- Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 Percent 2 '.l Key switch 3 Hi Voltage 1_ _ '-1 _ __ Hi Voltage 2 DAG Watchdog l. CSC Watchdog J Manual_'f _ __ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK :if Maximum NM1000 reading RJ,o;'/ W {>5 W) Source position Nb Background 7.?., 1. mW {>5 mW) '~ ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse ~IQ__ Demineralizer prefilter _3_,_~__mr/hr Shim 1 ___.ID....__ Demineralizer tank ?, 0 mr/hr Shim2 -~- North Pb cave ~.).. mr/hr Regulating r SW Pb cave
-l,'S'r
- - -mr/hr Above Rx tank
-.c: I- - -mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 1750 -'lrO - - -mr/hr (must be >250 mr/hr) Ludlum S/N 15c<B~J ---=---~3 0 mr/hr Startup checks completed by _.m...._~µ'"-'!~fff,f---------- Time O *n ~
Startup sheet reviewed by D 1~ << Date q ht? u~ (Senior Reactor Operator/S~pervisor)
5/16 Rev. 14 USGS TAIGA REACTOR FACILITY START-UP CHECKLIST Date 1(16/tC Operator~ VENTILATION SYSTEM (all L'lPs must be >0.1) Emergency: Reactor L'lP to control room fJ./l&, in. H20. Reactor L'lP to outside ,2, i t.l in. H20. Vent system reset____~..__t>"---- Normal: Reactor L'lP to control room {),l"":> in. H20. Supply system on_'ll........_S_ __ Reactor L'lP to outside (), ~) in .. H20. Main exhaust on Y.e, RADIATION MONITORING SYSTEMS RAM #1: Background 0.3 mR/h Alarm setpoint :,b mR/h (50) RAM #4: Background tJ,O mR/h Alarm setpoint 15 mR/.h (15) RAM #6.: Background 1,3 mR/h Alarm setpoint 20 mR/h (20) CAM:
Background:
tWO . cpm Lo alarm: '5 I< cpm (5K) Hi alarm: IO[(. cpm ( 1OK) Air flow: ,:; , o cfm (5:t0.1)
- Calibration: 3 5 14 cpm (3600:t360)
WATER SYSTEMS Demineralizerflow IQ gpm (5 to 10) Sump level okay__._fe~s~- Primary cooling on &851- Inlet: 10,V °C Outlet: W,r: °C Pressure: j3.5"" psig (10-14) Secondary*cooling on fJ!vr Inlet: 1\,0 psig (18 to 25), .f:i.L°F Lo Pressure signals Dk.. Outlet: 5.r, psig (4 to 10), ~ ° F Conductivity: lnlet&,'fl µSiem (<5.0) Outlet O,?.'t: µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure x?b psig (>50) Pulsing scheduled?_....M-a'----- Pulse rod functional check NIA Water level alarm enabled Yes REACTOR ROOM All rods down it> Tank/Core integrity OK Y~s Dry tube_,,e..,_.m..,.fl&---- -- Central thimble (-If/ tf').(p~"il l/f ...,5\azy Susan...... e..,..1t1-~TJ---- Other 8" b&tu, t..be-i,,,t.fer.(.l/.J~ Neutron radiography tube S ;Je d Tcm k
- Pump tube ft,,,,,J I: 1
.r-...
4/11 Rev"' USGS TRIGA REACTOR START-UP CHECKL1ST-page2 No. M'i?Q Pneumatic systems: Receiver Core Connected IYQ& Location Location or Plugged Bare p,,J Rlf- p Cd-lined p Other CONSOLE CHECKS Prestart checks passed~'ft~{}.~:S_ _ __ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 I Percent 2 ~ Key switch 3 Hi Voltage 1__ lf-'---- Hi Voltage 2 / DAC Watchdog 'l CSC Watchdog 3 Manual_!f _ __
- Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK:
Intercom check OK \~ Maximum NM1000 reading ~.1'2. W (>5 W) Source position NE. Background 2J, mW (>5 mW) .__,, ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse io Demineralizer prefilter 5. \ mr/hr Shim 1 _u9__ Demineralizer tank '1i mr/hr Shim 2 9
--=--- North Pb cave z.1 mr/hr Regulating --'-~-- SW Pb cave L\ nir/hr Above Rx tank L.. \ mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N 7-f]O ~(Qo mr/hr (must be >250 mr/hr) Ludlum S/N \ "':)q 'ot \ L.{'30 mr/hr Startup checks completed by -l/l.'Vlt114'tl44#-~ ---~...---- Time fJlif!
