Text

Corrections to the 2014 Annual Radioactive Effluent Release Report
	ML15365A581
Person / Time
Site:	Diablo Canyon
Issue date:	12/31/2015
From:	Welsch J; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	DCL-15-137
	Download: ML15365A581 (69)
	v • d • e

Pacific Gas and Electric Company James M. Welsch Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 December 31 , 2015 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 PG&E Letter DCL-15-137 U.S. Nuclear Regulatory Commission 10 CFR 50.36a(a)(2)

ATIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Corrections to the 2014 Annual Radioactive Effluent Release Report

References:

1. . PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report," dated April29, 2015. (Accession Number ML15133A141)

Dear Commissioners and Staff:

Pacific Gas and Electric Company (PG&E) submitted the 2014 Annual Radioactive Effluent Release Report (ARERR) in Reference 1 in accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3 of the Diablo Canyon Power Plant (DCPP)

Technicaf Specifications.

Subsequently, three categories of errors were identified that impact the information reported in the 2014 ARERR. These errors have been entered into the DCPP corrective action program. As part of the corrective actions, DCPP is submitting , which includes details on the errors and the corresponding corrections to the 2014 ARERR. Enclosure 2 provides a copy of the revised 2014 ARERR. No regulatory limits were exceeded as a result of the correction of these errors.

PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

If you have any questions, please contact Mr. Clint Gans at (805) 545-3419.

Sincerely,

~d~

James M. Welsch A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Document Control Desk PG&E Letter DCL-15-137 December 31 , 2015 Page2 bnsm/4540/50815806 Enclosures cc: Diablo Distribution cc/encl: Penny Borenstein, San Luis Obispo County Health Officer Marc L. Dapas, NRC Region IV Administrator Kenneth A. Harris Jr., Executive Officer, CCRWQCB Siva P. Lingam, NRR Project Manager Bernice E. Minga, INPO Gonzalo Perez, Branch Chief, California Department of Public Health John P. Reynoso, Acting NRC Senior Resident Inspector A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure 1 PG&E Letter DCL-15-137 Enclosure 1 Diablo Canyon Power Plant Details on Corrections to the 2014 Annual Radioactive Effluent Release Report

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR) 12/4/15, Revision 1 Prepared by C. Gans Part A- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

A) Two gaseous effluent post-release reports that were prepared in June 2014 for information only to support Licensing Basis Verification Project were not canceled prior to submittal of the 2014 Annual Radioactive Effluent Release Report (ARERR) in April of 2015. Therefore, the hypothetical radionuclides and dose associated with these information-only post-releases were mistakenly included in the ARERR. Canceling the two information-only post release reports resulted in significant reductions in the values for several gaseous release parameters from second quarter of 2014 (See tables below). Liquid release parameters were not affected.

2014 ARERR Report Category Gaseous Effluent Parameter 2014 ARERR Value Corrected Value 1 Table Number Type 1A Gaseous Fission and Activation Second Quarter 5.89E+O 1.82E-2 Effluents- Gases Total Release (Ci)

Summation of All Releases Second Quarter Average Release Rate for Period 7.49E-1 2.32 E-3

_fj..JCi/second)

Second Quarter Percent of Technical Specification 2.24E-3 2.17E-5 Limit(% of TS limit) 1C Annual Total Release (Ci) 8.14E+O 2.26E+O Annual Average Release Rate for Period 2.58E-1 7.17E-2 (l-ICi/sec, Total)

Annual Percent of Technical Specification Limit 1.21 E-3 6.62E-4

(%of TS limit, Total) 2A Gaseous Nuclides Released Argon-41 (Ci) , Batch Mode, Second Quarter 1.36E+O 1.82E-2 Effluents- (Fission Gases)

Ground Level Releases Xenon-133 (Ci), Batch Mode, Second Quarter 2.89E+O MDA*

Xenon-133m (Ci), Batch Mode, Second Quarter 2.21 E-2 MDA*

Xenon-135 (Ci), Batch Mode, Second Quarter 1.47E+O MDA*

Xenon-135m (Ci), Batch Mode, Second Quarter 4.01 E-2 MDA*

Xenon-138 (Ci), Batch Mode, Second Quarter 1.08E-1 MDA*

Total for Period (Ci), Batch Mode, Second Quarter 5.89E+O 1.82E-2

below Minimum Detectable Activity 1

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR Report Category Gaseous Effluent Parameter 2014 ARERR Value Corrected Value Table Number Type 8B Radiation Dose Noble Gas Second Quarter Dose (mrad) 2.95E-3 1.34E-5 Due to the Gamma Air Dose Release of (at Site Boundary)

Radioactive Gaseous Effluents (Unit 2)

. Annual Total Dose (mrad) 4.79E-3 1.86E-3*

Noble Gas Second Quarter Dose (mrad) 1.96E-3 4.74E-6 Beta Air Dose

. . :, (at Site Boundary)

:* :*. Annual Total Dose (mrad) 2.61 E-3 6.61 E-4*

.* Iodine, Particulate, Second Quarter Dose (mrem) 8.44E-4 7.00E-5 Tritium Critical Receptor (Highest Organ)

(at Nearest Residence-

NNW)

- . Annual Total Dose (mrem) 1.49E-3 7.17E-4 Iodine, Particulate, Second Quarter Dose (mrem) 5.06E-5 1.43E-5**

Tritium Critical Receptor (Highest Organ)

(at Nearest Vegetable Garden-NNE)

L__

.. Annual Total Dose (mrem) 9.54E-5 1.34E-4**

Result also affected by change to First Quarter 2014 values as described in (B) below.

- Result also affected by correction of nearest ingestion receptor location as described in (C) below.

2

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR Report Category Gaseous Effluent Type Parameter 2014 Corrected Table Number ARERR Value Value 10B Percent of Technical Noble Gas Second Quarter 5.89E-2 2.69E-4 Specification Limits Gamma Air Dose (% of TS limit) for Radioactive (at Site Boundary)

Gaseous Effluents I

I (Unit 2) I Annual Total Dose 4.79E-2 1.86E-2*

(% of TS limit)

Noble Gas Second Quarter Dose 1.96E-2 4.74E-5 Beta Air Dose (% of TS limit)

(at Site Boundary)

Annual Total Dose 1.31 E-2 3.31 E-3*

(% of TS limit)

... Iodine, Particulate, Tritium Second Quarter Dose 1.13E-2 9.34E-4 Critical Receptor (Highest (% of TS limit)

Organ)

(at Nearest Residence-NNW)

I Annual Total Dose 9.94E-3 4.78E-3 I

.. *. (% of TS limit)

Iodine, Particulate, Tritium Second Quarter Dose 6.75E-4 1.91 E-4**

Critical Receptor (Highest (% of TS limit)

Organ)

(at Nearest Vegetable Garden-NNE)

Annual Total Dose 6.36E-4 8.94E-4**

(%of TS limit)

Result also affected by change to First Quarter 2014 values as described in (B) below.

- Result also affected by correction of nearest ingestion receptor location as described in (C) below.

3

Enclosure 1 PG&E Letter DCL-15-137 Corrections t o PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR, Table 11 B, Radiation Dose Due to Release of Radioactive Gaseous Effluents-Second Quarter On-Site Dose to Members of the Public-Special Interest Groups Special Interest Group and Location Gaseous Effluent Type Parameter 2014 ARERR Value Corrected Value Police at Shooting Range (SE) Noble Gas External Dose to Whole Body (mrem) 1.06E-4 1.03E-6

... .*. . **.* *. ... Skin Dose (mrem) 1.74E-4 1.51 E-6 Tour Participants at Simulator Building (S) Noble Gas External Dose to Whole Body (mrem)' 1.40E-6 1.35E-8

- ** *. *: . Skin Dose (mrem) 2.28E-6 1.98E-8 Tour Participants at Bio Lab (SSE) Noble Gas External Dose to Whole Body (mrem) 2.09E-6 2.03E-8 Skin Dose (mrem) 3.42E-6 2.96E-8 Tour Participants at Overlook (E) Noble Gas External Dose to Whole Body (mrem) 9.71E-7 9.42E-9

.* ,*: * .* .' .. Skin Dose (mrem) 1.59E-6 1.38E-8 American Indians at Burial Ground (NW) Noble Gas External Dose to Whole Body (mrem) 3.85E-4 3.74E-6

.. *: : :: Skin Dose (mrem) 6.29E-4 5.46E-6 American Indians at Burial Ground (NNW) Noble Gas External Dose to Whole Body (mrem) 2.70E-4 2.62E-6

. ... . Skin Dose (mrem) 4.40E-4 3.82E-6 Ranch Hands Driving Cattle Around Site (NW) Noble Gas External Dose to Whole Body (mrem) 2.69E-6 2.61 E-8 Skin Dose (mrem) 4.39E-6 3.81 E-8 Ranch Hands Driving Cattle Around Site (NNW) Noble Gas External Dose to Whole Body (mrem) 1.03E-6 9.99E-9

*. Skin Dose (mrem) 1.68E-6 1.46E-8 Ranch Hands Driving Cattle Around Site (N) Noble Gas External Dose to Whole Body (mrem) 6.84E-7 6.64E-9

.*.*. Skin Dose (mrem) 1.12E-6 9.69E-9 Ranch Hands Driving Cattle Around Site (NNE)

Noble Gas External Dose to Whole Body (mrem)

Skin Dose (mrem) 2.68E-7 4.37E-7 2.60E-9 3.79E-9 Ranch Hands Driving Cattle Around Site (NE) Noble Gas External Dose to Whole Body (mrem) 1.36E-7 1.32E-9

.. :.' . . .* Skin Dose (mrem) 2.22E-7 1.93E-9 4

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR, Table 11 E, Radiation Dose Due to Release of Radioactive Gaseous Effluents-Annual Total On-Site Dose to Members of the Public-Special Interest Groups Special Interest Group and Location Gaseous Effluent Type Parameter 2014 ARERR Value Corrected Value Police at Shooting Range (SE) Noble Gas External Dose to Whole Body (mrem) 2.31 E-4 1.26E-4

Skin Dose (mrem) 3.56E-4 1.84E-4 Tour Participants at Simulator Building (S) Noble Gas External Dose to Whole Body (mrem) 3.04E-6 1.65E-6

. *, Skin Dose (mrem) 4.67E-6 2.41 E-6 Tour Participants at Bio Lab (SSE) Noble Gas External Dose to Whole Body (mrem) 4.55E-6 2.48E-6

..... > :,_ .* *. Skin Dose (mrem) 7.01 E-6 3.62E-6 Tour Participants at Overlook (E) Noble Gas External Dose to Whole Body (mrem) 2.11 E-6 1.15E-6

.*..* .** Skin Dose (mrem) 3.25E-6 1.68E-6 American Indians at Burial Ground (NW) Noble Gas External Dose to Whole Body (mrem) 8.38E-4 4.57E-4

. Skin Dose (mrem) 1.29E-3 6.67E-4 American Indians at Burial Ground (NNW) Noble Gas External Dose to Whole Body (mrem) 5.86E-4 3.20E-4

. . *::*.*. Skin Dose (mrem) 9.03E-4 4.67E-4 Ranch Hands Driving Cattle Around Site (NW) Noble Gas External Dose to Whole Body (mrem) 5.85E-6 3.19E-6

. * . Skin Dose (mrem) 9.01 E-6 4.65E-6 Ranch Hands Driving Cattle Around Site (NNW) Noble Gas External Dose to Whole Body (mrem) 2.24E-6 1.22E-6

" Skin Dose (mrem) 3.45E-6 1.78E-6 Ranch Hands Driving Cattle Around Site (N) Noble Gas External Dose to Whole Body (mrem) 1.49E-6 8.11E-7

.. *, Skin Dose (mrem) 2.29E-6 1.18E-6 Ranch Hands Driving Cattle Around Site (NNE) Noble Gas External Dose to Whole Body (mrem) 5.82E-7 3.17E-7 Skin Dose (mrem) 8.96E-7 4.63E-7 Ranch Hands Driving Cattle Around Site (NE) Noble Gas External Dose to Whole Body (mrem) 2.96E-7 1.61 E-7

. * * *. .** : Skin Dose (mrem) 4.56E-7 2.36E-7 5

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part B - Gaseous effluent post-release reports prepared prior to entry of respective atmospheric dispersion factors.

