Text

2011 Annual Radiological Environmental Operating Report. Part 2 of 5
	ML12125A384
Person / Time
Site:	Diablo Canyon
Issue date:	04/16/2012
From:	Wright M B; Pacific Gas & Electric Co
To:	; Office of Nuclear Reactor Regulation
References
	DCL-12-041
	Download: ML12125A384 (60)
	v • d • e

0 S S 0 S S 0 0 0 S 0 0 0 0 0 0 0 0 0 ELaboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 41 of 58 FIGURE 6 GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS 2011 Gross Beta Performance Evaluation Results and % Bias 200.0 150.0 100.0--,--Gross Beta 50.0------- Lower Control-0.0 Limit.... Upper Control-50.0 Limit-100.0-150.0-200.0 November 2010 -November 2011 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 42 of 58 FIGURE 7 IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS 0 0 2011 Iodine-131 Performance Evaluation Results and % Bias 100.0 75.04 50.0 Iodine-131 25.0----Lower Control 0.0 Limit----Upper Control-25.0 Limit-50.0-75.0-100.0 January 2011 -Januaryl2012 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ILaboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 43 of 58 FIGURE 8 AMERICIUM-241 PERFORMANCE EVALUATION RESULTS AND % BIAS 0 0 0 0 0 0 0 0 0 0 2011 Americium-241 Performance Evaluation Results and % Bias 100.0-75.0 5n-241 25.0--i ----Lower Control j 0.0 Limit---.- Upper Control-25.0 -* Limit-50.0--75.0-100.0 November 2010 -November 2011 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 44 of 58 FIGURE 9 PLUTONIUM-238 PERFORMANCE EVALUATION RESULTS AND % BIAS 2011 Plutonium-238 Performance Evaluation Results and % Bias 100.0 -7 7 75.0-50.0-Plutonium-238 25.0 (A , -.-.- Lower Control@ 0.0 Limit---- Upper Control-25.0 .Limit-50.0-75.0_100.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 November 2010- November 2011 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 45 of 58 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TABLE 6 2011 CORRECTIVE ACTION REPORT

SUMMARY

CORRECTIVE ACTION ID#&PE FAILURE DISPOSITION CARR101122-526 MAPEP Series 23 Failure for Plutonium-238 by Alpha Spec During March of 2010, a high rate of recounting Plutonium analysis was identified.

An investigation concluded that this was due to peak tailing for the Pu-236 tracer utilized for Plutonium analysis (Pu-236 region of interest is in close proximity to the Pu-238 region of interest).

Pu-236 had recently replaced Pu-242 as the primary tracer in alpha spectroscopy Plutonium analysis, due to a worldwide shortage in available NIST traceable Pu-242. To reduce/eliminate the false positive rate, the standard Region of Interest (ROI) for Pu-238 analysis was updated. This update included moving the high energy end marker to 5508 kev. It was known at this time that this change may result in low results for Pu-238 if there were high levels of Pu-238 or there were any slight gain drifts in the electronics.

The analysts were reminded of the need for careful review of all spectra to ensure that all of the PEAK AREA was included within the ROI. If not, manual integration would need to be performed and documented.

For the MAPEP 23 results, it was apparent that both the primary and secondary data reviewers failed to identify that the full peak area was not included in the Pu-238 ROI for both the soil matrix and the water matrix.In should be noted that the peaks were properly adjusted and documented for all other matrices in the MAPEP 23 study. It was also noted that the graphical display of the spectrum on the data report can make it difficult to notice this problem.All data review analyst have had additional training on how to recognize exclusion of peak area during spectral data review.This included a careful review of the peak markers (and how to expand the view to help identify marker issues), and how to identify the properly using other parameters such as Peak Centroid location and FWHM (which may be zero when the higher energy peak is not included).

The Standard ROI high energy marker for Pu-238 will be adjusted on 01-Jan-2011 to decrease the probability of inadvertent oeak striDDina.

ULaboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 46 of 58 2011 ANNUAL QUALITY ASSURANCE REPORT Page 46 of 58 The laboratory reviewed all data processed for Plutonium-238 since 01-Jan-2010 to ensure all results were properly adjusted when necessary.

There were more than 8,000 results for Plutonium reported.

Out of these, approximately 700 had activity greater than detection limit (or >2 sigma TPU). Of these, 9 samples were identified that had suspect ROI integration due to analyst error (possible incomplete inclusion of all of the peak area). These samples were reprocessed with corrected ROIs. Three (3) results may be statistically different from the original reported.

The clients for these three samples were notified of the differences.

Initial responses from the clients were that the changes were insignificant and no additional revisions were needed at this time.CARR1 10107-533 MAPEP Series 23 Failures for Plutonium-238 and Plutonium-239/240 by Alpha Spec During March of 2010, a high rate of recounting Plutonium analysis was identified.

An investigation concluded that this was due to peak tailing for the Pu-236 tracer utilized for Plutonium analysis (Pu-236 region of interest is in close proximity to the Pu-238 region of interest).

Pu-236 had recently replaced Pu-242 as the primary tracer in alpha spectroscopy Plutonium analysis, due to a worldwide shortage in available NIST traceable Pu-242. To reduce/eliminate the false positive rate, the standard Region of Interest (ROI) for Pu-238 analysis was updated. This update included moving the high energy end marker to 5508 kev. It was known at this time that this change may result in low results for Pu-238 if there were high levels of Pu-238 and any slight gain drifts in the electronics.

The analysts were reminded of the need for careful review of all spectra to ensure that all of the PEAK AREA was included within the ROI. If not, manual integration would need to be performed and documented.

For the MAPEP 22 and MAPEP 23 results, both the primary and secondary data reviewers failed to identify that the full peak area was not included in the Pu-238 ROI for the soil matrix. It should also be noted that while the ROI may have contributed to the overall failure of MAPEP 23, when integrated correctly, the result still fell outside the acceptable range. GEL processed the MAPEP samples using a leaching procedure which is routine procedure used for processing typical environmental samples unless otherwise specified by the client based on sample matrix or site specific QAP.GEL's standard leaching procedure is a very strong acid digestion that will dissolve (leach) almost all elements that are"environmentally available" (i.e. resulting from the 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 S 0 0 S 0 0 S 0 S 0 0 MLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 47 of 58 environment in which the sample was collected).

By design, refractory compounds are not normally dissolved by this procedure, as they are not usually mobile in the environment.

Our investigation revealed that MAPEP-1 O-MaS23 contained both "environmentally available" and refractory Plutonium.

As explained during our discussions with RESL, this sample was prepared by RESL using a rigorous total dissolution process to digest the sample, therefore determining both the environmentally available and refractory isotopes as the true value for this sample.Therefore, the results reported by GEL using the less rigorous digestion for MAPEP 23 were biased low due to the inability of the process to breakdown the refractory compounds.

Upon discovery of the use of an inadequate digestion method, a comparison study was conducted by processing the samples concurrently using GEL's leaching procedure and a total dissolution digestion with use of Hydrofluoric Acid as described in Standard Operating Procedure (SOP) GL-RAD-A-015. Samples from MAPEP 21 and 23 were reanalyzed in duplicate for each digestion process.As expected, the hydrofluoric acid digested soil samples yielded results that were within the acceptable ranges of the studies. The leaching process yielded results similar to the original results reported for each sample in the MAPEP studies. Results for both the leached and total digested aliquots of MAPEP-09-MaS21 fell within the acceptance range because refractory Plutonium was not evident in this sample. However, results for the leached aliquot of MAPEP-1 0-MaS23 yield low biased results that fell outside the acceptance range. The totally digested aliquots of this sample yield results that all fell within the acceptance range, indicating that the refractory Plutonium was present. Refer to CARR1 10228-545 for documentation.

In the future, a total dissolution digestion will be used on all MAPEP soils. A requirement to use a total dissolution digestion procedure was also added to each soil test code. A test code is used during the log in process to identify special requirements.

CARR1 10209-542 The laboratory was unable to confirm the root cause of this failure due to the short half-life of the Fe-59. For this reason, Eckert & Ziegler Analytics (ANA2Q10) the sample was not re-analyzed.

The following steps were Failure for Iron-59 by Gamma Spec taken to prove that this failure was an isolated occurrence and that our overall process is within control.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 48 of 58 2011 ANNUAL QUALITY ASSURANCE REPORT Page 48 of 58* The instrument calibrations were reviewed for any anomalies that could have attributed to these failures.None was noted." The instrument logs were also reviewed and no anomalies were found.* The sample was also originally analyzed in triplicate and the other two results, while duplicating the reported result, fell within the acceptance range." The less abundant energy line for Fe-59 was also reviewed and its result fell within the acceptance range.* Laboratory Control Sample (LCS) data analyzed on the same detector used to analyze the sample were also reviewed and no anomalies were found.Verification that this was an isolated event was confirmed through the successful analysis the third (3d) and fourth (4 th)quarter 2010 performance evaluation samples.CARR1 10307-548 ERA RAD-84 Failure for Barium-1 33 by Gamma Spec After a review of the data, an apparent reason for this discrepancy could not be determined.

The following steps were taken to prove that this failure was an isolated occurrence and that our overall process is within control.The batch quality control samples were reviewed and found to be compliant.

A duplicate of this sample was also prepared and counted along side the original.

Its result was 54.3 pCi/L and falls well within the PT acceptance range.The instrument calibrations were reviewed for any anomalies that could have attributed to this failure. None was noted.Verification will be conducted through the next successful round of subsequent test samples.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CARR1 10603-600 MRAD 14 Failures for Cesium-134 by Gamma spec, Americium-241 by Alpha Spec, Iron-55 by Liquid Scintillation, Gross Alpha by GFPC, and Gross Beta by GFPC Cs-1 34: After a review of the data, an apparent reason for this discrepancy could not be determined.

A slight positive bias was noted in the LCS. However, its recovery fell well within the acceptance range. The following steps were taken to prove that this failure was an isolated occurrence and that our overall process is within control.The batch quality control samples were reviewed and found to be compliant.

