ML12345A379

Diablo Canyon, Units 1 and 2, Issuance of Amendment Nos. 214 and 216, Revise Final Safety Analysis Report Update Section 4.3.2.2 to Allow Use of Beacon Power Distribution Monitoring System (TAC Nos. ME7803 and ME7804)

ML12345A379
Person / Time
Site:	Diablo Canyon
Issue date:	01/09/2013
From:	Joseph Sebrosky Plant Licensing Branch IV
To:	Halpin E D Pacific Gas & Electric Co
Sebrosky J M
References
TAC ME7803, TAC ME7804
Download: ML12345A379 (15)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 9, 2013 Mr. Edward D. Halpin Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: CHANGE TO FINAL SAFETY ANALYSIS REPORT UPDATE TO ALLOW THE USE OF BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM (TAC NOS. ME7803 AND ME7804)

Dear Mr. Halpin:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 214 to Facility Operating License No. DPR-80 and Amendment No. 216 to Facility Operating License No. DPR-82 for the Diablo Canyon Power Plant (DCPP), Units 1 and 2, respectively.

The amendments consist of changes to the Final Safety Analysis Report Update (FSARU) in response to your application dated January 5,2012. Specifically, the amendments revise DCPP FSARU Section 4.3.2.2, "Power Distribution," to allow the use of the Westinghouse Electric Company LLC's Best Estimate Analyzer for the Core Operations-Nuclear (BEACON) Power Distribution Monitoring System methodology as described in WCAP-12472-P-A, Addendum 1-A, "BEACON Core Monitoring and Operation Support System," January 2000. A copy of the related Safety Evaluation is enclosed.

The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. roject Manager Docket Nos. 50-275 and 50-323

Enclosures:

1. Amendment No. 214 to DPR-80 2. Amendment No. 216 to DPR-82 3. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 PACIFIC GAS AND ELECTRIC DOCKET NO. DIABLO CANYON NUCLEAR POWER PLANT, UNIT AMENDMENT TO FACILITY OPERATING Amendment No. 214 License No. DPR-80 The Nuclear Regulatory Commission (the Commission) has found that The application for amendment by Pacific Gas and Electric Company (the licensee), dated January 5,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

-Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating license No. DPR-BO is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 214, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

In addition, by Amendment No. 214, the license is amended to authorize revision of the Final Safety Analysis Report Update (FSARU), as set forth in the application dated January 5, 2012. The licensee shall update the FSARU to incorporate the BEACON Power Distribution Monitoring System methodology, as described in the licensee's application dated January 5, 2012, and the NRC staff's safety evaluation enclosed with this amendment, and shall submit the revised description authorized by this amendment with the next update of the FSARU. This license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.

The FSARU changes shall be implemented in the next periodic update to the FSARU in accordance with 10 CFR 50.71(e).

FOR THE NUCLEAR REGULATORY COMMISSION t:

Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. DPR-BO Date of Issuance:

January 9, 2013 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 PACIFIC GAS AND ELECTRIC DOCKET NO. DIABLO CANYON NUCLEAR POWER PLANT, UNIT AMENDMENT TO FACILITY OPERATING Amendment No. 216 License No. DPR-82 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Pacific Gas and Electric Company (the licensee), dated January 5,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 2

-Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating license No. DPR-82 is hereby amended to read as follows: Technical Specifications (SSER 32, Section 8)* and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 216, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

In addition, by Amendment No. 216, the license is amended to authorize revision of the Final Safety Analysis Report Update (FSARU), as set forth in the application dated January 5, 2012. The licensee shall update the FSARU to incorporate the BEACON Power Distribution Monitoring System methodology, as described in the licensee's application dated January 5, 2012, and the NRC staff's safety evaluation enclosed with this amendment, and shall submit the revised description authorized by this amendment with the next update of the FSARU. This license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.

The FSARU changes shall be implemented in the next periodic update to the FSARU in accordance with 10 CFR 50.71(e).

FOR THE NUCLEAR REGULATORY COMMISSION , J,A L4 Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating license No. DPR-82 Date of Issuance:

January 9. 2013 ATTACHMENT TO LICENSE AMENDMENT NOS. 214 AND TO FACILITY OPERATING LICENSE NOS. DPR-80 AND DOCKET NOS. 50-275 AND Replace the following pages of the Facility Operating license Nos. DPR-80 and DPR-82 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Facility Operating license No. DPR-80 REMOVE INSERT Facility Operating license No. DPR-82 REMOVE INSERT Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This License shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level The Pacific Gas and Electric Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% rated power) in accordance with the conditions specified herein. Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 214, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Initial Test Program The Pacific Gas and Electric Company shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Pacific Gas and Electric Company's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval.