Startup sheet reviewed by Date rf.t47/(? (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 USGS TAIGA REACTOR FACILITY START-UP CHECKLIST Date 9 lI oi l It.? No. ~ q \ Operator CD
--~+-'"=-+.~------
VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~P to control room o, Z'Z in. H20. Reactor ~p to outside 0,20 in. H20. Vent system reset._-,fr.r'----- Normal: Reactor ~P to control room f),'2 ~ in. H20. Supply system on_,~~~s___ Reactor ~P to outside B~'?-D in. H20. Main exhaust on fe 5 RADIATION MONITORING SYSTEMS RAM #1: Background '9i( mR/h Alarm setpoint._-5""'"'2D~_ _ mR/h (50) RAM #4: Background <9,l mR/h Alarm setpoint ~6 mR/h * (15) RAM #6: Background__..&-1_/__ mR/h Alarm setpoint ;i.O mR/h (20) CAM:
Background:
i:rttJ cpm Lo alarm: 5 Jc. cpm (5K) Hi alarm: /OK cpm (1 OK) Air flow:_S:_.,_.,Q,.____cfm (5+/-0.1) Calibration: '3409 cpm (3600+/-360) WATER SYSTEMS Demineralizer flow ID gpm (5 to 10) Sump level okay---'-'Yt=.s_ _ Primary cooling on O(o 13 lnlet:2/,3 °C Outlet:~l,t:. °C Pressure: G.0 psig (10-14) Secondary cooling on o(al\ Inlet: 21,D psig (18 to 25), .MJ._°F Lo Pressure signals f) /( Outlet: ~. 0 psig (4 to 10), ~ ° F Conductivity: Inlet (2,':10 µS/cm (<5.0) Outlet f), :2& µSiem AUXILIARY SYSTEMS Lazy susan flush o ml/hr Pulse rod air pressure 2() psig (>50) Pulsing scheduled?_~('l~o_ _ Pulse rod functional check t1{A Water level alarm enabled # REACTOR ROOM All rods down Ye5 Tank/Core integrity OK }?;-,5 Dry tube emp& ~ Central thimble (- '16tfl6"Bo Lazy Susan 4-dft=JJ1.-lr):t'J.k"blbther ""*'"'~* wafett.ffJ5~;Ht41~ Neutron radiography tube SJ? ~-f Ta,if Pump tube Pl"99ecl
4/11 Rev'"" USGS TAIGA REACTOR START-UP CHECKLIST-page 2 No. ~'H \~ Pneumatic systems: Receiver Core Connected JYQ.§ Location Location or Plugged Bare <t)N RL\ \"' Cd-lined Other CONSOLE CHECKS Prestart checks passed _ _,-t=\_ __ 1 Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 ~ Percent 2 Lf" Key switch / Hi Voltage 1----'~--- Hi Voltage 2 / DAC Watchdog 3
- CSC Watchdog Cl\, Manual___ tl"'----
Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK 'f Maximum NM1000 reading .%.eio W (>5 W) Source position f:.(E Background 2&f~ mW (>5 mW) '- ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse H Demineralizer prefilter -a.,;- mr/hr Shim 1 °I Demineralizer tank 'i,O mr/hr Shim2 r North Pb cave 3,'2 mr/hr Regulating 0 SW Pb cave l,1-f mr/hr Above Rx tank L. I mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovi_sion S/N '2.1:iO (must be >250 mr/hr) Ludlum S/N lj'f,PrJ
~,o
~1a mr/hr mr/hr Startup checks completed by _.l!!!.~'4441)! '..__----o:~--:: ----- Time 9 (i1n Startup sheet reviewed by Date f/J" (;e, (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 USGS TRIGA REACTOR FACILITY START-UP CHECKLIST No. 019'2- Operator 12":9 VENTILATION SYSTEM (all .1.Ps must be >0.1) Emergency: Reactor .1.P to control room 'O :z:z.. in. H20. Reactor .1.P to outside o,i:z, in. H20. Vent system reset_¥f....,f,"'---- Normal: Reactor .1.P to control room 0.1\.o in. H20. Supply system on___..'a......