A duplicate of this sample was also prepared and counted along side the original.

A 3.31% difference was observed between the two results.

0* Laboratories LLC 0 0 P.O. Box 30712, Charleston, SC 29417* 2011 ANNUAL QUALITY ASSURANCE REPORT Page 49 of 58* The instrument calibrations were reviewed for any anomalies* that could have attributed to this failure. None was noted.* Am-241: After a review of the data, an apparent reason for* this discrepancy could not be determined.

The original count of the samples indicated the potential for error due to tailing 0 from the large Am-241 peak. The sample was reanalyzed

using a shorter count time and the spectral resolution was dramatically improved.

Using a shorter count time caused the 0 uncertainty to be elevated on the second count. The following* steps were taken to prove that this failure was an isolated* occurrence and that our overall process is within control.* The batch quality control samples were reviewed and found to be compliant.

Duplicates of this sample were also prepared 0and analyzed along side the original.

Their results were 1050* pCi/kg and 1110 pCi/kg and falls well within the PT* acceptance range.* The instrument calibrations were reviewed for any anomalies* that could have attributed to this failure. None was noted.* Gross Alpha and Gross Beta: 0The root cause of the Gross Alpha and Gross Beta failures was determined to be human error. It appears that the filter* was counted upside down. After confirming the correct "up" 0side as indicated with purple dots, the filter was recounted in triplicate with the following results: Alpha 98.5, 103.7, 106.5* and Beta 74.4, 73.7, 73.3. All results fell within the* acceptance ranges; confirming the analyst's error and that the method is performing appropriately.

0* Fe-55: After review of the data, it was determined that the Fe-55 results were biased low due to the high amount of Fe-59* tracer used. Initially, it was suspected that the Fe-55 leachate 0 was heated to complete dryness during the preparation.

The samples were re-prepared as per the SOP and the results fell 0 within the acceptance range. However, while investigating a* Fe-55 failure in a sample of like matrix, the amount of tracer used in two separate studies were significantly different.

Results analyzed in October 2010 were compared to results* analyzed in March 2011. It was noted during the review that the amount of tracer used during the March analysis was* significantly higher than the amount of tracer used during the* October analysis. (October water sample passed with a 0 recovery of 102%)* After review of the data, it was determined that the Fe-55 results were biased low due to the high amount of Fe-59* tracer used. The method accounts for this by correcting the 0 0 0 0 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 50 of 58 2011 ANNUAL QUALITY ASSURANCE REPORT Page 50 of 58 Fe-55 region for the calculated cross talk (due to Fe-59).However, in this case, the Fe-59 tracer accounted for a large percent of the counts in the Fe-55 region. Even a small uncertainty in this correction can account for a significant bias in the results.When MRAD-14 water sample was reanalyzed, the activity of the tracer had decayed to a more reasonable amount. This reanalysis using this more appropriate amount of tracer indicates that it is a possibility that a low bias was created due to the elevated amount of tracer used for the analysis.

This is the reason why an acceptable result was obtained when the sample was re-prepared and analyzed.MRAD Water Fe-55: Verification of the changes to the procedures will be conducted during the next internal audit scheduled for February 2012.i CARR1 10705-612 MAPEP Series 24 Failures for Iron-55 by Liquid Scintillation and Gross Alpha by GFPC While there were no duplicate failures of any matrix from the last set of MAPEP samples, there are specific concerns regarding the failures for Fe-55 due to the number of values reported outside the Acceptance Range for this MAPEP sample set. Unfortunately, a new set of samples cannot be requested because there are no duplicate failures for any matrix. However, as part of this corrective action "old" PTs for those matrices were used to verify correction to our process improvements.

These findings were documented in CARR1 10809-618.

The root cause of the Gross Alpha and Gross Beta failures was determined to be human error. It appears that the filter was counted upside down. MAPEP filter instructions are that the "activity" side of the filter faces the label. This is referring to the MAPEP label. It is suspected that there was some confusion since the GEL label is placed on the opposite side of the filter casing. A recount of the sample showed a result of 0.444 Bq/Sample, thus confirming the analyst's error and that the method is performing appropriately.

Additional training was provided to all staff in this area. The opening of the filter will be witnessed and the word "up" will be written at the edge of the "activity" side (side facing MAPEP label).0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CARR1 10809-618 Water: After review of the data, it was determined that the Fe-55 results were biased low due to the high amount of Fe-MAPEP Series 24 Letter of Concern 59 tracer used.for Iron-55 by Liquid Scintillation 0 0 0 0 0 0 0 0 S 0 0 0 0 0 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 51 of 58 Soil: According to the recoveries achieved with the digestion procedure, it has been determined that the leach procedure was not aggressive enough in removing the Fe-55 for this sample.According to the recoveries achieved with the digestion procedure, it is possible that we have difficulty removing the Fe-55 from the soil using our current leaching procedure.

Our procedure will be updated and all analysts will be trained to perform a total dissolution for Fe-55 analysis.i CARR1 10812-621 ERA 071111 J Failure for Zinc-65 by Gamma Spec After a review of the data, an apparent reason for this discrepancy could not be determined.

However, it is suspected that the age of the PT sample and the half-life of the radionuclide are major contributing factors in this failure.The half-life of Zn-65 is 244.26 days. Since the reference date provided by the provider was March 23, 2009, 3.5 half lives had passed prior to receiving the sample into the laboratory.

The PT provider was contacted to discuss the age of the sample. They indicated that the sample is deemed acceptable for use as long as 5 half lives have not passed.Due to the samples age, it was counted for the maximum count time (1000 minutes).

A small number of counts and an elevated uncertainty were observed.The following steps were taken to prove that this failure was an isolated occurrence and that our overall process is within control.The batch quality control samples were reviewed and found to be compliant.

A duplicate of this sample was also prepared and counted along side the original.

Its result was 3290 pCi/Kg and fell outside the PT acceptance range as well.The instrument calibrations were reviewed for any anomalies that could have attributed to this failure. None was noted.In the future, if an older Quick Response PT sample is received, short-lived isotope results will not be reported when a small amount of counts for a given count time is observed.CARR1 10912-626 After a review of the data, an apparent reason for this discrepancy could not be determined.

However, it is Eckert & Ziegler Analytics (ANA2Q1 1) suspected that the half-life of the radionuclide and the Failure for Chromium-51 by Gamma resulting elevated uncertainty are major contributing factors in Spec this failure. The half-life of Cr-51 is 27.7 days. To try to combat issues with short-lived radionuclides, the 500 mL of Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 52 of 58 sample was counted for the maximum count time (1000 minutes).

This would allow us to obtain the best statistical data possible.

A small number of counts and an elevated uncertainty were observed.The following steps were taken to prove that this failure was an isolated occurrence and that our overall process is within control.The batch quality control samples were reviewed and found to be compliant.

A duplicate of this sample was also prepared and counted along side the original.

Its result also fell outside the PT acceptance range as well.The instrument calibrations were reviewed for any anomalies that could have attributed to this failure and none was noted.CARR1 10912-628 ERA RAD-86 Failure for Iodine- 131 by Gamma Spec After a review of the data, an apparent reason for this discrepancy could not be determined.

However, it is suspected that the age of the PT sample and the half-life of the radionuclide are major contributing factors in this failure.The half-life of 1-131 is 8 days. Since the reference date provided by the provider was July 5, 2011, 2.75 half lives had passed prior to sample analysis.

The policy is that a sample is deemed acceptable for reporting as long as 5 half lives have not passed. Due to the samples age, it was counted for the maximum count time (1000 minutes).

A small number of counts and an elevated uncertainty were observed.

Due to the short half, the sample was not reanalyzed upon notification of the failure. The following steps were taken to prove that this failure was an isolated occurrence and that our overall process is within control.The batch quality control samples were reviewed and found to be compliant.

A duplicate of this sample was also prepared and counted along side the original.

Its result was 31.3 pCi/L and fell outside the PT acceptance range as well.The instrument calibrations were reviewed for any anomalies that could have attributed to this failure. None was noted.In the future, data will thoroughly scrutinized and short-lived isotope results may not be reported when a small amount of counts for a given count time is observed.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CARR1 11129-644 Eckert & Ziegler Analytics Failure (ANA2Q1 1) for Strontium-90 by GFPC After reviewing the Sr-90 milk results, it is suspected that a discrepancy with the second separation may account for the low bias. The investigation found that the laboratory met all 0 0* ~I Laboratories LLC P.O. Box 30712, Charleston, SC 29417* 2011 ANNUAL QUALITY ASSURANCE REPORT Page 53 of 58*quality control criteria for instrument and process controls*D specified by each method. Additionally, all internal*t procedures and policies were performed as required.* For Analytics milk samples, the Sr-90 result is derived from Sr-89/90 procedure in order to report both Sr-89 and Sr-90 parameters.

The initial count of the sample represents a Total* Strontium value and includes both Sr-89 and Sr-90 in the sample. The sample filter is allowed to in-grow for a minimum of five days. After which it is returned to the lab for separation

of the Sr-90 portion as Y-90. The sample is counted a second time. Both counts are used to calculate the values of the two isotopes.

The lab reported an acceptable result for Sr-89 with 0105% of the known value, indicating a slight positive bias.* With the Sr-89 result being biased slightly, a low bias is expected for the Sr-90 result. However, the Sr-90 result was* lower than the acceptance range of 75-125%. The low result* for the Sr-90 portion indicates that an error may have occurred during the second separation of the analysis, thus*accounting for the bias. Unfortunately, due to the short half-*I life of Sr-89, our suspicions could not be confirmed because it is difficult to reanalyze the sample for this method in order to provide conclusive evidence.

However, we will continue to* monitor quality control sample recoveries to ensure that problems are not noted.*Additionally, historical Sr-90 milk results from first (I ") quarter 2006 to present were trended to verify that positive or 0 negative bias trends have not been encountered.

Biases were* not noted. This method has performed well for milk samples for the past few years.Another PT sample was analyzed during the fourth quarter.The sample was monitored for acceptability.

