ML13249A030

Annual Report of the Wsu Facility for Operating Period July 1, 2012 Through June 30, 2013

ML13249A030
Person / Time
Site:	Washington State University
Issue date:	08/20/2013
From:	Wall D Washington State Univ
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML13249A030 (19)

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WASHINGTON STATE MUNIVERSITY Nuclear Radiation Center August 20, 2013 Document Control Desk U.S. Nuclear Regulatory Commission Washington DC, 20555 Re: Docket No. 50-27; Facility License R-76 In accordance with Technical Specifications for Facility License R-76 the attached Annual Report prepared by C. Corey Hines, Reactor Supervisor of the WSU Facility, is hereby submitted. The report covers the operating period July 1, 2012 through June 30, 2013.

Respectfully Submitted, Donald Wall, Ph.D.

Director Enclosure cc: C.C. Hines Ao0Zo P.O. Box641 300, Pullman, WA 99164-1 300 509-335-8641

• Fax: 509-335-4433

• www.wsu.edu/nrc

ANNUAL REPORT WASHINGTON STATE UNIVERSITY NUCLEAR RADIATION CENTER TRIGA REACTOR Facility License R-76 for the Reporting Period of July 1,2012 to June 30, 2013 Nuclear Radiation Center Washington State University Pullman, WA 99164-1300

201 3 Annual Report TABLE OF CONTENTS

1. Narrative Sum m ary of the Year's Operation ............................................................. 2

2. Energy and C um ulative O utput ................................................................................... 3

3. Emergency Shutdowns and Inadvertent Scrams ........................................................ 3

4. Majo r Maintenance ................................................................................................... .. 4

6. Radioactive Effluent D ischarges ............................................................................... 7

7. Personnel and Visitor Radiation Doses .................................................................... 9

8. Reactor Facility Radiation and Contamination Levels ............................................ 11

9. Environm ental Monitoring Program ........................................................................ 14 Washington State University Nuclear Radiation Center

201 3 Annual Report ANNUAL REPORT ON THE OPERATION OF THE WASHINGTON STATE UNIVERSITY NUCLEAR RADIATION CENTER TRIGA REACTOR Facility License R-76 for the Reporting Period of July 1, 2012 to June 30, 2013

1. Narrative Summary of the Year's Operation A. Operating Experience Core 35A has accumulated 4,966 MWH from beginning of life (BOL) through June 30, 2013. A total of 960 samples were irradiated, for a total of 12,537 user-hours. In addition, 59 pulses greater than $1 .00 of reactivity addition were performed during this reporting period. The quarterly operations summaries are shown in Table I located in Section 2.

B. Changes In Facility Design, Performance Characteristics, and Operating Procedures Related to Reactor Safety.

No changes were performed during the reporting period.

C. Results of Surveillance Tests and Requirements On March 1 5, 2013 the Reactor Supervisor discovered that several maintenance items required for the month of February were performed two days later than is required by Section 4 (Surveillance - Requirements) of the Technical Specifications (monthly not to exceed 45 days). The following maintenance items, while performed in the correct month and yielding satisfactory results, were not performed within the time period of 45 days.

The items that were not performed were the EGM Channel Test and the Ventilation System Operability Test, as required by the Technical Specifications 4.4 and Technical Specifications 4.5, respectively.

On March 26, 2013 the Reactor Safeguards Committee met and was informed of the lapsed time period. The committee asked for clarification on how the missed maintenance items were discussed with the WSUNRC licensed staff members, and what steps were taken to prevent recurrence. These changes were addressed by WSUNRC management and involved modifications to both the administration and performance of monthly maintenance, and they are as follows:

1. A two week maintenance check cycle has been adopted by the entire operating staff to remove the possibility of a maintenance item exceeding the 45 day timeline.

2. A two week check is signed off by a Senior Reactor Operator in the 0.9 Log, and the form has been modified to accommodate this check.

3. The Reactor Supervisor has reviewed the maintenance leadership responsibilities with the Senior Reactor Operating Staff.