£(____
Reactor .1.P to outside ~. \r in. H20. Main exhaust on 1' RADIATION MONITORING SYSTEMS RAM #1: Background o.o mR/h Alarm setpoint '5'6 mR/h (50) RAM #4: Background Q,O mR/h Alarm setpoint I '.5 mR/h (15) RAM #6: Background 6. 5 mR/h Alarm setpoint Zo mR/h (20} CAM:
Background:
10s cpm Lo alarm: '5k cpm (5K) Hi alarm: 10/::.. cpm (1 OK) Airflow: [,O cfm (5_+/-0.1) Calibration: :351 <a cpm (3600.+/-360) WATER SYSTEMS Demineralizer flow /"O gpm (5 to 10) Sump level okay_'ff--- Primary cooling on o~5'1 lnlet:-io,"t- °C Outlet: zl,3 °C Pressure: 1'3 psig(10-14) Secondary cooling on :Q-1-3~ Inlet: Zt, 5 psig (18 to 25), .fet._°F Lo Pressure. signals ok Outlet: c;;.s- psig (4 to 10), ~ ° F Conductivity: Inlet 9 .1.{~ µSiem (<5.0) Outlet 0 .1.s µSiem AUXILIARY SYSTEMS Lazy susan flush o ml/hr Pulse rod air pressure eoo psig (>50) Pulsing scheduled?__;f\;...:.o.;;.....___ Pulse rod functional check &(A Water level alarm enabled 1s REACTOR ROOM All rods down ~tC Tank/Core integrity OK '1f-- Dry tube ~pra Central thimble c.-3842-i/~4
- Lazy Susan____ :;""'"'"\!"...,.,~--- Other<&Mtd-k.D., :-ik.. oi:.~
Neutron radiography tube 5 ,~ ~ ~¥'.- Pump tube ~v..sqc.o\
4/11 Rev"' USGS TAIGA REACTOR START.. UP CHECKLIST-page2 No.ffi<t7. ~ Pneumatic systems: Receiver Core Connected
~ Location Location or Plugged Bare DN R~ t>
Cd-lined Other CONSOLE CHECKS Prestart checks passed _ _ ~-&:c_ __ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 '3 Percent 2 L.\ Key switch Hi Voltage 1__2. _ __ Hi Voltage 2 '.? DAC Watchdog L( CSC Watchdog Manual_Z. _ __ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom ch.~ck OK fr .Maximum NM1000 reading g::z; W (>5 W) Source pos1t1on N: Background :z.o,.ca mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse l( Demineralizer prefilter z.'3 mr/hr Shim 1 "I __ _.., Demineralizer tank ~.5 mr/hr Shim 2 ~
--=-- North Pb cave -is mr/hr Regulating 3:: SW Pb cave l,~ mr/hr Above Rx tank "-l mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N~1L}-1~C)_ _ 41ob mr/hr (must be >250 mr/hr) Ludlum S/N \ t;'\ ~1' ~ t.-l'LO mr/hr Startup checks completed b y - - -...........
~ +--_ _ _ _ __ _ , , . ._ _ _ Time o~o~
Startup sheet reviewed by U~~ ,c . Date qht1 /;r,,
/ (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 r"'\ USGS TAIGA REACTOR FACILITY START-UP CHECKLIST Date f7f /;)>/i(R Operator (!dar11Jlr:l:j VENTILATION SYSTEM (all L'lPs must be >0.1) Emergency: Reactor L'lP to control room fJ.~t in. H20. Reactor L'lP to outside {9, 7..?-. in. HzO. Vent system reset._'"'"'Ye;;..;::s:;,...___ Normal: Reactor L'lP to control room &/J.') in. H20. Supply system on~)1-=.!2.S~-- Reactor L'lP to outside Q.;2,+ in. H20. Main exhaust on Yt__s RADIATION MONITORING SYSTEMS RAM #1: Background fJ. I mR/h Alarm setpoint 50 mR/h (50) RAM #4: Background Q.O mR/h Alarm setpoint 15 mR/h (15) RAM #6: Background 0. I mR/h Alarm setpoint 2o mR/h (20) CAM:
Background:
l:SOQ cpm Lo alarm: talc.
