ML20239A017
| ML20239A017 | |
| Person / Time | |
|---|---|
| Site: | University of California-Davis |
| Issue date: | 09/01/1998 |
| From: | Richards W AIR FORCE, DEPT. OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20239A019 | List: |
| References | |
| NUDOCS 9809080052 | |
| Download: ML20239A017 (28) | |
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DEPARTMENT OF THE AIR FORCE HEADQUARTERS SACRAMENTO AIR LOOISTICS CENTER (AFMC) McCLELLAN AIR FORCE BASE, CALIFORNIA 1 Sep 98 SM-ALC/TI-l 5335 Price Avenue j McClellan AFB CA 95652-2504 i l Document Control Desk U.S. Nuclear Regulatmy Commission Washington DC 20555 ) Ref: License #R-130
Subject:
Reportable Occurrence: Failed Fuel Element Fourtee" Day Report Dear Sir The following reportable occurrence is being documented in accordance with the McClellan Nuclear Radiation Center's (MNRC) Technical Specifications 6.6.2(a, b and c) and
)
6.7.2(a.8.2). 19 Aue 98, at 1835 hours, the senior reactor operator granted permission to start reactor
- run #3072. The reactor was taken to the critical power of 50 kW at 1841 hours. At this time all l "at critical" readings were taken, all readings (i.e., operational and radiation) were nonnal at this time. The senior reactor operator authorized power to be increased to 2 MW. The reactor 1 operator continued to raise power and at approximately 1849 hours the reactor was at 1.6 MW.
At this time, the reactor room CAM alerted and alarmed. The reactor was shutdown immediately. Health physics staff were immediately notified and began an investigation. the reactor , room ventilation system automatically went into the recirculation mode upon receiving the l alarm, thereby closing the stack damper. The reactor room stack CAM reading never indicated a , release of any kind (Atch 1). l As per the MNRC Technical Specifications 6.6.2(a and b), the operations supervisor and !- MNRC facility director were notified immediately. 1 Health physics personnel obtained a reactor room portable air sample (PAS), primary water samples, and pulled the reactor room CAM particulate filter. Gamma spectroscopy analysis revealed the presence of fission product daughters in all three samples. The stack CAM \ particulate filter was analyzed and no fission product daughters were found. Therefore, no inadvertent release of fission products to the environment resulted as a consequence of this failed k , fuel element. ,[ s o,
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A portable air sample in the room adjacent to the reactor room (Atch 2) was taken. The PAS revealed no abnormal radionuclides, in addition contamination surveys performed outside the reactor room were also negative. Direct radiation surveys performed outside the reactor room door indicated a dose rate of 0.25 mR/hr on contact with the door. The highest contact dose rate on the air recirculation system was 0.8 mR/hr. The condensation from the dehumidifier was analyzed and fission products were observed confirming a failed fuel element source. Entry into the reactor room was restricted. Periodic reactor room air samples, primary water samples and dehumidifier condensation water samples were taken and analyzed. 20 Aue 98, the facility director notified the following individuals and agencies in accordance with the MNRC Technical Specifications paragraph 6.6.2(a, b and c). 0620 Brigadier General Michael Wiedemer (licensee) 0653 Lt Col Catherine Zeringue (AFSC) 0705 Dr. Warren Eresian (USNRC Project Manager) 0754 USNRC Operations Center 1000 McClellan Nuclear Safety Committee Members A preliminary status report was sent to the NRC Operations Center at 1000 (Atch 3) The facility director called a meeting at 0930 to put together a plan to recover from the failed fuel event. The recovery planning was accomplished by the following McClellan Air Force Base organizations: 77 MedGrp/SGPB Patrick Pierce (Bioenvironmental) 77 MedGrp/SGPB Dale Gillespie (Bioenvironmental) SM-ALC/SEG John O'Brien (Safety Office) SM-ALC/flMR Charles Heidel (MNRC Operations Supervisor) SM-ALC/TIMH Jeffrey Ching (MNRC Health Physics Supervisor) SM-ALC/TI-l Wade Richards (MNRC Facility Director) The consensus of the recovery planning group was to follow the radiation work permit (Atch 4). to make an entry into the reactor room. The operations and health physics personnel developed the fuel inspection and entry procedures. The procedures were sent to AFSC, Kirtland AFB NM, for review and approval. AFSC approved both procedures. An entry was made into the reactor room to perform radiological surveys. Radiation levels were normal, no loose contamination was found, and Xe-133 was the primary airborne contaminate (Atch 5).