Major modifications are defined as: Elimination of any test identified in Section 14 of PG&E's Final Safety Analysis Report as amended as being essential; Amendment No. 214 Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This License shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level The Pacific Gas and Electric Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% rated power) in accordance with the conditions specified herein. Technical Specifications (SSER 32, Section 8)* and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 216, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Initial Test Program (SSER 31, Section 4.4.1) Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change. *The parenthet ical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No. 216 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 214 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 216 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-275 AND 50-323

1.0 INTRODUCTION

By application dated January 5, 2012 (Reference 1), Pacific Gas and Electric Company (PG&E, the licensee) requested changes to the Final Safety Analysis Report Update (FSARU) for the Diablo Canyon Power Plant (DCPP), Unit Nos. 1 and 2. Specifically, the amendments would revise the DCPP Units 1 and 2 FSARU Section 4.3.2.2, "Power Distribution," to allow the use of the Best Estimate Analyzer for the Core Operations-Nuclear (BEACON) Power Distribution Monitoring System methodology, as described in Westinghouse Electric Company LLC's WCAP-12472-P-A, Addendum 1-A, "BEACON Core Monitoring and Operation Support System," January 2000 (Reference 2).

2.0 REGULATORY EVALUATION

The BEACON core monitoring system methodology was approved by the U.S. Nuclear Regulatory Commission (NRC) for use at DCPP, Unit Nos. 1 and 2, on March 31, 2004, via Amendment Nos. 164 and 166, respectively, for monitoring and determining the dimensional core power distribution (Reference 3). This calculation was performed with the NRC-approved Westinghouse SPNOVA nodal method (Reference 4). SPNOVA employs a single effective neutron fast group calculation to determine the global neutron flux solution, and then uses a local correlation to determine thermal flux and power distribution (Reference 4). SPNOVA is a simplified neutron diffusion equation code which was used due to limited computational power of early vintage work stations.

The licensee, as a result of enhanced capability workstations and improvements in numerical solution technique of nodal expansion method, proposes to upgrade the BEACON core monitoring system to use the three-dimensional advanced nodal code (ANC) neutronic model Enclosure 3

-2 (Reference

2) in WCAP-12472-P-A, Addendum 1-A. Because the licensee determined that adopting the BEACON Power Distribution Monitoring System methodology required NRC approval under 10 CFR 50.59, the licensee submitted this license amendment request (LAR) pursuant to 10 CFR 50.90. The regulations in 10 CFR 50.36 specify requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in five categories related to station operation, such as, safety limits (SLs), limiting safety system settings (LSSSs), limiting conditions for operation (LCOs), design features, and administrative controls.

Under 10 CFR 50.36(c) (2)(ii), an LCO must be included in the TS for any item that meets anyone of the criteria listed in 10 CFR 50.36(c)(2)(ii) (A) through (D). The Power Distribution Monitoring System instrumentation does not meet any of the Criteria of 10 CFR 50.36(c)(2)(ii) for inclusion in the TS. Therefore, PG&E has included the Power Distribution Monitoring System instrumentation requirements in equipment control guidelines (ECGs) which are controlled by PG&E in accordance with 10 CFR 50.59. The NRC staff reviewed the license amendment request to evaluate the applicability of the proposed methodology in compliance with the requirements of the following General Design Criteria (GDC) specified in Appendix A to 10 CFR, Part 50. GDC-13, "Instrumentation and Control':

Instrumentation shall be provided to monitor variables and systems over their antiCipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges. The NRC staff also independently reviewed the license amendment request against the requirements of 10 CFR 50.59, "Changes, tests, and experiments." 3.0 TECHNICAL EVALUATION

3.1 Background

and Methodology PG&E has been using the BEACON system to augment the functional capability of the flux mapping system for the purpose of core power surveillances using the WCAP-12472-P-A methodology (Reference

5) since 2004 (Reference 3). The 2004 license amendment included a revision of the applicable TSs and included the original BEACON WCAP-12472-P-A as a methodology referenced in the TS Bases. PG&E proposes to add the version of BEACON described in WCAP-12472-P-A, Addendum 1-A, to the FSARU and TS Bases. The BEACON system was originally developed by Westinghouse to monitor core power distribution in Westinghouse reactors.

The monitoring operation was based largely on, and tied together by, the use of the NRC-approved three-dimensional neutronics analysis code SPNOVA (Reference 4). SPNOVA's primary role in BEACON was to generate detailed power distribution

-3 and compare to core limits (e.g., departure from nucleate boiling) on a nearly continuous basis and supply that information to the operator.

SPNOVA was calibrated periodically using the incore neutron flux measurement system to provide details of the power distribution and calibrated frequently using the exit thermocouples for radial updating and the excore neutron detectors for axial updating.