B) Eleven gaseous effluent post-release reports from January 2014 were prepared prior to entry of the respective atmospheric dispersion factors.

Because the dispersion factors for these releases were treated as zero, the associated doses were also calculated as zero.

Therefore, the dose reported for First Quarter and the respective Annual Total in the 2014 ARERR did not include the dose that was actually related to these releases.

Due to the very small quantities of activity that were associated with the affected releases, the corrected values are greater by an insignificant amount.

(See table below) 2014 Report Category Gaseous Effluent Type Parameter 2014 ARERR Corrected ARERR Value Value Table Number 8A Radiation Dose Due to the Release of Noble Gas Gamma Air Dose First Quarter Dose 1.57E-3 1.58E-3 Radioactive Gaseous Effluents (Unit 1) (at Site Boundary) (mrad)

Annual Total Dose 1.61 E-3 1.62E-3

... (mrad)

Noble Gas Beta Air Dose First Quarter Dose 5.56E-4 5.58E-4 (at Site Boundary) (mrad)

Annual Total Dose 5.71 E-4 5.73E-4

.* (mrad) 8B Radiation Dose Due to the Release of Noble Gas Gamma Air Dose First Quarter Dose 8.64E-6 1.29E-5 Radioactive Gaseous Effluents (Unit 2) (at Site Boundary) (mrad)

Annual Total Dose 4.79E-3 1.86E-3*

. . * . (mrad)

Noble Gas Beta Air Dose First Quarter Dose 3.05E-6 4.57E-6

.*. (at Site Boundary) (mrad)

Annual Total Dose 2.61E-3 6.61 E-4*

.* (mrad)

Iodine, Particulate, Tritium Critical Receptor First Quarter Dose 8.35E-6 2.34E-5**

(Highest Organ) (mrem)

- (at Nearest Vegetable Garden-NNE)

Annual Total Dose 9.54E-5 1.34E-4***

(mrem)

Result also affected by change to Second Quarter values described in (A) above.

- Result also affected by correction of nearest ingestion receptor location as described in (C) below.

- - Result also affected by changes described in both (A) above and (C) below.

6

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part B (continued)- Gaseous effluent post-release reports prepared prior to entry of respective atmospheric dispersion factors.

2014 Report Category Gaseous Effluent Type Parameter 2014 ARERR Corrected ARERR Value Value Table Number 10A Percent of Technical Specification Limits for Noble Gas Gamma Air Dose First Quarter Dose 3.15E-2 3.16E-2 Radioactive Gaseous Effluents (Unit 1) (at Site Boundary) (% of TS limit)

Annual Total Dose 1.61 E-2 1.62E-2

*. *.* .* . (%of TS limit)

Noble Gas Beta Air Dose First Quarter Dose 5.56E-3 5.58E-3

,: . . .. .* . (at Site Boundary) (%of TS limit)

Annual Total Dose 2.85E-3 2.86E-3

. .* .** *: (%of TS limit) 10B Percent of Technical Specification Limits for Noble Gas Gamma Air Dose First Quarter Dose 1.73E-4 2.59E-4 Radioactive Gaseous Effluents (Unit 2) (at Site Boundary) (% of TS limit)

Annual Total Dose 4.79E-2 1.86E-2*

.... < ... (% of TS limit)

Noble Gas Beta Air Dose First Quarter Dose 3.05E-5 4.57E-5

.. (at Site Boundary) (% of TS limit)

I Annual Total Dose 1.31 E-2 3.31 E-3*

(% of TS limit)

Result also affected by change to Second Quarter values described in (A) above.

7

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part C - Receptor location for dose from ingestion of vegetation was incorrectly entered.

C) The ingestion dose receptor location nearest to Diablo Canyon Power Plant (DCPP) in 2014 was found to have been incorrectly entered in the Effluents Management System (EMS). This resulted in omission of the internal dose caused by hypothetical ingestion of vegetation from what should have been inhalation-plus-ingestion dose that was reported for an adult member of the public residing 4.4 miles North-northeast (NNE) of DCPP. Entry of the correct location in the EMS and recalculation increased the calculated ingestion-plus-inhalation dose at the affected location during all of 2014 by a factor of approximately two (See table below). The updated results are all below the respective dose limit by a factor of approximately 10,000.

2014 Report Category Gaseous Effluent Type Parameter 2014 Corrected ARERR ARERR Value Table Value Number 8A Radiation Dose Due to the Release of Iodine, Particulate, Tritium Critical Receptor First Quarter Dose (mrem) 4.17E-5 1.12E-4 Radioactive Gaseous Effluents (Unit 1) (Highest Organ)

(at Nearest Vegetable Garden-NNE)

Second Quarter Dose 1.27E-5 3.56E-5

.** (mrem)

Third Quarter Dose 1.21 E-5 3.39E-5

... .* (mrem)

Fauth Quarter Dose 1.27E-5 3.54E-5 (mrem)

.* . Annual Total Dose (mrem) 7.92E-5 2.17E-4 8B Radiation Dose Due to the Release of Iodine, Particulate, Tritium Critical Receptor First Quarter Dose (mrem) 8.35E-6 2.34E-5*

Radioactive Gaseous Effluents (Unit 2) (Highest Organ)

(at Nearest Vegetable Garden-NNE)

Second Quarter Dose 5.06E-5 1.43E-5**

.. (mrem)

Third Quarter Dose 6.67E-6 1.86E-5

. . *. (mrem)

I Fauth Quarter Dose 2.98E-5 7.78E-5

.* .* (mrem)

Annual Total Dose (mrem) 9.54E-5 1.34E-4***

Result also affected by change to First Quarter 2014 values described in (B) above.

- Result also affected by change to Second Quarter values described in (A) above.

- - Result affected by changes described in both (A) and (B) above.

8

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part C (continued)- Receptor location for dose from ingestion of vegetation was incorrectly entered .

2014 Report Category Gaseous Effluent Type Parameter 2014 ARERR Corrected ARERR Value Value Table Number 10A Percent of Technical Specification Limits for Iodine, Particulate, Tritium Critical Receptor First Quarter Dose 5.56E-4 1.50E-3 Radioactive Gaseous Effluents (Unit 1) (Highest Organ) (mrem)

(at Nearest Vegetable Garden-NNE)

Second Quarter Dose 1.70E-4 4.74E-4

. (mrem)

Third Quarter Dose 1.62E-4 4.52E-4 (mrem)

Fouth Quarter Dose 1.69E-4 4.73E-4

.. -: .* (mrem)

Annual Total Dose 5.28E-4 1.45E-3

. . (mrem) 108 Percent of Technical Specification Limits for Iodine, Particulate, Tritium Critical Receptor First Quarter Dose 1.11 E-4 3.12E-4 Radioactive Gaseous Effluents (Unit 2) (Highest Organ) (mrem)

(at Nearest Vegetable Garden-NNE)

Second Quarter Dose 6.75E-4 1.91 E-4*

(mrem)

Third Quarter Dose 8.89E-5 2.49E-4

.* (mrem)

Fouth Quarter Dose 3.97E-4 1.04E-3 (mrem)

Annual Total Dose 6.36E-4 8.94E-4*

(mrem)

Result also affected by change to Second Quarter values described in (A) above.

9

Enclosure 2 PG&E Letter DCL-15-137 Enclosure 2 Diablo Canyon Power Plant Revised 2014 Annual Radioactive Effluent Release Report

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

DIABLO CANYON POWER PLANT 2014 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1 -December 31, 2014

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

DIABLO CANYON POWER PLANT Annual Radioactive Effluent Release Report January 1, 2014 through December 31, 2014 Table of Contents Introduction 1 I. Supplemental Information 2 II. Changes to Radwaste Management 9 Ill. Changes to the Offsite Dose Calculation Manual 10 IV. Land Use Census 11 V. Gaseous and Liquid Effluents 11 Table 1- Gaseous Effluents - Summation of All Releases 12 Table 2- Gaseous Effluents - Ground-Level Releases 15 Table 3- Gaseous Effluents- Lower Limits of Detection 19 Table 4- Liquid Effluents- Summation of All Releases 21 Table 5- Liquid Effluents- Nuclides Released 24 Table 6- Liquid Effluents - Lower Limit of Detection (LLD) 30 VI. Solid Waste Shipments 33 VII. Radiation Dose due to Gaseous and Liquid Effluents 35 Table 7- Radiation Dose Due to the Release of Radioactive Liquid 41 Effluents Table 8- Radiation Dose Due to the Release of Radioactive Gaseous 42 Effluents Table 9- Percent of Technical Specification Limits for Radioactive Liquid 45 Table 10- Percent of Technical Specification Limits for Radioactive 46 Gaseous Effluents Table11- On site Dose to Members of the Public 48 VIII. Meteorological Data 53

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

DIABLO CANYON POWER PLANT Annual Radioactive Effluent Release Report January 1, 2014 through December 31, 2014 Attachments (not included with 12/4/15 revision)

1. Diablo Canyon Power Plant Program Directive, CY2, "Radiological Monitoring and Controls Program," Revision 7

2. Diablo Canyon Power Plant Interdepartmental Administrative Procedure (IDAP),

CY2.1D1, "Radioactive Effluent Controls Program," Revision 12

3. IDAP RP1.1D11, "Environmental Radiological Monitoring Procedure," Revision 12

4. IDAP RP1.1D11, "Environmental Radiological Monitoring Procedure," Revision 12A

5. Diablo Canyon Power Plant Chemical Analysis Procedure, CAP A-8, "Off-Site Dose Calculations," Revision 36

6. Diablo Canyon Power Plant Departmental Administrative Procedure, RP2.DC2, "Radwaste Solidification Process Control Program," Revision 15

7. Diablo Canyon Power Plant Departmental Administrative Procedure, RP2.DC3, "Radwaste Dewatering Process Control Program," Revision 9

8. 2014 DCPP Land Use Census ii

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

DIABLO CANYON POWER PLANT 2014 Annual Radioactive Effluent Release Report Introduction The 2014 Annual Radioactive Effluent Release Report (ARERR) summarizes gaseous and liquid radiological effluent releases from Diablo Canyon Power Plant's (DCPP) Units 1 and 2. The report includes the dose due to release of radioactive liquid and gaseous effluents and summarizes solid radwaste shipments. The report contains information required by Units 1 and 2 Technical Specification (TS) 5.6.3 and is presented in the general format of Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Nuclear Power Plants," Appendix B, "Effluent and Waste Disposal Report." Procedure revisions that implement the Off-Site Dose Calculation Manual and one compact disk containing meteorological data are attached .

In all cases, the doses associated with plant effluent releases during the report period were much less than the respective TS limits.

The ARERR was revised on 12/4/15 to incorporate corrections to the gaseous effluent tables. The corrections were made necessary by three issues that have been recorded in the DCPP corrective action program. Each correction is detailed in Enclosure 1 that accompanies this revision.

1

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

I. Supplemental Information A. Regulatory Limits

1. Gaseous Effluents

a. . Noble Gas Dose Rate Limit The dose rate in areas at or beyond the site boundary due to radioactive noble gases released in gaseous effluents is limited to less than or equal to 500 millirem (mR) per year to the total body and less than or equal to 3000 mR per year to the skin. (Attachment 6 of CY2 .1D1, "Radioactive Effluent Controls Program" [RECP])

b. Particulate and Iodine Dose Rate Limit The dose rate in areas at or beyond the site boundary due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents, is limited to less than or equal to 1500 mR per year to any organ. (Attachment 6 of RECP )

c. Noble Gas Dose Limit The air dose due to noble gases released in gaseous effluents from each reactor unit to areas at or beyond the site boundary is limited to the following:

Radiation Calendar Quarter Limit Calendar Year Limit Type Attachment 7 of RECP Attachment 7 of RECP Gamma 5 millirad 10 millirad Beta 10 millirad 20 millirad

d. Particulate and Iodine Dose Limit The dose to an individual from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from each reactor unit to areas at or beyond the site boundary is limited to less than or equal to 7.5 mR to any organ in any calendar quarter and less than or equal to 15 mR to any organ during a calendar year. (Attachment 8 of RECP) 2

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

2. Liquid Effluents

a. Concentration With the exception of dissolved or entrained noble gases, the concentration of radioactive material released from the site in liquid form is limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the total specific activity o-is limited to 2 X 1 4 microcuries/milliliter (J.-LCi/ml).