4. The Reactor Supervisor has consulted the SRO In Charge of the Facility (the Facility Director) on all actions taken to address the problem and to prevent any future occurrences.

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201 3 Annual Report All other surveillance tests and requirements were performed and completed within the prescribed time period.

2. Energy and Cumulative Output The quarterly operations summaries are given in Table I. The cumulative energy output since criticality of the TRIGA core (1967) is 1436.8 Megawatt Days (MWD).

The mixed Standard Fuel and 30/20 LEU Fuel Core 35A installed in 2008 has accumulated a total of 206.9 MWD.

Table I Fiscal Year 2013 Summary of Reactor Operation Q3 2012 Q4 2012 Q1 2013 Q2 2013 TOTALS Hours of Operation 386 311 449 390 1535 Megawatt Hours 319 284 407 341 1352 No of Sample Irradiations 1 18 52 92 76 238 No. of Samples 121 265 370 204 960 No. of Iridium Cans Irradiated 36 33 42 33 144 User Hours 2 3166 2089 3796 3484 12535 No. of Pulses > $1.00 15 9 17 18 59 1

2 Number or samples and sample irradiations do not include iridium data.

User hours denotes the total user hours, including iridium.

3. Emergency Shutdowns and Inadvertent Scrams There were no emergency shutdowns that occurred during the reporting period. The dates and causes of the 20 inadvertent scrams are listed in Table 1l. No scrams were due to exceeding the Limiting Safety Systems Setting or Safety Limit.

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201 3 Annual Report Table II Inadvertent SCRAMS Date SCRAM 7/2/2012 No indication. SCRAM reset possible. Restart OK.

7/9/2012 Electrical short due to maintenance. No indication. Restart OK.

7/10/2012 Electrical short due to maintenance. No indication. Restart OK.

9/25/2012 Operator switched mode switch to test when attempting to rundown. Restart OK.

12/8/2012 Trainee switched to pulse mode with the Reactor at 10 W. Restart OK.

1/3/2013 Trainee switched to test mode with the Reactor at 1 MW. Restart OK.

1/9/201 3 Log-NHV failure probably due to overheat in Log-N channel. HV restored to normal. Restart OK.

1/22/2013 High rad count. SRO pulled sample out of reactor position D8.

Restart OK.

1/28/2013 Building power failure due to weather. Restart OK.

2/1/2013 Pulse high power SCRAM. NPP-1 000 malfunctioned during a pulse.

Restart OK.

2/4/2013 Pulse high power SCRAM. NPP-1 000 malfunctioned during pulse.

Restart OK.

2/8/2013 Power failure due to tripped relay. Restart OK.

3/6/201 3 Power flicker resulted in dropped control rods. Power restored to normal. No action necessary. Restart OK.

3/11/2013 Log-N high voltage failure due to thermally (induced) voltage fluctuation in the transformer. Restart OK.

3/1 8/2013 High power level on linear channel. Electrical only no actual power change as verified by Log-N, pulse and fuel temp. Restart OK.

4/12/2013 Trainee accidentally switched mode switch to pulse mode while at 1 MW. Restart OK.

5/1/2013 Trainee bumped key causing SCRAM. Restart OK.

5/8/2013 Log-N high voltage failure due to channel overheating. Restart OK.

6/5/2013 Log-N high voltage failure due to channel overheating. Restart OK.

6/11/2013 Log-N high voltage failure due to channel overheating. Restart OK.

4. Major Maintenance The below listed items were performed, although they are not part of routine preventative maintenance.