The NRC staff approved the changes involving the adoption of the BEACON system (Reference

3) consistent with WCAP-12472-P-A.

These changes were (1) TS 3.1.7, "Rod Position Indication," in which the verification of the rod position was revised to use core power distribution measurement information, (2) surveillance requirement (SR) 3.2.1.3, Heat Flux Hot Channel Factor, was revised to require verification by power distribution measurements, (3) SR 3.2.4, Quadrant Power Tilt Ratio (QPTR) was revised to use the core power distribution measurements information, and (4) SR 3.3.1.3 and SR 3.3.1.6, Reactor Trip System Instrumentation was revised to require incore power distribution measurements.

All these revisions allowed for the use of either the Power Distribution Monitoring System or the movable incore detectors (MIDS) for performance of the surveillances.

The BEACON monitoring system that used the SPNOVA neutronic methodology employed node-per-assembly (radial) representation to achieve the rapid running times required by hardware platforms available in the late 1980s. Recent workstation advancements, coupled with improvements in numerical solution techniques of the nodal expansion method, have permitted the optional use of the ANC neutronic code in the BEACON system while maintaining BEACON functionality.

The NRC staff reviewed the Addendum 1-A to WCAP-12472-P-A and approved the use of PHOENIX-P/ANC code (Reference 6). Addendum 1-A to WCAP-12472-P-A incorporates additional features into BEACON system, such as (1) use of self-powered detectors and (2) use of the three-dimensional ANC neutronic model code. However, the incore instrumentation system at DCPP is composed of thermocouples and movable fission chamber detectors positioned in guide tube thimbles that run the length of selected fuel assemblies.

The MIDS provides assembly-by-assembly core power distribution.

The PHOENIXIANC code is a licensed methodology that is supported by many critical experiments and plant data. The method is based on neutron physics and avoids the use of empirical correlations and data. Another advantage is that this method can be applied over a wider range of design and operating conditions.

3.2 Implementation

of WCAP-12472-P-A Addendum 1-A Methodology at DCPP DCPP employs two methods for calculating core power distributions, either BEACON or MIDS. Either BEACON or MIDS can be used to satisfy core power peaking TS SRs. The BEACON system provides an on-line monitoring of the reactor core using current plant instrumentation.

Excore neutron detectors and core exit thermocouples are used with a three-dimensional calculated power distribution on a nearly continuous basis. The generation of three-dimensional power distribution involves periodic calibration of BEACON using the MIDS, a three-dimensional nodal simulation of the core, and frequent processing of excore neutron detector and core exit thermocouple readings.

The BEACON system generated MIDS flux map data results can be compared to TS limits for surveillance.

BEACON can also be used to provide core reactivity calculations such as estimated critical conditions, shutdown margin calculations in order to meet TS requirements, and can provide load follow simulations.

The current licensing basis for BEACON methodology at DCPP is WCAP-12472-P-A.

The three conditions specified by NRC staff in the safety evaluation for Reference 5 had been fully addressed by the licensee.

The TSs were previously revised as part of implementation of the DCPP license amendments that allowed use of the BEACON system described in WCAP-12472-P-A (Reference 3). This license amendment request for implementation of WCAP-12472-P-A, Addendum 1-A, does not require any additional changes for the power distribution monitoring system and TS monitoring system. Since the BEACON monitoring system is statistical in nature, the determination of the measured peaking factor is affected by such things as the detector measurement variability, the number and layout of detectors, interpolation techniques, and any differences between predicted and true power distribution.

Westinghouse implemented the BEACON system uncertainty using a statistical method in which the detector behavior is simulated on the basis of measurement variability statistics (Reference 5). Details of the calculations for the bounding 95/95 upper tolerance limit in the fuel assembly power and peak node power, the total uncertainty in the assembly power, the total uncertainty in the peak node power, the total hot channel F measurement uncertainty, the total hot channel Fa measurement uncertainty are detailed in References 2 and 5. The NRC staff concludes that the proposed changes are acceptable and would permit the licensee to revise the FSARU Section 4.3.2.2, "Power Distribution." Implementation of the upgrade of BEACON requires that the plant-cycle-specific components shall be determined on a plant-specific basis and confirmed each cycle. The NRC staff has determined that in order to ensure that the assumptions made in BEACON uncertainty analyses remain valid, the uncertainty components will require re-evaluation when BEACON is applied to plant or core designs each cycle of operation.

