ML023090413

Part 1 of 3, Sequoyah Nuclear Plant Fire Protection Report, Revision 9 Dated 10/12/2001

ML023090413
Person / Time
Site:	Sequoyah
Issue date:	10/25/2002
From:	Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML023090413 (175)

Text

TVAN FIRE PROTECTION REPORT APPROVAL PAGE SEQUOYAH NUCLEAR PLANT FIRE PROTECTION REPORT Revision 9 Effective Date: 16112/2001 Technical Review:

Technical Review:

Technical Review:

Technical Review:

Technical Review:

Technical Review:

Submitted by:

Concurrence:

PORC Meeting No.:

Plant Manager:

B. F. SimralIc(,,a Curato r)

Site Eng(eenng-Fire Protectoon John F. Thomas (wa curator)

Site Engineenng-Desvgfl H. R. Rogers (wa Curator)

Site Engineenng-System Engrneenng J.A. Dvorak (vda Curator)

Plant Operations-Procedures R. V. Drake (via curator)

Plant Maintenance K.S. Frazier (wa Curator)

Plant Operations - Fire Protecton D.C. Johnsorf '(a Curator)

Fire Ptection Supersor Mike Lorek M$a Curator)

PORC Chairperson 6010 D.L Koehi (via Curator)

Date 4/09/01 (wa Curator)

Date 4/10/01 (va Curator)

Date 4110/01 (wa Curator)

Date 4/10/01 (via Curator)

Date 4/10/01 (wa Curator)

Date 4/10/01 (vwa Curator)

Date 4/10/01 (ma Curator)

Date 4/12/01 (wa Curator)

Date 4/12/01 Date 4/17/01 (via Curator)

FPDP-3-1 [12-03-1998]

iVA 40706 Cl 2-1998]

Page 1 at 1 Page I of I TVA 40706 (12-19981

SQN FIRE PROTECTION REPORT Rev. 9 TABLE OF CONTENTS Page i Pa*e Rev.

REVISION LOG i

9 TABLE OF CONTENTS ii 9

PART I - INTRODUCTION I-1 1.0

Background

I-1 2.0 Purpose I-1 3.0 Scope I-1 4.0 References-Appendix A Program 1-4 5.0 References-Appendix R Progam 1-7 6.0 References-Fire Protection Improvement Program (FPIP) 1-11 PART II - FIRE PROTECTION PLAN II-8

1.0 Purpose and Scope

II-1 2.0 Objectives of the Fire Protection Plan 11-1 3.0 Basis of the Fire Protection Plan II-1 4.0 References 11-2 5.0 Definitions 11-5 6.0 Fire Protection Quality Assurance 11-13 7.0 Fire Protection Organization/Programs 11-14 8.0 Fire Protection Program Administrative 11-18 and Technical Controls 9.0 Emergency Response 11-20 10.0 Control of Combustibles 11-24 11.0 Control.of Ignition Sources 11-25 12.0 Description of Fire Protection Systems and Features 11-26

SQN FIRE PROTECTION REPORT Rev. 9 TABLE OF CONTENTS Page ii PART II - FIRE PROTECTION PLAN(Continued)

Page Rev 13.0 Fire Protection System Impairments and Compensatory Actions 11-36 14.0 Fire Protection Systems and Features, Operating Requirements 11-39 (OR's) and Surveillance Requirements (SR's)

PART III - SAFE SHUTDOWN CAPABILITIES III-1 9

1.0 Introduction 111-1 2.0 Safe Shatdown Functions 111-2 3.0 Analysis of Safe Shutdown Systems 111-3 4.0 Safe Shutdown Systems 111-8 5.0 Identification of Safe Shutdown System Components 111-17 6.0 Identification of Safe Shutdown Circuits and Cables 111-18 7.0 Associated Circuits of Concern 111-18 8.0 High/Low Pressure Boundary Interfaces 111-22 9.0 Location of Safe Shutdown Equipment, Cables 111-23 and Raceways 10.0 Safe Shutdown System Separation Evaluation Methodology 111-23 Sa 111-24 11.0 References PART IV - ALTERNATE SHUTDOWN CAPABILITY IV-1 1.0 Introduction IV-1 2.0 Discussion IV-1 3.0 Alternate Control Room Capabilities IV-1 4.0 References IV-4

SQN FIRE PROTECTION REPORT Rev. 9 TABLE OF CONTENTS Page iii Page Rev.

PART V - EMERGENCY LIGHTING AND REACTOR COOLANTV-1 9

PUMP OIL COLLECTION 1.0 Introduction V-1 2.0 Emergency Lighting V-1 3.0 Reactor Coolant Pump Oil Collection V-2 4.0 References V-3 PART VI - NFPA CODE EVALUATION VI-1 5

1.0 Introduction VI-1 2.0 Scope VI-1 3.0 Applicable NFPA Codes VI-2 PART VII - DEVIATIONS AND EVALUATIONS VII-1 5

1.0 Introduction VII-1 2.0 Deviations to 10CFR50 Appendix R VII-1 3.0 SQN 86-10 Evaluations for IOCFR50 Appendix R VII-39 4.0 Deviations to BTP 9.5-1 Appendix A VII-91 5.0 NFPA Code Deviations VII-99 - Sprinkler System Criteria VII-105 for Resolving Intervening Combustible Concerns PART VIII - CONFORMANCE TO APPENDIX A VIII-1 4

TO BTP 9.5-1 GUIDELINES PART IX - APPENDIX R COMPLIANCE MATRIX IX-1 I

PART X - FIRE HAZARDS ANALYSIS X-1 I

SQN FIRE PROTECTION REPORT Rev. 9 TABLE OF CONTENTS Page iv LIST OF TABLES PART II - FIRE PROTECTION PLAN Page Table 5.1 Operational Modes 11-12 Table 3.3-11 Minimum Fire Detector Instruments Operable 11-43 Table 3.7-5 Fire Hose Stations 11-57 PART III-SAFE SHUTDOWN CAPABILITIES Table 111-1 Safe Shutdown Systems and Subsystems by Key 111-26 Table 111-2 Shutdown Logic Component List 111-27 Table 111-3 Instrumentation list For Main Control Room 111-58 PART V - EMERGENCY LIGHTING AND REACTOR COOLANT PUMP OIL COLLECTION Table V-I 8-Hour Emergency Lighting Units V-4 PART VII - DEVIATIONS AND EVALUATIONS Table 2.0-1 Process Control Requirements for Validating VII-33 Appendix R Deviation Bases Table 2.2-1 Control Building Rooms Containing Redundant Safe VII-34 Shutdown Equipment, without Fire Detection and/or Automatic Suppression Table 2.12-1 Auxiliary Building Rooms Containing Redundant Safe VII-35 Shutdown Equipment, without Fire Detection and/or Automatic Suppression Table 2.12-2 Auxiliary Building Rooms Containing Redundant Safe VII-38 Shutdown Equipment, with only Partial Fire Detection and/or Automatic Suppression' Table VII-1 Auxiliary Building Special Purpose Doors VII-107 Table VII-2 Main Control Room Bullet Resistant Security Doors VII-108