2/5/2013: NPP-1000 Pulse Channel-Screen Malfunction and High Power SCRAM:

During a pulse on 2/4/2012, after completing three successful pulses, the reactor Pulse High Power scrammed upon initiation of the pulse. The NPP-1 000 pulse channel screen was also malfunctioning and periodically would cut out entirely. The NPP-1 000 pulse channel cover was taken off and all wires were checked for continuity. The NPP-1 000 pulse channel cover was put back on. The J5 plug was taken apart to determine if any wires were loose. All wires were connected and current was detected flowing through the system. The ground and flux peak to meter wires (green and white wires respectively) going from the plug to the console were checked for secureness. The flux peak to meter wire (white wire) connection to the console was loose which would explain why we were able to pulse three times Washington State University Nuclear Radiation Center 4

201 3 Annual Report before a SCRAM. The flux peak to meter wire (white wire) was secured into the console and the NPP-1 000 pulse channel placed back into the console. A checkout was performed and the NPP-1 000 pulse channel operated normally. The reactor has since been pulsed and no further Pulse High Power scrams have occurred.

2/6/201 3: NPP-1000 Pulse Channel-Screen Malfunction: The screen on the NPP-1000 pulse channel went out again. When the cover for the channel was removed it was seen that the wire ribbon going to the screen has a single wire that goes to the side and it had been wiggled slightly loose. Ensuring the single wire was securely inserted fixed the screen problem and it has not been an issue since.

2/8/2 013: Cooling tower-Sprinklerhead assembly and distributortubes: On 2/1/2013, an SRO noticed the secondary water inlet and outlet temperatures were not showing a large difference. Upon inspection of the cooling tower it was found that the cooling tower distribution tubes were not rotating thus the cooling tower was not cooling off the secondary water efficiently. The cooling tower distribution tubes were removed from the sprinkler head assembly which was then examined.

Upon examination it was found that the top fixture on the sprinkler head assembly (where the distribution tubes tension wires were attached) had sheared off from the sprinkler head assembly. This is mostly likely due to the maintenance fix on 12/22/2010 where destroyed ball bearings were removed. The bearings were not replaced and the top fixture on the sprinkler head assembly may have been rotating at an angle. The entire sprinkler head assembly was removed from the cooling tower. A new sprinkler head assembly (RSD SH-09), tension wire hub hanger (RSD HH-03), distribution tubes (RSD ST-1 6), distribution tube caps (RSD STC-03), tension wires (RSD TW-02), and turn buckles for tension wires (RSD TBL-02) were ordered from Refrigeration Supplies Distributor (RSD) and arrived on 2/8/2013. Until the new sprinkler head assembly could be installed, regular reactor operations were halted.

The new sprinkler head assembly and distribution tubes are no longer threaded but held in place with set screws. After the new sprinkler head assembly and distribution tubes were installed, the cooling tower operated properly and regular reactor operations were resumed.

2/21/2013: Exhaust Gas Monitor-EGM Pump Control and Time Delay Switch: On 2/20/2013 when a SRO was trying to turn off the EGM it would not turn off. In the morning on 2/21/2013, the EGM had turned off. The head unit for pump control was powered down and racked out of the console. Upon investigation, it was determined that the switch had come loose from the button housing. A wire on the switch was also loose. The wire was re-soldered to the switch and the switch was connected back to the button housing.

The time delay switch was not lighting either. From listening to the EGM pump it was shown that the EGM and time delay switch were operating properly even though the switch was not indicating operation. The CAM and EGM time delay switches were switched and both switches indicated time delay. Upon investigation, it was found that the EGM time delay button housing is missing a post on the bottom of the housing. If both lights in the bottom of the time delay switch are burned out the time delay switch will not indicate as on. After replacing the bottom two lights on the EGM time delay switch, it worked in both the CAM and EGM button housings.

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201 3 Annual Report 4/29/2013" Console Power Supply-Replaced Transformer T- I: The console has been blowing fuse F9 intermittently due to a short between the 24VDC power supply and the neutral. In an effort to trace the short, it was discovered that transformer T-1 was faulty and was replaced with an equivalent model. The console power supply was not discussed in the Safety Analysis Report and the replacement was with a model with equivalent performance so this does not require a 50.59 review, but a 50.59 screening is on file in the A.5 binder.

5. Changes, Tests, and Experiments Performed Under 10 CFR 50.59 Criteria A total of five proposed changes to the reactor console were made during the 2012-2013 year. All of these proposals made were screened with the 10 CFR 50.59 requirements and found to screen out, thus allowing for the change to be made without further approval.