- cpm (5K) Hi alarm: r Ok cpm (1 OK)
Air flow: v/0 cfm (5.+/-0.1) Calibration: 35:/-t' cpm (3600.+/-360) WATER SYSTEMS Demineralizer flow t 5" gpm (5 to 10) Sump level okay Ye>,S Primary cooling on f/l:f)?.. Inlet: :Z.O,l °C Outlet:;20,;; °C Pressure: 13.0 psig-(10-14) Secondary cooling on ~W Inlet: 21, ~ psig (18 to 25), .b...G.._°F Lo Pressure signals f2/C Outlet: 5,S" psig (4 to 10), ~ ° F Conductivity: Inlet().,~ µSiem (<5.0) Outlet f), :26 µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure ao psig (>50) Pulsing scheduled?-'M~'cJ_ __ Pulse rod functional check NIA Water level alarm enabled )i:, REACTOR ROOM All rods down Yes Tank/Core integrity OK 'Ye$ Dry tube...;:;./3...:.:.m-~f.-&---- 11 Central thimble e MpEJ Lazy Susan eMpty Other 8 +11.bs -WJ.ix *MW s:-tkof1vlc Neutron radiography tube _*...:!.>=*,J=e;.:,_,s:,QV~J..ua4Lt1J..A.I:_______ Pump tube -'-f.,_.,.,lv&,-e=-d_ _
4/11 USGS TAIGA REACTOR START-UP CHECKL1ST-page2 Pneumatic systems: Receiver Core Connected
~ Location Location or Plugged Bare oAI R't p Cd-lined NII+ p Other CONSOLE CHECKS Prestart checks passed- -'~"'"'f.S ~---
Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 L-1 Percent 2 3 Key switch J. Hi Voltage 1_.1. Hi Voltage 2 :f DAC Watchdog 3 CSC Watchdog ;;;i, Manua l._.i~-- Rod 1= Pulse, Rod 2= Shim 1 , Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK Yes Maximum NM1000 reading 2. I W (>5 W) Source position N'c- Background "15 mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse __._,l/'--- Demineralizer prefilter Z,I mr/hr Shim 1 _I().,__ Demineralizer tank 3,5 mr/hr Shim 2 __.S?.___ North Pb cave 7.,S mr/hr Regulating ___._f_ _ SW Pb cave l, z. mr/hr Above Rx tank L-1 mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N z.]-'StJ '-f4D mr/hr (must be >250 mr/hr) Ludlum S/N I <5~~1-! 420 mr/hr
~~
Startup checks completed by ....~-~,,___...... - _),___ _-=---- - Time
........... ©¥15' Startup sheet reviewed b/_ ~ D.r/!;,_.J>J< Date qPt1k I (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 r--s, USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Date j(23j( v No. ?f/t!lf Operator~ VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room o,i~ in. H2 0. Reactor ~p to outside 0,25 in. H2 0. Vent system reset._-]_g,r..____ Normal: Reactor ~p to control room (2,7.. 4 in. H2 0. Supply system on_Y...,.......*e;s--- Reactor ~p to outside &,?v ~ in. H20. Main exhaust on Yt:5 RADIATION MONITORING SYSTEMS (#ff RAM #1: Background @ Q.1 mR/h Alarm setpoint :50 mR/h (50) RAM #4: Background {9, I mR/h Alarm setpoint._.._ 1~_ _ _ mR/h (15) RAM #6: Background (}, 'l mR/h Alarm setpoint 'J.0 mR/h (20) CAM:
Background:
- z. ,s5o cpm . Lo alarm: 5k cpm (5K) Hi alarm: !Q\s cpm (1 OK)
Air flow: 5,Q cfm (5+/-0.1) Calibration: .35& 1 cpm (3600,:!:360) r---.. WATER SYSTEMS Demineralizer flow °/*S gpm (5 to 10) _ __ Sump level okay_'{)?.v Primary cooling on 12~15: Inlet: J'J),~ °C Outlet: tPJ.0/ °C Pressure: ~3'.Q psig (10-14) Secondary cooling on ~~IO Inlet:* 11,n psig (18 to 25), l..f_°F Lo Pressure signals r)K. Outlet: 6,!f psig (4 to 10), .kl:_°F Conductivity: Inlet 0.11 µS/cm (<5.0) Outlet o. z(p µSiem AUXILIARY SYSTEMS Lazy susan flush O ml/hr Pulse rod air pressure <to psig (>50) Pulsing scheduled?__,r.-'-o_ __ Pulse rod functional check NIl A Water level alarm enabled 1!) REACTOR ROOM All rods down ~s:.. Tank/Core integrity OK._\-fJt._:S_ _ Dry tube.-'4::.::.L.. .hr~----- Central thimble (J., Lazy Susan~ Other 8't4<:,w,.f....-,s,o<, 911-1_ Neutron radiography tube St@ 6lf' ~L Pump tube p6 rwC
4/11 USGS TAIGA REACTOR START-UP CHECKL1ST-page2 Pneumatic systems: Receiver Core Connected
- [yQ§ Location Location or Plugged Bare ~Al 'RL{
Cd-lined Al/A: t Other CONSOLE CHECKS Prestart checks passed___,.f=t-..:;..~_ _ __ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 :1. Percent 2 Lf: Key switch / Hi Voltage 1_____ 3___ Hi Voltage 2 I DAC Watchdog ¥ CSC Watchdog A Manua1_3_ _ __ Rod 1= Pulse, Rod 2= Shim 1., Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK._,_v..e....s__ Maximum NM1000 reading Jl: 3 W {>5 W) Source position # Backgroun d Z1* f mW (>5 mW) ROD DOWN READINGS (each <25) BACKGRO UND RADIATION LEVELS Pulse
-t(- - Demineral izer prefilter .....;2=-*....::::2.---mr/hr Shim 1
-'1- - Demineral izer tank __,_7,-"'--B_ _ _ mr/hr
-z..z.