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS Added Auxiliary Building Fire Rated Doors Alarmed Security Doors Certified Fiie Dampers Equivalent Fire Dampers Certification/Equivalent Construction Features Added Fire Dampers in HVAC Ducts Table VII-3 Table VII-4 Table VII-5 Table VII-6 Table VII-7 Table VII-8 Rev. 9 Page v VII-108 VII-109 VII-110 VII-112 VII-113 VII-114 I

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS LIST OF FIGURES Rev. 9 Page vi PART II - FIRE PROTECTION PLAN (All drawings will be current active version)

Figure II-1 Figure 11-2 Figure 1H-3 Figure 11-4 Figure 11-5 Figure 1H-6 Figure 11-7 Figure 11-8 Figure 11-9 Figure II-10 Figure II-1I Figure 11-12 Figure 11-13 Figure II-14a Figure U-14b1 Figure II-14c Figure 11-15 Figure 11-16 Figure 11-17 Figure 11-18 Figure 11-19 Figure 11-20 1,2-47W850-1 1,2-47W850-2 1,2-47W850-3 1,2-47W850-4 1,2-47W850-5 1,2-47W850-6 1,2-47W850-7 1,247W850-8 1,2-47W850-9 1,2-47W850-10 1,2-47W850-11 1,2-47W850-12 1,2-47W850-20 1,2-47W850-24 1,2-47W8V5o-26 1,247W850-27 1,2-47W843-1 1,2-47W843-2 1,2-47W610-26-1 1,2-47W610-26-2 1,2-47W611-26-1 1,2-47W611-26-2 Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Transgrmer Fire Protection System Flow Diagram Transformer, Yard & MWTP HPFP Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram CQ Storage, Fire Protection and Purging System Flow Diagram CQ Storage and Fire Protection Mechanical Control Diagram High Pressure Fire Protection System Mechanical Control Diagram High Pressure Fire Protection System Mechanical Logic Diagram High Pressure Fire Protection Mechanical Logic Diagram High Pressure Fire Protection I

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS LIST OF FIGURES PART II - FIRE PROTECTION PLAN (Continued)

Figure 11-21 1,2-47W610-39-1 Figure 11-22 1,2-47W610-39-2 1,2-47W611-39-1 1,2-47W611-39-2 1,2-47W611-13-1 1,2-47W611-13-2 1,2-47W611-13-3 1,2-47W611-13-4 1,2-47W611-13-5 1,2-47W611-13-6 1,2.47W611-13-7 1,2-47W600-245 1,2-47W600-246 1,2-47W600-247 1,2-47W600-248 1,2-47W600-249 1,2-47W600-250 1,2-47W600-251 1,247W600-252 1,2-47W600-253 Mechanical Control Diagram C02 Storage Fire Protection and Purging System Mechanical Control Diagram C02 Storage Fire Protection and Purging !stem Logic Diagram C02 Storage, Fire Protection Purging System Logic Diagram C02 Storage, Fire Protection and Purging System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Rev. 9 Page vii Figure 11-23 Figure 11-24 Figure 11-25 Figure 11-26 Figure 11-27 Figure 11-28 Figure 11-29 Figure 11-30 Figure 11-31 Figure 11-32 Figure 11-33 Figure 11-34 Figure 11-35 Figure 11-36 Figure 11-37 Figure 11-38 Figure 11-39 Figure H-40

SQN FIRE PROTECTION REPORT Rev. 9 TABLE OF CONTENTS Pagze viii LIST OF FIGURES PART II - FIRE PROTECTION PLAN (Continued)

Figure 11-41 1,2-47W600-254 Mechanical Instruments and Controls Figure 11-42 1,2-47W600-255 Mechanical Instruments and Controls Figure 11-43 1,2-47W600-256 Mechanical Instruments and Controls Figure 11-44 1,2-47W600-257 Mechanical Instruments and Controls Figure 11-45 L,2-47W600-258 Mechanical Instruments and Controls Figure 11-46 1,2-47W600-259 Mechanical Instruments and Controls Figure 11-47 1,2-47W600-260 Mechanical Instruments and Controls Figure 11-48 1,2.47W600-270 Mechanical Instruments and Controls PART m - SAFE SHUTDOWN CAPABILITIES Figure III-1 Appendix R Safe Shutdown Logic Diagram PART X - FIRE HAZARDS ANALYSIS Figure X-1 1,2-47W494-1 Auxiliary Building CompartmentationfEL 653 & 669 Figure X-2 1,2-47W494-2 Auxiliary Building and Reactor Building Compartmentation EL 685 & 690 Figure X-3 1,2-47W494-3 Auxiliary Building Compartmentation EL 706 & 714 Figure X-4 1,247W494-4 Auxiliary Building Compartmentation EL 732 & 734 Figure X-5 1,2-47W494-5 Auxiliary Building Compartmentation EL 749, 759, & 763 Figure X-6 1,2-47W494-6 Control Building Compartmentation EL 669 & 685 Figure X-7 1,2-47W494-7 Control Building Compartmentation EL 706 & 732 Figure X-8 1,2-47W494-8 Diesel Generator Building Compartmentation EL 722 & 740.5 Figure X-9 1,2-47W494-9 ERCW Pumping Station Compartmentation EL 625 & 688 Figure X-10 1,247W494-10 ERCW Pumping Station Conipartmentation EL 704 & 720

SQN FIRE PROTECTION REPORT Rev. 9 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

Approved 0

Initial Issue 8/23/96 Revision 1 to the Fire Protection Report (FPR) is a complete revision of the 11/19/98 document. The previously issued change packages (FPR-01-1 thru -13) have all been incorporated and interfiled with this revision. These change packages have been approved by PORC independently. Besides minor editorial changes (e.g.,

correction of typographical errors, clarification of wording, etc.), the only new change to the FPR is to Part II, Section 14, in which the surveillance requirements (SR) for hose station inspections and valve position verification of valves in the Reactor Buildings have been revised. Also, a new SR has been added for valve actuation of hose station standpipe valves.

All significant changes made by Revision 1 (e.g., change package revisions, the above mentioned surveillance requirements, etc.) are designated by revision bars.

2 Revision 2 to the FPR is to incorporate Fire Detection Zones 547 and 548 into 12/17/98 Part II, Table 3.3-11. These zones are being added by DCN M-14226-A, which is installing automatic fire suppression and detection into the general area of Elevation 690.0, above the Boric Acid Tanks.