(Attachment 3 of RECP)

b. Dose The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from each reactor unit to areas at or beyond the site boundary is limited to the following:

Dose Type Calendar Quarter Limit Calendar Year Limit Attachment 4 of RECP Attachment 4 of RECP Total Body 1.5 millirem 3 millirem Any Organ 5 millirem 10 millirem B. Maximum Permissible Concentrations

1. Gaseous Effluents IV1aximum permissible concentrations are not used for determining allowable release rates for gaseous effluents at DCPP.

2. Liquid Effluents With the exception of dissolved or entrained noble gases, the concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides are used for determining the allowable release concentration at the point of discharge from the site for liquid effluents. For dissolved or entrained noble gases, the allowable release concentration for liquid effluents at the point of discharge is o-limited to 2 X 1 4 J.-LCilml total activity.

3

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

C. Measurements and Approximations of Total Radioactivity

1. Gaseous Effluents

a.

Fission and Activation Gases A pair of off-line monitors equipped with beta scintillator detectors measure the gaseous radioactivity released from the plant vent. The readings from these monitors are correlated to the isotopic concentrations determined in grab samples that are analyzed in the laboratory using a germanium detector.

For plant vent noble gas releases, grab sample results are used to quantify releases. The individual batch release data are used to quantify the radioactivity discharged from the gas decay tanks and containment.

A noble gas grab sample is obtained from the plant vent and analyzed at least weekly. The isotopic mixture is assumed to remain constant between grab sample analyses.

Containment purges, gas decay tank releases, and air ejector discharges are released via the plant vent.

The gaseous radioactivity released from the steam generator blowdown tank vent is measured by analyzing liquid or steam condensate grab samples with a germanium detector.

The ratio of unit masses of water flashing to steam and water entering the tank is used to calculate the activity. The isotopic concentrations are assumed to remain constant between grab samples.

Other potential pathways for releasing gaseous radioactivity are periodically monitored by collecting grab samples and analyzing these samples with a germanium detector system.

b. lodines Radioiodines released from the plant vent are measured through continuous sample collection on silver zeolite cartridges. The cartridges are changed at least weekly and analyzed with a germanium detector. The radioiodine releases are .averaged over the period of cartridge sample collection.

4

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

Other potential pathways for releasing radioiodines are periodically measured by collecting samples using charcoal or silver zeolite cartridges and analyzing with a germanium detector.

Radioactive materials in particulate form released from the plant vent are measured through continuous sample collection on particulate filters. The filters are changed at least weekly and analyzed with a germanium detector. The particulate radioactivity is averaged over the period of particulate filter sample collection. Each filter is analyzed for alpha emitters using an internal proportional counter. Plant vent particulate filters collected during a quarter are used for the composite analysis for strontium-89 and -90, which is counted on an internal proportional counter after chemical separation.

Other potential pathways for releasing radioactive particulate are periodically monitored by collecting samples using particulate filters and analyzing these filters with a germanium detector.

c. Tritium Tritium released from the plant vent is monitored by passing a measured volume of plant vent sample through a water column and determining the tritium increase in the water. An aliquot of the water is counted in a liquid scintillation spectrometer. The minimum routine sample frequency for tritium in the plant vent is weekly. The tritium concentration is assumed to remain constant between samples.

d. Estimations of Overall Error Sources of error considered for gaseous batch releases are:

1) calibration source; 2) calibration counting; 3) sampling;

4) sample counting; and 5) gas decay tank pressure gauge/containment exhaust fan flow rate.

Sources of error for continuous release are: 1) calibration source; 2) calibration counting; 3) sampling; 4) sample counting; 5) process monitor (RE-14) reading (fission gases only); and 6) plant vent exhaust fan flow rate.

Total error= (cr 2 1 + cr 2 2 + cr 2 3 + ... cr 2 i) 112 Where cri = error associated with each component.

5

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

2. Liquid Effluents

a. Batch Releases Each tank of liquid radwaste is analyzed for principal gamma emitters using a germanium detector prior to release. A monthly prerelease analysis includes measurement of dissolved and entrained gases. Volume-proportional monthly and quarterly composites are prepared from aliquots of each tank volume discharged. The monthly composite is analyzed for tritium using a liquid scintillation spectrometer and gross alpha radioactivity using an internal proportional counter. The quarterly composite is analyzed for iron-55 using a liquid scintillation spectrometer and for strontium-89 and -90 using an internal proportional detector following chemical separations. The quarterly composite for discharges from the auxiliary building are also analyzed for nickel-63, uranium-233/234/235/236/238 and plutonium-238/239/240/241 /242.

b. Continuous Releases For the continuous liquid releases of the steam generator blowdown tank and turbine building sump oily water separator, daily grab samples are collected and aliquots are proportioned for weekly, monthly, and quarterly composites.

The oily water separator weekly composite is analyzed for principal gamma emitters using a germanium detector. The steam generator blowdown tank weekly composite is analyzed for principal gamma emitters and iodine-131.

The steam generator blowdown tank monthly composite is analyzed for tritium using a liquid scintillation spectrometer and for gross alpha using an internal proportional counter.

The steam generator blowdown tank quarterly composite is analyzed for iron-55 using a liquid scintillation spectrometer and for strontium-89 and strontium-90 using an internal proportional counter following chemical separation. The results for each of the composites are averaged over the period of the composite.

6

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

In addition, one grab sample of the steam generator blowdown tank is analyzed monthly for dissolved and entrained gases using a germanium detector. The results of this analysis are assumed to remain constant over the period of one month.

A grab sample of the steam generator blowdown is collected at least weekly and analyzed for gamma activity using a germanium detector. This analysis is used to monitor activity, however, is not used in effluent calculations unless a significant change is detected.

Note on dilution volume:

Tables 4A, 48 and 4C, "Liquid Effluents- Summation of All Releases," Item F., lists the, "Volume of circulating saltwater used during release periods," in liters. This value is calculated by multiplying the discharge duration by the circulating water flow rate. The values listed in the Tables are the summation of the circulating water discharge volume calculated for each individual batch and continuous discharge period. Therefore, in the case where two or more simultaneous discharges into the same circulating water are occurring, the calculated volume of circulating water is duplicated, and therefore the sum of the dilution volumes for the batch releases and continuous releases are greater than the actual dilution volume since each discharge incorporates the circulating discharge flow rate in its own dose calculation .

c. Estimation of Overall Error Sources of error considered for liquid releases are: 1) calibration source error; 2) calibration counting error; 3) sampling error; 4) sample counting error; and 5) volume of waste release error.

These sources of error are independent of one another.Therefore the total error is calculated according to the following formula :

Total error= (cr 2 1 + cr 22 + cr 2 3 + ... cr 2 i) 112 Where cri = error associated with each component.

7

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

D. Batch Releases

1. Liquid

a. Number of batch releases...... ..................................... 627

b. Total time period for batch releases........................ 2766 hours0.032 days 0.768 hours 0.00457 weeks 0.00105 months

c. Maximum time period for a batch release................. 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months

d. Averagetime period for a batch release..................... 4.41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months

e. Minimum time period for a batch release.................... 0.38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months

f. Average saltwater flow during batch releases............. 1.06E+06 gallons per minute (gpm)

2. Gaseous

a. Number of batch releases ...................................... . 140

b. Total time period for batch releases .......................... . 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months

c. Maximum time period for a batch release ................. . 72.00 hours0 days 0 hours 0 weeks 0 months

d. Average time period for a batch release ...... ......... .. . 10.21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months

e. Minimum time period for a batch release ............... .. 0.30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months E. Abnormal Release (Gaseous and Liquid)

No abnormal releases occurred during 2014.

F. Any liquid or gaseous effluent monitoring systems that became inoperable during the reporting period were corrected within the time limits specified in Attachments 1 and 2 (not included with 12/4/15 revision).

8

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

II. Changes to Radwaste Management A. Major Changes to Liquid, Gaseous and Solid Radwaste Treatment System No major changes were made to the treatment system during 2014 . .

As reported in 2012, an enhancement was made to the liquid radwaste treatment system in 2012. Modifications were made to provide mobile radwaste system connections downstream of in-plant vessels. This enables the use of a leased reverse osmosis unit (RO) in place of the vendor-supplied advance filtration unit that had been connected to the mobile radwaste system at the front of in-plant treatment systems.

During 2014, a leased RO unit remained in service.

B. Changes to the Radwaste Process Control Program (PCP)

There were no changes to the Radwaste PCP promulgated by Plant Administration Procedures. See Attachments 6 and 7:

RP2.DC2, "Radwaste Solidification Process Control Program,"

RP2.DC3, "Radwaste Dewatering Process Control Program" 9

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

Ill. Changes to the Offsite Dose Calculation Manual (ODCM)

The Diablo Canyon ODCM is made up of the following procedures:

Nuclear Power Generation Program Directive Procedure, CY2, "Radiological Monitoring and Controls Program" (RMCP)

Nuclear Power Generation Interdepartmental Administrative Procedure (IDAP), CY2.1D1, "Radioactive Effluent Controls Program" (RECP)

IDAP RP1.1D11, "Environmental Radiological Monitoring Procedure (ERMP)

Diablo Canyon Power Plant Chemical Analysis Procedure, CAP A-8, "Offsite Dose Calculation Procedure" (ODCP)

If no changes were made to an ODCM procedure during the reporting period, the most recent revision is included as an attachment in order to provide a complete, current copy of the ODCM used during the reporting period .

If changes were made to procedures during the reporting period, they are described below. A copy of each revision made during the reporting period is included as an attachment. Changes that were strictly editorial are not described below.

A. RMCP

1. No changes were made to the RMCP during 2014.

2. See Attachment 1 (not included with 12/4/15 revision).

B. RECP

1. Revision 12 of the RECP was implemented during 2014.

2. Revision 12 added new step that directs the user to ensure that changes to RP2.DC3 are described in the ARRER.

3. Revision 12 adds direction for sampling the condenser vacuum pump exhaust; specifically while the main steam isolation valves are open . This addition corrects an inconsistency between plant procedures and the UFSAR section 10.4.2.3. Frequency of sampling this exhaust is set at every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for consistency and conservatism . References have been added to ensure these commitments are not modified without due consideration.

4. This revision was implemented on 09/04/2014.

5. See Attachment 2 (not included with 12/4/15 revision) .

10

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

C. ERMP

1. Revisions 12 and 12A of the ERMP were implemented during 2014.

2. Revision 12 included enhancement of Table 2 for Detection Capabilities/Lower Limits of Detection to NUREG-1301 values and to add soil matrix detection limits.

3. Revision 12 also added supplementary sampling for airborne carbon-14 and vegetation at location 7E1. A TLD was also added at location 2F2.

4. Revision 12 was issued on 2/10/2014. See Attachment 3 (not included with 12/4/15 revision).

5. Revision 12A was an editorial correction issued on 2/20/2014.

6. See Attachment 4 (not included with 12/4/15 revision).

D. ODCP

1. No changes to the ODCP were made during 2014.

2. See Attachment 5 (not included with 12/4/15 revision).

IV. Land Use Census Changes to the Land Use Census Program are included as Attachment 7 (not included with 12/4/15 revision).

V. Gaseous and Liquid Effluent Release Report Tables 1 through 3 describe 2014 releases of gaseous effluents.

Tables 4 through 6 describe 2014 releases of liquid effluents.