3.3 ProposedTechnical

Specification Bases Changes The licensee also proposed changes to the TS Bases, a licensee-controlled document, to support the proposed changes to the FSARU. These changes included changes to TS Bases Sections 3.1.7, "Rod Position Indication;" 3.2.1, "Heat Flux Hot Channel Factor" (Fa(Z)), 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor" (F N 3.2.4, "Quadrant Power Tilt Ratio" (QPTR); and 3.3.1, "Reactor Trip System Instrumentation" (RTS), to add a new reference for the Westinghouse BEACON Core Monitoring and Operation Support System methodology contained in WCAP-12472-P-A, Addendum 1-A. The NRC staff has reviewed the proposed TS Bases changes and concludes that they are consistent and supportive of the proposed FSARU changes. Thus, the NRC staff has no comments.

3.4 NRC Staff Conclusion

The NRC staff has reviewed the license amendment request to evaluate the upgrade of BEACON core monitoring and operations support system to use the three-dimensional ANC in place of SPNOVA code. Based on the review, the NRC staff has determined that the licensee provided sufficient information to support the proposed changes. The NRC staff concludes that the licensee would comply with the processes and procedures set forth in the topical reports (References 2 and 5) while the update of BEACON is implemented at DCPP. Furthermore, because the changes result in a departure from a method of evaluation described in the FSARU used in establishing the design bases, the staff concludes that the change to the FSARU to allow the use of BEACON core monitoring and operations meets the requirements of 10 CFR 50.59(c)(2}(viii}

and, therefore, is acceptable. STATE CONSULTATION In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendments.

The State official had no comments. ENVIRONMENTAL CONSIDERATIONS The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendments involve no Significant hazards consideration and there has been no public comment on such finding published in the Federal Register on May 15,2012 (77 FR 28633). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9}.

Pursuant to 10 CFR 51.22(b}, no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments. CONCLUSION The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. REFERENCES Becker, J. R., Pacific Gas and Electric Company, letter to U.S. Nuclear Regulatory Commission, "License Amendment Request 12-01, Revision to the Updated Final Safety Analysis Report Section 4.3.2.2, "Power Distribution;" and Technical Specification Bases 3.1.7, "Rod Position Indication;" 3.2.1, "Heat Flux Hot Channel Factor (Fo(Z>>, "3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor" (F N t.H); 3.2.4, "Quadrant Power Tilt Ratio" (QPTR); and 3.3.1, "Reactor Trip. System Instrumentation (RTS)", dated January 5, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120060162).

-6 Westinghouse Electric Company LLC, WCAP-12472-P-A, Addendum 1-A, BEACON Core Monitoring and Operations Support System," Westinghouse Electric Company, January 2000 (proprietary);

nonproprietary version designated as WCAP-12472-A, Addendum 1-A (ADAMS Accession No. ML003678347). Shukla, G. S., U.S. Nuclear Regulatory Commission, letter to Gregory M. Rueger, Pacific Gas and Electric Company, "Diablo Canyon Power Plant, Unit No.1 (TAC No. MB9640) and Unit No.2 (TAC No. MB9641) -Issuance of Amendment Re: Use of a Power Distribution Monitoring System," dated March 31,2004 (ADAMS Accession No. ML040920245). Westinghouse Electric Company LLC, WCAP-12394, "SPNOVA-A Multidimensional Static and Transient Computer Program for PWR Analysis," Westinghouse Electric, September 1989 (proprietary). Westinghouse Electric Company LLC, WCAP-12472-P-A, "BEACON Core Monitoring and Operations Support System, "Westinghouse Electric Company, August 1994 (proprietary) . Westinghouse Electric Company LLC, WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," Westinghouse Electric Corporation, June 1998 (proprietary).

Principal Contributor:

Mathew M. Panicker January 9, 2013 January 9, 2013 Mr. Edward D. Halpin Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: CHANGE TO FINAL SAFETY ANALYSIS REPORT UPDATE TO ALLOW THE USE OF BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM (TAC NOS. ME7803 AND ME7804)

Dear Mr. Halpin:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 214 to Facility Operating License No. DPR-80 and Amendment No. 216 to Facility Operating License No. DPR-82 for the Diablo Canyon Power Plant (DCPP), Units 1 and 2, respectively.

The amendments consist of changes to the Final Safety Analysis Report Update (FSARU) in response to your application dated January 5, 2012. Specifically, the amendments revise DCPP FSARU Section 4.3.2.2, "Power Distribution," to allow the use of the Westinghouse Electric Company LLC's Best Estimate Analyzer for the Core Operations-Nuclear (BEACON) Power Distribution Monitoring System methodology as described in WCAP-12472-P-A, Addendum 1-A, "BEACON Core Monitoring and Operation Support System," January 2000. A copy of the related Safety Evaluation is enclosed.

The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. Sincerely.

IRA! Joseph M. Sebrosky, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323

Enclosures:

1. Amendment No. 214 to DPR-80 2. Amendment No. 216 to DPR-82 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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