While hardcopy*reports have not been received yet, the PT provider supplied*the true values after the closing date of the study. The results 4fell within the acceptance range.0 CARR1 11129-645 After a review of the data, an apparent reason for this discrepancy could not be determined.

The following steps MRAD 15 Failure for Lead-214 by were taken to prove that this failure was an isolated Gamma Spec occurrence and that our overall process is within control.* The batch quality control samples were reviewed and found to be compliant.

The sample was also duplicated within the batch and those results compared very well. The duplicate*D samples were counted on different days and on different detectors.

S 0 0 0 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 54 of 58 The instrument calibrations were reviewed for any anomalies that could have attributed to this failure. None was noted.A soil PT samples from the MAPEP 25 study was analyzed during the same time frame as this sample. The MAPEP 25 results fell within the assigned acceptance range.The laboratory must assume an unidentified random error caused the elevated result since the results was just above the acceptance range. All quality control criteria were met for the batch. A soil sample from MAPEP 25 was also reported and rated acceptable during the same time frame. The first (1st) quarter sample will be monitored for acceptability.

CARR1 11219-653 MAPEP Series 25 Failures for Plutonium 239/240 by Alpha Spec, Uranium-238 by Alpha Spec, Gross Alpha by GFPC, and Gross Beta by GFPC Pu-239/240 and Uranium-238:

After a thorough investigation, it was determined that the root cause for the low bias in results in filter MAPEP-1 1-RdF25 is due to an incomplete digestion of the filter during the initial preparation step.This filter is dissolved/digested in the preparation area and then diluted to a known volume in a JAR geometry.

The dissolved/diluted sample is counted on an HpGe detector for quantification of the Gamma emitters.

The Gamma results, while meeting the acceptance criteria, indicated an approximate 25% low bias. The results of the other tests also showed the same bias. The broad low bias amongst the individual tests support the assumption of an incomplete digestion.

A second MAPEP-1 1 -RDF25 filter sample was analyzed for all results with a not acceptable or warning rating. All results fell within their acceptance ranges.Additional training on the handling of MAPEP PT samples was provided to all staff in this area. A second MAPEP-1 1-RDF25 filter sample was analyzed for all results with a not acceptable or warning rating. All results fell within their acceptance ranges.Gross Alpha: Refer to CARR1 20118-659 for details.Gross Beta: Upon investigation, it was determined that the MAPEP 25 Gross Beta failure was due to the laboratory's failure to blank-correct the results prior to reporting.

Per the MAPEP instructions, a blank filter is provided for those laboratories wanting to calibrate using the same sample media. The use of a blank filter to calibrate is not a GEL practice.

GEL processes blank filters as method blanks in the analytical 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 55 of 58 batch but does not use the results for blank corrections.

The blank filter associated with this study contained similar levels of activity.

Since the MAPEP instructions, the MAPEP handbook, or the ICPT BOA do not specify that blank correction is required, the results were reported without blank correction.

QSAS section D.4.1.a.3 also states that blank correction is prohibited unless permitted by the method or program. GEL typically does not blank correct Gross Beta results unless, specified by contract.When the results were corrected for the activity inherently found in the filter media (filter blank correction), all results were less than the 3-sigma uncertainty and met the acceptance criteria.

Results from the recalculations are provided for review.Additional training on the handling of MAPEP PT samples was provided to all staff in this area. The Excel spreadsheet used to process raw data was also revised to automatically blank correct the MAPEP data for Gross Beta filters.The following steps will be used to process future MAPEP Gross Alpha/Beta Filter data. The correction will be performed during data reduction using the revised spreadsheet to process the raw data." For initial data reduction, the appropriate spreadsheet will be selected by choosing PTQA as the client code.* Within that spreadsheet, the net count rate of the blank filter will be adjusted for the difference in detector efficiency." The adjusted filter blank count rate will be subtracted from the net count rate of the sample.Subsequent calculations will remain unchanged.

CARR120118-659 MAPEP-1 1-GrF24: I MAPEP Series 25 The root cause of the MAPEP 24 Gross Alpha failure was Letter of Concern for Gross Alpha by determined to be human error. The filter was counted upside GFPC down. MAPEP filter instructions are that the "activity" side of the filter faces the label. This is referring to the MAPEP label.There was some confusion because the GEL label is also placed on the opposite side of the filter casing. Client samples and samples from other PT programs were not affected because particulates are usually visible on the filters.

0~ Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 56 of 58 A recount of the sample showed a result of 0.444 Bq/Sample, thus confirming the analyst's error and verification that the method is performing appropriately.

The corrective action from this initial failure was to place the word "up" on the filter 0 (we initially were using a felt pen and placing a dot on the front but found that the pen leaked through to the back of the filter).0 Examples of the recounted MAPEP 24 filter are included for review. Also, pictures of the filter (containing a dot on the front side), PT samples from other vendors who use dyes in their process to help identify the front of the filter, along with a routine field sample are included.MAPEP-1 1 -GrF25: Upon investigation, it was determined that the MAPEP 25 Gross Alpha failure was due to the laboratory's failure to blank-correct the results prior to reporting.

Per the MAPEP instructions, a blank filter is provided for those laboratories wanting to calibrate using the same sample media. The use of a blank filter to calibrate is not a GEL practice.

GEL processes blank filters as method blanks in the analytical batch but does not use the results for blank corrections.

In this case, the reported result was less than MDA but slightly greater than the 3-sigma uncertainty.

The blank filter contained similar levels of activity.

Since the MAPEP instructions, the MAPEP handbook, or the ICPT BOA do not specify that blank correction is required, the results were reported without blank correction.

QSAS section D.4.1.a.3 also states that blank correction is prohibited unless permitted by the method or program. GEL typically does not blank correct Gross Alpha results unless specified by contract.When the results were corrected for the activity inherently found in the filter media (filter blank correction), all results were less than the 3-sigma uncertainty and met the acceptance criteria.

Results from the recalculations are provided for review.The following steps will be used to process future MAPEP Gross Alpha/Beta Filter data. The correction will be performed during data reduction using the revised spreadsheet to process the raw data.* For initial data reduction, the appropriate spreadsheet S will be selected by choosing PTQA as the client code. 5* Within that spreadsheet, the net count rate of the blank filter will be adjusted for the difference in 0 S S 0 0* I Laboratories LLC 0 P.O. Box 30712, Charleston, SC 29417* 2011 ANNUAL QUALITY ASSURANCE REPORT Page 57 of 58*detector efficiency.

The adjusted filter blank count rate will be subtracted from the net count rate of the sample.* 0 Subsequent calculations will remain unchanged.

0*MAPEP-1 1 -GrF24:*The opening of the filter for MAPEP 25 study was witnessed and the word "up" written at the edge of the "activity" side (side facing MAPEP label).* MAPEP- 11 -GrF25:*The impact of blank-correcting Gross Alpha/Beta direct count*filter results was evaluated using data from six (6) previous MAPEP studies. All corrected results were within the*applicable acceptance ranges. For future MAPEP direct count*GAB filters, the provided blank will be used to correct results for the activity in the filter media.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2011 ANNUAL QUALITY ASSURANCE REPORT Page 58 of 58 0 0 APPENDIX 1 2011 NUPIC AUDIT REPORT The Nuclear Procurement Issues Committee (NUPIC) audit was conducted on November 14, 2011 through November 18, 2011. This Duke Energy/NUPIC QA audit was performed for the activities and/or documentation/records associated with GEL Laboratories supplying general chemistry, radiochemistry and bioassay analytical services.

This audit found that the GEL Laboratories quality system is well documented and/or implemented, and is acceptable.

With the exception of the six (6) audit findings, all of the requirements of GEL Laboratories Quality 0 Assurance Plan audited were found to be satisfactorily implemented, and therefore, "Continued 0 approval of GEL Laboratories as an Appendix B supplier of general chemistry, radiochemistry and bioassay analytical services is recommended." All responses to the six findings have been adequately addressed by GEL. The Audit Report #22837-A for Supplier Number 5644 has been posted on the NUPIC website.0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 S 0 S S S S S 0 S S S S*- 8.0 DCPP LAND USE CENSUS S 0 S S S S S S S S S S S S S S S S S S S S S 0 S S 0 0 0 0 0 0 0 0 0 0 0 0 PageIntntinaly Bank0 0 0 0 0 0 0 0 PageIntntinaly Bank0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 S* 8.0 DCPP 2011 ANNUAL LAND USE CENSUS*Diablo Canyon Power Plant (DCPP) Radiological Environmental Monitoring Program (REMP)personnel conducted a land use census in the vicinity of DCPP for 2011. The land use census is based on Nuclear Regulatory Commission (NRC) Regulatory Guide 4.8, "Environmental Technical 0Specifications for Nuclear Power Plants" and 10 CFR 50 Appendix I section IV. B. 3.0 DCPP Program Directive CY2, "Radiological Monitoring and Controls Program" requires performance of a land use census.* DCPP IDAP RP 1 .ID 11, "Environmental Radiological Monitoring Procedure", requires identification of the nearest milk animal, nearest residence, and the nearest broadleaf producing garden greater than 50 square meters (500 square feet) in each of the landward meteorological sectors within a distance of 8 kilometers (5 miles) of the plant. The land use census is conducted at least once per 5year during the growing season (between Feb 15 and Dec 1) for the Diablo Canyon environs.0 The 2011 Land Use Census was conducted via a helicopter over-flight and landowner telephone interviews.

The helicopter over-flight was conducted on March 4th, 2011. The telephone interviews were conducted March 1 0 th through November 2 9 th, 2011. Eleven individual landowners or tenants 0were contacted.

0 Milk: No milk animals were identified within the first 8 kilometers (5 miles) of any sector.Residences:

The nearest residence, relative to all sectors, was a small trailer located in the NW sector about 1.93*kilometers (1.2 miles) from the plant. Ranch workers occupied this BLANCHARD residence approximately 1 month (per year) during cattle round-ups.