Pages Changed: Coversheet, i, ii, iii, 11-48 Pages Added: 11-67 Pages Deleted: None Note: Sections with page(s) affected by this change are being included in their entirety and issued with this change package. Therefore, the entire sections will be issued as Rev. 2, with the specific changes denoted by revision bars.

i I

SQN FIRE PROTECTION REPORT Rev. 9 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

Approved 3

Revision 3 to the FPR affects Part VII and Part II, Sections 5.0 and 14.0. For 2/11/99 continuity and consistency in pagination, the sections are being issued in their entirety as Rev. 3, with the actual changes denoted by revision bars.

The changes to Part VII of the FPR were made as part of the corrective action plan for resolution of CAQ SQ962075PER. The PER was originally initiated due to a discrepancy between actual plant configuration and the justification for an NRC approved deviation to 10CFR50 Appendix R. The changes made in Rev. 3 of the FPR include resolution of documentation discrepancies involving combustible loading values, updates of cable rerouting, raceway barrier installations, procedure changes, etc. The nature of the discrepancies were all documentation only, and did not represent any unanalyzed configurations in the plant. Also, minor changes to existing evaluations in Part VII were done as enhancements.

Changes to Part II of the FPR included the addition of the definition of "In-situ Combustible Loading," and the allowance for exceeding the compensatory measure time requirements, as specified by the Fire Operating Requirements (FORs), for fire suppression/detection equipment and fire barriers taken out of service during outages. The compensatory measures (i.e., backup fire suppression and/or fire watches) will remain in place until the equipment is placed back in service after the necessary outage-related work is completed.

4 Revision 4 to the FPR is in support of DCN D-20152. The change to the FPR involves deleting the discussion on the smoke detection in the ventilation intake ducts in the Main Control Room from Part VIII, pages 53 and 54. The DCN abandons the detectors in place, and disconnects the annunciation circuits to the MCR.

Pages Changed: Coversheet, i, ii, iii, v, VIII-53, VIII-54 Pages Added: None Pages Deleted: None Note: Section VIII is being included in its entirety in the R4 change package, with the specific changes denoted by revision bars.

ii

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SQN FIRE PROTECTION REPORT Rev. 9 RIVlTITON 1 OG("

Revision DESCRIPTION OF REVISION Date No.

Approved 4

Minor format change to support electronic filing (Curator) conversion.

8/19/99 5

Revision 5 to the Fire Protection Report (FPR) was performed to incorporate the following changes:

Added Part II, Section 14.7 to incorporate new Fire Operating Requirement (FOR) 3.7.14 and Surveillance Requirement (SR) 4.7.14 for Emergency Battery Lighting (EBL) units, including compensatory actions and testing frequencies. Also revised Part V "Emergency Lighting and Reactor Coolant Pump Oil Collection" to address new FOR and SR; Revised Part II, Section 14.5 (FOR/SR 3/4.7.11.4) for Fire Hose Stations to allow use of portable hose packs and removal of fire hoses from the hose stations inside the Reactor Buildings; Clarified definitions for continuous and roving fire watches 'n Part II, Section 13.0; Clarified compliance with NFPA-72D regarding exception to G-73 for "bypassing the audible annunciation system in the Main Control Room (MCR),

Panel 0-M-29, under the direct supervision of a dedicated operator at the console.

Revised Section 3.31 of Part VII to replace summary of superseded calculation MDQ0026-980017, "Fire Barrier Rating Evaluation for Hollow Block and Partially Filled 8" Concrete Block Walls" with calculation SCGI S591, "Fire Ratings of Hollow Core Masonry Walls."

"* Corrected minor documentation discrepancy in Part II, Table 3.3-11, in which the number of ionization fire detectors for Zone 230 was listed as 9, instead of the correct number of 10 detectors in the zone.

"* Revised Part II, Section 14.0 to reference Calculation SQN-SQS2-203, which addresses processes for restoring inoperable Appendix R equipment that is not currently boundea by existing Tech Specs to operable status.

"* Minor administrative change to Revision 4 Rev Log description1to delete statement regarding MCR HVAC duct smoke detector abandonment in response to a recommendation from QA audit SSA0001. The recommendation was to remove the statement, "The duct detectors have been determined unnecessary based on the absence of industry in the vicinity that could be capable of producing significant enough smoke to affect the habitability in the MCR, and the detectors in the El. 732.0' Mechanical Equipment Room which will detect smoke entering the MCR ventilation system intake and subsequently alarm in the MCR," because it provided unnecessary detail that was not discussed in the FPR.

iii r

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SQN FIRE PROTECTION REPORT Rev. 9 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

Approved Changed required testing frequency for inaccessible detectors from "each COLD 6

SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 month" to 10/18/00 every 18 months during cold shutdowns (page 11-42). Related editorial changes to this page, FPR cover sheet, and the table of contents.

Changed the compensatory actions for LCO 3.3.3.8 to delete fire watches and 7

temperature monitoring inside primary containment upon failure of a detector 1/29/01 inside primary containment (page 11-42). The bases for the LCO compensatory (effective actions for inoperable detectors inside primary containment were also changed.

2/1/01)

(pages 11-65 and 66).

This revision incorporates the following changes to parti 2:

"" Changes the testing frequency for detectors which require removing plant 2/26/01 equipment from service from 6 to 18 months and deletes the requirement to perform the 18 month detector tests during cold shutdowns from Surveillance Requirement 4.3.3.8.1 on page 11-42.

"* Adds a fire detection basis on page 11-66 for the above change in test frequency which gives examples of the equipment which must be removed from service for detector testing (EGTS, ABGTS, CREVS and containment purge). They two above changes are corrective action for PER-00-006637 000.

Adds a definition for "accessible" on page 11-5.

Adds an existing heat detector to zone 466 in Table 3.3-11 on page 11-49.

Adds a end-of-quarter "grace period" to the annual fire brigade medical examination requirement on page 11-20.

Deletes three references to raw service water flow diagrams and adds five references to fire protection flow diagrams on page 11-73 (added diagrams are for the fire pumps/tanks, yard piping, the ERCW Bldg. and two cable tray water spray systems).

Related editorial changes were made to this Rev. Log, the FPR cover sheet, and the table of contents.

This revision incorporates the following changes to the FPR Parts III and V, due 9

to the Vital Inverter System modification per DCN D20071A/P20872A as 10/12/2001 applicable:

"* Added references to DCN D20071A/P20872A, see section 11.2.13 of Part III and section 4.1.5 of Part V.

"* Revised the description of the 120VAC Vital Instrument and 25OVdc Power System, see section 4.10.3 and 4.10.5 respectively, of Part Il1.

"* Added Components to the illuminated list of Part V, see Table V-I, pages V 4 and V-7.

Related editorial changes were made to this revision log, the FPR cover sheet and the table of contents.

