DCL-13-091, Submittal of Revision 21 to Updated Final Safety Analysis Report

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Submittal of Revision 21 to Updated Final Safety Analysis Report
ML13280A391
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 09/16/2013
From: Allen B
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML13280A390 List:
References
DCL-13-091
Download: ML13280A391 (9)


Text

PacificGas and ElectricCompany' Barry S. Allen Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 805.545.4888 September 16, 2013 Internal: 691.4888 Fax: 805.545.6445 PG&E Letter DCL-13-091 U.S. Nuclear Regulatory Commission 10 CFR 50.4 ATTN: Document Control Desk 10 CFR 50.54 Washington, DC *20555-0001 10 CFR 50.71 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plant Units 1 and 2 Updated Final Safety Analysis Report, Revision 21

Dear Commissioners and Staff:

Pursuant to 10 CFR 50.71(e), 10 CFR 50.54(a)(3) and 10 CFR 50.4(b)(6), Pacific Gas and Electric Company hereby submits the Diablo Canyon Power Plant (DCPP)

"Final Safety Analysis Report Update" (UFSAR), Revision 21. DCPP UFSAR, Revision 21, represents the status of DCPP Units 1 and 2 through March 23, 2013.

As a minimum, DCPP UFSAR, Revision 21, reflects: (1) changes made under the provisions of 10 CFR 50.59, which are identified in Enclosure 1; and (2) changes made as a result of license amendments, which are identified in Enclosure 2. contains the DCPP UFSAR, Revision 21, on one compact disc (CD),

labeled "Diablo Canyon Power Plant FSAR Update, Revision 21," dated September 2013. The contents are in Adobe Acrobat portable document format.

A copy of this CD is being provided to the Regional Administrator, Region IV, the DCPP NRR Project Manager, and the DCPP NRC Senior Resident Inspector.

The CD contains the following file:

File Name File Size (Mb) 01 DCPP UFSAR R21.pdf 39.8 There are no new or revised regulatory commitments as defined by Nuclear Energy Institute 99-04, "Guidelines for Managing NRC Commitment Changes," dated July 1999, in this submittal.

If you have any questions regarding this submittal, please contact Mr. Tom Baldwin at (805) 545-4720.

rjýs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance I?

Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek

Document Control Desk PG&E Letter DCL-13-091 September 16, 2013 NP] Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on September 16, 2013.

Sincerely, Barry S. Allen Site Vice President Enclosures cc: Diablo Distribution cc:/enc. Thomas R. Hipschman, NRC Senior Resident Inspector Jennivine K. Rankin, NRR Project Manager Steven A. Reynolds, Acting NRC Region IV Administrator A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway i Comanche Peak e Diablo Canyon

  • Palo Verde
  • San Onofre
  • Wolf Creek

PG&E Letter DCL-13-091 Enclosure 1 Changes Incorporated into the Diablo Canyon Power Plant Final Safety Analysis Report Update, Revision 21 Resulting from 10 CFR 50.59 Evaluations

PG&E Letter DCL-13-091 Enclosure 1 Changes Incorporated into the Diablo Canyon Power Plant Final Safety Analysis Report Update, Revision 21 Resulting from 10 CFR 50.59 Evaluations Numberý1 ) Description 2009-004 DDPC*2 1000000120: Revise Figure 5.3-1 for Reactor Coolant System Hot Leg, Cold Leg, and Average Reactor Coolant Loop Temperature (Unit 1 and Unit 2).

2010-009 DDP 1000000290 and 1000000291: Upgrade Safety Parameter Display System (SPDS). The SPDS was upgraded to improve reliability and security, and to resolve obsolescence issues (Unit 1 and Unit 2).

2010-025 DDP 1000000321: Auxiliary Building Control Board Upgrade-Phase 4B, Digital Upgrade. The upgrade integrates the temperature monitoring system at the auxiliary building control board into the new digital control system (Unit 1 and Unit 2).