Shim 2 ___.f__ North Pb cave
- - -mr/hr Regulating -1 SW Pb cave
-~ -mr/hr Above Rx tank
-t- - (
- -mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N ~73Q
- t..f'-to
- - -mr/hr (must be >250 mr/hr) Ludlum S/N /b-qg;q
--------J../1.D
-mr/hr Startup checks completed by"""~:...::=,,.~=_-_/ _____ -=--- - Time ()~2""3 Startup sheet reviewed by / . uel3:E:2. Date Cf/s1:1Uk,
. 7c (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 /~, USG S TRIGA REACTOR FACILITY START-UP CHECKLIST No. fil'1 S Operator_ _ _ ]?==i,. ---- --- 7 VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room h.z.<o in. H20. Reactor ~P to outside o.z.ll in. H20. Vent system reset._ _,;faf------ Normal: Reactor ~p to control room a,z:z.. in. H20. Supply system on_-,1,'f'-s_ __ Reactor ~p to outside--=-(>i-'--to_ _ in. H20. Main exhaust on_J/"-'r'--- RADIATION MONITORING SYSTEMS RAM #1: Background 0.12 mR/h o,J Alarm setpoin t_-"u"--__ mR/h (50) RAM #4: Background o.o mR/h Alarm setpoint t5 mR/h (15) RAM #6: Background o.l mR/h Alarm setpoint "J.0 mR/h (20) Coo cpm Lo alarm: ,;le cpm (5K) Hi alarm: {;)k: cpm (1 OK) CAM:
Background:
-ii Airflow : 5".o cfm (5+/-,0.1) Calibration: '331f?i cpm (3600+/-,360)
WATER SYSTEMS Demineralizer flow 9.13 gpm (5 to 10) Sump level okay lp.J Primary cooling on 0<oS"Z Inlet: ('l.Ct °C Outlet: 20."3 °C Pressure: 11.1:> psig (10-14) Secondary cooling on oto4.6 Inlet: 1- \, <;; psig (18 to 25), ~ ° F Lo Pressure signals 015 Outlet: S".5 psig (4 to 10), .0!.__°F Conductivity: Inlet o,32.- µSiem (<5.0) Outlet o,i.i. µSiem AUXILIARY SYSTEMS Lazy susan flush o ml/hr Pulse rod air pressure 't.lO psig (>50) Pulsing schedu led?~n...... o _ __ Pulse rod functional check g[A I Water level alarm enabled ff REACTOR ROOM All rods down ?fJ Tank/Core integrity OK 'fr Dry tube _a.;'<Y'pb
&J,,,,X.
