ZS-2010-0329, Submittal of Defueled Safety Analysis Report Update, Revision 6, Report of Changes, Tests and Experiments

Submittal of Defueled Safety Analysis Report Update, Revision 6, Report of Changes, Tests and Experiments

ML102780217
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	10/01/2010
From:	Tramm T ZionSolutions
To:	Document Control Desk, NRC/FSME
References
ZS-2010-0329
Download: ML102780217 (37)

Text

ZIONSOLUTIONSLLC An EnergySolutions Company 10 CFR 50.4(b)(6) 10 CFR 50.71(e) 10 CFR 50.59(d)(2)

ZS-2010-0329 October 1,2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Zion Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304

Subject:

Submittal of Defueled Safety Analysis Report Update, Revision 6 Report of Changes, Tests and Experiments

References:

(1) Exelon Generation Company, LLC (EGC) letter, "Submittal of Defueled Safety Analysis Report Update," dated October 2, 2008 In accordance with the requirements of 10 CFR 50.71, "Maintenance of records, making of reports," paragraph (e), ZionSolutions, LLC (ZS) is submitting Revision 6 of the Defueled Safety Analysis Report (DSAR) for the Zion Nuclear Power Station (ZNPS). In accordance with 10 CFR 50.71 (e)(4), the DSAR update is being submitted within 24 months of the previous ZNPS DSAR revision which was submitted in Reference (1).

The changes to the DSAR reflect administrative changes (i.e., editorial and DSAR text changes) and plant design changes. Revision 6 includes changes made from June 2009, through September 2010. We have evaluated the DSAR changes and determined the changes screened out as not requiring an evaluation under 10 CFR 50.59. contains a summary of the DSAR changes. Attachment 2 contains page change instructions. Attachment 3 contains the update to the ZNPS DSAR. As required by 10 CFR 50.71(e), this attachment consists of replacement pages to be inserted the DSAR.

Changes to the DSAR are indicated by revision bars.

ki ~kno 101 Shiloh Boulevard

• Zion, IL 60099 224.789.4016

• Fax 224.789.4008

October 1, 2010 U.S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.59, "Changes, tests, and experiments," paragraph (d)(2), a report of changes, tests, and experiments, including a summary of the 10 CFR 50.59 evaluation of each change is also required to be submitted on a biennial basis. In Reference (1), the previous ZNPS 10 CFR 50.59 report was submitted. There were no 10 CFR 50.59 evaluations performed for ZNPS in the reporting period from September 2008 through August 2010 and therefore, a summary of evaluations is not required to be submitted for this reporting period.

As Director, Regulatory Affairs & QA, I certify that the information in this submittal accurately presents changes made since the previous submittals necessary to reflect information and analyses submitted to the NRC or prepared in accordance with NRC requirements.

Should you have any questions concerning this letter, please contact Jim Ashley at (847) 379-2978.

Respectfully, Tom R. Tramm Director, Regulatory Affairs & QA ZionSolutions, LLC : Summary of Changes : Page Change Instructions : ZNPS DSAR Revision 6

ATTACHMENT I Changes Made to the DSAR But Not Previously Submitted Pages Description of Change Page 3-55, Delete references to Unit 2 Main Power Transformers and Unit Figure 3-45 Auxiliary Transformer which have been physically removed.

Pages, 3-50, 3-52a, Eliminate discussion of Fuel Building ventilation system and 3-60, 4-13, Figures associated effluent radiation monitors since the Fuel Building has 3-41, 3-42, 3-42A, been reconnected to the Auxiliary Building ventilation system.

Table 4-3 Page 3-47, Figure Revise system description to reflect Service Water Booster Pump 3-40 supply isolation to traveling screens and copper injection system.

Pages 1-1, 1-4, 1-5, Update document to reflect license transfer from Exelon 1-6, 1-9, 2-1, 3-4, 4- Generation Company (EGO) to Zion Solutions (ZS).

1,4-3, 4-5, 6-1,6-4, 6-5

ATTACHMENT 2 PAGE CHANGE INSTRUCTIONS To perform the October 2010 Zion Defueled Safety Analysis Report (DSAR) update, please remove the existing pages and insert pages dated October 2010 as follows:

SECTION REMOVE INSERT List of Effective Pages LOEP-2 LOEP-2 List of Effective Pages LOEP-4 LOEP-4 List of Effective Pages LOEP-5 LOEP-5 List of Effective Pages LOEP-6 LOEP-6 List of Effective Pages LOEP-7 LOEP-7 Master Table of Contents 3-v 3-v Chapter 1 1-1 1-1 Chapter 1 1-4 1-4 Chapter 1 1-5 1-5 Chapter 1 1-6 1-6 Chapter 1 1-9 1-9 Chapter 2 2-1 2-1 Chapter 3 Table of Contents 3-v 3-v Chapter 3 3-4 3-4 Chapter 3 3-47 3-47 Chapter 3 3-50 3-50 Chapter 3 3-52a 3-52a Chapter 3 3-55 3-55 Chapter 3 3-60 3-60 Chapter 3 Figure 3-40 Figure 3-40 Chapter 3 Figure 3-41 Figure 3-41 Chapter 3 Figure 3-42 Figure 3-42 Chapter 3 Figure 3-42A Figure. 3-42A Chapter 3 Figure 3-45 Figure 3-45 Chapter 4 4-1 4-1 Chapter 4 4-3. 4-3 Chapter 4 4-5 4-5 Chapter 4 4-13 4-13 Chapter 4 Table 4-3 Table 4-3 Chapter 6 6-1 6-1 Chapter 6 6-4 6-4 Chapter 6 6-5 6-5

ATTACHMENT 3 ZION NUCLEAR POWER STATION DEFUELED SAFETY ANALYSIS REPORT REVISION 6

ZION STATION DSAR LIST OF EFFECTIVE PAGES PAGE DATE PAGE DATE Controlled Copy Cover OCTOBER 2002 Figure 1-8 AUGUST 1998 Sheet Figure 1-9 AUGUST 1998 List of Effective Pages Tab Figure 1-10 AUGUST 1998 LOEP-2 OCTOBER 2010 Figure 1-11 AUGUST 1998 LOEP-3 OCTOBER 2000 Figure 1-12 OCTOBER 2000 LOEP-4 OCTOBER 2010 Figure 1-13 AUGUST 1998 LOEP-5 OCTOBER 2010 Figure 1-14 OCTOBER 2000 LOEP-6 OCTOBER 2010 Figure 1-15 AUGUST 1998 LOEP-7 OCTOBER 2010 Figure 1-16 AUGUST 1998 Master Table of Contents Tab Figure 1-17 AUGUST 1998 1-i AUGUST 1998 Chapter 2 Tab 2-i AUGUST 1998 2-i AUGUST 1998 2-ii AUGUST 1998 2-ii AUGUST 1998 34 AUGUST 1998 2-iii AUGUST 1998 3-ii OCTOBER 2002 2-iv AUGUST 1998 3-iii AUGUST 1998 2-v AUGUST 1998 3-iv OCTOBER 2000 2-1 OCTOBER 2010 3-v OCTOBER 2010 2-2 AUGUST 1998 4-i AUGUST 1998 2-3 AUGUST 1998 4-ii OCTOBER 2004 2-4 AUGUST 1998 5-i AUGUST 1998 2-5 AUGUST 1998 6-i OCTOBER 2006 2-6 AUGUST 1998 7-i OCTOBER 2000 2-7 AUGUST 1998 Chapter I Tab 2-8 OCTOBER 2000 1-4 AUGUST 1998 2-9 OCTOBER 2000 1-ii AUGUST 1998 2-10 AUGUST 1998 1-iii AUGUST 1998 2-11 AUGUST 1998 1-1 OCTOBER 2010 2-12 AUGUST 1998 1-2 AUGUST 1998 2-13 AUGUST 1998 1-3 OCTOBER 2002 2-14 AUGUST 1998 1-4 OCTOBER 2010 2-15 AUGUST 1998 1-5 OCTOBER 2010 2-16 AUGUST 1998 1-6 OCTOBER 2010 2-17 AUGUST 1998 1-7 OCTOBER 2000 2-18 AUGUST 1998 1-8 AUGUST 1998 2-19 AUGUST 1998 1-9 OCTOBER 2010 2-20 AUGUST 1998 Table 1-1 (1) AUGUST 1998 2-21 AUGUST 1998 Figure 1-1 AUGUST 1998 2-22 AUGUST 1998 Figure 1-2 AUGUST 1998 2-23 AUGUST 1998 Figure 1-3 AUGUST 1998 2-24. AUGUST 1998 Figure 1-4 AUGUST 1998 2-25 AUGUST 1998 Figure 1-5 AUGUST 1998 2-26 AUGUST 1998 Figure 1-6 AUGUST 1998 2-27 AUGUST 1998 Figure 1-7 OCTOBER 2000 Table 2-1 (1) AUGUST 1998