1) A proposed change to the reactor console was made. The proposal was for a channel identical to the current pulse power channel except for the added ability to log and report pulse shape information and was to be ordered from General Atomics and installed in the console. Both the current NPP-1 000 (analog only) and the new NPP-1 000 Data Capture would be swappable should the need arise.

On August 31, 2013 the proposed modification was reviewed for the additional reporting requirements of 10 CFR 50.59, and it was determined that the change could be made without prior US NRC approval.

2) A proposed modification to the facility as described in the SAR was made.

The proposal was to replace the current beam port doors with hardened, locked beam port covers. The proposed changes increased the safety of the beam port covers by using not only hardened doors but also the addition of locks.

On March 8, 201 3 the proposed modification was reviewed for the additional reporting requirements of 10 CFR 50.59, and it was determined that the change could be made without prior US NRC approval.

3) A proposed modification to the facility as described in the SAR was made.

The proposal was for the addition of the Treatment Room Door in Room 2 North. The proposed change increases safety by adding an additional barrier to the Treatment Room that was previously not included. The proposed change does not currently have a scram function but could be integrated in the future.

On March 8, 201 3 the proposed modification was reviewed for the additional reporting requirements of 10 CFR 50.59, and it was determined that the change could be made without prior US NRC approval.

4) A proposed change to the reactor console was made. The proposal was for the replacement of transformer T-1 in the console power supply with an equivalent model. The transformer converts 120 VAC to 24 VAC and supplies power to the scram chain, blade magnets, and many other systems.

The old transformer was found to have a chassis ground on one of the output due to excessive overheating in its history. The new transformer has Washington State University Nuclear Radiation Center 6

201 3 Annual Report exactly the same input and output capabilities as well as equivalent heat dissipation.

On May 6, 201 3 the proposed modification was reviewed for the additional reporting requirements of 10 CFR 50.59, and it was determined that the change could be made without prior US NRC approval.

5) A proposed -change to the reactor console was made. The proposal was for the replacement of diodes D5 and D7 and transistor Q1 in the PA-I 000 preamplifier on the Log-N Channel. The transistor was replaced with an exact replacement; however the diodes were obsolete and replaced with equivalent parts. The new diodes reproduce the performance of the original parts.

On June 17, 2013 the proposed modification was reviewed for the additional reporting requirements of 10 CFR 50.59, and it was determined that the change could be made without prior US NRC approval.

6. Radioactive Effluent Discharges A. Radioactive Liquid Releases The liquid effluent releases for the facility during the reporting period can be found in Table Ill.

Table III Monthly Liquid Waste Releases Month Volume (gallons)

July 2012 0 August 0 September 5,287 October 0 November 0 December 0 January 2013 0 February 0 March 0 April 0 May 0 June 0 Approximately 5,287 gallons of liquid waste was released from the storage tank. Prior to discharge, a sample of the liquid waste was analyzed using gamma spectroscopy, and no radioactivity above the limit of detection was found.

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201 3 Annual Report B. Radioactive Gaseous Release During the reporting period, no measurable quantity of gaseous or particulate material with a half-life greater that eight days was released. At no time did the argon-41 release exceed 20% of the effluent release limit. A total of 0.559 curies of argon-41 was released, with an average argon-41 concentration of 8.31 x 1091pCi/mL of air, before dilution. The release of 0.559 curies of argon-41 as stated in the 2013 Annual Report for Air Operating Permit 06-602, per COMPLY v1 .6, the facility is in compliance at level 4 with an effective dose equivalent of 5.0 x 10.4 mrem/yr. The monthly releases are summarized in Table IV.