The Nuclear Safety Assessment for the above changes is in the "Fire protection (Appendix R)" section of Block 15 in DCN D20071A iv

SQN FIRE PROTECTION REPORT PART Il - SAFE SHUTDOWN CAPABILITIES Rev. 9

1.0 INTRODUCTION

This part describes the safe shutdown analysis methodology used to identify, select, and analyze the systems, components, and cables needed to demonstrate compliance with Appendix R to 1 OCFR50, and the applicable NRC generic letters.

Paragraph 50.48(a) & (e) and Appendix R of 10CFR50 became effective on February 17, 1981 and requires all nuclear plants licensed to operate prior to January 1, 1979 to comply with the requirements of IOCFR50 Appendix R Sections III.G, III.J, and 111.0. SQN was licensed after this date and must comply with these sections of Appendix R Additionally, by a Unit 2 license condition, SQN must comply with Sections III.G, III.J, II.L, and 111.0 of Appendix R.

Section III.G.l requires that fire protection features be provided for those systems, structures, and components important to safe shutdown. These features must be capable of limiting fire damage so that:

(1)

One train of systems necessary to achieve and maintain hot shutdown conditions from either the Control Room or the Emergency Control Station(s) is free of fire damage; and, (2)

Systems necessary to achieve and maintain cold shutdown from either the Control Room or the Emergency Control Station(s) can be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Where alternative shutdown capability is required (i.e., for control building fires that require "shutdown from outside of the Control Room), cold shutdown must be achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Alternate shutdown capability is evaluated per Appendix R Sections III.G.3 and III.L. Plant locations that do not require alternative shutdown capability are evaluated per Section III.G.2 of Appendix R. Generic Letter 81 12 (February 20, 1981) Enclosure 1 "Staff Position", provides additional guidance on the NRC's requirements for safe shutdown capability.

1.1 Design Basis Evaluation The purpose of this evaluation is to demonstrate fire safe shutdown capability for postulated fires involving in situ and/or transient combustibles that could imlkact systems, structures, or compotints located in or adjacent to that area. For purposes of this evaluation, it is assumed that these fires may adversely affect these systems, structures or components essential to safe shutdown. The availability of offsite power for specific systems and/or fire scenarios has been evaluated for non-alternative shutdown locations. Loss of offsite power has been assumed for control building fires, for which alternative shutdown is provided. No concurrent or sequential design basis accidents or transients are assumed to occur. Failures that are a consequence of the fire are evaluated. No additional single failures are assumed (ref. 11.1.1).

1.2 Limiting Safety Consequences The limiting safety consequences used in the evaluation of fire safe shutdown are: (1) no fuel failure due to calculated cladding temperature increases; (2) no rupture of any primary coolant boundary; (3) no rupture of the containment boundary; (4) following the event, the reactor coolant system process variables shall be within those predicted for a loss of normal ac power; and (5) shutdown capability shall be able to achieve and maintain subcritical conditions in the reactor, maintain reactor coolant inventory, achieve and maintain hot standby conditions for an extended period of time, achieve cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with equipment powered by onsite power sources if using alternative shutdown methods, and maintain III-1

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 cold shutdown conditions thereafter (ref. 11.1.1).

Generic Letter 81-12, Enclosure 1, specifies the performance goals and associated safe shutdown functions necessary to ensure the limiting safety consequences of the fire safe shutdown analysis. Other subfunctions may exist under each of these broad headings. Examples of such subfunctions are steam generator secondary side isolation, and RCS seal injection. Other subfunctions such as on site emergency power, environmental control, etc., are included as support functions.

The performance goals and safe shutdown functions identified in the generic letter adequately ensure that the containment pressure boundary will not be threatened. Uncontrolled mass and energy releases to the containment from the primary systems are limited by the achievement of these safe shutdown functions and will ensure that no rupture of the reactor coolant or containment pressure boundaries will occur.

2.0 SAFE SHUTDOWN FUNCTIONS This section provides a brief overview of the SQN safe shutdown functions. The specific safe shutdown functions necessary to satisfy the performance goals and safe shutdown functions of Appendix R as identified in Enclosure 1 to Generic Letter 81-12 are:

(1)

Reactivity control function (2)

Reactor coolant makeup function (3)

Reactor coolant pressure control function

"(4)

Decay heat removal function (5)

Process monitoring function (6)

Support function 2.1 Reactivity Control Reactor trip capability is by inserting control and shutdown rods into the reactor. After a reactor trip, the reactivity control system (boration),must be capable of achieving and maintaining adequate shutdown reactivity from zero power hot standby to cold shutdown. The function must be capable of compensating for any re-itivity" changes associated with xetfon decay and reactor coolant temperature decrease which occur during cooldown to cold shutdown conditions.

2.2 Reactor Coolant Make-up The reactor coolant make-up systems shall be capable of assuring that shfficient make-up inventory is provided to compensate for reactor coolant system (RCS) fluid losses due to identified leakage from the reactor coolant pressure boundary and shrinkage of the RCS water volume during cooldown from hot standby to cold shutdown conditions. Adequate performance of this function is demonstrated by the maintenance of reactor coolant level within the pressurizer.

2.3.

Reactor Coolant Pressure Control Reactor coolant pressure control is required to assure that the RCS is operated:

(1)

Within the technical specifications for RCS pressure-temperature requirements; (2)

To prevent peak RCS pressure from exceeding 110% of system design pressure; and III-2

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 (3)

With a sufficient subcooling margin to minimize void formation within the reactor vessel.

2.4 Decay Heat Removal The decay heat removal systems shall be capable of transferring fission product decay heat from the reactor core at a rate such that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. The function shall be capable of maintaining hot standby using AFW for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, achieving cold shutdown (within a 72-hour period for alternate shutdown), and maintaining cold shutdown conditions thereafter using RHR.

2.5 Process Monitoring When information on process variables is required by operators to achieve/maintain safe shutdown system or control safe shutdown equipment, such monitoring information must be available. The process monitoring function shall be capable of providing, if possible, direct readings of those plant process variables necessary for plant operators to perform and/or control the previously identified functions.

2.6 Support The systems and equipment used to perform the Fire Safe Shutdown (FSSD) functions may require miscellaneous support functions such as process cooling, lubrication and ac/dc power. These supporting functions shall be available and capable of providing the support necessary to assure acceptable performance of the FSSD functions.

3.0 ANALYSIS OF SAFE SHUTDOWN SYSTEMS 3.1 Introduction Various analytical approaches ensure that sufficient plant systems are available to perform the FSSD functions. Numerous plant systems are available, alone and in combination with other systems, to provide these required functions. A minimum set of plant systems and components is identified to demonstrate that the plant can achieve and maintain 'safe shutdown. In addition, for control building fires that require shutdown from outside of the main control room, the concurrent loss of off-site power is also assumed.