A total of sixteen residences were identified within the 8-kilometer (5-mile) radius of the plant, which were confirmed or appear to have been occupied in 2011. Six abandoned structures were also*identified.

The nearest residence in each sector is summarized in Table 1.Gardens: The land use census identified two household gardens greater than 50 square meters (500 square 5feet) that produced broadleaf vegetation.

The READ garden (REMP 3C 1) was approximately 1/4 acre*and located in the NNE sector at 7.08 kilometers (4.41 miles). The KOONZE garden (REMP 6C1)was approximately 500 square feet and located in the E sector at 7.24 kilometers (4.5 miles).*Sampling of the READ garden (REMP 3C1) began during fourth quarter 2010 (4Q10).MELLO managed a farm in the ESE sector along the site access road coastal plateau. The farm*started at approximately 4.8 km and extended to 7.2 km (3 to 4.5 miles) from the plant. This commercial farm produced no broadleaf vegetation.

The farm area was about 100 acres of land with*rotational planting.

Commercial crops consisted of about 100% cereal grass (oat hay) and straw grass. Less than 10 farm workers periodically occupied this area during the growing season.S S S S S S 0 Additional Land Use: Much of the area outside the plant site-boundary was used for rotational cattle grazing by five separate cattle operations.

For purposes of this census, the five cattle ranches were called BLANCHARD, SINSHEIMER, READ, ANDRE, and MELLO.0 BLANCHARD had about 100 cattle outside the plant site-boundary and utilized the NW, NNW, N, and NNE sectors. About 80 yearling cattle were sold under the "Old Creek Ranch" label at local farmer's markets in 2011.Additionally, BLANCHARD managed about 150 goats that were used for weed abatement in all landward sectors within the plant site-boundary.

During 2011, approximately 100 baby goats were born and taken to Santa Margarita California where they were grass fed for one year. After one year, the 100 yearling goats were sold under the "Old Creek Ranch" label at local farmer's markets in 2011.BLANCHARD also managed about 150 sheep outside the plant site-boundary in the NW and NNW sectors. These sheep were allowed to breed and the yearlings were sold under the "Old Creek Ranch" label at local farmer's markets in 2011.The BLANCHARD's consumed about 75 pounds of these various meats during 2011."Old Creek Ranch" labeled meats were sampled quarterly by REMP personnel.

SINSHEIMER had about 100 cattle outside the plant site-boundary in the NNE sector. These cattle were allowed to breed and about 90 calves were sold to mass market in 2011. SINSHEIMER did not slaughter any cattle for personal consumption in 2011.READ had about 110 adult cattle and 110 calves outside the plant site-boundary in the NNE sector.About 110 yearling cattle were sold under the "Old Creek Ranch" label at local farmer's markets in 2011.ANDRE had about 80 cattle outside the plant site-boundary in the ENE sector. About 80 calves were sold to mass market in 2011. ANDRE did not slaughter any cattle in 2011 for personal consumption.

MELLO managed about 800 cattle outside the plant site-boundary in the E, ESE, and SE sectors.Harris Ranch Beef Corporation owned these cattle and sold all of them to mass market in 2011.MELLO did not slaughter any cattle in 2011 for personal consumption.

Two landowners (JOHE and ANDRE) harvested wild game for personal consumption outside the plant site-boundary in the NNE, NE, and ENE sectors. This wild game consisted of approximately 2 deer and 4 wild pigs per landowner.

There was a California State Park Ranger Office in the NNW sector at 7.483 kilometers (4.65 miles)from the plant. Approximately 3 people occupied this office from 1000 to 1500 each day per week.0 There was a public campground (Islay Creek Campground) located in the NNW sector at Montana de Oro State Park at 7.387 kilometers (4.59 miles). This campground was near Spooner's Cove.Approximately 713,000 people visited Montana de Oro State Park via day use permit.Approximately 22,000 people spent the night at Islay Creek Campground.

0 0 0 0 0 S 0 0 There was public access to hiking trails at the north and south ends of the PG&E property in 2011.0The Point Buchon Trail was located at the north end of PG&E property and had about 20,000 0visitors.

The trail traversed about 3.5 miles of coastline from Coon Creek to Crowbar Canyon. The*trail was open for day hikes Thursday thru Monday from approximately 0800-1600.

Two to three people from California Land Management occupied the trail head booth during operating hours. This trail was originally opened to the public on July 13, 2007.0*The Pecho Coast Trail was located at the south end of PG&E property and had about 2,500 visitors.The trail was approximately 3.7 miles long and led to the Point San Luis Lighthouse near Avila Beach. Access was controlled (by permission only) and conducted by docents. This trail was just*slightly outside the 5 mile radius of the plant. Pecho Coast Trail hikes were only available on*Wednesdays (about 20 people) and Saturdays (about 40 people). 30-40 Lighthouse keepers occupied the Lighthouse grounds on Tuesdays, Thursdays, and Saturdays from 0800-1600.

The Lighthouse property was owned by the Harbor District.*Groundwater Protection Initiative (GPI) Review: There were no site construction activities or spills that warranted changes to GPI monitoring frequencies, monitoring locations, contract lab analytical capabilities, or detection thresholds in* 2011.*There were no changes in on-site or near site water usage that would result in potential use of site ground water used as drinking / irrigation water in 2011.Two new GPI monitoring wells (to the west of the site) were expected to be completed in December 0of 2011. These two new monitoring wells were down gradient of the site along the Pacific Ocean boundary.

The two new well station codes were GW1 and GW2.5Additional Onsite Information:

The following plant equipment was placed into the Old Steam Generator Storage Facility (OSGSF)for the duration of the plant operating license on the dates indicated below. It should be noted that the Old Steam Generator Storage Facility is located within the site boundary.0Unit One old steam generators (4 total) 2-14-09 Unit Two old steam generators (4 total)

3-2-08*Unit One old reactor head (1 total) 10-23-10 Unit Two old reactor head (1 total): 11-6-09*DCPP began loading of the on-site Independent Spent Fuel Storage Installation (ISFSI) pad on 6-23-*09. This process was ongoing.0 0 0 Table 1 summarizes the nearest residence location in each meteorological sector.*Figure 3 shows the location of the residences and gardens in the vicinity of DCPP.0 0 0 0 0 0 0 Table 1 Land Use Census 2011 Distance in Kilometers (and Miles) from the point located centrally between both Units Nearest Milk Animal, Residence, and Vegetable Garden 22% Degree (a) Nearest Nearest Residence Nearest Radial Sector Milk Animal Residence Azimuth Vegetable km (mi) Degree Garden km (mi)NW None 1.93 (1.2) 319.5 None NNW None 2.41 (1.5) (b) 331 None N None None -None NNE None 5.21 (3.2) 019.8 7.08 (4.4) (c)NE None 7.89 (4.9) 036 None ENE None 7.08 (4.4) 063.5 None E None 5.95 (3.7) 097.5 7.24 (4.5)(d)ESE None None -5.31 (3.3) )SE None None -None Table Notation: (a) Sectors not shown contain no land (other than islets not used for the purposes indicated in this table) beyond the site-boundary.(b) BLANCHARD residence is the full-time residence for critical receptor calculations.(c) The READ vegetable garden is located in the NNE sector and located at the 020 azimuth degree. There is also a full time residence at this location.(d) The KOONZE vegetable garden is located in the E sector and located at the 098 azimuth degree. There is also a full time residence at this location.< The MELLO garden is the commercial farm along the westward side of the site access road; however, it does not produce broadleaf vegetation.

This farm extends from 4.8 km to 7.2 km (3 to 4.5 miles) from the plant.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0*NW N 0 DCPE 0" 5 Mile Radius SE Grovr Beach #PacificGr-vila Beach#* UNITS 1lAND 2 DIABLO CANYON SITE 0R Gardens or Farm A Residences SSCA0 1 2 3 4 5 SCALE IN MILES Figure 3. Units 1 and 2 Diablo Canyon Power Plant Land Use Census.

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 PageIntetionlly lan 0 0 0 PageIntntinaly Bank0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S S S 0 0 0 0 S S 0 0 0 S* 9.0 DCPP WIND ROSE CHART-So S S S S S S 0 S S S S S 0 S S S S S S S o o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 PageIntetionlly lan 0 0 PageIntntinaly Bank0 0 0 0 o 0 0 o 0 0 o 0 0 0 o o S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S S Joint Frequency Distribution Wind Speed and Wind Direction Diablo Canyon Power Plant 10 Meter Level -2011 N 3 3.32 2-_6.81 2.86 3.49W E 1.18 1.26 5.73 2.44 S 0W1 3.5 6.9 11(5 Mie 24 P Wind Speed ( Miles Per Hour)Calms excluded.Rings drawn at 10% intervals.