Table IV Monthly Argon-41 Releases Conc. Before  % of Release  % of DAC Limit Month Dilution, BCi/mL Limit Before Before Dilution' Quantity pCi 3 Dilution July 2012 4.42 x 10.` 0.18 0.00059 2.51 x 10" August 5.90 x 10-1 0.24 0.00079 3.36 x 10' September 7.04 x 10. 0.28 0.00094 3.88 x 10' October 6.11 x 10` 0.24 0.00081 3.47 x 104 November 6.27 x 10" 0.25 0.00084 3.45 x 10' December 3.29 x 10" 0.13 0.00044 1.87 x 10' January 2013 5.32 x 10`9 0.21 0.00071 3.03 x 10' February 6.62 x 10. 0.26 0.00088 3.52 x 10' March 7.57 x 10.9 0.30 0.00101 4.31 x 104 April 8.66 x 10. 0.35 0.00115 4.77 x 10" May 1.78 x 10` 0.71 0.00237 1.10 x 10, June 9.70 x 10` 0.39 .0.00129 5.34 x 10' Based on 10 CFR 20 effluent release limit of 1.0 x 10sQuCi/mL for Ar-41 (Table 2, Col.1), and a dilution factor of 4.0 x 10.' (SAR 6.4.2) giving a before dilution limit of 2.5 x 106 uCi/mL. (20% of this limit is 5.0 x 10-7 uCi/mL).

2 Based on 10 CFR 20 DAC limit of 3.0 x 10.6 uCi/mL for Ar-41 (Table 1, Col. 3) and a dilution factor of 4.0 x 10-3 giving a before dilution DAC limit of 7.5 x 10.' uCi/mL.

Based on 4500 CFM effluent of ventilation system in AUTO mode of operation.

C. Radioactive Solid Waste Disposal During the reporting period, 3.6 mCi in 39 cubic feet of non-compacted solid waste was transferred to the WSU Radiation Safety Office for packaging and disposal.

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2013 Annual Report

7. Personnel and Visitor Radiation Doses The quarterly doses of the WSU Nuclear Radiation Center reactor staff and experimenters who routinely utilize the WSU Reactor are given in Table V. The maximum quarterly dose of a reactor staff member was 111 mrem, whole body.

A total of 1,568 individual persons visited the Nuclear Radiation Center during the reporting period, of which 425 entered a controlled access area (CAA). 1 All doses as determined by digital pocket dosimeter were less than or equal to 0.3 mrem. A total of 38 group tours, consisting of 323 individuals, visited the center during the reporting period. As determined by digital pocket dosimeter, all doses were less than or equal to 0.2 mrem.

A controlled access area is an area in the building where radioactive materials are used or stored and is a part of the licensed reactor facility.

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f 2013 Annual Report Table V Quarterly Reactor and Experimenter Staff Dose (in mrem)1 adeN. Q3 Q4 Q1 Q2 Badge No. 2012 2012 2013 2013 10452 M 21 11 8 10455 M 30 9 2 10458 M 33 3 3 10462 M 36 11 4 10012 M 5 M M 7528 M M 9 M 8025 8 50 21 73 10448 1 M 11 2 10460 M 33 10 10 7463 5 54 18 12 8141 4 62 26 24 7588 7 86 95 111 10466 M 21 4 2 10400 M M M M 10465 M 23 11 10 10453 M 32 7 5 10296 M M M M 10283 1 27 13 6 10451 M 22 15 20 10232 M 39 29 18 10301 5 36 34 24 10447 1 34 8 6 10042 8 44 34 20 10231 3 38 16 12 08152 1 M M M 10461 M 33 6 1 07748 M M 7 4 10459 M 17 12 13 10443 M 31 6 12 An 'M denotes that the dosimeter reading was less than or equal to the background radiation level for that quarter.

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201 3 Annual Report

8. Reactor Facility Radiation and Contamination Levels The method detection limit (MDL) for building survey samples collected for removable contamination determination by liquid scintillation assay is 2.70 x 1 08 pCi/cm2 . Routine building surveys showed average counts less than the MDL for most CAAs and all non-CAAs. Areas that registered removable contamination levels above the MDL were Room 201 B, 201 Sample Drop Tube, 201 Reactor Bridge South and North, the 201 Experimental Platform, 201 South and North floors, the Sample Drop Bench and Hood in Room 101, Hood 1 in Room 101, and Room 2 South floor.