• LOEP-2 OCTOBER 2010

ZION STATION DSAR LIST OF EFFECTIVE PAGES PAGE DATE PAGE DATE 2C-17 AUGUST 1998 2C-61 AUGUST 1998 2C-18 AUGUST 1998 2C-62 AUGUST 1998 2C-19 AUGUST 1998 2C-63 AUGUST 1998 2C-20 AUGUST 1.998 2C-64 AUGUST 1998 2C-21 AUGUST 1998 2C-65 AUGUST 1998 2C-22 AUGUST 1998 2C-66 AUGUST 1998 2C-23 AUGUST 1998 2C-67 AUGUST 1998 2C-24 AUGUST 1998 2C-68 AUGUST 1998 2C-25 AUGUST 1998 2C-69 AUGUST 1998 2C-26 AUGUST 1998 2C-70 AUGUST 1998 2C-27 AUGUST 1998 2C-71 AUGUST 1998 2C-28 AUGUST 1998 2C-72 AUGUST 1998 2C-29 AUGUST 1998 2C-73 AUGUST 1998 2C-30 AUGUST 1998 2C-74 AUGUST 1998 2C-31 AUGUST 1998 2C-75 AUGUST 1998 2C-32 AUGUST 1998 2C-76 AUGUST 1998 2C-33 AUGUST 1998 2C-77 AUGUST 1998 2C-34 AUGUST 1998 2C-78 AUGUST 1998 2C-35 AUGUST 1998 2C-79 AUGUST 1998 2C-36 AUGUST 1998 2C-80 AUGUST 1998 2C-37 AUGUST 1998 2C-81 AUGUST 1998 2C-38 AUGUST 1998 2C-82 AUGUST 1998 2C-39 AUGUST 1998 2C-83 AUGUST 1998 2C-40 AUGUST 1998 2C-84 AUGUST 1998 2C-41 AUGUST 1998 2C-85 AUGUST 1998 2C-42 AUGUST 1998 Chapter 3 Tab 2C-43 AUGUST 1998 3-i AUGUST 1998 2C-44 AUGUST 1998 3-ii OCTOBER 2002 2C-45 AUGUST 1998 3-iii AUGUST 1998 2C-46 AUGUST 1998 3-iv OCTOBER 2000 2C-47 AUGUST 1998 3-v OCTOBER 2010 2C-48 AUGUST 1998 3-vi OCTOBER 2000 2C-49 AUGUST 1998 3-vii OCTOBER 2000 2C-50 AUGUST 1998 3-viii OCTOBER 2000 2C-51 AUGUST 1998 3-1 AUGUST 1998 2C-52 AUGUST 1998 3-2 AUGUST 1998 2C-53 AUGUST 1998 3-3 AUGUST 1998 2C-54 AUGUST 1998 3-4 ,OCTOBER 2010 2C-55 AUGUST 1998 3-5 AUGUST 1998 2C-56 AUGUST 1998 3-6 AUGUST 1998 2C-57 AUGUST 1998 3-7 AUGUST 1998 2C-58 AUGUST 1998 3-8 OCTOBER 2000 2C-59 AUGUST 1998 3-9 AUGUST 1998 2C-60 AUGUST 1998 3-10 AUGUST 1998 LOEP-4 OCTOBER 2010

ZION STATION DSAR LIST OF EFFECTIVE PAGES PAGE DATE PAGE DATE 3-11 AUGUST 1998 3-52 OCTOBER 2000 3-12 AUGUST 1998 3-52a OCTOBER 2010 I 3-13 AUGUST 1998 3 OCTOBER 2004 3-14 AUGUST 1998 3-54 -OCTOBER 2004 3-15 AUGUST 1998 3-55 OCTOBER 2010 3-16 AUGUST 1998 3-55a OCTOBER 2000 3-17 AUGUST 1998 3-56 OCTOBER 2000 3-18 AUGUST 1998 3-57 AUGUST 1998 3-19 AUGUST 1998, 3-58 OCTOBER 2002 3-20 OCTOBER 2002 3-59 OCTOBER 2000 3-21 AUGUST 1998 3-60 OCTOBER 2010 3-22 AUGUST 1998 3-61 OCTOBER 2000 3-23 AUGUST 1998 Table 3-1 (1) AUGUST 1998 3-24 AUGUST 1998 Table 3-2(1) AUGUST 1998 3-25 AUGUST 1998 Table 3-3(1) OCTOBER 2000 3-26 OCTOBER 2000 Table 3-4(1) AUGUST 1998 3-27 OCTOBER 2000 Table 3-4(2) AUGUST 1998 3-27a OCTOBER 2000 Table 3-4(3) AUGUST 1998 3-28 OCTOBER 2000 Table 3-4(4) AUGUST 1998 3-29 OCTOBER 2000 Table 3-4(5) AUGUST 1998 3-30 AUGUST 1998 Table 3-5(1) AUGUST 1998 3-31 OCTOBER 2000 Table 3-6(1) AUGUST 1998 3-32 AUGUST 1998 Table 3-7(1) AUGUST 1998 3-33 AUGUST 1998 Table 3-8(1) AUGUST 1998 -

3-34 AUGUST 1998 Table 3-9(1) OCTOBER 2000 3-35 OCTOBER 2000 Table 3-9(2) OCTOBER 2000 3-36 OCTOBER 2000 Table 3-9(3) AUGUST 1998 3-37 OCTOBER 2000 Table 3-10(1) OCTOBER 2000 3-38 OCTOBER 2002 Table 3-11 (1) OCTOBER 2000 3-39 AUGUST 1998 Table 3-12(1) OCTOBER 2000 3-40 AUGUST 1998 Table 3-13(1) OCTOBER 2000 3-41 AUGUST 1998 Table 3-14(1) OCTOBER 2000 3-42 AUGUST 1998 Table 3-15(1) AUGUST 1998 3-43 OCTOBER 2000 Figure 3-1 AUGUST 1998 3-43a OCTOBER 2000 Figure 3-2 AUGUST 1998 3-43b OCTOBER 2000 Figure 3-3 AUGUST 1998 3-44 OCTOBER 2000 Figure 3-4 AUGUST 1998 3-45 OCTOBER 2000 Figure 3-5 AUGUST 1998 3-46 OCTOBER 2000 Figure 3-6 AUGUST 1998 3-47 OCTOBER 2010 Figure 3-7 AUGUST 1998 3-48 OCTOBER 2000 Figure 3-8 AUGUST 1998 3-49 AUGUST 1998 Figure 3-9 AUGUST 1998 3-50 OCTOBER 2010 Figure 3-10 AUGUST 1998 I 3-51 OCTOBER 2000 Figure 3-11 AUGUST 1998 LOEP-5 OCTOBER 2010