Wind flow Is FROM the directions shown.656 observations were missing.PERCENT OCCURRENCE:

Wind Speed ( Miles Per Hour) PERCENT OCCURRENCE:

Wind Speed ( Miles Per Hour)LOWER BOUND OF CATEGORY LOWER BOUND OF CATEGORY D .R Qj L3 6.9 5 1 5 184 242 DI , .Q 3.5 § 92 115 18.4 24,2 N 0.75 1.38 0.84 0.31 0.04 0.00 S 1.53 0.72 0.19 0.01 0.00 0.00 NNE 1.01 1.20 0.46 0.17 0.02 0.00 SSW 0.77 0.36 0.10 0.04 0.00 0.00 NE 0.88 1.37 0.77 0.42 0.06 0.00 SW 0.72 0.37 0.09 0.01 0.00 0.00 ENE 0.64 0.79 0.74 0.32 0.02 0.00 WSW 0.79 0.52 0.12 0.00 0.00 0.00 E l.ll 0.84 0.15 0.06 0.04 0.00 W 0.72 1.05 0.41 0.16 0.00 0.00 ESE 1.58 1.43 0.77 1.11 0.23 0.00 WNW 1.11 2.94 3.94 4.73 2.31 0.48 SE 2.31 3.11 2.13 1.04 0.36 0.05 NW 1.11 3.42 7.34 10.50 7.91 4.53 SSE 1.62 2.62 0.99 0.23 0.20 0.07 NNW 0.62 1.91 2.39 1.49 0.35 0.05 TOTAL OBS = 8104 MISSING OBS = 656 CALM OBS ý 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page Intentionally Blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S*

10.0 REFERENCES

1. DCPP Interdepartmental Administrative Procedure (IDAP), RPI.ID11, "Environmental Radiological Monitoring Procedure.".2. NRC Branch Technical Position, Revision 1, November 1979.S 3. DCPP Program Directive, CY2, "Radiological Monitoring and Controls Program."* 4. NEI 07-07, "Industry Ground Water Protection

-Final Guidance Document", August 2007* 5. NRC Regulatory Issue Summary 2008-03, "Return/Re-use of Previously Discharged Radioactive

Effluents";

February 13, 2008 0 6. "Tritium Occurrence in Groundwater at Diablo Canyon Power Plant", by S.M. Stoller Corporation

7. "Groundwater Gradient Analysis", by Entrix Corporation, March 2010 o 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page Intentionally Blank0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 ,0 0 0 0* Appendix A O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

0 0 0 0 0-0 0 0 0 0 0 0 0 0 0Q 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page Intentionally Blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table A-1 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) Range(B) Mean IB) Range(B) Mean (B) Range(B) Occurrences Direct Radiation (mR/std quarter) 9S1, 0.6 mi, 167° I See Table 2.2 SF1, 4D1 ITLD Badges'C" (372) 3 mR/qtr 22.1 19.8- 23.3 (12/12) 16.4 18.8- 23.3 (348/348)1 14.3 19.9-18.2 (24/24) 0 IS4 IS1- IS8 5F1, 4D1 ISFS' TLDs(°) (96) 3 mR/qtr 76.3 72.1-78. (12/12) 43.3 21.1-78.8 (96/96) 14.3 9.9 18.2 (24/24) 0 Table Notation: (A) Sensitivity of TLD system B Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.(C) 93 TLD badges are distributed quarterly at 31 locations (29 indicator stations and 2 control stations).

Each quarter there are 3 badges per station.(D) 24 iSFSI TLD badges are distributed quarterly at 8 locations surrounding the ISFSI protected area within the site boundary.

Each quarter there are 3 badges per station.

Table A-2 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(s) RangV) Mean (B) Rang B) Mean (8) Rangd 6 Occurrences Airborne Iodine (364) 7D1, 6.6 mi, 118* 0S2, 151, 7D1, 851, 8S2, MT1 5F1, 10.2 mi, 79" (pCi/meter

3) 1-1311 0.07 16.94E-011 6.07E-2 to 1.68 (3/52) 6.IOE-02 1.66E-2 to 1.68 (20/312) 6.66E-01 7.64E-2 to 1.54 (3/52) 0 Air Particulates (364) 7D1, 6.6 mi, 1180 052, 1SI, 7D1, 8S1, 8S2, MT1 5F1, 10.2 mi, 790 Gross Beta 0.01 2.90E-2 2.43E-3 to 1.29E-1 (52/52) 2.74E-2I 2.62E -4to 1.29E-1 (312/312) 3.07E-2 2.60E-3 to 1.15E-1 (52/52) 0 Gamma Isotopic(C)

(28) 7D1, 6.6 mi, 118* 052, 151, 7D1, 8S1, 8S2, MT1 5F1, 10.2 mi, 79*Cs-1341 0.05 2.28E-3 2.38E-3 (1/4) 1.68E-3 1.01E-3 to 2.35E-3 (4/24) 1.23E-3 1.23E-3 ( 1/4) 0 CS-1371 0.06 12.28E-3 I 2.28E-3 ( 1/4) 1 2.04E-3 I1.48E-3 to 2.31E-3 (6/24) 1.60E-3 1.60E-3 (1/4)E 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.

1-131, Cs-134, and Cs-137 due to Fukushima Japan event.(C) These gamma isotopic samples are quarterly composite samples of all weekly particulate air sample filters. Approximately 13 particulate filters for each REMP location.Plant related radionuclides, not naturally occurring isotopes.

1-131, Cs-134, and Cs-137 due to Fukushima Japan event.0 0 0 0 0 0 0 0 0 0 0 00 00 040 0 0 400 00 00 Oe 0 0 Table A-2a Environmental Radiological Monitoring Program Summary -Supplemental Fukushima Air Monitoring Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(s) RangdB) Mean 1 8 1 Rangd 8) Mean(B) Range 8 1 Occurrences Airborne Iodine (29) 7D1, 6.6 mi, 118° OS2, 7D1, 8S1 SF1, 10.2 mi, 790 (pCi/meter

3) 1-131F 0.07 6 .6E-o1 6.OE-2 to 1.77 (4/8) 5.86E-OI 2.67E-2 to 1.77 (11/22) SS1E-01I 7.39E-2 to 1.65 (4/7) 0 Air Particulates (29) 7D1, 6.6 mi, 118° 0S2, 7D1, 8S1 5F1, 10.2 mi, 79°IGrossBeta 0.01 I8.93E-2 I .2-2 to 3.33-1 (8/8) 4.97E-2 1.11E-3 to 3.3E-1 (22/22) I.89E-2 I .23E-3to ,42E-1 (7/7) 0 Gamma Isotopic(c)

(29) 7D1, 6.6 mi, 1180 .OS2, 7D1, 8S1 SF1, 10.2 mi, 790 Be-7 1.08E-1 6.48E-2 to 1.52E-1 (4/8) 1.00E-1 1.33E-2 to 1.56E-1 ( 14/22) 9.71E-2 5.90E-2 to 1.45E-1 (5/7) 0 1-132 2.68E-2 2.68E-2 ( 1/8) 2.23E-2 1.78E-2 to 2.68E-2 (2/22) 3.OOE-2 3.OOE-2 (1/7) 0 Te-132 3.71E-2 3.45E-2 to 3.96E-2 (2/8) 3.73E-2' 2.49E-2 to S.00E-2 (4/22) S.OOE-2 5.OOE-2 (1/7) 0 Cs-134 0.05 7.00E-3 7.00E-3 ( 1/8) 1.20E-2 7.00E-3 to 1.56E-2 (4/22) 1.OOE-2 1.OOE-2 (2/7) 0 Cs-137 0.06 9.50E-3 4.OOE-3 to 1.45E-2 (3/8) 1.09E-2. 4.00E-3 to 1.59E-2 (8/22) 1.96E-2 1.22E-2 to 1.35E-2 (2/7) 0____________________

____________

______ _ -_- _ _ _ _ _ " .7 ITotal Strontium (20)I _ none detected (0/5) [ none detected (0/15) none detected (0/50 Table Notation: (A) Normal REMP LLDs may or may not apply due to changes in sampling protocols, increased sample flow rates, and increased sample volumes.(B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.

1-131, 1-132, Te-132, Cs-134, and Cs-137 due to Fukushima Japan event.(C) These gamma isotopic samples were analyzed for each weekly particulate sample filter (no composites).

AdditionalFukushima event sampling protocols were implemented.

Plant related radionuclides, not naturally occurring isotopes.

1-132, Te-132, Cs-134, and Cs-137 due to FukushimaiJapan event.

Table A-3 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)I Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(s) Range(B) Mean (B) Range(B) Mean (B) Range(8) Occurrences Surface Water DCM, 0.2 mi, 270" DCM, OUT 7C2, 4.7 mi, 124*pCi/Liter)

Gamma Isotopic (37)Mn-54 15 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Fe-59 30 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Co-58 15 none detected (0 / 12) none detected (0/ 24) none detected (0 / 13) 0 Co-60 15 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Zn-65 30 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Zr-95 15 none detected (0 / 12) none detected (0/24) none detected (0 / 13) 0 Nb-95 15 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 1-131 15 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Cs-134 15 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Cs-137 18 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Ba-La 140 15 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Additional Analysis Fe-55 (37) none detected (0/12) none detected (0/24) none detected (0/13) 0 Ni-63 (37) none detected (0 / 12) none detected (0 / 24) none detected (0/ 13) 0 Tritium H-3 (37) 400 none detected (0 / 12) none detected (0 / 24) none detected (0 / 13) 0 Total Strontium (37) 1 none detected (0/12) none detected (0/24) none detected (0/13) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.OOOOOOOOOOOOO1OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO0 00 0 0 0 0 0 Table A-4 Environmental Radiological Monitoring Program Summary -Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) Range(B) Mean 8 B) Range" 1) Mean (B) Range(B) Occurrences Drinking Water 5S2, 0.6 mi, 65" DW1, 5S2, WN2, 1A2 OEL, 10.2 mi, 79*pCi/Liter)

Gamma Isotopic (45)Mn-54 15 none detected (0/12) none detected (0/32) none detected (0/13) 0 Fe-59 30 none detected (0 / 12) I none detected (0 / 32) none detected (0 / 13) 0 Co-58 15 none detected (0/ 12) none detected (0/32) none detected (0/13) 0 Co-60 15 none detected (0 / 12) none detected (0 / 32) none detected (0 / 13) 0 Zn-65 30 none detected (0 / 12) none detected (0 / 32) none detected (0 / 13) 0 Zr-95 15 none detected (0 / 12) none detected (0 / 32) none detected (0/13 ) 0 Nb-95 15 none detected (0 / 12) none detected (0 / 32) none detected (0 / 13) 0 1-131 1 none detected (0 / 12) none detected (0 / 32) none detected (0 / 13) 0 Cs-134 15 none detected (0 / 12 ) -none detected (0 / 32) none detected (0 / 13) 0 Cs-137 18 none detected (0 / 12) none detected (0 / 32 ) none detected (0 / 13) 0 Ba-La 140 15 none detected (0 / 12) none detected (0 / 32) none detected (0/13 ) 0 Additional Analysis Fe-55 (45) none detected (0/12) none detected (0/32) none detected (0/13) 0 Ni-63 (45) none detected (0/12) none detected (0/32) none detected (0/13) 0 Tritium H-3 (45) 400 none detected (0/12) none detected (0/32) none detected (0/13) 0 Total Strontium ( 45) 1 none detected (0/12) ! none detected (0/32) none detected (0 /13) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.