All measurable counts were still well below Standard Operating Procedure limits for those areas.

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2013 Annual Report Table VI Average Removable Contamination (in pCi/cm2 )2 for Weekly Monitoring in CAAs and Non-CAAs' Contamination2 Location (pCi/cm )

201 B 4.20 x 10-8 201A M 201 RX BRIDGE STEPS M 210 SAMPLE DROP TUBE 2.65 x 10"7 201 RX BRIDGE - SOUTH 2.84 x 10"8 201 RX BRIDGE -NORTH 2.99 x 10-8 201 EXPERIMENTER PLATFORM 5.86 x 10-8 201 BENCHES M 201 FLOOR SOUTH 7.84 x 10.8 201 -C HEAT EXCHANGER FLOOR M 201 FLOOR NORTH 4.56 x 10-8 106 ION EXCHANGER PIT M 101 -A PURIFICATION PUMP PIT M 101 DOOR WAY M 101 SHIPMENT BENCH M 101 SAMPLE DROP HOOD #2 2.26 x 10.7 101 SAMPLE DROP BENCH 2.80 x 10-8 101 HOOD #1 2.61 x 10-7 116 FLOOR M 120 FLOOR M B21 PANORAMIC IRRADIATOR M B21 FLOOR M ROOM 2 SOUTH FLOOR M ROOM 2 THERMAL COLUMN 2.82 x 10.8 ROOM 2 THERMAL COLUMN FLOOR M ROOM 2 NORTH FLOOR M ROOM 2 WEST CAVE FLOOR M ROOM 2 EAST CAVE FLOOR M Bolded text indicates a non-CAA. Regular text indicates a CAA.

2 M indicates the value is below the MDL value of 2.70 x 10-8.

The routine area radiation surveys of the building in CAAs and non-CAAs are given in Table VII. The highest average dose rate for a single location in a CAA was 51.4 mrem/hr, which occurred in Room 2 East Cave. The lowest average dose rate for a single location in a CAA was 0.04 mrem/hr (a level considered background), which occurred in Rooms 201 A and B, on the benches in Room 201, and in the Heat Exchanger Room 201C. The average dose rate in the radiochemistry sample hoods Washington State University Nuclear Radiation Center 12

201 3 Annual Report (a non-CAA) was 11.02 mrem/hr. The highest onsite dose rate was 300 mrem/hr, which occurred in the Room 2 East Cave.

The East and West cave are a storage area designed to house radioactive sources such that they are shielded and are locked away from daily activities. This space is posted as a 'High Radiation Area' which permits radiation fields up to 500 rad/hr at 30 cm. Personnel do not typically work in this area and it is kept locked when not in use.

Table VII Average Radiation Dose Rates (in mrem/hr) for Weekly Monitoring in CAAs and Non-CAAs1 Average dose rate Location (mrem/hr)

Room 201B 0.11 Room 201A 0.20 Room 201 Bridge 3.90 Room 201 Benches 0.59 Room 201 South 1.07 Room 201 East 8.77 Room 201C Heat Exchanger 0.25 Room 201 Floor North 2.28 Room 106 Ion Exchanger Pit 3.12 Room 1 01 A Purification Pit 1.43 Sample Storage 3.61 Rom 101 Door Way 0.09 Room 101 Shipment Bench 0.17 Room 101 Sample Drop Hood 1.49 Room 101 Hood 1 11.02 Room 116 0.14 Room 120 0.04 Room B21 Panoramic Irradiator 0.04 Room 2 South 0.04 Room 2 Thermal Column 7.21 Room 2 North 0.37 Room 2 West Cave 1.16 Room 2 East Cave 51.4 Bolded text indicates a non-CAA. Regular text indicates a CAA.

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2013 Annual Report

9. Environmental Monitoring Program The environmental monitoring program uses thermoluminescent dosimeters (TLD's) placed at locations both on-site and off-site. The environmental monitoring program is used to determine the average background radiation levels through the use of offsite TLD locations. The offsite TLD locations are defined by Technical Specifications 1.0 and 5.1.1, and are TLDs 3, 7, 9, 15 through 35, and 39 through

44. The TLD's that are used to calculate the background do not have to meet the less than 20 % above background requirement. The average background radiation level is then compared to the nearest occupied dwelling to ensure it does not, on an annual basis, exceed the average offsite background radiation by more than 20 %.