11

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 1A GASEOUS EFFLUENTS- SUMMATION OF ALL RELEASES First Second Est. Total Units Quarter Quarter Error%

A. Fission and activation gases

1. Total release Ci 1.02E+O 1.82E-2 24%

I

2. Average release rate for period f.lCi/sec 1.32E-1 2.32E-3 1

3. Percent of technical specification limit % 1.23E-3 2.17E-5 B. lodines

1. Total iodine-131 Ci MDA MDA 24%

I

2. Average release rate for period f.lCilsec MDA MDA 1

3. Percent of technical specification limit % MDA MDA C. Particulates

1. Particulates with half-lives >8 days Ci MDA MDA 24%

I

2. Average release rate for period f.lCi/sec MDA MDA 1

3. Percent of technical specification limit % MDA MDA

4. Gross alpha radioactivity Ci MDA 2.21 E-7 D. Tritium

1. Total release Ci 4.37E+1 1.63E+1 13%

I

2. Average release rate for period f.lCi/sec 5.62E+O 2.08E+O 1

3. Percent of technical specification limit % 1.27E-5 4.70E-6

=

MDA Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume) . This note applies to all tables.

1 RECP Attachment 6 Limit 12

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 1B GASEOUS EFFLUENT~- SUMMATION OF ALL RELEASES Third Fourth Est. Total Units Quarter Quarter Error%

A. Fission and activation gases

1. Total release Ci 1.78E-2 1.20E+O 24%

I

2. Average release rate for period J..tCilsec 2.23E-3 1.51 E-1 1

3. Percent of technical specification limit % 2.09E-5 1.38E-3 B. lodines

1. Totaliodine-131 Ci MDA MDA 24%

I

2. Average release rate for period J..tCi/sec MDA MDA 1

3. Percent of technical specification limit % MDA MDA C. Particulates

1. Particulates with half-lives >8 days Ci MDA MDA 24%

I

2. Average release rate for period J..tCi/sec MDA MDA 1

3. Percent of technical specification limit % MDA MDA

4. Gross alpha radioactivity Ci 3.05E-8 2.90E-7 D. Tritium

1. Total release Ci 1.72E+1 3.60E+1 13%

I

2. Average release rate for period J..tCi/sec 2.16E+O 4.53E+O 1

3. Percent of technical specification limit % 4.89E-6 1.03E-5 MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

1 RECP Attachment 6 Limit 13

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 1C GASEOUS EFFLUENTS- SUMMATION OF ALL RELEASES Units Annual Total A . Fission and activation gases

1. Total release Ci 2.26E+O

2. Average release rate for period J..LCi/sec 7.17E-2 1

3. Percent of technical specification limit % 6.62E-4 B. lodines

1. Total iodine-131 Ci MDA

2. Average release rate for period J..LCi/sec MDA 1

3. Percent of technical specification limit % MDA C. Particulates

1. Particulates with half-lives >8 days Ci MDA

2. Average release rate for period J..LCilsec MDA 1

3. Percent of technical specification limit % MDA

4. Gross alpha radioactivity . Ci 5.42E-7 D. Tritium

1. Total release Ci 1.13E+2

2. Average release rate for period J..LCi/sec 3.59E+O 1

3. Percent of technical specification limit % 8.12E-6 MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

1 RECP Attachment 6 Limit 14

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 2A GASEOUS EFFLUENTS -GROUND LEVEL RELEASES First Quarter Second Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode

1. Fission gases argon-41 Ci MDA 1.02E+O MDA 1.82E-2 krypton-85 Ci MDA 3.67E-3 MDA MDA krypton-85m Ci MDA MDA MDA MDA krypton-87 Ci MDA MDA MDA MDA krypton-88 Ci MDA MDA MDA MDA xenon-131m Ci MDA MDA MDA MDA xenon-133 Ci MDA 1.49E-3 MDA MDA xenon-133m Ci MDA MDA MDA MDA xenon-135 Ci MDA MDA MDA MDA xenon-135m Ci MDA MDA MDA MDA xenon-138 Ci MDA MDA MDA MDA TOTAL FOR PERIOD Ci MDA 1.02E+O MDA 1.82E-2

2. lodines iodine-131 Ci MDA MDA iodine-133 Ci MDA MDA iodine-135 Ci MDA MDA TOTAL FOR PERIOD Ci MDA MDA MDA = Less than the lla posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

15

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 2A (Continued)

GASEOUS EFFLUENTS -GROUND LEVEL RELEASES Continuous Mode Nuclides Released Units First Quarter Second Quarter

3. Particulates barium-140 Ci MDA MDA cesium-134 Ci MDA MDA cesium-137 Ci MDA MDA cerium-141 Ci MDA MDA cerium-144 Ci MDA MDA chromium-51 Ci MDA MDA cobalt-57 Ci MDA MDA cobalt-58 Ci MDA MDA cobalt-60 Ci MDA MDA iron-59 Ci MDA MDA lanthanum-140 Ci MDA MDA manganese-54 Ci MDA MDA molybden u m-99 Ci MDA MDA ruthenium-1 03 Ci MDA MDA strontium-89 Ci MDA MDA strontium-90 Ci MDA MDA zinc-65 Ci MDA MDA zirconium-95 Ci MDA MDA TOTAL FOR PERIOD Ci MDA MDA

=

MDA Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume).

This note applies to all tables.

16

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 28 GASEOUS EFFLUENTS -GROUND LEVEL RELEASES Third Quarter Fourth Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode

1. Fission gases argon-41 Ci MDA 1.78E-2 MDA 1.17E+O krypton-85 Ci MDA MDA MDA 2.02E-3 krypton-85m Ci MDA MDA MDA MDA krypton-87 Ci MDA MDA MDA MDA krypton-88 Ci MDA MDA MDA MDA xenon-131m Ci MDA MDA MDA MDA xenon-133 Ci MDA MDA MDA 2.86E-2 xenon-133m Ci MDA MDA MDA 3.61 E-4 xenon-135 Ci MDA MDA MDA 2.13E-4 xenon-135m Ci MDA MDA MDA MDA xenon-138 Ci MDA MDA MDA MDA TOTAL FOR PERIOD Ci MDA 1.78E-2 MDA 1.20E+O

2. lodines iodine-131 Ci MDA MDA iodine-133 . Ci MDA MDA iodine-135 Ci MDA MDA TOTAL FOR PERIOD Ci MDA MDA MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

17

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 2B (Continued)

GASEOUS EFFLUENTS -GROUND LEVEL RELEASES Continuous Mode Nuclides Released Units Third Quarter Fourth Quarter

3. Particulates barium-140 Ci MDA MDA cesium-134 Ci MDA MDA cesium-137 Ci MDA MDA cerium-141 Ci MDA MDA cerium-144 Ci MDA MDA chromium-51 Ci MDA MDA cobalt-57 Ci MDA MDA cobalt-58 Ci MDA MDA cobalt-60 Ci MDA MDA iron-59 Ci MDA MDA lanthanum-140 Ci MDA MDA manganese-54 Ci MDA MDA molybdenum-99 Ci MDA MDA ruthenium-1 03 Ci MDA MDA strontium-89 Ci MDA MDA strontium-90 Ci MDA MDA zinc-65 Ci MDA MDA zirconium-95 Ci MDA MDA TOTAL FOR PERIOD Ci MDA MDA MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume).

This note applies to all tables.

18

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 3 GASEOUS EFFLUENTS - LOWER LIMITS OF DETECTION Batch Mode Nuclide Units Continuous Mode Containment Purge Gas Decay Tank

1. Fission gases argon-41 llCi/ml 3.17E-8 3.17E-8 3.17E-8 krypton-85 llCilml 2.20E-6 2.20E-6 2.20E-6 krypton-85m llCi/ml 6.24E-9 6.24E-9 6.24E-9 krypton-87 llCi/ml 5.05E-8 5.05E-8 5.05E-8 krypton-88 llCilml 3.22E-8 3.22E-8 3.22E-8 xenon-131m llCi/ml 1.87E-7 1.87E-7 1.87E-7 xenon-133 llCilml 1.70E-8 1.70E-8 1.70E-8 xenon-133m llCi/ml 4.91 E-8 4.91 E-8 4.91 E-8 xenon-135 llCi/ml 6.23E-9 6.23E-9 6.23E-9 xenon-135m llCi/ml 3.28E-6 3.28E-6 3.28E-6 xenon-138 llCilml 9.07E-6 9.07E-6 9.07E-6

2. Tritium lhydrogen-3 llCilml 4.52E-9 4.52E-9 N/A

3. lodines iodine-131 llCilml 4.89E-13 N/A iodine-133 llCilml 1.54E-12 N/A iodine-135 llCi/ml 9.98E-11 N/A 19

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 3 (Continued)

GASEOUS EFFLUENTS - LOWER LIMITS OF DETECTION I

Nuclide Units Continuous Mode

4. Particulates barium-140 ~Cilml 1.99E-12 cesium-134 ~Cilml 5.08E-13 cesium-137 ~Cilml 4.17E-13 cerium-141 ~Cilml 3.98E-13 cerium-144 ~Cilml 1.49E-12 chromium-51 ~Cilml 2.99E-12 cobalt-57 ~Cilml 2.18E-13 cobalt-58 ~Cilml 7.10E-13 cobalt-50 ~Cilml 8.81E-13 iron-59 ~Cilml 5.73E-13 lanthanum-140 ~Cilml 1.13E-12 manganese-54 ~Ci/ml 5.55E-13 molybdenum-99 ~Cilml 3.97E-13 ruthenium-1 03 ~Cilml 3.48E-13 strontium-89 ~Cilml 2.14E-15 strontium-90 ~Cilml 4.14E-16 zinc-65 ~Cilml 9.54E-13 zirconium-95 ~Cilml 3.67E-13 gross alpha ~Cilml 1.97E-15 20

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 4A LIQUID EFFLUENTS- SUMMATION OF ALL RELEASES First Second Est. Total Units Quarter Quarter Error%

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 1.05E-2 8.76E-3 24%

I

2. Average diluted concentration during period J.!Ci/ml 5.07E-12 3.27E-12 1

3. Percent of applicable limit % 5.49E-5 1.16E-5 B. Tritium

1. Total release Ci 1.02E+3 2.44E+2 13%

I

2. Average diluted concentration during period J.!Cilml 4.94E-7 9.1 OE-8

3. Percent of applicable limit1 % 4.94E-2 9.1 OE-3 C. Dissolved and entrained gasses

1. Total release Ci 1.02E-3 1.40E-4 24%

I

2. Average diluted concentration during period J.!Cilml 4.92E-13 5.23E-14 1

3. Percent of applicable limit % 2.46E-7 2.61 E-8 D. Gross Alpha

1. Total release Ci MDA MDA 61%

E. Volume of waste release (prior to dilution) 8.25E+7 8.14E+ 7 5%

F.

IVolume of circulating saltwater used during I release periods liters 2.07E+12 2.68E+12 I 7%

I

=

MDA Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

1 RECP 6.1.6.1 Limit 21

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON "POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 4B LIQUID EFFLUENTS- SUMMATION OF ALL RELEASES Third Fourth Est. Total Units Quarter Quarter Error%

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 3.08E-3 5.30E-3 24%

I

2. Average diluted concentration during period J..LCi/ml 1.15E-12 2.39E-12 1

3. Percent of applicable limit % 1.64E-5 1.80E-5 B. Tritium

1. Total release Ci 5.45E+2 4.27E+2 13%

I

2. Average diluted concentration during period J..LCilml 2.04E-7 1.92E-7 1

3. Percent of applicable limit % 2.04E-2 1.92E-2 C. Dissolved and entrained gasses

1. Total release Ci 7.09E-4 9.31 E-4 24%

I

2. Average diluted concentration during period J..LCi/ml 2.65E-13 4.19E-13 1

3. Percent of applicable limit % 1.32E-7 2.10E-7 D. Gross Alpha

1. Total release Ci MDA MDA 61%

E. Volume of waste release (prior to dilution) 8.30E+ 7 7.99E+ 7 5%

Volume of circulating saltwater used during F. 2.68E+12 2.22E+12 7%

release periods MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

1 RECP 6.1.6.1 Limit 22

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 4C LIQUID EFFLUENTS- SUMMATION OF ALL RELEASES Units Annual Total A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 2.77E-2

2. Average diluted concentration during period !lCilml 2.87E-12 1

3. Percent of applicable limit % 2.37E-5 B. Tritium 1 . Total release Ci 2.24E+3

2. Average diluted concentration during period !lCi/ml 2.32E-7 1

3. Percent of applicable liniit % 2.32E-2 C. Dissolved and entrained gasses

1. Total release Ci 2.80E-3

2. Average diluted concentration during period )lCilml 2.90E-13 1

3. Percent of applicable limit % 1.45E-7 D. Gross Alpha

1. Total release Ci MDA E. Volume of waste release (prior to dilution) liters 3.27E+8 Volume of circulating saltwater used during F. liters 9.65E+12 release periods MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume).