Table A-S Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(e) Rang- d) Mean (B) Range(B) Mean (8) Range(B) Occurrences Mussels (pCi/kg) DCM, 0.2 mi, 270- DCM, PON, POS 7C2, 4.7 mi, 1240 Gamma Isotopic (13)Mn-54 none detected (0/4) none detected (0/9) none detected (0/4) 0 Fe-59 none detected (0 / 4) none detected (0 / 9) none detected (0 / 4) 0 Co-58 none detected (0 / 4) none detected (0 / 9) none detected (0 / 4) 0 Co-60 none detected (0 / 4) none detected (0 / 9) none detected (0 / 4) 0 Zn-65 none detected (0 / 4) none detected (0 / 9) none detected (0 / 4) 0 Nb-95 none detected (0 / 4) none detected (0 / 9) none detected (0 / 4) 0 1-131 60 none detected (0 / 4) none detected (0 / 9) 23.7 (1/4) 1 23.7 (1/4) 0 Cs-134 60 none detected (0 / 4) none detected (0 / 9) none detected ( 0 / 4 ) 0 Cs-137 80 none detected (0 / 4) none detected (0 / 9) none detected ( 0 / 4 ) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.Note: The 1-131 detected at 7C2 during 1Q11 was due to rain washout of Fukushima Japan event isotopes.

This location has a large watershed that discharges directly into the 7C2 location and therefore concentrated 1-131 within the mussel sample. ( See Fukushima event SLO County rain sampling data in Appendix D)

Table A-6 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) .Range B) Mean (B) Range(B) Mean (B) Range(s) Occurrences Fish (pCi/kg) POS, 0.4 mi, 1800 DCM, PON, POS, 2F1, 7D3 7C2, 4.7 mi, 1240 Gamma Isotopic ( 37)Mn-54 130 none detected (0 / 8) none detected (0 / 29) none detected (0 / 8) 0 Fe-59 260 none detected (0 / 8) none detected (0 / 29) none detected (0 / 8) 0 Co-58 130 none detected (0 / 8) none detected (0 / 29) none detected (0 / 8) 0 Co-60 130 none detected (0 / 8) none detected (0 / 29) none detected (0 / 8) 0 Zn-65 260 none detected (0 / 8) none detected (0 / 29) none detected (0 / 8) 0 Cs-134 130 none detected (0 / 8) 6.36 6.36 (1/29) none detected (0 / 8) 0 Cs-137 150 5.89 1 4.1 to 7.7( 2/8) 5.44 4.1 to 7.7 ( 3/29) 6.35 3.9 to 10.8(4/8) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.NOTE : Cs-134 and Cs-137 due to Fukushima Event.

Table A-7 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(Al Name, Distance, and Direction Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean 1 BI Rang 4 8) Mean (a) Range(B) Mean (B) Range")1 Occurrences Algae*(pCi/kg) DCM, 0.2 miles, 270- DCM, 0.2 miles, 2700 7C2, 4.7 miles, 1240 Gamma Isotopic (8)Mn-54 none detected (0/4) none detected (0/4) none detected (0/4) 0 Fe-59 none detected (0 / 4) none detected (0/4) none detected (0/4) 0 Co-58 none detected (0 / 4) none detected (0 / 4) none detected (0/4) 0 Co-60 none detected (0 / 4) none detected (0 / 4) none detected (0/4) 0 Zn-65 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 Nb-95 I none detected (0 / 4) none detected (0 / 4 ) none detected (0 / 4) 0 1-131 60 none detected (0/4) none detected (0/4) 627 627 (1/4) 0 Cs-134 60 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 Cs-137 80 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.Note: The 1-131 detected at 7C2 during 1Q11 was due to rain washout of Fukushima Japan event isotopes.

This location has a large watershed that discharges directly into the 7C2 location and therefore concentrated 1-131 within the algae sample. ( See Fukushima event SLO County rain sampling data in Appendix D)* These samples are supplemental samples.OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO0 Table A-8 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County. State)Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Analyses Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Performed (LLD) Mean(B) Rang V) Mean (B) Range(B) Mean (B) Range(B) Occurrences Kelp*(pCi/kg) DCM, 0.2 mi, 2700 DCM, PON, POS 7C2, 4.7 mi, 1240 Gamma Isotopic ( 16 )Mn-54 none detected (0 / 4) none detected (0 / 12) none detected (0/4) 0 Fe-59 none detected (0 / 4) none detected (0 / 12) none detected (0/4) 0 Co-58 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 Co-60 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 Zn-65 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 Nb-95 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 1-131 60 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 Cs-134 60 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 Cs-137 80 none detected (0 / 4) none detected (0 / 12) none detected (0 / 4) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.* These samples are supplemental samples.

Table A-9 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection"A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) Range(B) Mean(6) Range(B) Mean(BI Range(") Occurrences Vegetative Crops (pCi/kg) 6C1, 4.5 mi, 98- 5F2, 7C1, 3C1, 6C1 7G1, 16.8 mi, 115-Gamma Isotopic ( 51)1-1311 60 67.7 67.7 (1/4) 65.4 18.9 to 115 ( 6/39 38.1 38.1 (1/12 ) 0 Cs-1341 60 103.5 34.9 to 172 ( 2/4 ) 78.1 7.9 to 181 (10/39 ) 6.5 76.5 (1/12) 0 Cs-1371 80 98.9 43.7 to 154 ( 2/4 ) 69.3 8.1 to 173 (11/39) 65.8 65.8 (1/12) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.Note : 1-131, Cs-134, and Cs-137 concentrations were due to Fukushima Japan event.0 0 0 0 00 00 0 0 0 00 00 0 0 011 0 0 00 00 0 0 0 0 01 Table A-9a Environmental Radiological Monitoring Program Summary -Supplemental Fukushima Vegetation Sampling Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) I Analyses Performed (LLD) Mean(B) RangeRange Mean B I Mean (B) Range(B) ' Occurrences Vegetative Crops (pCi/kg) ATAS3, 20.4 mi, 210 ATASI, ,TAS2, ATAS3, Acorns 17G1, 16.8 mi, 115°Gamma Isotopic ( 22 )Be-7 1020 1 010 to 1020 (2/3) 605 203 to 1060 (8/10) none detected (0/12) 0 1-131 60 278 208 to 347 ( 2/3) 237 51.1 to 462 (6/10) 38.1 38.1 (1/12) 0 Te-132 6. 12 9 8.3 (1/3) 18.3 18.3 (1/10) none detected (0/12 ) 0 Cs-134 60 182 9.85 to 279 (3/3) 126 9.9 to 279 (9/10) 76.5 76.5 (1/12) 0 Cs-137 80 185 17.1 to 279 (3/3) 125 13 to 279 (9/10) 65.8 65.8 (1/12) 0 IGross Beta (24) 4860 3270-6050 (3/3) 4820 13270-6050 24/24) not analyzed 0 ITotal Strontium (6) 1 none detected ( 0/2) none detected ( 0/6) not analyzed 0 Table Notation: (A) Unless specified, all required LIDs were met in accordance with Table 2.3 B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.ATAS1 = Fescue grass, ATAS2 = Milk Thistle, ATAS3 = Miners Lettuce, & Acorns all sampled in Atascadero California which is 20.4 miles at 21 degrees north of DCPP.Note : 1-131, Te-132, Cs-134, and Cs-137 concentrations were due to Fukushima Japan event. Supplemental Fukushima sampling.This sampling conducted to prove that isotopes were originating from Fukushima Japan. All samples above should be considered control samples to DCPP site.

Table A-1O Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Meani ) Rang 8 Mean (B) Range"'1 Mean (B) Range(e) Occurrences Milk (pCi/Liter)

SF2, 12.6 mi, 600 Iodine ( 14)1-131 1 None None 2.8 0.9 to 6.8 (4/14 0 Gamma Isotopic ( 14)Cs-134 15 None None 5.9 I 3.6 to 8.8 (6/14) 0 Cs-137 18 None None 6.2 3.9 to 8.8 (7/14) 0 Ba-La 140 15 None None none detected (0/14) 0 ITotal Strontium ( 14) 1 None None none detected (0/14) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.Note: 1-131, Cs-134, and Cs-137 were due to Fukushima Japan event.0 0 0 00 00 0 0 0 00 0 0 00 0 0 0 00 0 0 0 00 0* 0 0 Table A-11 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Nam Number of Sampled Number of Detection(A)

Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Meani B) Rangý B) Mean (B) Range(e) Mean (B) Range(B) Occurrences Meat (pCi/kg)BSM, 1.5 mi, 3310 BCM, BGM, BSM, JDM HCM, 37 mi, 3280 Gamma Isotopic (21)1-1311 60 none detected ( 0/5) none detected ( 0/15 none detected ( 0/6) 0 Cs-1341 60 80.6 1 25.5 to 132 (3/5 25.6 9.2 to 132 ( 6/15 ) 26.4 7.5 to 45 ( 4/6 0 Cs-137) 80 60.1 3.3 to 126 (4/5) 27.8 3.3 to 126 ( 9/15 ) 36.5 17.8 to 50.4 ( 3/6) 0_ _Total Strontium ( 21 none detected (0/5-) none detected (0/15) none detected ( 0/6) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis, e.g. (10/12) means 10 samples out of 12 collected showed activity.Note: Cs-134 and Cs-137 were due to Fukushima Japan Event.