SEP 02 '98 08:16AM MNPC 916 643 1024 MCCLELLAN AFB P.2 21 Aug 98 Based on the reactor room radiation levels and air monitoring data (Atch 5), it was decided to vent the reactor room to the environment through the HEPA and charcoal filters. The reactor room was vented for the day. The major release was in the first hour of venting, when 4.1 mci of Xenon-133 was released. The reactor room stack ventilation system was left on over the weekend. 24 Aug 98 Continued monitoring the air in the reactor room. The radiation levels in the reactor room are normal. The reactor room ventilation system has been returned to its normal configuration (Atch 1). Reactor room ventilation to remove Xenon-133 continued from 24-25 Aug. A total of 149 mci of Xenon-133 was released (Atch 6). The reactor operations and health physics personnel prepared the reactor room and tank for visually inspecting all fuel elements in the reactor grid plate to find the leaking element. 25 Aun 98 l Reactor operations and health physics started the visual inspection of each fuel element in the grid plate (Atch 7). 26 Au_g 98 l ne visual inspection resulted in the following:
- a. Element 10730 in position E-9 could not be removed from the upper grid plate.
Element 10730 is a 20 wt % element and had been in the reactor since Mar 97. The element had been in the E 9 position since Jun 97 (Atch 8). The power generated in position E-9 is 24.6 kW.
- b. Element 5279 in position F-12 appeared to have a crack in the bottom graphite section of the element (Atch 9). Element 5279 was inspected on 6 Feb 97. There were no indications of any cladding problems at that time. Element 5279 was then loaded into position F 04. On 16 Jun 97 element 5279 was moved to position F-12 (Atch 10). The power generated in position F-04 and F-12 are 9.8 and 10.6 kW respectively.
- c. Element 5304 in position M-05 appeared to have a crack in the bottom fuel meat area.
This crack appeared to be approximately 4-5 inches long and showed signs of having released fission gasses (i.e., white patchy areas in the right side of crack) (Atch 11). Element 5304 was i inspected on 6 Feb 97. There were no indications of any cladding problems at that time. Element 5304 was then loaded into position K-06. On 16 Jun 97 element 5304 was moved to position M 05 (Atch 12). The power generated in position K-06 and M-05 are 11.34 kW and 8.2 kW respectively. ; l l l i L____ _ _ _ . . . _ _
, _ __ _________ y,c l
l 27-28 Aun 98 A complete visual inspection of all fuel elements in the core was accomplished. All elements were found to be satisfactory with no apparent damage. The elements around element 10730 have been removed. A fixturing device was made to remove element 10730 from the core areas. 31 Aun 98 The core central facility was removed to facilitate the removal of element 10730. The procedure to remove element 10730 (Atch 13) was followed. Conclusion as of 31 Aug 98. There have been no radiation exposures to the unrestricted area at or even close to regulatory limits. The only direct radiation exposure was to a radiation worker who entered the reactor room on 20 Aug 98to assess the status of the reactor room environment. He received approximately 1,4 mrem. The highest airbome radioactivity concentration in the unrestricted area was 8.4 E-09 uCi/ml of Xe-133. This release is approximately 60 times lower than the regulatory effluent limit of 5 E-07 uCi/ml. At the present time there appears to be three suspect fuel elements that may be leaking. These are elements 10730,5279 and 5304. As described in the report, we are only sure of a leak in element $304 as the bottom cladding is cracked sufHciently to expose the fbel. We are in the process of evaluating the other two
- elements. .
The mechanism that caused the element (s) to leak is uncertain. As described in the report, the 8.5 wt % elements were in the central region next to a control rod during the early load and testing to run at 2 MW. The reactor was pulsed to $1.60 with these elements in the central region. We can speculate that the elements were damaged at this time, but not enough to cause a fission product leak. The elements were moved to the outer ring and subsequent thermal cycling caused the element (s) to fall. All the r-laing 8.5 wt % elements have been inspected and all are visually satisfactory. Another line of speculation is that the two 8.5 wt % elements in the outer ring are both on the l corner hex positions. The old style fbel elements may not be sitting correctly in the grid plate. This could result in a hot spot or mechanical vibration damage. A preventative measure will be taken to eliminate this possibility in that old style elements will not be put in the comer hex positions. The other 8.5 wt % elements on the hex corner positions were checked and found to be satisfactory.