ZION STATION DSAR LIST OF EFFECTIVE PAGES PAGE DATE PAGE DATE Figure 3-12 AUGUST 1998 4-iv AUGUST 1998 Figure 3-13 AUGUST 1998 4-1 OCTOBER 2010 Figure 3-14 AUGUST 1998 4-2 OCTOBER 2000 Figure 3-15 AUGUST 1998 4-3 OCTOBER 2010 Figure 3-16 AUGUST 1998 4-4 AUGUST 1998 Figure 3-17 AUGUST 1998 4-5 OCTOBER 2010 I Figure 3-18 AUGUST 1998 4-6 OCTOBER 2004 Figure 3-19 AUGUST 1998 4-7 OCTOBER 2004 Figure 3-20 AUGUST 1998 4-8 AUGUST 1998 Figure 3-21 AUGUST 1998 4-9 AUGUST 1998 Figure 3-22 AUGUST 1998 4-10 OCTOBER 2000 Figure 3-23 AUGUST 1998 4-11 OCTOBER 2008 Figure 3-24 AUGUST 1998 4-12 OCTOBER 2000 Figure 3-25 AUGUST 1998 4-13 OCTOBER 2010 Figure 3-26 AUGUST 1998 4-14 OCTOBER 2008 Figure 3-27 AUGUST 1998 4-15 OCTOBER 2000 Figure 3-28 AUGUST 1998 4-16 OCTOBER 2008 Figure 3-29 AUGUST 1998 4-17 OCTOBER 2000 Figure 3-30 AUGUST 1998 Table 4-1 (1) OCTOBER 2004 Figure 3-31 AUGUST 1998 Table 4-2(1) OCTOBER 2004 Figure 3-32 OCTOBER 2000 Table 4-3(1) OCTOBER 2010 Figure 3-33 AUGUST 1998 Figure 4-1 OCTOBER 2004 Figure 3-34 AUGUST 1998 Chapter 5 Tab Figure 3-35 AUGUST 1998 5-i AUGUST 1998 Figure 3-36 AUGUST 1998 5-ii AUGUST 1998 Figure 3-37 AUGUST 1998 5-iii AUGUST 1998 Figure 3-38 AUGUST 1998 5-1 AUGUST 1998 Figure 3-39 OCTOBER 2000 5-2 OCTOBER 2000 Figure 3-39A OCTOBER 2000 5-3 OCTOBER 2000 Figure 3-40 OCTOBER 2010 5-4 OCTOBER 2000 Figure 3-41 OCTOBER 2010 5-5 OCTOBER 2000 Figure 3-42 OCTOBER 2010 5-6 AUGUST 1998 Figure 3-42A OCTOBER 2010 5-7 AUGUST 1998

.Figure 3-43 AUGUST 1998 5-8 OCTOBER 2000 Figure 3-44 AUGUST 1998 Table 5-1 (1) AUGUST 1998 Figure 3-45 OCTOBER 2010 Table 5-2(1) AUGUST 1998 I Figure 3-45A OCTOBER 2000 Table 5-3(1) OCTOBER 2000 Figure 3-46 OCTOBER 2000 Table 5-4(1) OCTOBER 2000 Figure 3-47 OCTOBER 2000 Table 5-5(1) OCTOBER 2000 Figure 3-48 AUGUST 1998 Table 5-6(1) AUGUST 1998 Chapter 4 Tab Table 5-7(1) OCTOBER 2000 4-i AUGUST 1998 Figure 5-1 AUGUST 1998 4-ii OCTOBER 2004 Figure 5-2 AUGUST 1998 4-iii AUGUST 1998 Figure 5-3 AUGUST 1998 LOEP-6 OCTOBER 2010

ZION STATION DSAR LIST OF EFFECTIVE PAGES PAGE DATE PAGE DATE Figure 5-4 AUGUST 1998 Chapter 6 Tab 6-i OCTOBER 2006 6-1 OCTOBER 2010 6-2 OCTOBER 2006 6-3 OCTOBER 2000 6-4 OCTOBER 2010 6-5 OCTOBER 2010 Chapter 7 Tab 7-i OCTOBER 2000 7-1 OCTOBER 2000 7-2 OCTOBER 2000 LOEP-7 OCTOBER 2010

ZION STATION DSAR TABLE OF CONTENTS SECTION TITLE PAGE 3.10.3.3.3 Design Features Important to the. 3-52 Defueled Condition 3.10.3.4 Auxiliary Ventilation Systems 3-52 3.10.4 Fire Protection System 3-52a 3.10.5 Operating Control Stations 3-53 3.10.5.1 General Layout 3-53 3.10.5.2 Design Basis 3-53 3.10.5.2.1 Control Room Design 3-53 3.10.5.2.2 Annunciator and Audible Alarm System 3-53 3.10.5.2.3 Radwaste System Control Panels 3-53 3.10.5.2.4 Miscellaneous Local Control Panels 3-54 3.10.5.2.5 Pager Alarm System 3-54 3.10.5.2.6 Design Features Important to the 3-54 Defueled Condition 3.10.6 Lighting Systems 3-54 3.10.7 Communications System 3-54 3.11 ELECTRICAL SYSTEMS 3-55 3.11.1 Design Basis 3-55 3.11.2 System Description 3-55 3.11.2.1 Offsite Power System 3-55 3.11.2.2 Onsite Power System 3-55 3.11.2.2.1 AC Power Systems 3-55 3.11.2.2.1.1 4160-V System 3-55a 3.11.2.2.1.2 480-V System 3-56 3.11.2.2.1.3 120-Vac Instrument and 3-56 Control Power System 3.11.2.2.1.4 Cable Derating 3-56 3.11.2.2.1.5 Cable Tray Loading 3-57 3.11.2.2.1.6 Reliability of Power Supplies 3-58 3.11.2.2.2 DC Power Systems 3-59 3.11.2.2.2.1 125-Vdc Power System 3-59

.3.11.2.3 Design Features Important to the Defueled Condition 3-60 3.11.3 Fire Protection for Cable Systems 3-60 3.12 .REFERENCES SECTION 3.0 3-61 3-v October 2010

ZION STATION DSAR

1. INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

1.1 INTRODUCTION

The Nuclear Regulatory Commission approved the transfer of the facility licenses from Exelon Generation Company, LLC (EGC) to ZionSolutions, LLC (ZS) on May 4, 2009 (Reference 6).

References in the Defueled Safety Analysis Report (DSAR) to Corn Ed, CECo, and Commonwealth Edison have been retained, as appropriate, instead of being changed to ZS to properly preserve the historical context.

In February 1998, CornEd certified the permanent cessation of operation of Zion Station Units 1 and 2 to the NRC (Reference 3). In March 1998, ComEd certified to the NRC that all fuel assemblies have been permanently removed from both Zion Station reactor vessels and placed in the spent fuel pool (Reference 4). ZS plans to transition Zion Station from the SAFSTOR condition (a period of safe storage of the stabilized and defueled facility) and initiate active dismantlement.