Table A-12 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA T 1 Indicator with Highest Annual Mean Name, Distance, and Direction Indicator Locations Control Locations Ocean Sediment ( pCi/kg dry)DCM, 0.2 mi, 2700 DCM, 0.2 mi, 270* 7C2, 4.7 mi, 1240 Gamma Isotopic ( 2 )Mn-54 none detected (0/1) none detected (0 / 1) none detected (0/1) 0 Fe-59 none detected (0 / 1) none detected (0 / 1) none detected (0 / 1) 0 Co-58 none detected (0 / 1) none detected (0 / 1) none detected (0 / 1) 0 Co-60 none detected (0 / 1) none detected (0 / 1) none detected (0 / 1) 0 Zn-65 none detected (0 / 1) none detected (0 / 1) none detected (0 / 1) 0 Cs-134 150 none detected (0 / 1) none detected (0 / 1) none detected (0 / 1) 0 Cs-137 180 none detected (0 / 1) none detected (0 / 1) none detected (0 / 1) 0 Fe-55 (2 ) none detected (0/1) none detected (0/1) none detected (0/1) 0 Ni-63 (2) none detected (0/1) none detected (0/1) none detected (0/1) 0 Total Strontium (2) 2,000 none detected (0/1) none detected (0/1) none detected (0/1) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO0OO Table A-13 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Analyses Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unitof Measure) Performed (LLD) Mean(B) Ranged 1 Mean (B) Range (B) Mean (B) Range!8) Occurrences Beach Sand (pCi/kg dry) AVA, 7.3 mi, 1090 AVA, MDO, PMO, CYA CBA, 28.5 mi, 3300 Gamma Isotopic ( 15)I cs-1341 150 I none detected (0/3) none detected (0/12) none detected (0/3) 0 Cs-1371 180 none detected (0/3) none detected (0/12) none detected (0 /'3 0 Fe-55 (15 ) none detected (0/3) none detected (0/12) none detected ( 0 / 3 0 Ni-63 ( 15) none detected (0 / 3) none detected (0 / 12) none detected ( 0 / 3) 0 Total Strontium ( 15) 2,000 none detected ( 0 / 3) none detected (0 / 12) none detected ( 0 / 3 ) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.

Table A-14 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Groundwater ( pCi/Liter

)8S3, 0.3 mi, 145-8S3, 0.3 mi, 1450 WW2, 0.6 mi, 700 Gamma Isotopic (8)Mn-54 15 none detected (0/4) none detected (0/4) none detected (0/4) 0 Fe-59 30 none detected (0/4) none detected (0/4) none detected (0/4) 0 Co-58 15 none detected (0/4) none detected (0/4) none detected (0/4) 0 Co-60 15 none detected (0/4) none detected (0/4) none detected (0/4) 0 Zn-65 30 none detected (0 / 4) none detected (0 / 4) none detected (0/4) 0 Zr-95 15 none detected (0/4) none detected (0/4) none detected (0/4) 0 Nb-95 15 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 1-131 15 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 Cs-134 15 none detected (0/4) none detected (0/4) none detected (0/4) 0 Cs-137 18 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 Ba-La 140 15 none detected (0/4) none detected (0/4) none detected (0/4) 0 Gross Beta (8) 44.8 2.9 to 9.2 (4/4) 4.8 2.9 to 9.2 (4/4) 11.7 49 to 24.6 (3/4) 0 Fe-55 ( 8 ) none detected (0 /4) none detected (0 /4) none detected (0 /4) 0 Ni-63 (8) none detected (0 /4) none detected (0 /4) none detected (0 /4) 0 Total Strontium ( 8) 1 none detected (0 / 4) none detected (0 / 4) none detected (0 / 4) 0 TritiumH-3 (8) 400 none detected ( 0 / 4 ) none detected (0 /4) none detected (0 /4) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.0 0 0 010 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9 0 0 0 Table A-15 Environmental Radiological Monitoring Program Summary Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(A)

Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) Range 8) Mean (a 8 Range(BI Mean (8) Range"' Occurrences Monitoring Wells DY1, 0.03 mi, 770 DY1, OWl, OW2 WW2, 0.6 mi, 700 pCi/Liter ) Gamma Isotopic ( 12 )Mn-54 15 none detected (0/4) none detected (0/8) none detected (0/4) 0 Fe-59 30 none detected (0/4) none detected (0/8) none detected (0/4) 0 Co-S8 15 none detected (0/4)) none detected (0/8) none detected (0/4) 0 Co-60 15 none detected (0 / 4) none detected (0 / 8) none detected (0 / 4) 0 Zn-65 30 none detected (0 / 4) none detected (0 / 8) none detected (0 / 4) 0 Zr-95 15 none detected (0 / 4) none detected (0 / 8) none detected (0 / 4) 0 Nb-95 15 none detected (0/4) none detected (0/8) none detected (0/4) 0 1-131 15 none detected (0/4) none detected (0/8) none detected (0/4) 0 Cs-134 15 none detected (0/4) none detected (0/8) none detected (0/4) 0 Cs-137 18 none detected (0/4) none detected (0/8) none detected (0/4). 0 Ba-La 140 15 none detected (0 / 4) none detected (0 / 8) none detected ( 0 / 4) 0 Gross Beta (12) 4 24.6 20.7 to 28.6 (4/4) 15.6 4.1 to 28.6 (8/8) 11.7 4.9 to 24.6 (3/4) 0 Fe-55 (12 ) none detected (0 / 4) none detected (0 / 8) none detected ( 0 / 4 ) 0 Ni-63 (12) none detected (0/4) none detected (0 / 8) none detected (0/4) 0 Total Strontium (12) 1 none detected (0/4) none detected (0 / 8) none detected (0 /4) 0 Tritium H-3 ( 17) 400 38,680 I 1.2E4 to 6.5E4 (5/5) 15,432 I 400 to 6.5E4 (13/13) none detected (0 / 4) 0 Table Notation: (A) Unless specified, all required LLDs were met in accordance with Table 2.3 (8) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.Note : Monitoring well tritium concentrations due to rain washout of an approved airborne discharge pathway from plant vents.

Table A-16 Environmental Radiological Monitoring Program Summary -Supplemental Fukushima Rain Sampling Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA (County, State)Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(A) RangeA I Mean (A) Range(A) Mean (A) Range (A) Occurrences Rain Sampling 552, 0.6 mi, 650 0S2, 1S1, 5S2 5F1, 10.2 mi, 790 pCi/Liter)

Gamma Isotopic (17 ) _Be-7 87.5 42 to 146 (4/5) 85.6 41.6 to 146 ( 9/11) 29.2 29.2 (1/6) 0 Mn-54 15 none detected (0/5) none detected (0/11) none detected (0/6) 0 Fe-59 30 none detected (0/5) none detected (0/11) none detected (0/6) 0 Co-58 15 none detected (0 / 5) none detected (0 / 11) none detected (0 / 6) 0 Co-60 15 none detected (0/5) none detected (0/11) none detected (0/6) 0 Zn-65 30 none detected (0 / 5) none detected (0 / 11) none detected (0 / 6) 0 Zr-95 15 none detected (0/5) none detected (_0_/_11_)

none detected (0/6) 0 Nb-9S 15 none detected (0/5) none detected (0/11) none detected (0/6) 0 1-131 15 237 71 to 522 ( 5/5) 222 69 to 522 ( 11/11) 142 14 to 277 (6/6) 0 1-132 21.9 19.9 to 23.2 ( 3/5) 16.7 7.2 to 23.2 (7/11) 11.8 6.8 to 20.4 (3/6 ) 0 Te-132 21.7 8.1 to 28.3 ( 4/5) 19.4 7.0 to 28.3 (9/11) 15.9 10.4 to 24.9 (3/6) 0 Cs-134 15 14.5 9.9 to 23.4 (4/5) 13.2 3.6 to 23.4 (9/11) 5.5 3.8 to 8.9 (5/6 ) 0 Cs-137 18 15.2 9.0 to 25.4(4/5) 12.6 2.4 to 25.4 (9/11) 4.5 2.2 to 7.2 (6/6) 0 Ba-La 140 is none detected ( 0 / 5) none detected (0 / 11) none detected (0 / 6) 0 Gross Alpha (16) 3.5 1.6 to 5.3 (2/5) 3.4 1.6to5.3 (3/11 I none detected (0 /5) 0 GrossBeta (16) 4 78 10.6to166 (S/5) 62.5 11to166 (11/11) 55.6 I 26to103 (5/5) 0 Total Strontium ( 16) 1 none detected ( 0 / 5) none detected (0 / 11) none detected (0 / 5) 0 Tritium H-3 (16) 400 none detected ( 0 / 5) none detected (0 / 11) none detected (0 / 5) 0 Table Notation: (A ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.Note: Rain sampling performed to prove environmental isotopes were due to Fukushima Japan event. Each sample was a separate rain event.All detected isotopes were from nuclear event at Fukushima Prefecture, Japan. See Appendix D.

Table A-17 Environmental Radiological Monitoring Program Summary -Supplemental Fukushima Sticky Pad Sampling Report Period: 1/1/11 -12/31/11 Name of Facility:

Diablo Canyon Power Plant Location of Facility:

San Luis Obispo, CA Indicator with Highest Annual Mean Name, Distance, and Direction All Indicator Locations All Control Locations Sticky Pad Sampling pCi / 3 sq feet) Gamma Isotopic ( 14)0S2, 0.5 mi, 320- 0S2, 0.5 mi, 320' 5F1, 10.2 mi, 790 Be-7 167 1 80 to 254 ( 2/7) 167 1 80 to 254 ( 2/7) 275 197 to 352 ( 2/7)Mn-54 none detected (0 / 7) none detected (0 / 7) none detected (0 / 7)Fe-59 none detected (0 / 7) none detected (0 / 7) none detected (0 / 7)Co-S8 none detected (0 / 7) none detected (0/7) none detected (0 / 7)Co-60 none detected (0 / 7) none detected (0 / 7) none detected (0/7)Zn-65 none detected (0 / 7) none detected (0 / 7) none detected (0 / 7)Zr-95 none detected (0 / 7) none detected (0 / 7) none detected (0 / 7)Nb-95 none detected (0/7) none detected (0/7) none detected (0/7)1-131 28.1 13.2 to 52.8 (3/7) 28.1 13.2 to 52.8 (3/7) 53.9 26 to 82 ( 2/7)1-132 none detected ( 0 / 7) none detected ( 0 / 7) none detected ( 0 / 7 )Te-132 23.1 23.1 (1/7) 23.1 23.1 (1/7) 25.6 25.6 (1/7)Cs-134 81.1 70 to 92 (2/7) 81.1 70 to 92 (2/7) 48 40 to 56 2/7 Cs-137 65.7 45 to 87 (2/7) 65.7 45 to 87 (2/7) 25.3 9.2 to 58 (7/7)Ba-La 140 none detected (0 / 7) none detected ( 0 / 7) none detected ( 0 / 7)Total Strontium ( 10) 0.24 (1/5) 0.24 0.24 (1/5) none detected (0/5)0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table Notation: (A ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.NOTE: Sticky Pad sampling performed to prove environmental isotopes were due to Fukushima Japan event. Each sticky pad surface area was 3 square feet.Each sticky pad was in the environment for 1 week (i.e. pulled weekly from 3-23-11 to 5-4-11). All detected isotopes were from nuclear event at Fukushima Prefecture, Japan.See Appendix D.