2011-010 DDP 1000000237: Replace the Unit 1 Westinghouse 7100 Process Control System (PCS). The Unit 1 7100 PCS was replaced with a new programmable logic controller (PLC)-based system.

2011-014 Calculation 9000019736: Addition of Time Critical Operator Action (TCOA). Post Loss-of-Coolant design condition limits residual heat removal (RHR) pump time on recirculation flow without component cooling water cooling to RHR heat exchangers. This new design condition required the addition of a TCOA that was implemented in the emergency operating procedure EOP E-1 (Unit 1 and Unit 2).

2011-015 DDP 1000000390: Containment Polar Gantry Crane Modifications.

Upgraded antiquated design with new controls, motors, brakes, gearboxes, and associated modifications to the electrical power supply and circuits (Unit 2) to improve reliability.

2012-006 DDP 1000024850: Relocate Intake Facility Gantry Crane Anchored Location (Unit Common). The "not-in-use" stored position for the intake gantry crane was moved to a location approximately 20 feet toward the south.

2012-007 DDP 1000024811: Containment Polar Gantry Crane Modifications.

Upgraded antiquated crane design with new controls, motors, brakes, gearboxes, and associated modifications to the electrical power supply and circuits (Unit 2) to improve reliability.

I

PG&E Letter DCL-13-091 Enclosure I 2012-009 Class 1E Battery Qualification: The standard for performing the qualification for Class 1 E replacement batteries was changed from IEEE 535-1979, "IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations," to IEEE 535-1986 (Unit I and Unit 2).

2012-013 DDP 1000000501: Replace the Unit 2 Westinghouse 7100 PCS.

The Unit 2 7100 PCS was replaced with a new PLC-based system.

2012-033 DDP 1000024853: Remove the Unit 1 Auxiliary Building Heating Coils and Support Equipment. Removed the heating coils and associated support equipment from the Unit 1 auxiliary building heating, ventilating, and air conditioning system.

2012-034 DDP 1000000191: Remove the Unit 2 Auxiliary Building Heating Coils and Support Equipment. Removed the heating coils and associated support equipment from the Unit 2 auxiliary building heating, ventilating, and air conditioning system.

2012-039 Use of SAP2000 Computer Program. Structural analysis program SAP2000 was used to supplement the GT STRUDL (Georgia Tech Structural Design Language) for seismic analysis of the containment annulus structure (Unit 2).

(1) 10 CFR 50.59 Licensing Basis Impact Evaluation Number (2) DDP is the prefix for the SAP Design Change Package number (typical) 2

PG&E Letter DCL-13-091 Enclosure 2 Changes Incorporated into the Diablo Canyon Power Plant Final Safety Analysis Report Update, Revision 21 Resulting From License Amendments

PG&E Letter DCL-13-091 Enclosure 2 Changes Incorporated into the Diablo Canyon Power Plant Final Safety Analysis Report Update, Revision 21 Resulting From License Amendments Unit I LA Unit 2 LA Description 211 213 Revision to Technical Specification 3.8.1, "AC Sources -

Operating," to Incorporate TSTF-163, Revision 2 (TAC Nos. ME5939 AND ME5940).

212 214 Revision to Technical Specification 3.7.1, "Main Steam Safety Valves (MSSVs)," and Final Safety Analysis Report Update (TAC Nos. ME5713 and ME5714).

213 215 Revision to Technical Specification 3.7.10, "Control Room Ventilation System (CRVS)" (Emergency Circumstances) (TAC Nos. MF0317 and MF0318).

214 216 Change to Final Safety Analysis Report Update to Allow Use of Beacon Core Monitoring and Operations Support System (TAC Nos. ME7803 and ME7804).

PG&E Letter DCL-13-091 Enclosure 3 Compact Disc, Diablo Canyon Power Plant Final Safety Analysis Report Update, Revision 21

PG&E Letter DCL-13-091 Enclosure 3 Compact Disc, Diablo Canyon Power Plant Final Safety Analysis Report Update, Revision 21 w t r ,-*