Central thimble C-441.loi~ '""P""S Lazy Susa n._~= -+---- Otherg"-k.-.~(, ""t1Je.-,
$~
Neutron radiography tube :::nL ~ +9"\\< Pump tube -1<f=l"'-,:i..1~5..:c...*A.::.__ _
4/11 USGS TAIGA REACTOR STA.RT-UP CHECKL1ST-page2 Pneumatic systems: Receiver Core Connected
~ Location Location or Plugged Bare 'DtJ (?.~ "\)
Cd-lined Other CONSOLE CHECKS Prestart checks passed_~_s.:'-=-s_ _ __ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 '2:: Percent 2 2- Key switch \ Hi Voltage 1---=-3_ __ Hi Voltage 2 .3 DAC Watchdog '-1 CSC Watchdog ~ Manual_.____ _ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK y-1 Maximum NM1000 reading 1.<.:i/ W (>5 W) Source position NE Background,?{* 7 mW (>5 mW) ROD DOWN READINGS (each <25) BACKGROUND RADIATION LEVELS Pulse lZ. Demineralizer prefilter
-11'f
- ' - - -mr/hr Shim 1 "I Demineralizer tank ~,>
-=---=- ----mr/hr Shim2 7 North Pb cave 3.~ _ _mr/hr
--=---...........
.., ,~ ;q Regulating SW Pb cave Above Rx tank Lo}
----.1 ----mr/hr
--- mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N~i~1_1\::>_ __ 'frO mrlhr (must be >250 mr/hr) Ludlum S/N lS1~3:\ 1,f;z,O mr/hr
- Startup checks completed by (4/i' J Jibm,i Time J~1-lQ Startup sheet reviewed by U-P£7d.** Date (Senior Reactor Operator/Supervisor)
C/ hl/4'
5/16 Rev. 14 /""""'\, USGS TAIGA REACTOR FACILITY START-UP CHECKL IST No. B99(,q Operator_ _ \?""---: :------- - VENTILATIO N SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room ,0.2.~ in. H20. Reactor 6.P to outside ti ,'2'1 in. H20. Vent system reset__ d_er,___ Normal: Reactor ~p to control room 0.2-z. in. H2 0. Supply system on_'3.,,_Jlf_ __ Reactor ~p to outside o,io Main exhaust on 1r RADIATION MONITORING SYSTEMS RAM #1: Background_._. 0 .......o.....__mR/h Alarm setpoint ~ mR/h (50) RAM #4: Background o.o mR/h Alarm setpoint_"-",6'--_mR/h (15) RAM #6: Background__,.,p....,.1_ _ mR/h Alarm setpoint 2.0 mR/h (20) CAM:
Background:
1£>00 cpm Lo alarm: 6 lc=- cpm (5K) Hi alarm: r0 (s cpm (1 OK) Air flow:_s_.n_ _cfm (5.:+/-.0.1) Calibration: 3 S o(o cpm (3600.:+/-.360) WATER SYSTEMS Demineralizer flow 9, s gpm (5 to 1O) Sump level okay_Y/4,-= ---- Primary cooling on 1'2.'Z.'1 Inlet: r:J.y °C Outlet:,~.~ °C Pressure: !'3,5' psig (10-14) Secondary cooling on 1i'l'l Inlet: 2-1.s psig (18 to 25), .fil_°F Lo Pressure signals Ok Outlet: It> psig (4 to 10), JiL_°F Conductivity: Inlet o,:05 µSiem (<5.0) Outlet o.'Z~ µSiem AUXILIARY SYSTEMS Lazy susan flush o ml/hr Pulse rod air pressure <oo psig (>50) Pulsing scheduled?___,o......'O.___ _ Pulse rod functional check MIA I Water level alarm enabled 71 REACTOR ROOM All rods down ~ Tank/Core integrity OK. ¥{~ Dry tube 94~ Central thimble C. -\ l:lL\1. S"85 Lazy Susan---=~'-'-'-41i:..:...I---- Other ,e,-!-1..~ e, wd-cr ridv. o+4~ Neutron radiography tube $, <N> iJ. ,\-.,,,.)( Pump tube -Ffl.._,"-.._.l~""-'e,ol_ _
4/11 Rev USGS TRIGA REACTOR START-UP CHECKLIST-page2 No. eqg{o '-"' Pneumatic systems: Receiver Core Connect ed
~ Location Location or Plugged Bare 1:)N 1<.~. ~
Cd-lined ~l l\ (i\/\,1: 2ftr2 <<.., Other CONSOLE CHECKS Prestart checks passed __~-g._._l_ __ Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 d.. Percent 2 ~ Key switch / Hi Voltage 1_..,_,J_ __ Hi Voltage 2 DAC Watchdog 3 CSC Watchdog 1-- Manua l_lf-'--- -- Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRON SOURCE RESPONSE CHECK: Intercom check OK-~..... O~- Maximum NM1000 reading %,4o W (>5 W) Source position tJE. Backgrou nd *z.L\. ,I mW (>5 mW) ROD DOWN READINGS (each <25) BACKGR OUND RADIATION LEVELS Pulse 11 Deminer alizer prefilter 1.,'5 mr/hr Shim 1 j Deminer alizer tank '3.} mr/hr Shim2 £i North Pb cave '2.; mr/hr Regulating 1- SW Pb cave t. i. mr/hr Above Rx tank L\ mr/hr RX ROOM ION CHAMBER(s) check: Victoreen /lnovision S/N 11~0 ~~\) mr/hr (must be >250 mr/hr) Ludlum S/N 1t;;°1'611 ~1,\) mr/hr Startup checks completed by (f1ff .J fl..;,,,,J, Time._11:--=?,='3_ __ Startup sheet reviewed by ----' D~~ fj3= ~~-- ----- - Date 9jz;, /f?.