Providing adequate protection of this minimum system, component, and cable set from the effects of

.postulated fires constitutes an adequate and conservative demonstration of the ability to achieve and maintain safe shutdown for the purpose of fire protection.

The safe shutdown systems selected are capable of:

a) achieving and maintaining subcritical conditions in the reactor, b) maintaining reactor coolant inventory, c) achieving and maintaining hot shutdown conditions for an extended period of time, d) performing cold shutdown repairs needed to achieve and maintain cold shutdown (or, for control building fires that require shutdown from outside of the main control room, achieving cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />), and e) maintaining cold shutdown conditions thereafter.

3.2 Initial Assumptions 111-3

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 (1) The unit is operating at 100% power upon the occurrence of a fire.

(2) For alternative shutdown locations (Control Building fires that require shutdown from outside of the Control Room), a loss of off-site power is assumed.

(3) The reactor is tripped either manually or automatically.

(4) No failures are considered other than those directly attributable to the fire.

(5) Equipment required for safe shutdown is assumed to be operable (i.e., not out of service).

3.3 Definitions Hot Standby The initial safe shutdown state with the reactor at zero power, (Mode 3) less than 0.99 and average RCS temperature Tg greater than or equal to Hot Shutdown (Mode 4)

Cold Shutdown (Mode 5)

Subcooling Mar 3500F.

Reactor at zero power Kff less than 0.99 and average RCS temperature T, between 350CF and 20(PF.

Reactor at zero power, IKf less than 0.99 and average RCS temperature T, below or equal to 20(0F.

gin The difference between the saturation temperature at RCS pressure, and the maximum temperature in the hot legs.

3.4 Safe Shutdown Functions The following is a comparison of the Generic Letter 81-12 safe shutdown functions and the corresponding safety functions us~d in the Appendix R FSSD analysis (ref. 11.2.1):

GL 81-12 Safe Shutdown Function SQN Safety Functions Reactivity Control Initial Reactivity Control Long Term Reactivity Control Reactor Coolant Makeup Control RCS Inventory Control RCP Seal Integrity RCS Pressure Boundary Control RCS Makeup and Letdown Reactor Coolant Pressure.Control RCS Inventory Control RCS Pressure Boundary Control RCS Makeup/Letdown Decay Heat Removal SG Inventory Control Secondary Side Pressure Control 111-4

SQN FIRE PROTECTION REPORT PART IIH - SAFE SHUTDOWN CAPABILITIES Rev. 9 Secondary Side Isolation Long-Term Heat Removal Process Monitoring Instiumentation (no specific correlation, in logic by system)

Support Onsite Electrical Supply Environmental Control (Process Cooling, in logic by system)

Each plant system or subsystem function relied on to accomplish the above safe shutdown functions is identified (ref. 11.2.1). A separate designator identified as a safe shutdown "Key" is assigned to each plant system or subsystem function. Figure III-I "Appendix R Safe Shutdown Logic Diagram" depicts the safe shutdown system and/or system function, associated Key number, and logical relationships between systems and Keys used to demonstrate compliance with Appendix R criteria. The correlation between Keys and safe shutdown systems is provided in Section 4. The following sections provide a general description of the methods and systems used in reference 11.2.1 to satisfy the safe shutdown performance goals and functions as delineated in Generic Letter 81-12.

3.4.1 Reactivity Control At least one source range neutron monitor is provided for indication of count rate to verify the reactor is subcritical.

Initial reactivity control will result from an automatic reactor protection system (RPS) trip or from operator initiation of a manual trip upon notification of a major fire affecting safe unit operation. This action will deenergize the normally energized CRDMs to actuate a reactor trip. The RPS has a diversity of inputs, each of which "fails safe" and will actuate on an open circuit or a loss of power. As such, fire damage to the RPS will not preclude the initiation of an automatic trip or control rod insertion. There are four paths to manually trip the reactor. There is a shunt trip path for each of the two trains and an undervoltage trip path for each of the two trains. The shunt trip path trips the reactor by energizing the shunt trip coil in the reactor trip switchgear through a handswitch contact in the main control room. The undervoltage trip path trips the reactor by deenergizing the uhderV'1tage trip coil in thb reactor trip switchgear throngh a handswitch contact in the main control room. For an undervoltage trip path to fail, a perfect short to another power source must occur. For a shunt trip path to fail, the path must be open without shorting. It is therefore considered incredible that all four paths will fail in the specific manner to disable each representative path, particularly since the trip handswitches in the main control room utilize all four paths simultaneously when placed in the trip position. Procedure FR-S. 1, "ATWS", covers operator actions that may be required in the unlikely event that all four paths fail in the manual trip circuits.

Following rod insertion, additional negative reactivity insertion is required as xenon decays, and RCS temperature is decreased. The addition of borated water from the refueling water storage tank (RWST) is required to maintain the required shutdown reactivity. The chemical and volume control system (CVCS) is capable of injecting borated water into the RCS and the normal, excess, and alternate letdown paths (RVHV, PORVs) are capable of sufficient letdown to monitor shutdown reactivity.

3.4.2 Reactor Coolant Make-up Control For the assumed fire scenario, reactor coolant make-up control can be achieved by the following to 111-5

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 assure that primary side inventory (pressurizer level) is maintained:

I.

One CCP, including ERCW and CCS loops and room cooling for appropriate CCP must be operational.

2.

A suction path from either the VCT or the RWST to the CCPs must be available.

3.

Charging flow control valve or a bypass must be available (manual operation of by pass valves is acceptable) and pressurizer level indication.

4.

A charging path to the RCS through either the RCP seal injection or RCP thermal barrier cooling.

5.

Cooling to the RCP seals through either R(P seal injection or RCP thermal barrier cooling.

6.

RCS pressure boundary isolation for normal and excess letdown, reactor head vent, RHR suction, pressurizer PORV's

7.

Pressurizer level instrumentation.

8.

RCS Letdown (Normal/Excess/Altemate) 3.4.3 Reactor Coolant Pressure Control Establishing and maintaining a sufficient subcooling margin within the RCS is required to prevent void formation in the core and to ensure the ability to maintain natural circulation (if the RCPs are not operable) through the steam generators. Overpressure protection of the RCS is provided by the pressurizer safety valves prior to a controlled cooldown and depressurization. During cooldown from Mode 3 hot standby (above 35(0F) to Mode 4 hot shutdown (below 350F), pressure control may be by pressurizer heaters or by varying pressurizer level in combination with control of SG pressure and RCS temperature using SG PORVs Pressure may also be reduced by normal/excess/alternate letdown paths. To ensure adequate RCS pressure and adequate subcooling margin, the operator will isolate the normal pressurizer spray valves, or trip the RCPs to limit depressurization, and isolate the pressurizer PORVs and auxiliary spray. Entering Mode 4 will ¶ermit aligning the RIR system to the RCS for decayiieat removal.- While on RHR, the maximum pressures in both the RIR and RCS systems are limited by the RHR system safety valves.