This note applies to all tables.

1 RECP 6.1.6.1 Limit 23

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE SA LIQUID EFFLUENTS - NUCLIDES RELEASED First Quarter Second Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode antimony-122 Ci MDA MDA MDA MDA antimony-124 Ci MDA MDA MDA MDA antimony-125 Ci MDA 9.14E-4 MDA 1.05E-4 barium-140 Ci MDA MDA MDA MDA beryllium-? Ci MDA MDA MDA MDA bromine-82 Ci MDA MDA MDA MDA cerium-141 Ci MDA MDA MDA MDA cerium-143 Ci MDA MDA MDA MDA cerium-144 Ci MDA MDA MDA MDA cesium-134 Ci MDA MDA MDA MDA cesium-136 Ci MDA MDA MDA MDA cesium-137 Ci MDA 5.1 OE-5 MDA 2.75E-6 chromium-51 Ci MDA 4.69E-4 MDA 5.99E-5 cobalt-57 Ci MDA MDA MDA MDA cobalt-58 Ci MDA 4.04E-4 MDA 2.41 E-4 cobalt-60 Ci MDA 2.92E-3 MDA 6.40E-4 iron-55 Ci MDA 2.52E-3 MDA 7.60E-3 iron-59 Ci MDA 2.46E-5 MDA MDA Ia nth an u m-140 Ci MDA MDA MDA MDA MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

24

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE SA (CONTINUED)

LIQUID EFFLUENTS -NUCLIDES RELEASED First Quarter Second Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode manganese-54 Ci MDA 4.19E-5 MDA 1.52E-5 manganese-56 Ci MDA MDA MDA MDA molybden u m-99 Ci MDA MDA MDA 7.59E-7 nickel-63 Ci MDA 3.1 OE-3 MDA 8.56E-5 niobium-95 Ci MDA 5.35E-5 MDA 1.14E-5 neodymium-147 Ci MDA MDA MDA MDA plutonium-238 Ci MDA MDA MDA MDA plutonium-239/240 Ci MDA MDA MDA MDA plutonium-241 Ci MDA MDA MDA MDA plutonium-242 Ci MDA MDA MDA MDA ruthenium-1 03 Ci MDA MDA MDA MDA silver-11Om Ci MDA MDA MDA MDA sodium-24 Ci MDA MDA MDA MDA strontium-89 Ci MDA MDA MDA MDA strontium-90 Ci MDA MDA MDA MDA strontium-91 Ci MDA MDA MDA MDA strontium-92 Ci MDA MDA MDA MDA tellurium-129m Ci MDA MDA MDA MDA MDA =Less than the lla posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

25

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE SA (CONTINUED)

LIQUID EFFLUENTS - NUCLIDES RELEASED First Quarter Second Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode tellurium-132 Ci MDA MDA MDA MDA tin-113 Ci MDA MDA MDA MDA tin-117m Ci MDA MDA MDA MDA tungsten-187 Ci MDA MDA MDA MDA uranium-233/234 Ci MDA MDA MDA MDA uranium-235/236 Ci MDA MDA MDA MDA uranium-238 Ci MDA MDA MDA MDA zinc-65 Ci MDA MDA MDA MDA zirconium-95 Ci MDA 1.28E-5 MDA 2.42E-6 iodine-131 Ci MDA MDA MDA MDA iodine-132 Ci MDA MDA MDA MDA iodine-133 Ci MDA MDA MDA MDA iodine-135 Ci MDA MDA MDA MDA TOTAL FOR PERIOD Ci MDA 1.05E-2 MDA 8.76E-3 DISSOLVED AND ENTRAINED GASES xenon-133 Ci MDA 1.01 E-3 MDA 1.40E-4 xenon-133m Ci MDA MDA MDA MDA xenon-135 Ci MDA 7.52E-6 MDA MDA krypton-85 Ci MDA MDA MDA MDA krypton-88 Ci MDA MDA MDA MDA TOTAL FOR PERIOD Ci MDA 1.02E-3 MDA 1.40E-4 MDA =Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

26

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 58 LIQUID EFFLUENTS - NUCLIDES RELEASED Third Quarter Fourth Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode antimony-122 Ci MDA MDA MDA MDA antimony-124 Ci MDA MDA MDA MDA antimony-125 Ci MDA 2.10E-4 MDA 4.09E-5 barium-140 Ci MDA MDA MDA MDA beryllium-? Ci MDA MDA MDA MDA bromine-82 Ci MDA MDA MDA MDA cerium-141 Ci MDA MDA MDA MDA cerium-143 Ci MDA MDA MDA MDA cerium-144 Ci MDA MDA MDA MDA cesium-134 Ci MDA MDA MDA MDA cesium-136 Ci MDA MDA MDA MDA cesium-137 Ci MDA MDA MDA MDA chromium-51 Ci MDA MDA MDA 8.46E-4 cobalt-57 Ci MDA MDA MDA MDA cobalt-58 Ci MDA 1.32E-4 MDA 4.46E-4 cobalt-60 Ci MDA 1.23E-3 MDA 9.95E-4 iron-55 Ci MDA 1.07E-3 MDA 2.64E-3 iron-59 Ci MDA MDA MDA 5.04E-7 lanthan um-140 Ci MDA MDA MDA MDA MDA = Less than the lla posteriori~~ minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

27

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 58 (CONTINUED)

LIQUID EFFLUENTS - NUCLIDES RELEASED Third Quarter Fourth Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode manganese-54 Ci MDA 2.41 E-5 MDA 3.61 E-5 manganese-56 Ci MDA MDA MDA MDA molybdenum-99 Ci MDA MDA MDA MDA nickel-63 Ci MDA 4.13E-4 MDA 1.85E-4 niobium-95 Ci MDA 3.91 E-6 MDA 4.91 E-5 neodymium-147 Ci MDA MDA MDA MDA plutonium-238 Ci MDA MDA MDA MDA plutonium-239/240 Ci MDA MDA MDA MDA plutonium-241 Ci MDA MDA MDA MDA plutonium-242 Ci MDA MDA MDA MDA ruthenium-1 03 Ci MDA MDA MDA MDA silver-11Om Ci MDA MDA MDA MDA sodium-24 Ci MDA MDA MDA MDA stronti um-89 Ci MDA MDA MDA MDA strontium-90 Ci MDA MDA MDA MDA strontium-91 Ci MDA MDA MDA MDA strontium-92 Ci MDA MDA MDA MDA tellurium-129m Ci MDA MDA MDA MDA MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

28

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 58 (CONTINUED)

LIQUID EFFLUENTS - NUCLIDES RELEASED Third Quarter Fourth Quarter Continuous Continuous Nuclides Released Units Batch Mode Batch Mode Mode Mode tellurium-132 Ci MDA MDA MDA MDA tin-113 Ci MDA MDA MDA MDA tin-117m Ci MDA MDA MDA MDA tungsten-187 Ci MDA MDA MDA MDA uranium-233/234 Ci MDA MDA MDA MDA uranium-235/236 Ci MDA MDA MDA MDA uranium-238 Ci MDA MDA MDA MDA zinc-65 Ci MDA MDA MDA 6.13E-5 zirconium-95 Ci MDA MDA MDA MDA iodine-131 Ci MDA MDA MDA MDA iodine-132 Ci MDA MDA MDA MDA iodine-133 Ci MDA MDA MDA MDA iodine-135 Ci MDA MDA MDA MDA TOTAL FOR PERIOD Ci MDA 3.08E-3 MDA 5.30E-3 DISSOLVED AND ENTRAINED GASES xenon-133 Ci MDA 7.03E-4 MDA 9.03E-4 xenon-133m Ci MDA MDA MDA MDA xenon-135 Ci MDA 5.95E-6 MDA 2.85E-5 krypton-85 Ci MDA MDA MDA MDA krypton-88 Ci MDA MDA MDA MDA TOTAL FOR PERIOD Ci MDA 7.09E-4 MDA 9.31 E-4 MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or volume). This note applies to all tables.

29

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 6 LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Units LLD antimony-122 llCilml 1.98E-7 antimony-124 llCi/ml 1.05E-7 antimony-125 llCi/ml 2.53E-7 barium-140 llCi/ml 5.40E-7 beryllium-? llCi/ml 7.12E-7 bromine-82 J.lCilml 1.86E-7 cerium-141 llCi/ml 1.12E-7 cerium-143 llCi/ml 2.15E-7 cerium-144 llCilml 3.82E-7 cesium-134 llCilml 9.17E-8 cesium-136 llCi/ml 1.37E-7 cesium-137 llCi/ml 1.13E-7 chromium-51 J.lCilml 8.37E-7 cobalt-57 llCi/ml 6.18E-8 cobalt-58 !lCi/ml 1.39E-7 cobalt-60 !lCi/ml 3.60E-7 iron-55 llCi/ml 8.22E-7 iron-59 llCi/ml 1.67E-7 lanthan u m-140 llCi/ml 2.03E-7 manganese-54 J.lCi/ml 1.47E-7 manganese-56 !lCi/ml 7.28E-5 molybden um-99 llCi/ml 6.78E-8 nickel-63 J.lCilml 3.73E-8 niobium-95 llCilml 8.99E-8 30

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 6 (CONTINUED)

LIQUID EFFLUENTS ~LOWER LIMITS OF DETECTION Nuclide Units LLD neodymium-147 ~-tCilml 2.96E-7 plutonium-238 ~-tCi/ml 4.09E-8 plutonium-239/240 ~-tCi/ml 3.97E-8 plutonium-241 ~-tCi/ml 4.42E-8 plutonium-242 ~-tCi/ml 3.21 E-8 ruthenium-1 03 ~-tCi/ml 1.13E-7 silver-11Om ~-tCi/ml 1.01 E-7 sodium-24 ~-tCi/ml 5.56E-7 strontium-89 ~-tCi/ml 4.70E-8 strontium-90 ~-tCi/ml 2.38E-8 strontium-91 ~-tCi/ml 7.64E-7 strontium-92 ~-tCi/ml 1.02E-4 tellurium-129m ~-tCilml 3.56E-6 tellurium-132 ~-tCi/ml 1.05E-7 tin-113 ~-tCi/ml 9.33E-8 tin-117m ~-tCilml 7.60E-8 tungsten-187 ~-tCi/ml 4.97E-7 uranium-233/234 ~-tCi/ml 2.50E-8 uranium-235/236 ~-tCi/ml 3.80E-8 uranium-238 ~-tCi/ml 3.07E-8 zinc-65 ~-tCi/ml 3.06E-7 zirconium-95 ~-tCi/ml 2.38E-7 gross alpha ~-tCi/ml 9.85E-8 hydrogen-3 ~-tCi/ml 4.32E-6 31

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 6 (CONTINUED)

LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Units LLD iodine-131 ~Cilml 7.62E-8 iodine-132 ~Cilml 9.02E-5 iodine-133 ~Cilml 2.40E-7 iodine-135 ~Cilml 6.06E-6 xenon-133 ~Cilml 2.23E-7 xenon-133m ~Cilml 8.73E-7 xenon-135 ~Cilml 3.98E-7 krypton-85 ~Cilml 2.09E-5 krypton-88 ~Cilml 7.46E-5 32

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

VI. Solid Radwaste Shipments Solid Waste and Irradiated Fuel Shipment A. Solid Waste Shipped Off-site for Burial or Disposal (Not irradiated fuel)