, (Senior Reactor Operator /Supervis or)
5/16 Rev. 14 USGS TAIGA REACTOR FACILITY START-UP CHECKLIST Date '1~ gf(, No. {2917 Operator__,_~ ..=,a;;......;.-..:~ =.----- VENTILATION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room &.2? in. H20. Reactor ~p to outside 42, 2e in. H20. Vent system reset__ ~--- Normal: Reactor ~p to control room a,.~ o in. H20. Supply system on___,~---- Reactor ~p to outside &.-/ 'f in. H20. Main exhaust on ,kb: RADIATION MONITORING SYSTEMS RAM #1: Background (!), ( mR/h Alarm setpoint j-o mR/h (50) RAM #4: Background &, O mR/h Alarm setpoint ; mR/h (15) RAM #6: Background *(f), I mR/h Alarm setpoint 20 mR/h (20) CAM:
Background:
20"' cpm Lo alarm: ,SK cpm (5K) Hi alarm: /.t?,(: cpm (10K) Air flow: Sr tJ cfm (5+/-0.1) Calibration: 31)2"/ cpm (3600+/-360) WATER SYSTEMS Demineralizerflow q5" gpm (5 to 10) Sump level okay & Primary cooling on ~~~ lnlet:/g',f °C Outlet: 2,::z,o °C Pressure: J3,!i psig (10-14) Secondary cooling on 1761'1 Inlet: ~l.'J psig (18 to 25), ~ ° F Lo Pressure signals &:'/:( Outlet: 5".o psig (4 to 10), ~ ° F Conductivity: Inlet &,3.s' µSiem (<5.0) Outlet o.~ µSiem AUXILIARY SYSTEMS Lazy susan flush tt::7 ml/hr Pulse rod air pressure g,s- psig (>50) Pulsing scheduled? * /U'v' Pulse rod functional check ;V(/1-Water level alarm enabled Yqs REACTOR ROOM All rods down ft<< Tank/Core integrity OK____~...,,_,:.__ Dry tube C!Uf (7 1 Central thimble C.. l/tlf2S'W Lazy Susan 6y-ly Other&' t~"1P4-a{tq.,~tµ,~ Neutron radiography tube 1;c!e,, o.f ia11,e Pump tube r,04~~
4/11 USGS TAIGA REACTOR START-UP CHECKLIST-page2 Pneumatic systems: Receiver Core Connected JyQg Location Location or Plugged Bare j)Al l?f' Cd-lined f f Other CONS OLE CHECKS ,, Prestart checks pa~se d_......~ - - - - Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Scram checks: Raise a rod from its down limit for each check. Percent 1 Percent 2 Q Key switch s Hi Voltage 1--=-Y'_ __ Hi Voltage 2 f DAC Watch dog 3 CSC Watchdog 2_ Manual_......!_ __ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTR ON SOURCE RESPONSE CHECK: Intercom check OK t.;: 7. Maxim um NM1000 reading ~,z W (>5 W) Source position ;i/c Background :?s; 8 mW (>5 mW) "-.__,,* ROD DOWN READINGS (each <25) BACKG ROUN D RADIATION LEVELS Pulse 9 Demineralizer prefilter 2.. I mr/hr Shim 1 9 Demineralizer tank LtJ mr/hr Shim2 ~ North Pb cave 2,2 mr/hr Regulating 7 SW Pb cave J. .s mr/hr Above Rx tank L/ mr/hr RX ROOM ION CHAMBER(s) check: Victoreen/lnovision S/N .ZlJo _,P~~.::..'t:?_ _ mr/hr (must be >250 mr/hr} Ludlum S/N Ir fl?'?/ -=(e=e;:f);...__mr/hr 7~,,,__ _ 4 . .-..:..dJ.~= Startup checks completed by _ _ _ _ _ ,Uf,_, Time OGf'.7 Startup sheet reviewed by ~ Date 9\ '.)p \ l\q (Senior Reactor Operator/Supervisor)
5/16 Rev. 14 USGS TRIGA REACTOR FACILITY START-UP CHECKLIST Date tf/{%)/!p Operator J/a,utctqj VENTILAT ION SYSTEM (all ~Ps must be >0.1) Emergency: Reactor ~p to control room f),')_v-( in. H20.