This DSAR is derived from the July, 1996 update of the Zion Station Updated Final Safety Analysis Report (UFSAR). The DSAR has been developed as a licensing basis document that reflects the permanently defueled condition of Zion Station and supercedes the UFSAR. As such, the DSAR is intended to serve the same function during SAFSTOR and decommissioning that the UFSAR served during operation of the facility. An evaluation of the systems, structures and components (SSCs) described in the UFSAR was performed to determine the function, if any, these systems would perform in a defueled condition. Each major SSC was evaluated to determine if it was required to support the safe storage of irradiated fuel in the spent fuel pool, or needed to support decommissioning activities. The criteria used to evaluate the major SSCs and the conclusion of the evaluations are provided in Section 3 of the DSAR.

A brief history of major plant operations and licensing related actions for Zion Station is as follows:

1. Construction Permit issued, December 1968,

2. Final Safety Analysis Report submitted, December 1970,

3. Operating license issued, April 1973 for Unit 1 and November 1973 for Unit 2,

4. Commercial Operations achieved, December 1973 for Unit 1 and September 1974 for Unit 2,

5. Certification of permanent cessation of plant operation submitted, February 1998,

6. Certification of permanent removal of all fuel from the reactor vessels, March 1998.

Upon docketing of the, certification for permanent cessation of operation and permanent removal of fuel from the reactor vessels, the 10 CFR Part 50 license no longer authorizes operation of the reactors or emplacement or retention of fuel in the reactor vessels. In addition, the operating licenses scheduled to expire in April 2013 for Unit 1 and November 2013 for Unit 2 continue to remain in effect until the Nuclear Regulatory Commission notifies ZS that the licenses have been terminated.

1-1 October 2010

ZION STATION DSAR For valves purchased by Commonwealth Edison, audits and inspections of various vendors were conducted by Commonwealth Edison to verify that the vendors complied with the approved programs and procedures.

All of the above actions were performed in accordance with the Commonwealth Edison Company Quality Assurance Program.

No reliance has been placed on the ASME survey and inspection system for equipment.

The majority of the Seismic Class I equipment was purchased before the ASME system was instituted.

Structural, equipment, and piping materials, in the Auxiliary Building have been selected for their compatibility with the expected normal and accident environments.

2. Fire Protection Fire protection facilities are provided in accordance with the recognized guidelines of the National Fire Protection Association, Nuclear Electric Insurance Limited, and Underwriters Laboratory.

The Fire Protection Report outlines the basic design and operational features of the plant Fire Protection System.

3. Record Requirements ZS and EGC or their authorized representatives and Westinghouse Electric Corporation have retained complete documentation of the design, fabrication, and construction of all essential plant components.

These records are available to verify the high quality and performance standards applicable to all essential plant components.

1.2.1.2 Radiation Controls Monitoring potentially radioactive areas is accomplished in the Control Room from which most actions required to maintain the safe operational status of the plant are centered.

in addition to instrumentation and controls which are required to maintain plant variables within prescribed operating ranges, means are provided to monitor fuel and waste storage and handling areas and all potentially contaminated facility effluent discharge paths.

Monitoring and alarm instrumentation is provided for fuel and waste storage and handling areas to detect inadequate cooling and to detect excessive radiation levels. Radiation monitors are provided to maintain surveillance over the release of radioactive gases and liquids.

A controlled ventilation system removes gaseous radioactivity from the atmosphere of the fuel and waste storage and handling areas of the Auxiliary Building and discharges it to the atmosphere via the plant vent. Radiation monitors are in continuous service in these areas to actuate high-activity alarms in the Control Room, as described in Section 3.

1-4 October 2010

ZION STATION DSAR 1.2.1.3 Fuel and Waste Storage Systems All fuel storage and waste handling facilities are contained and the facility design is such that accidental releases of radioactivity directly to the atmosphere will not exceed the limits of 10CFR1 00.

All operations with the spent fuel are conducted underwater (see section 3). This provides visual control of the operation at all times and also maintains low radiation levels. The borated water assures subcriticality at all times and also provides adequate cooling for the spent fuel. The spent fuel storage pool is supplied with a cooling system for the removal of the decay heat of the spent fuel. Racks are provided to accommodate the storage of 3012 fuel assemblies. The storage pool is filled with borated water. The spent fuel is stored in a vertical array with sufficient center-to-center distance between assemblies to assure a K effective of less than 0.95, even if unborated water is used to fill the pit, for fuel having a maximum loading of 57.4 grams U-235 per axial centimeter of fuel assembly length. The water level maintained in the pool will provide sufficient shielding to permit normal occupancy of the area by operating personnel. The spent fuel pool is also provided with systems to maintain water cleanliness and to indicate pool water level. Gamma radiation in the Auxiliary Building is monitored and a high level is annunciated in the Control Room.

Water removed from the pool must be pumped out as there are no gravity drains. Spillage or leakage of any liquids from waste handling facilities go to floor drains which flow to sumps.

Postulated accidents involving the release of radioactivity from the fuel and waste storage and handling facilities are shown in Chapter 5 to result in exposures well within the limits of 10CFQR100.

The spent fuel storage pool is a reinforced concrete structure with a corrosion resistant liner.

This structure is designed to withstand the anticipated earthquake loadings so that the liner will prevent leakage even in the event the reinforced concrete develops cracks. The transfer tube which connects the refueling canal and the spent fuel pool and forms part of the Reactor Containment is provided with a valve and a blind flange which effectively closes off the transfer tube.

1.2.1.4 Effluents Gaseous, liquid, and solid waste disposal facilities are designed so that discharge of effluents and-offsite shipments shall be in accordance with applicable governmental regulations.

Process and discharge streams are appropriately monitored and safety features are incorporated to preclude releases more than the limits of 10CFR20.

The plant restricted area, as it is applied to the definitions in 1 OCFR20, is defined in Appendix F of the Offsite Dose Calculation Manual (ODCM). This area includes sections of shoreline. The area is owned by EGC and is leased from them and in the possession and control of ZS; the control being required in 10CFR20.

1-5 October 2010

ZION STATION DSAR Neither EGC nor ZS has any riparian ownership extending out into the lake.

Verification of annual exposures to persons in those portions of the lake which constitute the restricted area will be accomplished by station release records and the environmental monitoring program. The restricted area does include shoreline frontage. This shoreline will be controlled. The shoreline is monitored at both the northern and southern boundaries by on-site stations as shown on Figure 1-1.

Environmental conditions do not place any restrictions on the normal release of operational radioactive effluents to the atmosphere. Radioactive fluids entering the WD System are collected in analysis tanks until the course of subsequent treatment is determined.

All solid wastes are placed in suitable containers and stored onsite until shipment offsite for disposal.

Liquid wastes are processed to remove most of the radioactive material. The spent resins from the demineralizers and the filter cartridges are packaged and stored onsite until shipment offsite for disposal. The processed water, from which most of the radioactive material has been removed, is recycled for reuse within the plant or is discharged through a monitored line into the circulating water discharge.

1.2.2 Structures The major structures include a separate and independent Containment for each reactor, a common Auxiliary Building with holdup tank vault, a common Fuel Handling Building, a common Turbine Building, a common Cribhouse, and a common Administration and Service Building.

General layouts of the Reactor Containment, Auxiliary Building and interior components arrangements are shown in figures 1-1 through 1-16.

1.2.3 Waste Disposal System The shared WD System provides all equipment necessary to collect, process, and prepare for disposal all radioactive liquid, gaseous, and solid wastes produced as a result of reactor operation and decommissioning activities.

After collection, liquid wastes are demineralized. The treated water from the demineralizers may be recycled for use in the plant or may be discharged via the circulating water discharge at concentrations well within the limits of 10CFR20. The spent demineralizer resins are drummed, dewatered and shipped from the site for ultimate disposal in an authorized location.

Gaseous waste discharge to the environment is controlled to keep the offsite dose well within the limits of 10CFR20.