We will continue to investigate this problem and provide further information in the final (30 days) report. akt.- s 3'x
' DE J. R .IIAllDS, Ph.D.
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ATTACHMENT 3
DEPARTMENT OF THE AIR FORCE HEADQUARTERS SACRAMENTO AIR LOCISTICS CENTER dAFMC) McCLELLAN AIR FORCE BASE. CALIFORNIA 20 Aug 98 MEMORANDUM FOR NRC OPERATIONS CENTER FROM: SM-ALCm-1 5335 Price Ave. McClellan AFB CA 95652-2504
SUBJECT:
Preliminary Status Report #1 of Possible Failed Fuel Event at the MNRC
- 1. Reactor conditions prior to the anomaly and what occurred during the anomaly:
On 19 Aug 98, during run # 3071, the reactor was operating at 2 Mw. All of the radiation monitoring readings appeared normal. At 1829 hrs a watchdog scram occurred. The reactor was rebooted successfully arid all watchdog scram tests were satisfactorily performed prior to the start up of the reactor. The duty SRO granted permission to start the reactor, run number 3072. The reactor was taken critical at 1841 hrs, all radiation monitoring equipment readings were normal. Core excess was $3.93. The operator continued to raise power and at approximately 1849 hrs, the reactor was at 80% power. At this time the reactor room CAM Alerted, and Alarmed. The readings taken at this time were: At time of incident CAM Set Points Alert Alarm Particulate 2.0E5 cpm Particulate 2.8E3 cpm 5.1E3 cpm Noble Gas 1.0E4 cpm Noble Gas 4.9E4 cpm 9.8E4 cpm lodine 1.5E3 cpm lodine 3.1E3 cpm 6.3E3 cpm Health Physics staff was immediately notified and began the investigation. The reactor room ventilation system went into recirculation mode and the Stack cam readings did not change at the time of the incident. Operations Supervisor, Health Physics supervisor, and The facility director were all notified as soon as possible.
- 2. Actions to correct the anomaly:
The reactor room ventilation went into recirculation mode. The stack cam readings did not change at the time of the incident. The dehumidifier system tumed on and has continued to operate as designed. Health Physics personnel obtained a reactor room portable air sample (PAS), primary water sample, and pulled the reactor room CAM particulate filter. Gamma spectroscopy analysis revealed the presence of fission product daughters on all three samples. The stack CAM particulate filter was analyzed and no fission product daughters were l observed. A PAS in the equipment room outside the reactor room revealed no abnormal l radionuclides. Contamination surveys revealed no contamination outside of the reactor room or the recirc vent system. Radiation surveys were performed outside the reactor room and on the recirc vent system. The dose rate was 0.25 mR/hr on contact with the reactor room door and the highest contact dose rate on the recire vent system was 0.8 mR/hr. The condensate from the dehumidifier (part of the recirc vent system) was analyzed and fission product daughters were observed. (
.4 .
~ Entry into the reactor room has been restricted and the reactor room has been posted as a high airborne radioactivity area. Periodic reactor room air samples, primary water samples and dehumidifier condensate water samples are being obtained and analyzed.
The stack CAM filters and the reactor room CAM filters are being oeriodica!!y analyzed. l Contamination and radiation surveys are being performed on the recirc vent ducts. Stack CAM readings and filter analysis indicate that no release of fission products to the environment.