/
Reactor ~P to outside ~,2'9: in. H20. Vent system reset_1__e5=--- - Normal: Reactor ~p to control room @P,'t in. H20. Supply system on----"'Ye:~;_ __ Reactor ~p to outside (J,2'1 in. H20. Main exhaust on Ye.,s RADIATION MONITORING SYSTEMS RAM #1: Background {), ( mR/h Alarm setpoint 5[} mR/h (50) RAM #4: Background (.), l mR/h Alarm setpoint . It) mR/h (15) RAM #6: Background r!J. I mR/h Alarm setpoint '10 mR/h (20) CAM:
Background:
lff:PO cpm Lo alarm: at- cpm (5K) Hi alarm: l(!)/C cpm (1 OK) Air flow: lf,Q cfm (5.:t,0.1) Calibration: 3 fi /"{ cpm (3600.:t,360) WATER SYSTEMS Demineralizer flow q,,r- gpm (5 to 10) Sump level okay ~ Primary cooling on !12~ lnlet:/'tJ °C Outlet:# °C Pressure: /J> psig (10-14) Secondary cooling on m.l Inlet: ?/::5 psig (18 to 25), b8 °F Lo Pressure signals QK Outlet: Sr,5 psig (4 to 10), 6 7 °F Conductivity: Inlet ~,3~ µSiem (<5.0) Outlet ttv, µSiem AUXILIAR Y SYSTEMS Lazy susan flush CD ml/hr Pulse rod air pressure J>O psig (>50) Pulsing scheduled?-..L.M_.fJ"""'--- Pulse rod functional check IV/fl Water level alarm enabled )"e..s REACTOR ROOM All rods down 'ft.s Tank/Core integrity OK.___.Yc,=:.5_ _ Dry tube el'rtf& , Central thimble C-'lf0 'f),'5@(f Lazy Susan C!npfy Other 8rtf11fu~wa-fec fdbl- s.--k dt1::: Neutron radiography tube Si)e. gt 1'1L. Pump tube P'wti
r 4/11 Re, USGS TAIGA REACTOR START-UP CHECKL1ST-page2 No. <lo/I} **--- Pneumatic systems: Receiver Core Connect ed
~ Location Location or Plugged Bare OAI g 'f: f Cd-lined Other CONSOL E CHECKS Prestart checks passed ~Ye.;," ------
Exceptions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Scram checks: Raise a rod from its down limit for each check. Percent 1 3 Percent 2 Key switch 4 Hi Voltage 1_ _ 2-,___ Hi Voltage 2 t DAC Watchdo g 1. CSC Watchdog / Manual.__.3_ __ Rod 1= Pulse, Rod 2= Shim 1, Rod 3= Shim 2, Rod 4= Regulating NEUTRO N SOURCE RESPONSE CHECK: Intercom check OK Yes Maximum NM1000 reading f, 11 W (>5 W) Source position Alt- Backgrou nd t~ r mW (>5 mW) '.._..,/. ROD DOWN READINGS (each <25) BACKGR OUND RADIATION LEVELS Pulse tO Deminer alizer prefilter '.).,f" mr/hr Shim 1 q Deminer alizer tank 1,,Z mr/hr Shim2 B North Pb cave ~.~ mr/hr Regulating 1- SW Pb cave mr/hr
'* 3 Above Rx tank Lj mr/hr RX ROOM ION CHAMBER(s) check: Victoreen /lnovision S/N 17-J& ,go mr/hr (must be >250 mr/hr) Ludlum S/N t5'1#il') (2 ~t)_ mr/hr Startup checks completed by ...Lf.f4 'f1L-~~ 1444C ---.---- -- Time 11 UJ Startup sheet reviewed by Date IO/?# /16 (Senior Reactor Operator /Supervis or)}}