1. Type of Waste Unit 12 Month Period Est. Total Error, 0/o

a. Spent Resins, Filter Sludges, m3 7.93E+OO Evaporator Bottoms, etc. Ci 1.26E+02 9.00E+O

b. Dry Compressible Waste, m3 1.50E+01 Contaminated Equipment, etc. Ci 4.41 E-01 9.00E+O

c. Irradiated Components, Control m3 O.OOE+O Rods, etc. Ci O.OOE+O O.OOE+O

d. Other m3 O.OOE+O Ci O.OOE+O O.OOE+O

2. Estimate of Major Nuclide Composition (by type of waste)

a. Ni-63 Ofo 4.31 E+01 Co-60 % 2.40E+01 0

Fe-55 /o 2.01 E+01 C-14 Ofo 7.05E+OO H-3 % 9.17E-01 0

b. Fe-55 /o 3.16E+01 Co-60 % 2.39E+01 Ofo Ni-63 1.51 E+01 Cr-51 % 5.08E+OO Nb-95 Ofo 2.95E+OO

c. I_____N_ot_A_P_P_Ii_ca_b_le____~____%_o____________NI_A_______

d. I____N_o_t_A_P_P_Iic_a_b_le_________o_~----~------N_IA_______

33

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

Solid Waste and Irradiated Fuel Shipment (Continued)

3. Solid Waste Disposition Number of Shipments Mode of Destination Transportation 5 Truck Clive, UT 2 Rail Clive, UT 3 Truck Andrew, TX

4. Supplemental Information Required by former TS 6.9.1.6 Solidification Type of Container Number of 10 CFR 61 Shipping Type Agent Containers Waste Class Cement IP1 1 c IP2- LSAII Polymer IP1 2 c Type B B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A 34

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

VII. Radiation Dose Due to Gaseous and Liquid Effluents A. Radiation Doses from Radioactive Liquid Effluents The radiation dose contributions to the total body and each individual organ due to releases of radioactive liquid effluents for the maximum exposed adult member of the public have been calculated in accordance with the methodology stated in the ODCP. Dose contributions listed in Table 7 show conformance to Attachment 4 of the RECP.

B. Radiation Doses from Radioactive Gaseous Effluents

1. The radiation dose contributions due to radioactive gaseous effluents at the site boundary for each of the land sectors have been calculated in accordance with the calculation methodology stated in the ODCP. The dose contribution related to operation of each unit has been calculated separately.

The latest five-year historical average meteorology conditions were used in these calculations. In addition to the site boundary doses, the dose to an individual (critical receptor) due to radioiodines, tritium, and particulates released in gaseous effluents with half-lives greater than eight days is determined in accordance with the methodology in the ODCP that is based on the methodology described in NUREG-0133. Dose contributions listed in Table 8, which represents the maximum dose for age groups, organs, and geographic locations for the report period, show conformance to Attachments 6, 7 and 8 of the RECP .

2. The radiation dose to a member of the public at the site boundary from two locations other than the plant vent have been calculated. The results are conservatively based upon laboratory determination of the isotopic source term and calculation of the discharge flow. The respective doses from these two sources are reported separately here:

a. Radiation Doses from Chemistry Laboratory Radioactive Gaseous Effluents - Closest Site Boundary (800m)

i. The dose due to the radioactive gaseous effluent from the primary chemistry laboratory during the report period is evaluated to be:

1. Total gamma air dose = 4.25E-06 mrad

2. Total beta air dose = 1.51 E-06 mrad

b. Radiation Doses from Post Accident Sampling System Radioactive Gaseous Effluents - Closest Site Boundary (800m)

i. The dose due to radioactive gaseous effluents from the post accident sampling system during the report period is evaluated to be:

1. Total gamma air dose = 3.67E-07 mrad

2. Total beta air dose = 1.30E-07 mrad 35

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

3. Radiation Dose from Radioactive Gaseous Effluents to Individuals Due to Consumption of Grazing Animals on Property Surrounding the Site.

The Land Use Census identified that during 2014, ranchers in the area around the plant slaughtered cattle, goats, sheep, deer and wild pigs for personal consumption. As part of the DCPP Radiological Environmental Monitoring Program (REMP), samples of cow, goat and sheep meat were analyzed for radioactivity. Results of those analyses are available in the 2014 Annual Radiological Environmental Operating Report.

Based upon the isotopes (other than C-14) discharged in gaseous form during 2014, the maximum calculated dose due to these identified meat pathways is 4.92 E-03 mrem. The greatest contributor to this dose is H-3.

4. Atmospheric Release Of Carbon-14

a. Historically, C-14 has not been considered a "principle radionuclide" in terms of its concentration in radioactive effluents and its dose consequence to offsite receptors. Naturally occurring C-14 is prevalent in the environment. In addition, nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.

Therefore, power plants typically did not analyze for, nor report information for C-14 in annual reports.

b. In June, 2009, the NRC revised its guidance in Regulatory Guide (RG) 1.21, "Measuring, Evaluating and Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants", Revision 2. This document states that analytical methods for determining C-14 have improved. Coincidentally, the radioactive effluents from commercial power plants have decreased to the point that C-14 is likely to be a principle radionuclide in gaseous effluents. Also, because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required.

c. As a result, the NRC states that licensees should evaluate whether C-14 is a principal radionuclide for gaseous releases from their facility.

d. RG 1.21 goes on to explain, in part:

i. The quantity of C-14 discharged can be estimated by sample measurements or by use of a normalized C-14 source term and scaling factors based on power generation, or estimated by use of the GALE code from NUREG-0017.

ii. If sampling is performed, the sampling frequency may be adjusted to that interval that allows adequate measurement and reporting of effluents.

36

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053) iii. If estimating C-14 based on scaling factors and fission rates, a precise and detailed evaluation of C-14 is not necessary. It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any subsequent calculation of overall uncertainty.

e. In order to aid the nuclear power industry in estimating C-14 production, the Electric Power Research Institute (EPRI) developed 2010 Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents," December 2010. This is the guidance Diablo Canyon uses to estimate the production and release quantities of C-14.

f. Calculated carbon-14 production, discharge parameters and resulting dose to the nearest member of the public are reported here; separately from tables 1, 2, 8, 10 and 11 U1 =12.0 Ci/EFPY( 1)

Calculated C-14 production, per Unit U2=12.0 Ci/EFPY( 1)

U1 = 0.8691 2014 Unit capacity factors U2 = 0.8665 Fraction release of produced C-14 0.98 Organic = 0.70 Fraction of C-14 chemical form assumed Inorganic = 0.30 U1 = 10.22 Curies C-14 released to atmosphere U2 =*10.19 Critical receptor dose(2) [Adult (bone)], mrem 3.43E-01 1

( lEffective Full Power Year 2

( lDue to ingestion of meat (cattle) assumed to graze up to the site boundary in the NW sector

g. Summary:

i. The quantity of C-14 released to the atmosphere for 2014 was Unit 1 = 10.22 curies Unit 2 = 10.19 curies ii. The resulting critical receptor dose is:

Adult (bone), due to ingestion of meat= 3.43E-01 mrem.

37

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

C. Radiation Doses from Direct Radiation (Line-of-Sight Plus Sky-Shine)-

Closest Site Boundary

1. For the report period, the greatest radiation dose to a member of the public at the site boundary from the following areas is evaluated to be 2.53E-01 mR:

Radioactive waste containers outside of plant buildings

Storage of contaminated tools and equipment inside plant buildings

Old Steam Generator Storage Facility, which contains:

Four Unit 2 old steam generators since 2008.

Four Unit 1 old steam generators since 2009.

One Unit 2 old reactor head since 2009.

One Unit 1 old reactor head since 2010.

Independent Spent Fuel Storage Installation (ISFSI).

The Diablo Canyon ISFSI received casks as follows:

Year #Casks 2009 8 2010 8 2011 0 2012 7 2013 6 2014 0 The nearest full-time resident to the site is approximately 1.5 miles away, and is separated from direct line-of-site by mountainous terrain. However, doses from direct radiation are calculated at the site boundary. Sky-shine is included in the direct radiation calculation. The occupancy time at the site boundary is conservatively assumed to be 2,080 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months , based upon a 40-hour work week and 52 weeks per year.

D. 40 CFR 190 Considerations The release of radioactivity in liquid and gaseous effluents resulted in doses that are small percentages of the TS limits as shown in Tables 9 and 10.

In addition, the direct radiation from various sources, including the ISFSI, resulted in doses that are a small percentage of 40 CFR 190 limits.

The total doses reported for 2014 from liquid and gaseous effluents and direct radiation shows that Diablo Canyon complied with all 40 CFR 190 limits.

38

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

E. Radiation Doses from Radioactive Liquid and Gaseous Effluents to Members of the Public Due To Their Activities Inside The Site Boundary

1. Liquid Effluents The radiation dose to members of the public within the site boundary due to the release of radioactive liquid effluents is evaluated as negligible. The bases for this evaluation are discharge piping location and the source term that was present during the reporting period. Specifically; locations of the discharge piping for liquid radwaste are mostly embedded in concrete, located in remote or inaccessible areas, and/or underground. In addition, the quantity of radioactivity released through liquid radwaste piping was very small. (Refer to Tables 4A-4C.)

2. Gaseous Effluents The radiation dose to members of the public within the site boundary due to the release of radioactive gaseous effluents is listed in Table 11.

39

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

G. Sub-surface water radioactive contamination Recent events at other nuclear plant sites have involved identification of equipment leaks containing low levels of radioactivity. In some cases, these leaks have resulted in radioactive contamination of ground water and storm water that may leave the plant sites. Any plant equipment leaks that could result in such an event at Diablo Canyon are documented in the corrective action program (CAP). Analysis of samples of sub-surface water at Diablo Canyon has indicated the only radioactive isotope currently present is tritium. At this time, there is no evidence to point to plant system leakage as the source for this tritium.

Sampling and analysis of Auxiliary Building roof drains, Auxiliary Building drywell, and the containment structure observation wells have identified detectable tritium activity. This tritium has been evaluated as most likely coming from the rain wash-out of gaseous tritium exiting the plant vent system . This tritium is being accounted for in the plant vent release, and rain water tritium is being accounted for per plant approved procedures. These practices will continue until such time that new industry guidance is provided to account for this pathway in a different manner.

Refer to the 2014 Annual Radiological Environmental Operating Report for the data that has been evaluated to date for the sampling locations.

H. NEI 07-07 Voluntary Communication for sub-surface water Section 2, "Communication," Objective 2.4, "Annual Reporting," of NEI 07-07 lists the acceptance criteria for annual reporting of "ground water" information, as follows:

1. Acceptance Criterion 2.4.b.i:

Reporting of on-site ground water sample results that are taken in support of the Groundwater Protection Initiative (GPI), but are not part of the REMP program are reported in the ARERR required by 10 CFR 50 .36a(a)(2) .

For 2014, there were no on-site ground water results for samples taken in support of the GPI that are not part of the REMP program .

2. Acceptance Criterion 2.4.b.ii:

Reporting of on-site ground water "sample results for those long-term monitoring sample points that are not included in REMP are reported in the ARERR."

For 2014, there were no on-site ground water sample results for long term monitoring sample points not included in the REMP.

3. Acceptance Criterion 2.4.c.i Voluntary communications of the description of all spills or leaks, made per Objective 2.2 acceptance criterion, shall be included in the ARERR.

For 2014, no voluntary communications were made per Objective 2.2.

4. Acceptance Criterion 2.4.c.ii:

Voluntary communications of all on-site or off-site ground water sample results that exceeded the REMP reporting thresholds as described in the ODCM that were communicated per Objective 2.2 acceptance criterion b shall be included in the ARERR.

For 2014, no voluntary communications were made per Objective 2.2.