RCS temperature indication is provided for the two loops used for cooldown and one RCS wide range pressure indicator is provided. Note that RCS cold leg temperature is not provided in the ACR. (See deviation in Part VII.)

3.4.4 Decay Heat Removal Following a reactor trip with loss of off-site power (either assumed or caused by the fire), decay heat

• is initially removed by natural circulation within the RCS, heattansfer to the main steam system. via the steam generators, and operation of the steam generator PORVs or lift of the main steam system code safety valves. The secondary side of the SGs are isolated from the main turbine, main feedwater pumps, and other steam loads to prevent excessive heat removal from the RCS.

For decay heat removal via natural circulation a minimum of two steam generators will be available 111-6

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 (including SG pressure and level indication). Decay heat removal requires the ability to supply sufficient auxiliary feedwater to the steam generators to make up for the inventory discharged as steam by the safety valves or steam generator PORVs. For maintenance of initial hot standby conditions, the feedwater flow required to the steam generators is supplied by the auxiliary feedwater (AFW) system. AFW sources are available from the condensate storage tanks, and alternatively, from the essential raw cooling water (ERCW) system. AFW may be supplied to the steam generators by the motor-driven AFW pumps and/or by the turbine-driven AFW pump. Continued heat removal is achieved by the controlled operation of the PORVs and continued operation of the AFW system. After reduction of RCS temperature to 350'F, the RHR system is used to establish long-term core cooling by the removal of decay heat from the RCS to the environment via the RHR, CCS, and ERCW systems.

3.4.5 Process Monitorin2 Instrumentation The operator requires knowledge of various plant parameters to perform required system transitions and essential operator actions. A discussion by safe shutdown function of the necessary instrumentation is provided below.

For the fire scenarios assumed in this analysis, inventory make-up to the RCS will be from the refueling water storage tank through the RCP seal injection lines. Sufficient initial negative reactivity exists in the RCS after control rod insertion. The negative reactivity inserted by the control rods and borated water injected by the CVCS will maintain the core subcritical while cooling down from hot full power to cold shutdown. Core source range detectors will be available for core reactivity monitoring in the main control room. Source range channel indication is available in the auxiliary control room to provide this information for fires in control building areas requiring alternative shutdown.

Various process monitoring functions must be available to adequately achieve and maintain the reactor coolant makeup, pressure control and decay heat removal functions. For the assumed fire scenario, maintenance of hot standby requires that pressurizer level and RCS pressure instrumentation be available.

RCS temperature is maintained during hot standby by proper decay heat removal via steam generators using the steam generator PORVs. 'When the reii&or cdolant pumps are tripped and'cooling is required in the natural circulation mode of operation, the difference between the hot-leg and cold-leg wide range temperatures (or saturation temperature for SG pressure) provides indication of the existence of a natural circulation condition.

RCS hot and cold leg temperature instrumentation is available for use given a fire that does not require MCR abandonment. For alternative shutdown, steam generator (SG) pressure instrumentation is required in order to provide a means of determining RCS cold-leg temperature from the ACR. (Refer to Part VII for the deviation request associated with using Tt in lieu of direct indication of T in the ACR.) During RCS cooldown, SG pressure will be controlled to maintain desired RCS temperature by control of the SG PORVs.

Operating personnel will maintain RCS pressure to assure that appropriate subcooling margin is achieved by monitoring of RCS pressure and hot leg temperature (jD instrumentation. Manual control of the pressurizer heaters will be used if available, but is not required for safe shutdown. Pressurizer level control is maintained by monitoring pressurizer level instrumentation and manual control of CVCS charging flow through the RCP seals.

111-7

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 The above methods of controlling primary system parameters by means of the secondary system requires monitoring secondary system parameters. Steam generator level and pressure indicators are available for the loops being used for cooldown to assure adequate and controlled decay heat removal.

The plant operators will utilize the instrumentation discussed above for monitoring natural circulation conditions, subcooling margin, and heat removal.

3.4.6 Support Functions The support functions for various safe shutdown equipment or systems are provided by the following systems:

(1)

Emergency Power Distribution System (2)

Onsite Electric Supply (3)

Essential Raw Cooling Water System (4)

Component Cooling WaterSystem (5)

Ventilation to areas containing essential fire safe shutdownxequipment (6)

Control Air System The following sections discuss the required safe shutdown systems and support systems.

4.0 SAFE SHUTDOWN SYSTEMS The FSSD systems are identified by reference 11.2.1 and are listed by Key in Table III-1 and summarized as follows:

4.1 Chemical and Volume Control System (CVCS) - Keys 1, 2, 4, 5, 6. 9, 34 The charging portion of the Chemical Volume and Control System (CVCS) accomplishes the following safe shutdown functions:

(1)

Reactivity control by injection of boron into the RCS (2)

Reactor coolant make-up control by seal injection (3)

Maintenance of reactor coolant pump seal integrity Reactivity control for safe shutdown is initially provided by the control rods, with subsequent boron injection used to compensate for the xenon decay and positive reactivity insertion due to cooldown. Insertion of the control and shutdown rod groups make the reactor adequately subcritical following trip from any credible operation condition to the hot zero power condition, even assuming the most reactive rod remains in the fully withdrawn position.

For the assumed post-fire scenario, make-up water to the RCS.will be provided by.the CVCS initially from the VCT and then from the RWST. When the unit is at power, the concentration of boron in the RWST exceeds that quantity required to bring the reactor from an initial hot standby condition to hot shutdown and

" then to cold shutdown.

Numerous CVCS paths are normally available for charging to the RCS (normal charging, seal 111-8

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES Rev. 9 injection, ECCS charging). The post-fire flow path normally qualified to provide reactor coolant make-up and boration is the charging line to the reactor coolant pump seals. This path will be available by ensuring that at least one of the charging pumps is operable and charging flow control valve remains open or is manually bypassed.

For the assumed event, charging and boration will be accomplished by operating a minimum of one centrifugal charging pump taking suction from the RWST and injecting borated water through the RCP seal injection line to the RCS. Suction to the charging pump can be delivered from the RWST by opening either one of two normally closed motor-operated valves.

Letdown from the RCS normally occurs via the seal leak-off retum path and the normal and/or excess letdown paths. For the post-fire operational scenario, the normal and excess letdown paths may be isolated. Isolation of the normal and excess letdown lines may occur as a result of loss of instrument air or may be achieved by operator action to assure adequate inventory control. Procedural controls ensure isolation of all potentially spurious RCS letdown paths, including pressurizer PORVs and reactor head vents as necessary.