S 0 S S 0 S o S S S S o o 0 S o Page Intentionally Blank 5 0 S S S S S S S S S S S S S S S S S S S S S S S 0 0 S 0 0 S S S APPENDIX B 0DIRECT RADIATION RESULTS S 0 S 0 S 0 S S S 0 S S S S S S S S S S 0 S S S SO S S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 Page Intentionally Blank0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2011 DCPP Environmental TLD results per standard quarter 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 0 2011_QUARTER 0I11 ANNUAL st Qtr 2nd Qtr 3rd Qtr 4th Qtr Std 2x Std Station ID Avg : Std err Avg Std err Avg Std err I Avg nStd err Total Avg Dev Dev MTI 22.1 0.8 19.2 0.9 20.5 0.9 21.0 1.0 82.8 20.7 1.2 2.4 WNI 13.3 0.4 11.1 0.7 12.7 0.8 12.7 0.5 49.8 12.5 0.9 1.9 OSI 20.3 0.8 17.8 1.2 20.7 1.2 20.2 1.0 79.0 19.8 1.3 2.6 5Ss 22.0 0.9 20.3 1.2 22.2 1.5 23.1 0.8 87.6 21.9 1.2 2.3 6S1 14.4 0.4 12.2 0.6 13.8 0.9 13.0 0.9 53.4 13.4 1.0 1.9 8S1 17.3 0.8 14.8 0.9 17.6 0.9 17.6 0.7 67.3 16.8 1.4 2.7 8S2 21.7 0.5 18.6 0.8 20.9 1.1 21.5 1.0 82.7 20.7 1.4 2.8_________________

I-- --5S3 19.4 0.6 17.6 0.5 19.8 0.7 18.6 1.0 75.4 18.9 1.0 1.9 2D1 14.1 1.4 11.5 0.3 13.2 0.7 13.4 0.9 52.2 13.1 1.1 2.2 4D1 11.8 0.6 9.9 0.5 12.0 0.6 11.8 0.6 45.5 11.4 1.0 2.0 5F1 18.2 0.6 15.6 0.8 18.1 0.6 16.9 0.8 68.8 17.2 1.2 2.4 IAI 12.1 0.4 10.6 0.5 12.3 0.5 11.7 0.5 48.5 12.1 0.9 1.7 7D2 16.8 0.5 15.4 0.5 17.2 0.8 15.9 0.8 65.3 16.3 0.8 1.6 7G2 18.2 0.3 16.0 0.7 18.0 0.7 17.0 1.0 69.2 17.3 1.0 2.0 7CM 18.4 0.6 16.0 0.9 19.3 0.7 17.2 1.1 70.9 17.7 1.4 2.9 7F1 17.8 0.6 15.7 1.0 18.2 0.8 16.4 0.9 68.1 17.0 1.2 2.3 OB1 10.6 0.3 8.8 0.5 10.8 0.5 10.5 0.4 40.7 10.2 0.9 1.9 7D1 11.5 0.4 9.8 0.8 11.8 0.3 11.0 0.5 44.1 11.0 0.9 1.8 4C1 11.6 0.3 9.1 0.5 11.3 0.6 10.8 0.5 42.8 10.7 1.1 2.2 OS2 18.1 0.5 16.4 1.0 18.7 0.8 17.1 0.8 70.3 17.6 1.0 2.0 1S1 18.1 0.6 16.0 0.8 18.3 0.8 18.1 0.9 70.5 17.6 1.1 2.2 2S1 16.7 0.7 15.3 0.8 17.7 0.8 17.7 0.5 67.4 16.9 1.1 2.3 3S1 20.0 0.7 19.3 1.2 20.9 0.9 21.5 1.3 81.7 20.4 1.0 1.9 4SI 19.4 1.0 18.2 1.0 18.9 1.3 19.6 1.0 80.5 20.1 1.2 2.5 7S1 20.0 0.7 18.9 1.3 20.9 0.5 19.6 1.3 79.4 19.9 0.8 1.7 9Sl 22.7 1.0 19.8 1.4 23.3 1.5 22.5 0.8 88.3 22.1 1.6 3.1 ICI 13.9 0.5 11.9 0.7 13.1 0.7 12.8 0.8 51.7 12.9 0.8 1.7 5CI 16.0 0.5 13.4 0.9 17.1 0.7 15.4 0.9 61.9 15.5 1.6 3.1 3D1 12.7 0.7 11.7 0.8 13.5 0.3 12.7 0.7 50.6 12.7 0.7 1.5 6D1 14.2 0.7 13.6 0.5 15.0 0.7 14.3 0.8 57.1 14.3 0.6 1.1 5F3 17.7 0.9 16.1 0.7 16.8 0.8 18.0 1.0 68.6 17.2 0.9 1.7 IS-1 24.5 0.7 22.9 1.0 23.2 1.1 23.7 1.0 94.3 23.6 0.7 1.4 IS-2 25.9 0.9 24.3 0.4 25.3 0.6 24.1 0.4 99.6 24.9 0.8 1.7 IS-3 38.2 0.9 33.8 0.8 34.2 1-4 36.9 0.6 143.1 35.8 2.1 4.2 IS-4 78.4 3.5 75.8 2.2 72.1 2. 9 78.8 4.7 305.1 76.3 3.1 6.2 IS-5 78.1 2.5 69.8 1.5 69.0 4.7 74.4 5.3 291.3 72.8 4.2 8.5 IS-6 55.9 1.4 52.8 1.3 51.0 4.9 54.5 2.8 214.2 53.6 2.1 4.2 IS-7 38.6 1.8 35.8 2.3 38.5 2.5 38.0 1.6 150.9 37.7 1.3 2.6 IS-8 22.8 1.3 21.1 0.8 21.9 1.2 21.3 0.1 87.1 21.8 0.8 1.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page Intentionally Blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Name of Facility:

Diablo Canyon DCPP Direct Radiation Report Period: 1 / 1 / 2011 -12 / 3112011 0 0 0 0 0 0 0 0 0 0 0 S 0 Individual Environmental TLD Historical Ranges **Pre-2011 Pre-2011 Pre-2011 2011 Historical 2011 Historical 2011 Historical Results outside Station Low Qtr LOW Qtr Average High Qtr High Qtr Historical range?Code mrem mrem mrem mrem mrem Yes I No MTI 13.2 19.2 20.9 22.1 26.3 No WN1 8.8 11.1 12.7 13.3 18.4 No OS1 12.5 17.8 20.3 20.7 26.0 No 5S1 17.3 20.3 22.9 23.1 29.1 No 6S1 10.0 12.2 13.9 14.4 19.3 No 8S1 11.1 14.8 16.3 17.6 20.8 No 8S2 13.6 18.6 20.4 21.7 26.9 No 5S3 12.2 17.6 18.6 19.8 25.1 No 2D1 8.3 11.5 12.3 14.1 15.8 No 4D1 7.9 9.9 12.2 12.0 20.8 No 5F1 10.7 15.6 17.6 18.2 23.7 No IAI 8.2 10.6 12.1 12.3 17.8 No 7D2 12.0 15.4 16.6 17.2 27.7 No 7G2 13.7 16.0 17.3 18.2 27.7 No 7CM 14.4 16.0 17.9 19.3 23.1 No 7F1 13.6 15.7 16.7 18.2 23.6 No OBI 8.3 8.8 10.3 10.8 17.9 No 7D1 9.7 9.8 11.8 11.8 23.3 No 4C1 8.5 9.1 11.0 11.6 18.4 No OS2 14.3 16.4 17.1 18.7 22.1 No 1s' 13.5 16.0 16.8 18.3 21.7 No 2S1 13.3 15.3 16.9 17.7 23.3 No 3S1 16.4 19.3 20.4 21.5 26.2 No 4S1 15.0 18.2 18.9 19.6 26.4 No 7S 14.3 18.9 18.3 20.9 26.1 No 9S1 12.8 19.8 21.7 23.3 26.7 No ICI 10.3 11.9 13.3 13.9 19.4 No 5Cl 12.3 13.4 16.5 17.1 21.3 No 3D1 9.6 11.7 12.8 13.5 22.2 No 6D1 11.7 13.6 15.4 15.0 23.1 No 5F3 13.3 16.1 19.6 18.0 25.0 No IS-1 22.0 22.9 23.2 24.5 25.0 No IS-2 22.4 24.1 23.9 25.9 26.1 No IS-3 22.5 33.8 30.5 38.2 37.2

Yes IS-4 23.1 72.1 56.6 78.8 86.1 No IS-5 23.1 69.0 49.5 78.1 76.8

Yes IS-6 21.9 51.0 39.1 55.9 58.8 No IS-7 19.5 35.8 31.1 38.6 38.9 No IS-8 19.0 21.1 20.8 22.8 22.7 *Yes* Yes due to ISFSI loading** Exposure comparison data range from 1987 to 2010 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 S 0 0 0

DCL-12-041, 2011 Annual Radiological Environmental Operating Report. Part 2 of 5

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DCL-12-041, 2011 Annual Radiological Environmental Operating Report. Part 2 of 5

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