Table VIII shows the quarterly dose rates for those TLD's located at offsite locations.

From Table VIII, the background radiation levels and the 20 % above background radiation levels can be seen in Table XI. This data will be used for comparison to the closest offsite area of extended occupancy.

Table IX shows the quarterly exposures for those TLD's located at onsite locations.

These locations are not required to be compared to background radiation levels.

The dose rate for the closest offsite points of extended occupancy can be found in Table X. In Chart I the closest offsite points of extend occupancy are compared to both the background radiation levels and 20 % above background radiation levels from Table Xl. Technical Specifications describing ALARA effluent releases in 3.5.2(3) specify annual radiation exposure due to reactor operation, at the closest offsite extended occupancy, shall not, on an annual basis, exceed the average offsite background radiation by more than 20 %. For the reporting period, the average background radiation dose rate for off-site locations was 0.346 mrem/day, while the highest average radiation dose rate at the closest extended occupancy area 600 meters away was 0.340 mrem/day. This result indicates that no exposure level above normal background radiation was found. While Chart III indicates that TLD 36 was higher than background radiation levels for Q3 2012, Q1 2013, and the average for the year, TLD 36 was still well below the 20 % above background radiation levels required by the Technical Specifications. This result shows that no dose levels exceeded Technical Specification requirements for an offsite area of extended occupancy.

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2013 Annual Report Table VIII Environmental Radiation Levels at Offsite Locations to the Nuclear Radiation Center"2 (Dose rate in mrem/day)

Location Q3 2012 Q4 2012 Qi 2013 Q2 2013 Average Fence E of NRC 0.364 0.326 0.295 0.304 0.322 Fence, N of Rad Waste Shed 0.409 0.358 0.364 0.337 0.367 Fence directly N Rad Waste Shed 0.432 0.463 0.602 0.783 0.570 S NRC, on parking lot fence 0.330 0.303 0.357 0.283 0.318 Fence S Roundtop Dr, 101hpole W of 0.409 0.347 0.364 0.348 0.367 pole CI14 Telephone pole C12 0.341 0.326 0.352 0.304 0.331 Telephone pole near golf course gate 0.352 0.337 0.341 0.293 0.331 E across fairway on pine tree 0.352 0.337 0.330 0.293 0.328 Maple tree #54 along driving range 0.352 0.326 0.318 0.293 0.322 NW to fence uphill from driving range 0.398 0.379 0.386 0.359 0.381 Follow fence E to fence corner 0.386 0.347 0.364 0.337 0.359 S to lone spruce tree near water hazard 0.364 0.347 0.31 8 0.315 0.336 Roundtop hill park, NW fence corner 0.330 0.337 0.318 0.304 0.322 Deciduous tree edge of 18th green 0.375 0.316 0.318 0.293 0.326 6ft pine tree, 3rd W down cart path from clubhouse 0.409 049 0.379 039 0.364 034 --

_ 3 0.384

.8 3rd to last tree after gap in same line of 0.330 0.316 0.341 0.315 0.326 trees SW to fence along path near 2nd to last 0.375 0.326 0.364 0.315 0.345 tee box at bottom hill Follow fence partway up hill after fence 0.375 0.358 0.352 0.304 0.347 turns S Follow fence,- 15th pole E after fence 0.352 0.337 0.307 0.359 0.339 turns W Follow fence about halfway between 0.352 0.337 0.341 0.315 0.336 last TLD and corner Largest bush S of NRC 0.341 0.368 0.364 0.315 0.347 2nd fence S NRC, W end at gate 0.341 0.337 0.295 0.304 0.319 S Fairway Rd, P' light post on right -- 0.327 0.360 0.330 0.339 S Fairway Rd, 2nd light post on right 0.398 0.316 0.337 0.308 0.340 Ellis Way and Hog Lane sign 0.318 0.327 0.349 0.297 0.323 Bottom of radio antenna hill, fence 0.364 0.316 0.349 0.363 0.348 next to shrub left of gate 3rd fence S of NRC, SE corner, cow 0.398 0.316 0.360 0.319 0.348 pasture Airport fence W end runway at gate 0.352 0.316 0.337 0.319 0.331 Fence/entry bar EJewett Observatory 0.330 0.296 0.302 0.308 0.309 Granite rock Terrall Mall, hole in back -- 3 -- 3 __3 0.264 0.264 Offsite defined by the Technical Specification 1.0 and 5.1.1.