The injection path from the charging pumps to the reactor coolant pump seals contains the charging flow control valve (normally open) which is provided with a minimum-flow stop on the controller. Thus,

-operation of one charging pump will ensure availability of minimum RCS charging flow. In the event of failure of the minimum flow stop and complete cutoff of injection path flow, thermal barrier cooling (Key 9) is credited to assure seal integrity until charging is reestablished. Thermal barrier cooling ensures that the "RCP seal integrity is maintained. No boron injection is required during this period.

Isolation of the volume control tank (VCT) by closure of either one of two motor-operated valves during makeup from the RWST can be performed either remotely or by local manual operation. The VCT is isolated to prevent introduction of Ii covergas into the CCP suction in the event of VCT drainage.

Pressurizer water level is maintained by operation of one centrifugal charging pump using pressurizer level instrumentation. The two high-head centrifugal charging pumps are normally available for the CVCS charging function and have a miniflow path through the seal water heat exchanger. The pumps require cooling water fromfi the component c661ing -ystem (CCS) to their mechatfical-seal heat exchangers and ERCW to the gear oil coolers and pump bearing oil coolers. The CCP room coolers require ERCW.

The capacity of the refueling water storage tank is based on ECCS injection and for filling the refueling cavity. This quantity is in excess of that required for makeup due to fire safe shutdown requirements.

4.2 Reactor Coolant System - Keys 7, 8. 28. 48 The RCS consists of four similar heat transfer loops connected in parallel to the reactor vessel. Each loop contains a reactor coolant pump and a steam generator. In addition, the system includes a pressurizer with associated code safety and power-operated relief valves (PORVs). RCS instrumentation includes wide range cold-leg (except in ACR) and wide range hot-leg temperatures indication, pressure indication, and pressurizer water level indication.

The natural circulation capability of the plant provides a means of decay heat removal when the reactor coolant pumps are unavailable. Natural circulation flow rates are governed by the amount of decay Ili-9

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 heat, relative component elevations, primary to secondary heat transfer, loop flow resistance, steam generator and RCS inventories, and any RCS voiding. These conditions determine whether adequate primary to secondary heat transfer and subcooling during natural circulation can be maintained For this analysis of safe shutdown capability, two of the four RCS loops (for which steam generator level and pressure are controlled) will be available to ensure that natural circulation is established and maintained. Additionally, RCPB isolation is provided to ensure subcooling margin is maintained. RCPB consists of isolation of normal letdown, excess letdown, pressurizer PORVs or blocks, RVHV and RHR letdown. Referto the discussion on High/Low pressure boundary interfaces in Section 8.0 of this part.

While in natural circulation, adequate heat transfer and coolant flow are dependent on adequate inventory in both the primary and secondary systems. Maintaining water level in the secondary side of the steam generators and adequate level within the pressurizer are required for natural circulation. RCS loop temperatures confirm flow and heat transfer while in natural circulation.

RCS inventory control is based on the operation of CVCS charging paths as previously described.

Maintenance of either seal injection or thermal barrier cooling provides adequate protection of the RCP seals Letdown is provided to allow for a method of depressurizing the RCS and further boration of the RCS.

Letdown path options include normal letdown, excess letdown, RCP seal return, RVHV and pressurizer PORVs.

The pressurizer heaters are not required to operate for safe shutdown. Alternate means of controlling RCS pressure are available. However, should the pressurizer heaters be available, subcooling within the RCS can be maintained by controlled operation of the pressurizer heaters. The availability of pressurizer heaters will enhance the capability of controlling RCS pressure and subcooling margin.

4.3 Main Steam Systems - Keys 20, 21, 22, 23, 24, 25, 26 For the post-fire scenario, maintenance of the steam generator inventory and control of steam generator pressure are required for both hot standby and subsequent primary system cooldown to support the decay and sensible heat removal function, within the applicable operational limits, until initiation 'of RHR to bring the plant to cold shutdown.

The main steam (MS) system consists of four parallel flow paths, one from each steam generator to the main turbine of the unit. The MS system will be isolated either by operation of the turbine stop and control, dump, reheat, feed turbine stop and control, and gland steam valves; or by the main steam isolation valves.

The main feedwater system will be isolated by the MFIV, regulating valves and bypasses, or trip of the MFW pumps.

Inventory control of two steam generators provides the reactor heat removal function during natural circulation conditions. Maintenance of the steam generator water level during the period of AFW operation.

(hot standby) involves positioning of AFW valves and operation of the motor-driven and/or turbine-driven AFW pumps. Steam generator water level and pressure indication are available in the MCR and in the ACR.

The MS system also delivers motive steam to the turbine-driven AFW pump. Steam to the turbine is supplied by branch connections upstream of the main steam isolation valves on two steam lines II-10

SQN FIRE PROTECTION REPORT PART 11 - SAFE SHUTDOWN CAPABILITIES Rev. 9 (corresponding to steam generators No. 1 and 4). Either line is sufficient to supply steam for the AFW pump turbine.

A power-operated relief valve (PORV) provided on each steam line is capable of releasing the sensible and decay heat to the atmosphere. The SG PORVs are used for plant cooldown by steam discharge to the atmosphere since the steam dump system is assumed to be unavailable. The SG PORVs have a total combined capacity of approximately 10% of the maximum steam flow. For the assumed fire scenario, a minimum of two PORVs will be available to support controlled cooldown of the Reactor Coolant System.

Controls for the steam generator PORVs are provided in the MCR and locally at the shutdown stations.

4.4 Auxiliary Feedwater System - Keys 11, 12, 14, 15, 16 17, 19 The AFW system is required during hot standby to support RCS decay heat removal. For hot standby, secondary system (steam generator) inventory control is provided by the AFW system. Two motor driven pumps and one turbine-driven pump are available to each unit.

The AFW system is designed to deliver enough water to maintain sufficient heat transfer in the steam generators in order to prevent loss of primary water through the RCS pressurizer safety or relief valves.

The turbine-driven AFW pump is designed to deliver sufficient flow to all four steam generators and maintain steam generator water levels. Steam generators No. 1 and/or 4 provide motive steam to the turbine driven AFW pump. The turbine-driven AFW pump is capable of operating down to a steam pressure of 90 psia, which is below the point at which the RHR system can be placed in service.

Each unit is supplied with two motor-driven AFW pumps with only one required for safe shutdown.

Pump A supplies SGs 1 and 2 and B supplies SGs 3 and 4.

The Condensate Storage Tank (CST) contains a minimum volume of water required by the plant technical specification. As a backup, cross-ties to the Essential Raw Cooling Water System (ERCW) are provided. Ample time is available post-fire for realignment of the normally closed valves that isolate ERCW from the suction of the AFW pumps.

"III-11

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES Rev. 9 4.5 Residual Heat Removal System - Keys 30, 31, 40 The RHR system is designed to remove residual and sensible heat from the core by reducing the temperature of the RCS during the hot shutdown and cold shutdown modes.