1-6 October 2010

ZION STATION DSAR 1.4 DRAWINGS AND OTHER DETAILED INFORMATION Table 1-1 lists DSAR figures that are controlled drawings.

1.5 REFERENCES

, Section 1.0

1. Atomic Energy Commission, Proposed General Design Criteria, Federal Register, July 11, 1967.

2. Atomic Energy Commission, General Design Criteria, Federal Register, July 1971.

3. Letter from 0. D. Kingsley, CoinEd to U.S. NRC, dated February 13, 1998, Certification of Permanent Cessation of Plant Operation

4. Letter from 0. D. Kingsley, ComEd to U.S. NRC, dated March 9, 1998, Certification of Permanent Removal of all Fuel from the Reactor Vessels

5. NRC letter "Braidwood, Byron, Dresden, LaSalle, Quad Cities and Zion - Orders Approving Transfer of Licenses from Commonwealth Edison Company to Exelon Generation Company, LLC, and Approving Conforming Amendments,"

dated August 3, 2000.

6. NRC letter, "Order Approving Transfer of Licenses and Conforming Amendments Relating to Zion Nuclear Power Station, Units 1 and 2", dated May 4, 2009.

1-9 October 2010

ZION STATION DSAR

2. SITE CHARACTERISTICS

2.0 INTRODUCTION

This chapter summarizes information on the geological, seismological, hydrological, and meteorological characteristics of the site and vicinity, in conjunction with population distribution, land use, and site activities and controls. The purpose is to indicate how these site characteristics influenced plant design, operating criteria, and overall adequacy of the site for nuclear power operations. Much of this information is historical in nature. This information demonstrates, in complement with more detailed discussions provided in other chapters, the overall adequacy of the site for safely storing, monitoring, and handling of fuel, to safely handle radioactive waste, and to monitor all radiological effluent release paths.

2.1 GEOGRAPHY AND DEMOGRAPHY 2.1.1 Site Location and Description The site is in Northeast Illinois on the west shore of Lake Michigan about 40 miles N of Chicago, Illinois, and about 42 miles S of Milwaukee, Wisconsin, as shown in Figure 2-1. The site is in the extreme eastern portion of the city of Zion, (Lake County) Illinois, on the west shore of Lake Michigan approximately 6 miles NNE of the center of the city of Waukegan, Illinois, and 8 miles south of the center of the city of Kenosha, Wisconsin. It is located at longitude 87 degrees 48.1 minutes W and latitude 42 degrees 26.8 minutes N.

The site comprises approximately 250 acres which is owned by EGC. The site is traversed from west to east by Shiloh Boulevard near the northern property boundary. Site maps covering details out to a 10 mile radius and in the Low Population Zone (LPZ) and Exclusion areas, are respectively shown in Figures 2-1 and 2-2. Figure 2-3 is an aerial photograph depicting the site boundaries and details of the site.

In addition to those roads which connect directly with the site, there is a network of primary and secondary highways and section line roads in the adjacent area which provide a variety of high capacity routes to and from the site and the immediate vicinity, as indicated on Figure 2-2. For example, in addition to Shiloh Boulevard, which extends approximately 2 miles west of the plant site, there are within 1-mile of the site three other highways or roads (I11.Rt. 173, 29th Street, and Wadsworth Road) extending westerly and intersecting each of the principal north-south secondary highways located within four miles of the site, i.e., Sheridan Road, Lewis Avenue, Kenosha and Green Bay Roads (i11.Rt. 131), and also U.S. Rt. 41, a four lane, highspeed, divided highway. In addition, Interstate 94, a limited access, four lane tollway, is situated approximately 6 miles west of Zion.

2.1.2 Exclusion Area Authority and Control The site, consisting of approximately 250 acres owned solely by EGC and controlled by ZS under lease, provides the requisite exclusion area. Reference Section 1.2.1.4 for discussion of the restricted area.

There are no residences on the site or within 2000 feet of the station structures.

2-1 October 2010

ZION STATION DSAR TABLE OF CONTENTS SECTION TITLE PAGE 3.10.3.3.3 Design Features Important to the 3-52 Defueled Condition 3.10.3.4 Auxiliary Ventilation Systems 3-52 3.10.4 Fire Protection System 3-52a 3.10.5 Operating Control Stations 3-53 3.10.5.1 General Layout 3-53 3.10.5.2 Design Basis 3-53 3.10.5.2.1 Control Room Design 3-53 3.10.5.2.2 Annunciator and Audible Alarm System 3-53 3.10.5.2.3 Radwaste System Control Panels 3-53 3.10.5.2.4 Miscellaneous Local Control Panels 3-54 3.10.5.2.5 Pager Alarm System 3-54 3.10.5.2.6 Design Features Important to the 3-54 Defueled Condition 3.10.6 Lighting Systems 3-54 3.10.7 Communications System 3-54 3.11 ELECTRICAL SYSTEMS 3-55 3.11.1 Design Basis 3-55 3.11.2 System Description 3-55 3.11.2.1 Offsite Power System 3-55 3.11.2.2 Onsite Power System 3-55 3.11.2.2.1 AC Power Systems 3-55 3.11.2.2.1.1 4160-V System 3-55a 3.11.2.2.1.2 480-V System 3-56 3.11.2.2.1.3 120-Vac Instrument and 3-56 Control Power System 3.11.2.2.1.4 Cable Derating 3-56 3.11.22.1.5 Cable Tray Loading 3-57 3.11.2.2.1.6 Reliability of Power Supplies 3-58 3.11.2.2.2 DC Power Systems 3-59 3.11.2.2.2.1 125-Vdc Power System 3-59 3.11.2.3 Design Features Important to the Defueled Condition 3-60 3.11.3 Fire Protection for Cable Systems 3-60 3.

1.2 REFERENCES

SECTION 3.0 3-61 3-v October 2010

ZION STATION DSAR Criterion 5 - Records Requirements Records of the design, fabrication, and construction of essential components of the plant shall be maintained by the reactor operator or under its control throughout the life of the reactor.

Answer The applicant intends to maintain, either in its possession or under its control, a complete set of records of the design, fabrication, construction and testing of major Seismic Class I plant components throughout the life of plant. A quality assurance program has been employed and appropriate records have been and are being maintained in conformance with applicable quality requirements by EGC under agreement with ZS or are under ZS control.

I1l. Nuclear- and Radiation Controls Criterion 11 - Control Room The facility shall be provided with a control room from which actions to maintain safe operational status of the plant can be controlled. Adequate radiation protection shall be provided to permit access, even under accident conditions, to equipment in the control room or other areas as necessary to shut down and maintain safe control of the facility without radiation exposures of personnel in excess of 10CFR20 limits. It shall be possible to shut the reactor down and maintain it in a safe condition if access to the control room is lost due to fire or other cause.

Answer A common control room contains all controls and instrumentation that were necessary for operation of each unit's reactor, turbine generator, and auxiliary and emergency systems under normal or accident conditions.

The Control Room is designed and equipped to minimize thepossibility of events which might preclude occupancy. In addition, provisions were made for bringing both units to and maintaining them in a hot shutdown condition for an extended period of time from locations outside the Control Room. Chapter 3 discusses the Control Room Ventilation System.

Criterion 12 - Instrumentation and Control Systems Instrumentation and controls shall be provided as required to monitor and maintain variables within prescribed operating ranges.

Answer Sufficient instrumentation and controls are provided for safe and efficient operation of the facility. Additional details on instrumentation and controls are included in sections relating to specific systems and components.