40

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 7 RADIATION DOSE DUE TO THE RELEASE OF RADIOACTIVE LIQUID EFFLUENTS millirem First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Total Body 1.50E-04 5.34E-05 5.29E-05 8.49E-05 3.41 E-04 Bone 2.05E-04 2.00E-04 3.91 E-05 1.22E-04 5.66E-04 Liver 2.01 E-04 1.58E-04 6.70E-05 1.55E-04 5.80E-04 Thyroid 1.20E-04 2.00E-05 4.54E-05 5.24E-05 2.38E-04 Kidney 1.21 E-04 2.00E-05 4.54E-05 7.05E-05 2.57E-04 Lung 1.57E-04 9.64E-05 5.64E-05 9.32E-05 4.03E-04 G.l. LLI 3.04E-04 1.20E-04 8.12E-05 1.89E-04 6.93E-04 41

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 8A 1

RADIATION DOSE DUE TO THE RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS (UNIT 1)

First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Dose Dose Dose Dose Dose Site Boundary Noble Gas Gamma Air Dose mrad 1.58E-3 1.51 E-5 1.21 E-5 1.36E-5 1.62E-3 Beta Air Dose mrad 5.58E-4 5.31 E-6 4.28E-6 4.81 E-6 5.73E-4 First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Dose Dose Dose Dose Dose Nearest Residence-NNW I p T2,3 I I 5.95E-4 I 1.74E-4 I 1.66E-4 I 1.73E-4 I 1.11 E-3 First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Dose Dose Dose Dose Dose Nearest Ve9etable Garden- NNE I P T 2.4 I I 1.12E-4 I 3.56E-5 I 3.39E-5 I 3.54E-5 I 2.17E-4 42

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE BB 1

RADIATION DOSE DUE TO THE RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS (UNIT 2)

First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Dose Dose Dose Dose Dose Site Boundary Noble Gas Gamma Air Dose mrad 1.29E-5 1.34E-5 1.56E-5 1.82E-3 1.86E-3 Beta Air Dose mrad 4.57E-6 4.74E-6 5.50E-6 6.46E-4 6.61 E-4 First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Dose Dose Dose Dose Dose Nearest Residence-NNW I p T2,3 I I 1.14E-4 I ?.OOE-5 I 9.12E-5 I 4.41 E-4 I 7.17E-4 First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Dose Dose Dose Dose Dose 2.34E-5 1.43E-5 1.86E-5 7.78E-5 1.34E-4 43

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

Notes for Tables SA and 88

1. The doses reported in these tables represent the maximum doses due to the stated source term for the most-affected age groups and organs at the respective geographic locations for the quarter and the year.

2. Radioiodines, radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than eight days.

3. The inhalation and ground plane pathways are included for this location.

4. The inhalation, ground plane and vegetable pathways are included for this location.

44

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 9 1

PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADIOACTIVE LIQUID EFFLUENTS Percent First Quarter Second Quarter Third Quarter Fourth Quarter Annual Total Total Body 9.97E-03 3.56E-03 3.52E-03 5.66E-03 1.14E-02 Bone 4.09E-03 4.01 E-03 7.81 E-04 2.43E-03 5.66E-03 Liver 4.02E-03 3.15E-03 1.34E-03 3.09E-03 5.80E-03 Thyroid 2.41 E-03 4.00E-04 9.08E-04 1.05E-03 2.38E-03 Kidney 2.41 E-03 4.01 E-04 9.09E-04 1.41 E-03 2.57E-03 Lung 3.15E-03 1.93E-03

1.13E-03 1.86E-03 4.03E-03 G.l. LLI 6.07E-03 2.40E-03 1.62E-03 3.78E-03 6.93E-03 NOTE:

1 RECP 6.1.4.1 45

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE10A 1

PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADIOACTIVE GASEOUS EFFLUENTS (UNIT 1)

First Quarter % Second Quarter Third Quarter % Fourth Quarter% Annual Total %

of TS Limit % ofTS Limit of TS Limit of TS Limit of TS Limit Site Boundary Noble Gas Gamma Air Dose 3.16E-2 3.01 E-4 2.43E-4 2.73E-4 1.62E-2 Beta Air Dose 5.58E-3 5.31 E-5 4.28E-5 4.81 E-5 2.86E-3 First Quarter%

of TS Limit I Second Quarter

% of TS Limit I of TS Limit I

Third Quarter% Fourth Quarter of TS Limit

%1 Annual Total %

of TS Limit 7.94E-3 I 2.32E-3 I 2.21 E-3 I 2.31 E-3 I 7.39E-3 First Quarter % Second Quarter Third Quarter% Fourth Quarter% Annual Total %

of TS Limit %of TS Limit of TS Limit of TS Limit of TS Limit Nearest Vesetable Garden- NNE L.e.J . . 1.50E-3 I 4.74E-4 I 4.52E-4 I 4.73E-4 I 1.45E-3 NOTE:

1 RECP Attachments 6, 7 and 8 46

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE10B 1

PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADIOACTIVE GASEOUS EFFLUENTS (UNIT 2)

First Quarter % Second Quarter Third Quarter% Fourth Quarter% Annual Total %

of TS Limit %of TS Limit of TS Limit of TS Limit of TS Limit Site Boundary Noble Gas Gamma Air Dose 2.59E-4 2.69E-4 3.12E-4 3.64E-2 1.86E-2 Beta Air Dose 4.57E-5 4.74E-5 5.50E-5 6.46E-3 3.31 E-3 I First Quarter%

of TS Limit I Second Quarter

% of TS Limit I of TS Limit I

Third Quarter% Fourth Quarter %1 Annual Total%

of TS Limit of TS Limit Nearest Residence-NNW L.E.J . . 1.52E-3 I 9.34E-4 I 1.22E-3 I 5.88E-3 I 4.78E-3 First Quarter % Second Quarter Third Quarter% Fourth Quarter% Annual Total %

of TS Limit %of TS Limit of TS Limit of TS Limit of TS Limit Nearest Vegetable Garden - NNE I ,P, T (ESE)

Critical Receptor (Highest Organ) I I 3.12E-4 I 1.91 E-4 I 2.49E-4 I 1.04E-3 I 8.94E-4 NOTE:

1 RECP Attachments 6, 7 and 8 47

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 11A RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS FIRST QUARTER, 2014 ON-SITE DOSE TO MEMBERS OF THE PUBLIC (SPECIAL INTEREST GROUPS)

External Dose Internal Dose Noble Gas lodines, Particulates, and Tritium Exposure Exposure Exposure Time Location Closest Dist. Whole Body Skin Ground Plane Inhalation (Hours)

Specific Activity (Sectors) (meters)

Police at Shooting Range SE 700 52.0 5.77E-5 8.42E-5 O.OOE+O 1.79E-4 Tour Participants (a) Simulator Bldg. s 310 1.00 7.56E-7 1.10E-6 O.OOE+O 2.35E-6 (b) Bio Lab SSE 460 1.50 1.13E-6 1.66E-6 O.OOE+O 3.52E-6 (c) Overlook E 210 0.25 5.26E-7 7.69E-7 O.OOE+O 1.63E-6 American Indians NW 200 24.0 2.09E-4 3.05E-4 O.OOE+O 6.48E-4 at Burial Grounds NNW 200 24.0 1.46E-4 2.13E-4 O.OOE+O 4.54E-4 Ranch Hands driving NW 250 0.25 1.46E-6 2.13E-6 O.OOE+O 4.52E-6 cattle around site NNW 350 0.25 5.58E-7 8.15E-7 O.OOE+O 1.73E-6 N 320 0.25 3.71 E-7 5.41E-7 O.OOE+O 1.15E-6 NNE 450 0.25 1.45E-7 2.12E-7 O.OOE+O 4.50E-7 NE 630 0.25 7.38E-8 1.08E-7 O.OOE+O 2.29E-7 NOTE: All doses are in mrem.

48

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 11B RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS SECOND QUARTER, 2014 ON-SITE DOSE TO MEMBERS OF THE PUBLIC (SPECIAL INTEREST GROUPS)

External Dose Internal Dose I Noble Gas lodines, Particulates, and Tritium I I

Exposure Exposure Exposure Time Specific Activity Location Closest Dist. Whole Body Skin Ground Plane Inhalation I

I (Hours) I (Sectors) (meters)

I Police at Shooting Range SE 700 52.0 1.03E-6 1.51 E-6 O.OOE+O 6.69E-5 Tour Participants (a) Simulator Bldg. s 310 1.00 1.35E-8 1.98E-8 O.OOE+O 8.78E-7 (b) Bio Lab SSE 460 1.50 2.03E-8 2.96E-8 O.OOE+O 1.32E-6 (c) Overlook E 210 0.25 9.42E-9 1.38E-8 O.OOE+O 6.11 E-7 I American Indians NW 200 24.0 3.74E-6 5.46E-6 O.OOE+O 2.42E-4 I at Burial Grounds NNW 200 24.0 2.62E-6 3.82E-6 O.OOE+O 1.70E-4 Ranch Hands driving NW 250 0.25 2.61 E-8 3.81 E-8 O.OOE+O 1.69E-6 cattle around site NNW 350 0.25 9.99E-9 1.46E-8 O.OOE+O 6.48E-7 N 320 0.25 6.64E-9 9.69E-9 O.OOE+O 4.30E-7 NNE 450 0.25 2.60E-9 3.79E-9 O.OOE+O 1.68E-7 I NE 630 0.25 1.32E-9 1.93E-9 O.OOE+O 8.56E-8 NOTE: All doses are in mrem.

49

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE11C RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS THIRD QUARTER, 2014 ON-SITE DOSE TO MEMBERS OF THE PUBLIC (SPECIAL INTEREST GROUPS)

External Dose Internal Dose Noble Gas lodines, Particulates, and Tritium Exposure Exposure Exposure Time Specific Activity Location Closest Dist. Whole Body Skin Ground Plane Inhalation (Hours)

(Sectors) (meters)

Police at Shooting Range SE 700 52.0 1.01 E-6 1.47E-6 O.OOE+O 7.05E-5 Tour Participants (a) Simulator Bldg. s 310 1.00 1.32E-8 1.92E-8 O.OOE+O 9.24E-7 (b) Bio Lab SSE 460 1.50 1.98E-8 2.89E-8 O.OOE+O 1.39E-6 (c) Overlook E 210 0.25 9.17E-9 1.34E-8 O.OOE+O 6.43E-7 American Indians NW 200 24.0 3.64E-6 5.31 E-6 O.OOE+O 2.55E-4 at Burial Grounds NNW 200 24.0 2.55E-6 3.72E-6 O.OOE+O 1.79E-4 Ranch Hands driving NW 250 0.25 2.54E-8 3.71E-8 O.OOE+O 1.78E-6 cattle around site NNW 350 0.25 9.73E-9 1.42E-8 O.OOE+O 6.82E-7 N 320 0.25 6.46E-9 9.43E-9 O.OOE+O 4.53E-7 NNE 450 0.25 2.53E-9 3.69E-9 O.OOE+O 1.77E-7 NE 630 0.25 1.29E-9 1.88E-9 O.OOE+O 9.02E-8 NOTE: All doses are in mrem.

50

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE 110 RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS FOURTH QUARTER, 2014 ON-SITE DOSE TO MEMBERS OF THE PUBLIC (SPECIAL INTEREST GROUPS)

External Dose Internal Dose Noble Gas lodines, Particulates, and Tritium Exposure Exposure Exposure Time Specific Activity Location Closest Dist. Whole Body Skin Ground Plane Inhalation (Hours)

(Sectors) (meters)

Police at Shooting Range SE 700 52.0 6.64E-5 9.69E-5 O.OOE+O 1.48E-4 Tour Participants (a) Simulator Bldg. s 310 1.00 8.70E-7 1.27E-6 O.OOE+O 1.94E-6 (b) Bio Lab SSE 460 1.50 1.31 E-6 1.91 E-6 O.OOE+O 2.91 E-6 (c) Overlook E 210 0.25 6.06E-7 8.85E-7 O.OOE+O 1.35E-6 American Indians NW 200 24.0 2.40E-4 3.51E-4 O.OOE+O 5.35E-4 at Burial Grounds NNW 200 24.0 1.68E-4 2.46E-4 O.OOE+O 3.74E-4 I Ranch Hands driving NW 250 0.25 1.68E-6 2.45E-6 O.OOE+O 3.73E-6 I

cattle around site NNW 350 0.25 6.42E-7 9.38E-7 O.OOE+O 1.43E-6 N 320 0.25 4.27E-7 6.23E-7 O.OOE+O 9.50E-7 NNE 450 0.25 1.67E-7 2.44E-7 O.OOE+O 3.71 E-7 NE 630 0.25 8.49E-8 1.24E-7 O.OOE+O 1.89E-7 NOTE: All doses are in mrem.