- 3. Corrective actions needed to prevent this anomaly from reoccurring in the future:
TBD I M WADE J. RIC 6 S, Ph.D. Director McClellan Nuclear Radiation Center cc: Dr. Warren Eresian, NRC NSC Members ____i___.__________ m__.__________._E_._...__ _-
McCLELLAN NUCLEAR SAFETY COMMITTEE (NSC) As of 20 Aug 98 i Name Office
- ColGerald Adair(Chairman) Tl
- Wade J. Richards TI-1 Jeffrey Ching TIMH Charles Heidel TIMR
- John O'Brien (Primary) SEG Gary Percival(Alternate) SEG
* ~ Robert Woodson (Primary) SGPB Patrick Pierce (Alternate) SGPB Warren Eresian NRC Lt Col Catherine Zeringue AFSC/SEWE Capt Edward Jakes AFSC/SEWE Kenneth Tallman AFMC/SES' Maj James Hicks AFMOA/SGOR Independent Members
- Donald Feltz
- Lt Col Kenneth Hodgdon
- Arthur Johnson
- Dr. Robert Nelson
- William Stephens -
- Voting Member L______________________-_______-- - - - -
E O ATTACHMENT 4 l-L________-_--_-- . . - - . - _ - . _- .b
APPENDIX A RADIAHON WORK PERMIT RWP NUMBER b IOI . PARTI Requested by: 5. 0 6 t* TI % -107 S oate: 1WM6 Name Organizaten , Phone Location of work to be perforrned: SEA (. Tot EW Desenption of work to be performed: Ml048dM ) b ME % MT PART11 Hnghest contact readings EXPECTED RADIOLOGICAL CONDITIONS: Highest readings in the general area Contamnatson: Airborne concentrabon Pre Job tn;,,v 9 HEALTH PHYSICS REQUIREMENTS pfOtective Clothing and Equipment Job Coverson fiaudL fant; S9dy; 3 Intermeent O Rubber gloves e I TyvekShoe Covers O Lab Coat O Continious 9 1 pair @ Rubber Boots e Tyvek Suit e ACNNEL6 O O O O Des.,i,etry; tigag; Restwratory; Mag; TLD e Safety glasses O SCBA Direct Reading e Tyvek Hood O O O R pirator O O O Face hield O kPR S la SPECIAL REQUIREMENTS
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, eo - - --- - - > - r.o RADIOLOGICAL DATA The following is a summary of the radiologicalinformation at the time of the problem on 19 Aug 98:
Radiation Contamination Airbome Radioactivity 0.25 mR/hr None detected outside Reactor Room CAM: Outside reactor room door reactor room Particulate 5.8E-07 uCi/mi lodine 1.6E-08 uCi/ml 11 mR/hr on reactor room RAM Noble gas 2.7E-04 uCi/ml 0.85 mR/hr on recirc vent Stacx CAM: Normal readings system (recirc system operating) 560 mR/hr on domin system Analysis of the reactor room CAM (continuous air monitor) particulate filter revealed the presence of Rb-88, Rb-89, and Cs-138 which are particulate daughter products of fission gases. A portable grab air sample from the reactor room revealed the presence of Rb-88 and Cs 138' A portable grab mir sample taken in the equipment room just outside of the reactor room revealed no fission product daughters. Analysis of the stack CAM particulate filter showed no fission product daughters Analysia results of primary water samples are shown on Table 1. Analysis of the recirculation ventilation system dehumifier condensate water revealed the presence of fission products. An entry was made into the reactor room on 20 Aug 98 to perform radiological surveys. The results are as follows: Radiation Contaminahort Airborne Radioactivity 0 9 mR/hrinside the None detected inside the Particulate: 1.99E-08 uCi/mi reactor room reactor room - (Rb-88) lodine: None detected Noble gas: 2.88E-05 uCl/ml (Xe-133, Xe-133m, and Xe-135) l Based on the derived air concentrations (DACs) for Xe-133, Xe-133m, and Xe-135, the individual making the entry into the reactor room received 1.4 mrem during the i hour spent inside the reactor room. On 21 Aug 98, the reactor room was vented out the stack to clear the reactor room of xenon. A total of approximately 153 mCl of Xe-133 was released up the stack on 21 Aug 98 and 24-25 Aug
. 98. Figures 1 and 2 are graphs of the two Xe-133 releases. The highest concentration of Xe-133 in the unrestnoted area was estimated to be 8.4E-09 uCi/ml (the 10 CFR 20 effluent limit for Xe-133 is SE-07 uCi/ml).
On 24 Aug 98, the reactor room was released for unrestricted entry after contamination surveys revealed no loose surface contamination. l 1
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