3-4 October 2010

ZION STATION DSAR 3.10.2.2 System Description The six service water pumps are rated at 22,000 gpm at 210 feet TDH. The pumps are located in the Crib House and take their suction from the Crib House forebay which receives water from the lake through three, 13-foot steel intake lines. Two of the intake lines have 24-foot diameter bell-shaped inlets and are covered by a flat protective canopy. The third intake line receives water through an annular structure with 55 openings separated by as much as 96 feet. During the spring, summer, and fall months, a fishnet barrier is installed around the perimeter of the intake structure to meet the facilities' National Pollution Discharge Elimination System (NPDES) permit requirements and is removed in the winter months. It is extremely improbable that any single barge or ship on Lake Michigan could block all of the circulating water intake structure.

Any two of the openings in the annular intake structure which supplies one 13-foot intake line, or a small fraction of one of the two 24-foot diameter bell-shaped inlets, each of which supply one 13-foot intake line, would be adequate to provide full service water flow for both Unit 1 and Unit 2. In the event that all three intake lines are blocked, water can be admitted to the forebay through one discharge line and its recirculation connection to the forebay.

The discharge of three service water pumps passes through two 40,000 gpm strainers with

'/ 8-inch openings to a common header for all six pumps. The main supply headers connect to this common discharge header.

Service Water is taken from the discharge of the service water booster pumps, treated by an electrolytic dissolution of both copper and aluminum and returned to the Service Water system upstream of the Service Water pumps into the intake bays. The copper and aluminum will control the Zebra Mussel population by reducing their ability to attach to substrate and by inhibiting settlement of the Zebra larvae.

The normal water supply to the Fire Protection System is provided by the service water booster pumps. These pumps take suction from each of the main headers in the Crib House. The main headers pass under the Turbine Building after leaving the Crib House and enter the Auxiliary Building where the cooling water loops are supplied.

Pushbuttons are installed at the 4-kV buses 147, 148, 149, 247, 248 and 249 for local start of the service water pumps.

3-47 October 2010

ZION STATION DSAR 3.10.3.1.4 Design Features Important to the Defueled Condition The Control Room Ventilation System was designed to handle a loss of coolant accident.

Therefore, it is sufficiently designed to accommodate the significantly reduced source term in the permanently defueled condition. The consequences of the accidents in the defueled condition are significantly below the 10CFR100 guidelines. In addition, no credit for control room ventilation isolation is taken in the safety analysis since the dos'e consequences to control room inhabitants is significantly low without ventilation isolation. In the event of evacuation, cooling of the stored irradiated fuel in the spent fuel pool can be monitored locally.

The Control Room Ventilation System is not considered ITDC.

3.10.3.2 Auxiliary Building Ventilation 3.10.3.2.1 Design Bases The Auxiliary Building Ventilation system is designed to maintain acceptable ambient air temperatures for equipment operation and personnel habitability, provides air flow in a cascading fashion from areas of lesser contamination potential to areas of greater contamination potential (for ALARA considerations), and provides a bulk exhaust flow for ease of effluent sampling.

3.10.3.2.2 Normal Operation The Auxiliary Building Ventilation system supplies filtered, conditioned outside air to the various areas of the Auxiliary Building and Fuel Building and exhausts filtered air back to the outside.

The supply and exhaust air flows are balanced to maintain air flows in the Auxiliary Building in a cascading fashion from areas of lesser contamination potential to areas of greater contamination potential. The exhaust fans draw filtered air from the common exhaust plenum and discharge air to the Auxiliary Building vent stack past a radiation sampling monitor. The exhaust system can operate to maintain the required pressure gradients by vortex control dampers and the operation of one or more exhaust fans. Individual filter units treat the exhaust from miscellaneous areas of the Auxiliary Building prior to discharge via the main exhaust fans.

See figures 3-41 and 3-42.

Each supply and exhaust fan may be manually started and stopped from the Control Room.

System variables pertaining to normal operation are indicated on the main control room panel.

Abnormal conditions, such as high temperature, low temperature, low building differential pressure, and high pressure drop across filters are annunciated either locally or on the main control room panel.

3-50 October 2010

ZION STATION DSAR 3.10.4 Fire Protection System Zion Station utilizes the defense-in-depth concept, placing special emphasis on detection and suppression in order to minimize radiological releases to the environment. This system is, therefore, considered Important to the Defueled Condition. A detailed description of the plant's Fire Protection System is contained in the Fire Protection Report.

Unit 1 and 2 Containment Building air terminals as well as the 75 foot high 345kV tower are credited with providing lightning protection for the SFNI Cooling Towers and SFNI HVAC equipment as detailed in Reference 12.

3-52a 3 October 2010

ZION STATION DSAR 3.11 Electrical Systems 3.11.1 Design Basis The Electrical Power System to the station is designed to distribute electrical power to structures, systems, and components (SSCs) important to the defueled condition (ITDC) and other SSCs that support other activities that may be conducted at Zion Station.

3.11.2 System Description 3.11.2.1 Offsite Power System Figure 3-45 shows the physical layout of the 345-kV switchyard and transmission facilities. The figure shows six transmission lines, two system auxiliary transformers and one main power transformer bank terminating on the 345-kV bus consisting of 10 circuit breakers. The transmission lines are installed two lines to a tower and two of these lines leave the switchyard on a separate right-of-way.

The control power for the 345-kV switchyard breakers is supplied by two 125-Vdc feeds (one fed from a Unit 1 battery and the other from a Unit 2 battery). The feeds from each battery establish separate trip circuits for the two trip coils in each breaker in the switchyard.

In addition, there are two independent 12-kV feeds from the commercial electrical distribution system. They supply two 12-kV to 480V step down Spent Fuel Nuclear Island (SFNI) transformers. These transformers provide the normal power supplies to the spent fuel pool support systems. The switchgear buses are located in the fuel building. Each independent line can supply power to the SFNI transformers.

3.11.2.2 Onsite Power System 3.11.2.2.1 AC Power Systems The Auxiliary Power. System provides a reliable source of power to structures, systems, and components (SSCs) important to the defueled condition (ITDC) and other SSCs that support other activities that may be conducted at Zion Station.

The basic arrangement of the plant electrical system is shown on the Single Line Diagram; Figure 3-46 for Unit 1 and Figure 3-47 for Unit 2.

Auxiliary power at 4160 V is provided by the system auxiliary transformer (142 for Unit 1 and 242 for Unit 2). The system auxiliary power transformers are rated at 55MVA (force oil air rating).

3-55 October 2010

ZION STATION DSAR 3.11.2.3 Design Features Important to the Defueled Condition Electrical equipment necessary to perform the following functions is regarded as Important to the Defueled Condition:

1. Adequate offsite power from the switchyard to supply at least one System Auxiliary Transformer (Transformer 142/242) and one SFNI transformer. Adequate 4160-V, 480-V, and 120 Vac distribution bus equipment for the following reasons:

a. Provide power to the Fuel Handling system as discussed in section 3.9.3

b. Provide power to the Spent Fuel Pool Cooling system as discussed in section 3.9.4

c. Provide power to the Spent Fuel Pool Secondary Loop Cooling system as discussed in section 3.10.1.

d. Provide power to the Auxiliary Building Ventilation system as discussed in section 3.1.0.3.2

e. Provide power to the Containment Purge system equipment as discussed in section 3.10.3.3

f. Provide power to the Liquid Radwaste system equipment as discussed in section 4.5.2

g. Provide power to the Solid Radwaste system equipment as discussed in section 4.5.3

h. Provide power to the Process Radiation Monitoring equipment as discussed in section 4.6.2

i. Provide power to the Area Radiation Monitoring equipment as discussed in section 4.6.3 Note: 480 V to 120 V inverters, to supply instrument power as discussed in section 3.11.2.2.1.3, are not considered ITDC.