51

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 Revision of DCL-15-053)

DIABLO CANYON POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2014 TABLE11E RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS ANNUAL TOTAL, 2014 ON-SITE DOSE TO MEMBERS OF THE PUBLIC (SPECIAL INTEREST GROUPS)

External Dose Internal Dose Noble Gas lodines, Particulates, and Tritium Exposure Exposure Exposure Time Specific Activity Location Closest Dist. Whole Body Skin Ground Plane Inhalation (Hours)

(Sectors) (meters)

Police at Shooting Range SE 700 208.0 1.26E-4 1.84E-4 O.OOE+O 4.64E-4 Tour Participants (a) Simulator Bldg. s 310 4.00 1.65E-6 2.41 E-6 O.OOE+O 6.09E-6 (b) Bio Lab SSE 460 6.00 2.48E-6 3.62E-6 O.OOE+O 9.13E-6 (c) Overlook E 210 1.00 1.15E-6 1.68E-6 O.OOE+O 4.24E-6 American Indians NW 200 96.0 4.57E-4 6.67E-4 O.OOE+O 1.68E-3 at Burial Grounds NNW 200 96.0 3.20E-4 4.67E-4 O.OOE+O 1.18E-3 Ranch Hands driving NW 250 1 3.19E-6 4.65E-6 O.OOE+O 1.17E-5 cattle around site NNW 350 1 1.22E-6 1.78E-6 O.OOE+O 4.49E-6 N 320 1 8.11 E-7 1.18E-6 O.OOE+O 2.98E-6 NNE 450 1 3.17E-7 4.63E-7 O.OOE+O 1.17E-6 NE 630 1 1.61E-7 2.36E-7 O.OOE+O 5.94E-7 NOTE: All doses are in mrem.

52

Enclosure 2 PG&E Letter DCL-15-137 (12/4/15 revision of DCL-15-053)

VIII. Meteorological Data Meteorological Data (not included with 12/4/15 revision)

The hour-by-hour listing of wind speed, wind direction, atmospheric stability and precipitation is contained on compact disc with this submittal.

Compact Diskette Information Filename Sensitivity File Size Description NRC13 Non-SGI 1.3Mb Diablo Canyon Primary Meteorological Data Special Instructions: The CD-R media are read-only, 700MB compact diskettes.

53

Pacific Gas and Electric Company James M. Welsch Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 December 31 , 2015 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 PG&E Letter DCL-15-137 U.S. Nuclear Regulatory Commission 10 CFR 50.36a(a)(2)

ATIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Corrections to the 2014 Annual Radioactive Effluent Release Report

References:

1. . PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report," dated April29, 2015. (Accession Number ML15133A141)

Dear Commissioners and Staff:

Pacific Gas and Electric Company (PG&E) submitted the 2014 Annual Radioactive Effluent Release Report (ARERR) in Reference 1 in accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3 of the Diablo Canyon Power Plant (DCPP)

Technicaf Specifications.

Subsequently, three categories of errors were identified that impact the information reported in the 2014 ARERR. These errors have been entered into the DCPP corrective action program. As part of the corrective actions, DCPP is submitting , which includes details on the errors and the corresponding corrections to the 2014 ARERR. Enclosure 2 provides a copy of the revised 2014 ARERR. No regulatory limits were exceeded as a result of the correction of these errors.

PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

If you have any questions, please contact Mr. Clint Gans at (805) 545-3419.

Sincerely,

~d~

James M. Welsch A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Document Control Desk PG&E Letter DCL-15-137 December 31 , 2015 Page2 bnsm/4540/50815806 Enclosures cc: Diablo Distribution cc/encl: Penny Borenstein, San Luis Obispo County Health Officer Marc L. Dapas, NRC Region IV Administrator Kenneth A. Harris Jr., Executive Officer, CCRWQCB Siva P. Lingam, NRR Project Manager Bernice E. Minga, INPO Gonzalo Perez, Branch Chief, California Department of Public Health John P. Reynoso, Acting NRC Senior Resident Inspector A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure 1 PG&E Letter DCL-15-137 Enclosure 1 Diablo Canyon Power Plant Details on Corrections to the 2014 Annual Radioactive Effluent Release Report

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR) 12/4/15, Revision 1 Prepared by C. Gans Part A- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

A) Two gaseous effluent post-release reports that were prepared in June 2014 for information only to support Licensing Basis Verification Project were not canceled prior to submittal of the 2014 Annual Radioactive Effluent Release Report (ARERR) in April of 2015. Therefore, the hypothetical radionuclides and dose associated with these information-only post-releases were mistakenly included in the ARERR. Canceling the two information-only post release reports resulted in significant reductions in the values for several gaseous release parameters from second quarter of 2014 (See tables below). Liquid release parameters were not affected.

2014 ARERR Report Category Gaseous Effluent Parameter 2014 ARERR Value Corrected Value 1 Table Number Type 1A Gaseous Fission and Activation Second Quarter 5.89E+O 1.82E-2 Effluents- Gases Total Release (Ci)

Summation of All Releases Second Quarter Average Release Rate for Period 7.49E-1 2.32 E-3

_fj..JCi/second)

Second Quarter Percent of Technical Specification 2.24E-3 2.17E-5 Limit(% of TS limit) 1C Annual Total Release (Ci) 8.14E+O 2.26E+O Annual Average Release Rate for Period 2.58E-1 7.17E-2 (l-ICi/sec, Total)

Annual Percent of Technical Specification Limit 1.21 E-3 6.62E-4

(%of TS limit, Total) 2A Gaseous Nuclides Released Argon-41 (Ci) , Batch Mode, Second Quarter 1.36E+O 1.82E-2 Effluents- (Fission Gases)

Ground Level Releases Xenon-133 (Ci), Batch Mode, Second Quarter 2.89E+O MDA*

Xenon-133m (Ci), Batch Mode, Second Quarter 2.21 E-2 MDA*

Xenon-135 (Ci), Batch Mode, Second Quarter 1.47E+O MDA*

Xenon-135m (Ci), Batch Mode, Second Quarter 4.01 E-2 MDA*

Xenon-138 (Ci), Batch Mode, Second Quarter 1.08E-1 MDA*

Total for Period (Ci), Batch Mode, Second Quarter 5.89E+O 1.82E-2

below Minimum Detectable Activity 1

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR Report Category Gaseous Effluent Parameter 2014 ARERR Value Corrected Value Table Number Type 8B Radiation Dose Noble Gas Second Quarter Dose (mrad) 2.95E-3 1.34E-5 Due to the Gamma Air Dose Release of (at Site Boundary)

Radioactive Gaseous Effluents (Unit 2)

. Annual Total Dose (mrad) 4.79E-3 1.86E-3*

Noble Gas Second Quarter Dose (mrad) 1.96E-3 4.74E-6 Beta Air Dose

. . :, (at Site Boundary)

:* :*. Annual Total Dose (mrad) 2.61 E-3 6.61 E-4*

.* Iodine, Particulate, Second Quarter Dose (mrem) 8.44E-4 7.00E-5 Tritium Critical Receptor (Highest Organ)

(at Nearest Residence-

NNW)

- . Annual Total Dose (mrem) 1.49E-3 7.17E-4 Iodine, Particulate, Second Quarter Dose (mrem) 5.06E-5 1.43E-5**

Tritium Critical Receptor (Highest Organ)

(at Nearest Vegetable Garden-NNE)

L__

.. Annual Total Dose (mrem) 9.54E-5 1.34E-4**

Result also affected by change to First Quarter 2014 values as described in (B) below.

- Result also affected by correction of nearest ingestion receptor location as described in (C) below.

2

Enclosure 1 PG&E Letter DCL-15-137 Corrections to PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR Report Category Gaseous Effluent Type Parameter 2014 Corrected Table Number ARERR Value Value 10B Percent of Technical Noble Gas Second Quarter 5.89E-2 2.69E-4 Specification Limits Gamma Air Dose (% of TS limit) for Radioactive (at Site Boundary)

Gaseous Effluents I

I (Unit 2) I Annual Total Dose 4.79E-2 1.86E-2*

(% of TS limit)

Noble Gas Second Quarter Dose 1.96E-2 4.74E-5 Beta Air Dose (% of TS limit)

(at Site Boundary)

Annual Total Dose 1.31 E-2 3.31 E-3*

(% of TS limit)

... Iodine, Particulate, Tritium Second Quarter Dose 1.13E-2 9.34E-4 Critical Receptor (Highest (% of TS limit)

Organ)

(at Nearest Residence-NNW)

I Annual Total Dose 9.94E-3 4.78E-3 I

.. *. (% of TS limit)

Iodine, Particulate, Tritium Second Quarter Dose 6.75E-4 1.91 E-4**

Critical Receptor (Highest (% of TS limit)

Organ)

(at Nearest Vegetable Garden-NNE)

Annual Total Dose 6.36E-4 8.94E-4**

(%of TS limit)

Result also affected by change to First Quarter 2014 values as described in (B) below.

- Result also affected by correction of nearest ingestion receptor location as described in (C) below.

3

Enclosure 1 PG&E Letter DCL-15-137 Corrections t o PG&E Letter DCL-15-053, "2014 Annual Radioactive Effluent Release Report" (ARERR)

Part A (continued)- Gaseous effluent post-release reports created for information only were left open in Effluent Management System.

2014 ARERR, Table 11 B, Radiation Dose Due to Release of Radioactive Gaseous Effluents-Second Quarter On-Site Dose to Members of the Public-Special Interest Groups Special Interest Group and Location Gaseous Effluent Type Parameter 2014 ARERR Value Corrected Value Police at Shooting Range (SE) Noble Gas External Dose to Whole Body (mrem) 1.06E-4 1.03E-6

... .*. . **.* *. ... Skin Dose (mrem) 1.74E-4 1.51 E-6 Tour Participants at Simulator Building (S) Noble Gas External Dose to Whole Body (mrem)' 1.40E-6 1.35E-8

- ** *. *: . Skin Dose (mrem) 2.28E-6 1.98E-8 Tour Participants at Bio Lab (SSE) Noble Gas External Dose to Whole Body (mrem) 2.09E-6 2.03E-8 Skin Dose (mrem) 3.42E-6 2.96E-8 Tour Participants at Overlook (E) Noble Gas External Dose to Whole Body (mrem) 9.71E-7 9.42E-9

.* ,*: * .* .' .. Skin Dose (mrem) 1.59E-6 1.38E-8 American Indians at Burial Ground (NW) Noble Gas External Dose to Whole Body (mrem) 3.85E-4 3.74E-6

.. *: : :: Skin Dose (mrem) 6.29E-4 5.46E-6 American Indians at Burial Ground (NNW) Noble Gas External Dose to Whole Body (mrem) 2.70E-4 2.62E-6

. ... . Skin Dose (mrem) 4.40E-4 3.82E-6 Ranch Hands Driving Cattle Around Site (NW) Noble Gas External Dose to Whole Body (mrem) 2.69E-6 2.61 E-8 Skin Dose (mrem) 4.39E-6 3.81 E-8 Ranch Hands Driving Cattle Around Site (NNW) Noble Gas External Dose to Whole Body (mrem) 1.03E-6 9.99E-9

*. Skin Dose (mrem) 1.68E-6 1.46E-8 Ranch Hands Driving Cattle Around Site (N) Noble Gas External Dose to Whole Body (mrem) 6.84E-7 6.64E-9

.*.*. Skin Dose (mrem) 1.12E-6 9.69E-9 Ranch Hands Driving Cattle Around Site (NNE)