Missing data indicates a TLD which was unavailable for sampling.

The "--" indicates a TLD which was unavailable for sampling Washington State University Nuclear Radiation Center 15

2013 Annual Report Table IX Environmental Radiation Levels at Onsite Locations to the Nuclear Radiation Center1 (Dose rate in mrem/day)

Location Q3 Q4 Q1 Q2 2012 2012 2013 2013 Average E lower loading dock 0.352 0.337 0.352 0.297 0.335 Pool room truck door fence S end 0.443 0.463 0.523 0.478 0.477 Pool room truck door fence N end 0.364 0.695 0.682 0.848 0.647 Ewall rad waste shed 0.330 0.347 0.443 0.511 0.408 N wall rad waste shed 0.443 0.400 0.523 0.641 0.502 Cooling tower fence, NE corner 0.364 0.400 0.568 1.250 0.646 Room 101 window 0.364 0.495 0.420 0.337 0.404 Railing next to upper liquid waste tank 0.409 0.389 0.364 0.370 0.383 Room 2 truck door fence 0.341 0.337 0.330 0.304 0.328 Transformer vault vent louvers 0.398 0.358 0.386 0.359 0.375 NRC main entrance, light fixture 0.420 0.388 0.395 0.407 0.403 NRC roof, pool room vent stack 0.330 0.286 0.430 0.319 ,0.341 NRC roof, guide wire E end of building 0.330 0.306 0.326 0.330 0.323 NRC roof, E pool room vent support leg 0.750 0.755 1.849 1.044 1.100 NRC roof, air conditioning support leg 0.795 0.847 1.163 0.846 0.913 NRC roof, W pool room vent support leg 0.352 0.367 0.360 0.319 0.350 1Onsite defined by the Technical Specification 1.0 and 5.1.1.

Table X Environmental Radiation Levels for the closest offsite point of extended occupancy (Dose rate in mrem/day)

Location Q3 Q4 Q1 Q2 2012 2012 2013 2013 Average Apt complex C, gas meter 0.375 0.316 .0.349 0.319 0.340 Apt complex B, gas meter 0.318 0.245 0.302 0.253 0.280 1st fence S apt complex A 0.330 0.286 --' 0.275 0.297 1 The "--" indicates a TLD which was unavailable for sampling Table Xl Background Environmental Radiation Levels (Dose rate in mrem/day)

Q3 Q4 Qi Q2 Average 2012 2012 2013 2013 Background Radiation Levels 0.365 0.339 0.350 0.330 0.346 20 % Above Background Radiation 0.438 0.406 0.420 0.396 0.415 Levels Washington State University Nuclear Radiation Center 16

F I . I i.

2013 Annual Report Chart I Environmental Radiation Levels for the Closest Offsite Point of Extended Occupancy as Compared to Background Radiation Levels and 20 % Above Background Radiation Levels' 0.500 0.450 --

0.400 --

0.350.... .

0.300

ý TLD 36

,E 0.250 - 1 TLD 37 t* , TLD 38 1 0.200 - Background 0.150 --- 20% Above Background 0.100 0.050 i ..

0.000 Q3 2012 Q4 2012 Q1 2013 Q2 2013 Quarter The missing bar in Q1 201 3 is due to the TLD being unavailable for sampling.

Washington State University Nuclear Radiation Center 17