2. 125 Vdc distribution bus 111, and its battery, to realign the switchyard.

3.11.3 Fire Protection for Cable Systems The Zion Station Fire Protection Report provides fire protection information and the effect of postulated fires on plant cable systems.

3-60 October 2010

To Turbine Building Loads ZION STATION DSAR I

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October 2010

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OCTOBER 2010

ZION STATION DSAR Figure 3-42A Fuel Suflding Ventilation System (SIMPLIFIED) October 2OLO

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ZION STATION DSAR I

! Figure 3-45 345Kv INTERCONNECTION WITH TRANSMISSION SYSTEM OCTOBER 2010

ZION STATION DSAR

4. RADIATION PROTECTION 4.1 Ensuring That Occupational Radiation Exposures are As Low As Reasonably Achievable (ALARA)

Consistent with station modification, maintenance, operational requirements, and economic and social considerations, the policy of ZS is to:

1. Maintain the occupational dose equivalent to the individual As Low as is Reasonably Achievable (ALARA);

2. Maintain the sum of occupational dose equivalents received by all exposed workers ALARA; and

3. Limit the number of workers authorized to receive exposure to radiation.

Regulatory Guide 8.8, Revision 3, Sections C.1, C.3, and C.4 is used as a basis for developing the ALARA and radiation protection programs.

Station management's commitment to this policy is reflected in radiological procedures and programs. The Radiation Protection staff provides the radiological conditions and protective requirements necessary to complete work safely. Each individual's responsibility to adhere to these requirements and the procedures governing their work is key to the success of the program.

4.2 Radiation Sources The source terms used in the design and evaluation of Zion Station consists of the types and quantities of radionuclides that are produced in the fuel, primary coolant, and structural materials of the reactor coolant system, and the rate of transfer of these nuclides into other systems for an operating plant. In a permanently defueled plant, the number and magnitude of potential radiation sources have been reduced substantially from the original design bases source terms. The source terms in the defueled condition are bounded by the source terms existing during normal plant operations and relate to stored spent fuel, residual post operational radioactive material, structure and component activation, and new radioactive material generated during plant decontamination. The source terms used in the original plant design are historical information and are not discussed here since they are not applicable for a permanently defueled plant. The radiation protection program will continue to monitor appropriate areas to ensure proper confinement of existing radioactive material.

4-1 October 2010

ZION STATION DSAR 4.3.1.1.2 Fuel Handling Buildinq The Fuel Handling Building houses the spent fuel pool and associated pumping, cooling, and filtering equipment and is considered ITDC. The spent fuel pool provides water shielding of approximately 25 feet over the stored spent fuel. The minimum wall thickness of the pool is 6 feet 0 inches of ordinary concrete.

Concrete shielding is provided for the following spent fuel pool service equipment:

Heat Exchangers Pumps Skimmer Filter Demineralizer After Filter 4.4 Health Physics Program 4.4.1 Equipment, Instrumentation, and Facilities 4.4.1.1 Personnel Monitoring All personnel entering radiologically posted areas onsite are required to wear personnel monitoring devices, except for visitors. The minimum requirements include an electronic dosimeter (or its equivalent) and a thermoluminescent dosimeter (TLD) badge. Additional dosimeters such as finger rings, electronic dosimeter, high range pocket dosimeter, neutron dosimeter, etc. are required when radiological conditions warrant their use. Visitors to the station who enter radiologically posted areas are required to either wear the minimum dosimetry described above, or they are provided with an escort who will wear an extra TLD badge to collectively monitor their dose. As a minimum, each visitor will wear an electronic dosimeter (or its equivalent) inside posted areas.

As a general rule, the TLD badge will provide the official record of personnel exposure. If this device is lost or fails to respond properly, the official record will be determined by a health physicist after evaluating electronic dosimeters, radiation surveys, radiation timekeeping records, etc. The electronic dosimeter readings (or equivalent) and applicable timekeeping results are normally recorded daily. These records are routinely reviewed by radiation protection management and, if applicable, by management in the individual's work group. The TLD badges are changed at regular intervals. Badge results are reviewed by Health Physics Management and are entered in the computerized dose records system. These official and permanent records provide the exposure data for the administrative control of radiation exposure. Required exposure reports are made by radiation protection management utilizing the dose records system.

A portal personnel radiation monitor is provided at the plant exit for monitoring of surface and internal activity of people leaving the plant. The portal monitor provides for complete head-to-foot coverage. The portal console monitor located on the portal frame includes status lights including a contamination alarm. The contamination signal from the console alerts personnel to the contamination condition so that the proper action can be taken.

4-3 October 2010

ZION STATION DSAR 4.4.2 Procedures The Radiation Protection Program and Procedures are designed to provide protection of personnel against exposure to radiation and radioactive materials in a manner consistent with applicable regulations. The policy of ZS is to maintain personnel radiation exposure As Low as is Reasonably Achievable (ALARA). Therefore, each individual is trained to minimize his exposure consistent with discharging his duties. Each individual is responsible for observing rules adopted for his safety and that of others.

Radiation protection personnel evaluate radiological conditions of operations and establish the procedures to be followed by all personnel. They ensure that all applicable regulations are complied with and that the required radiation protection records are adequately maintained.

Training of operators, maintenance, and technical personnel in radiation protection principles and procedures took place before initial unit operation. New employees, contractors, and other supporting personnel are given initial training at the beginning of their work assignments and annual retraining thereafter.

Procedures are in place which require performance of ALARA reviews, as necessary, of proposed plant design changes and modifications.

4.5 Radioactive Waste Manaqement 4.5.1 General Radioactive waste management is maintained through the use of the Liquid and Solid Waste Systems. These systems collect, process, monitor, and regulate the discharge of all potentially radioactive wastes from both units. Storage of radioactive gaseous waste for decay is not anticipated in the defueled condition. The contents of the six gas decay tanks have been sampled and determined to have negligible activity. As such, the Gaseous Waste System is not important to the defueled condition of the station and is not discussed as part of Radioactive Waste Management. The design of the waste systems is in accordance with USNRC Regulatory Guide 1.143.

Normally, all waste systems are operated remotely so as to minimize the radiation exposure of plant personnel. Waste processing is a batch-type operation which allows a determination of the activity to be discharged before any action is undertaken to make the actual release.

Monitoring equipment is provided to maintain surveillance over the release operations and to halt these operations on indication of radioactivity concentrations above established limits.

The design of the waste systems was based on 1% of the fuel rods releasing fission products into the coolant by diffusion out of the pellets through defects in the cladding. In the defueled condition, the normal sources of radioactive wastes are activated corrosion products and fission products generated during power operations, liquid wastes generated while maintaining spent fuel pool water chemistry, liquid wastes generated during decommissioning activities, ground water in-leakage through contaminated areas in the auxiliary building, and solid wastes in the form of spent demineralizer resins, filters and sludge. Since neither of the Zion Station reactor cores operated with 1% failed fuel, the design of the Radioactive Waste Systems in the defueled condition is bounded by the original design of the system.

4-5 October 2010

ZION STATION DSAR The detector output is transmitted to the SPING system control terminal console in the Control Room. The radioactivity level is output on the console at the request of the operator. High radioactivity indications are displayed by an alarm and automatic data output at the control console. The system can detect, quantify, and identify alpha and beta particulate. The monitors are located in the Fuel Building and alarm locally.

Isolation valves are installed on the inlet and discharge sample lines to the monitors to allow for maintenance and calibration.

4.6.2.1.1.2 Auxiliary Building Vent Stack SPING Air Monitor This vent stack SPING continuously monitors the vent stack effluent for beta and alpha particulate and noble gas. The monitor outputs data and alarms to the SPING central control console.

This monitor outputs low flow and flow irregularity alarms to the control console.

This SPING monitor has no self-contained pump to induce a sample flow through the SPING.

The sample is fed to the SPING by the Isokinetic Sampling System at a flow rate of up to approximately 2 cfm. The purpose of this system is to regulate the sample flow to accurately duplicate stack gas velocity and pressure to the vent stack SPING monitor. This allows a valid indication of the particulate content of the vent stack effluent.

4.6.2.1.1.3 Fuel Building Exhaust Air Monitor The Fuel Building Ventilation exhaust is monitored via the Auxiliary Building ventilation stack effluent monitors.

4.6.2.1.2 Liquid Radiation Monitors The liquid radiation monitors are a set of self-contained monitors used to measure radioactivity levels in liquid process and effluent streams. Table 4-3 provides a list of these monitors and identifies their tag numbers and sensitivities.

Detector outputs are transmitted to the Radiation Monitoring System cabinets in the Control Room. The radioactivity levels are indicated by the module meters and recorded on paper.

High radioactivity-alarm indications are displayed on the Radiation Monitoring System cabinets.

4-13 October 2010

ZION STATION DSAR TABLE 4-3 PROCESS RADIATION MONITORS INSTRUMENT DETECTOR SERVICE MONITOR NO. CHANNEL TYPE SENSITIVITY ISOTOPE (1)

Containment Air 1 RIA-PR40 Particulate Beta Scintillation 1.09 E 5 cpm/pCi Sr-90/Y-90 2RIA-PR40 Particulate Beta Scintillation 1.09 E 5 cpm/4Ci Sr-90/Y-90 Auxiliary Building Vent 1RIA-PR49 Low Range Noble Gas Beta Scintillation 5.0 E-7 to 1.0 E-2 0Ci/cc Kr-85 Stack 2RIA-PR49 Mid Range Noble Gas G-M 1.0 E-2 to 1.0 E 4 pCi/cc Kr-85 High Range Noble Gas G-M 1.0 to 5.0 E 5 gCi/cc Kr-85 Fire Sump Discharge ORT-PR25 Scintillation 9.0 E-7 to 8.0 E-2 piCi/ml Cs-1 37 Waste Disposal System Lake ORT-PRO5 Scintillation 1.0 E-7 to 5.0 E-3 gCi/ml Cs-137 Discharge Effluent I IIII (1) Sensitivity Ranges are based on these isotope October 2010

ZION STATION DSAR

6. CONDUCT OF OPERATIONS 6.1 RESPONSIBILITY AND ORGANIZATION Onsite and offsite organizations are established for unit and corporate management, respectively. The onsite and offsite organizations include the positions for activities affecting the safety of the facility.

1. Lines of authority, responsibility, and communication are established and defined for the highest management levels through intermediate levels including all operating organization positions. These relationships are documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent form of documentation.

2. A Corporate Vice President has corporate responsibility for decommissioning activities and the safe storage of spent nuclear fuel at the facility.

3. Zion Station is managed by the Decommissioning Plant Manager. The Decommissioning Plant Manager has day-to-day responsibility for the facility and has control of the onsite activities necessary for the safe operation and maintenance of structures and systems required for the safe storage of spent nuclear fuel.

4. The individuals who train the operating staff and those who carry out radiation protection and quality functions may report to an appropriate onsite manager; however, they have sufficient organizational freedom to ensure their independence from operating pressures.

6.1.1 On-Site Organization 6.1.1.1 Duties and Responsibilities of Staff Personnel Duties and responsibilities of staff personnel are contained in the ZS Quality Assurance Project Plan (see Section 6.5.8) and site administrative procedures and organizational charts published in Zion Administrative Procedure ZAP-200-01, Zion Decommissioning Organization.

6-1 October 2010

ZION STATION DSAR The DSEP is distributed on a controlled basis to all stations and emergency facilities requiring them, including appropriate Federal, State, and local agencies.

The DSEP has been submitted to and approved by the NRC. It is reviewed annually, and any changes or revisions that pertain to regulatory requirements are submitted to the NRC for approval.

6.5.2 Security Plan A detailed Zion physical security plan, withheld from public disclosure pursuant to 2.790 of 10CFR2, has been made available to the NRC.

The Zion Station physical security plan conforms to the requirements of 1 OCFR73.55.

6.5.3 Fire Protection Program The Zion Station Fire Protection Program describes how Zion Station complies with and meets the objectives of 10CFR50.48(f) and describes the fire detection and suppression systems. The Fire Protection Program includes provisions for periodic assessments to ensure that the Program is maintained and is appropriate throughout the various stages of facility decommissioning. A fire suppression water system consists of: a water source(s); pumps; and distribution piping with associated sectionalizing isolation valves. Such valves shall include yard hydrant valves, and the first valve upstream of the water flow alarm device on each sprinkler, hose standpipe or spray system riser.

6.5.4 Fitness for Duty The ZS Fitness for Duty (FFD) Program meets the requirements and standards of 10CFR26.

6.5.5 Offsite Dose Calculation Manual The Zion Station Offsite Dose Calculation Manual (ODCM) is defined by Technical Specifications to contain the methodology and parameters used in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain the Radioactive Effluent Control and Radiological Environmental Monitoring Programs and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

6-4 October 2010

ZION STATION DSAR 6.5.6 Process Control Program The Process Control Program (PCP) contains the current formulas, sampling analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFRParts 20, 61, and 71; state regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste. Dry active waste (DAW) such as compacted trash and contaminated components are not included in the scope of the PCP. Written procedures are established, implemented, and maintained covering the key activities of the Process Control Program.

Changes to the PCP shall be documented and records of reviews performed shall be retained as required by Technical Specifications.

6.5.7 Maintenance Rule Program A Maintenance Rule Program has been established, in accordance with 10CFR50.65, for monitoring the performance of structures, systems, and components associated with the storage, control, and maintenance of spent fuel in a safe condition. The Maintenance Rule Program has established performance criteria for these SSCs such that attainment of the criteria provides reasonable assurance that the SSCs are capable of fulfilling their intended functions.

6.5.8 Quality Assurance Program The Quality Assurance Program is implemented in accordance with the Quality Assurance Project Plan (QAPP), ZS-QA-1 0. The QAPP defines the ZionSolutions LLC Quality Assurance Program to be implemented during the Zion Station Restoration and Dry Cask Storage (DCS)

Project at the Zion Nuclear Power Station (ZNPS) site. The QAPP is designed to meet the requirements of Title 10 of the Code of Federal Regulations, Part 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," ANSI/ASME NQA-1-1994, Part 71, Subpart H, "Quality Assurance Requirements for Packaging and Transportation of Radioactive Waste" and Part 72, Subpart G, "Quality Assurance Requirements for the Independent Storage of Spent Nuclear Fuel, High Level Radioactive Waste, and Reactor-Related Greater than Class C Waste."

The QAPP incorporates the applicable portions of the current EnergySolutionsQuality Assurance Program (QAP) Revision 0, effective date May 31, 2007, and the existing Exelon Quality Assurance Topical Report (QATR) Revision 84, Appendix A, Section 2.6, Augmented Quality requirements for Zion Station. Augmented Quality requirements are addressed in the appropriate subsections of Section 4.0 of the QAPP, and are implemented in a graded approach via station administrative procedures.

6.6 REVIEW AND INVESTIGATIVE FUNCTION The review and investigative functions are conducted in accordance with the plant Technical Specifications.

6-5 October 2010