The RHR system consists of two RHR heat exchangers, two RHR pumps and associated piping, valving and ihstrumentation necessary on each unit.

During hot shutdown and cold shutdown operations, reactor coolant flows from the RCS to the RHR pumps, through the tube side of the RHR heat exchangers and back to the RCS. The heat load is transferred to CCS on the shell side of the RHR heat exchangers.

Two series motor-operated valves (FCV-74-1,-2) isolate the inlet line to the RHR system from the RCS. To avoid potential RCS boundary leakage at this high/low pressure interface, both of the motor operated valves in the RHIR suction line will be kept closed (pre-fire condition) with the corresponding motor control center breaker in the open position. The return lines are isolated by two series check valves and a motor-operated valve in each return line.

A minimum-flow line from the downstream side of each RIJ-R heat exchanger to the corresponding pump's suction line is provided to assure that the RHR pumps do not overheat under low flow conditions. A motor-operated valve located in each minimum flow line is opened if RHR pump flow falls below a low set point and will be closed when the flow increases above a high set point.

The cooldown rate of the reactor coolant is controlled by regulating the flow through the tube side of the RHR heat exchangers. A bypass line, which serves both residual heat exchangers, is used to regulate the temperature of the return flow to the RCS as well as to maintain a minimum flow through the RHR system.

The RHR system can be placed in operation when the pressure and temperature of the RCS are about 380 psig and 35CPF, respectively. If one of the two RHR pumps and/or one of the two RHR heat exchangers is not operable, safe operation of the plant is not affected; however, the time for cooldown is extended.

Each RHR pump is sized to deliver sufficient reactor cloolant flow through the residual heat exchangers to meet the plant cooldown requirements. A seal heat exchanger for each pump is cooled by CCS. RHR pump room cooling is provided by a room cooler and ERCW. Local handwheel operation of all RHR valves requiring realignment for cooldown is acceptable based on the time to achieve cold shutdown.

The RHR system safety valves (although not specifically listed in the shutdown logic) are available to provide RHR and RCS cold overpressure protection whenever the RHR system is in operation.

111-12

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 4.6 Safety Iniection System Accumulators - Key 36 During normal plant operating conditions, the safety injection system accumulators are pressurized by nitrogen gas in order to inject borated water into the RCS when RCS pressure falls below 600 psi due to a LOCA. During a controlled depressurization, the accumulators are isolated to prevent injection of safety injection system accumulator borated water and nitrogen gas into the RCS. Injection of nitrogen into the RCS occurs when RCS pressure is less than 150 psi.

The manual isolation of the accumulators or nitrogen gas venting to depressurize the accumulators is assumed as a post-fire activity. The isolation valve at each accumulator is closed only when the RCS is intentionally depressurized below 1000 psig. If the cables associated with these valves were damaged by fire, the accumulators are vented. The isolation or venting may be locally, governed by appropriate plant procedures (post-fire). In the event the valves are inaccessible, RCS pressure will be maintained greater than 150 psi to preclude nitrogen injection into the RCS via the accumulators.

4.7 Component Cooling Water System - Key 1. 9,31 CCS is a supporting system to other safe shutdown systems. Two redundant paths are available, each consisting of pump(s), heit exchanger(s), surge tank(s) and associated valves, piping and local instrumentation. The CCS system serves as an intermediate heat transfer loop between the various safe shutdown -components and the Essential Raw Cooling Water System (ultimate heat sink).

The CCS system provides cooling for the following safe shutdown equipment:

(1)

Residual Heat Removal exchangers (2)

Centrifugal charging pumps mechanical-seal heat exchangers (3)

Residual heat removal pumps mechanical-seal heat exchangers (4)

Reactor coolant pump thermal barrier heat exchanger (loaded on train A CCS only)

One pump and one or two component cooling heat exchangers fulfill the heat removal function during normal full-load operation and post fire SSD for various components located in the auxiliary and reactor buildings.

Other than the RHR heat exchangers, the essential loads are normally valved open to the supply header and discharge to the suction of the CCS pump with which they are normally associated, so that component cooling water is circulated coritinuously through the essential loads during normal operation.

The CCS outlet from the RHR heat exchangers have motor-operated valves which must be opened or remain open during RHR cooldown. The motor-operated valves that isolate the RCP thermal barrier coolers (Train A CCS only) are included as safe shutdown components for operational flexibility in a post-fire scenario, since the thermal barriers may be required to perform a diverse function to RCP seal injection.

4.8 Essential Raw Cooling Water System - Key 3 (additional ERCW is Keys 1, 133, 19, 37. 40)

The ERCW system provides cooling for the following safe shutdown heat transfer equipment (additional equipment in other keys):

(1)

Component cooling heat exchangers 111-13

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 (2)

Emergency diesel generator heat exchangers (3)

Essential ventilation coolers and water chillers The system also provides a back-up supply of water to the AFW pump suction in the event that the condensate storage tank is depleted.

This system consists of four traveling water screens and their wash pumps, eight pumps, four discharge strainers, four main supply headers (lA, IB, 2A, and 2B) and 2 discharge headers (A, B). These components, together with the associated heat exchangers, valving, piping and instrumentation, complete the ERCW system.

There are four ERCW pumps per train. Interlocks exist to preclude starting more than one ERCW pump on a single diesel generator. Two ERCW pumps are required per train and one train is required for FSSD.

4.9 Essential HVAC - Keys 37A, 37B, 37C, 37F, 37K, 37N, 370, 37S Essential HVAC is provided for the control, auxiliary, diesel generator, and reactor buildings.

Portions of the systems in each building that service safe shutdown equipment required for compliance with Appendix R have been analyzed to determine if HVAC is required and to ensure that at least one path of the required systems will be available for an Appendix R fire when required. The systems consist of filters, fans, ductwork, dampers, heating/cooling coils, instrumentation, and controls for general building ventilation, along with separate systems for individual rooms. The required systems, components, and cables for those subsystems relied on to protect equipment for safe shutdown have been incorporated into the Appendix R analysis as required equipment and cables. The location of equipment and routing of cables has been identified and evaluated as described in Sections 5 and 6 of this Part. These systems are discussed below.

The primary safety-related portions of the control room are cooled by two independent trains of HVAC. The two trains are separated by fire barriers and/or separation distance in accordance with Appendix R requirements to ensure that the control building HVAC system will remain functional during a fire in the auxiliary building except as provided by an approved deviation. Alternate shutdown is provided for a fire in the control building. The HVAC system in the control rooTn is separate from the HVAC system servicing the ACR.

Portions of the auxiliary building HVAC system is required to achieve and maintain hot standby with subsequent cold shutdown. HVAC is required for the 480V transformer rooms (Key 37K). Individual room coolers are also required for the CCP and RHR pumps and are addressed in the equipment logics for their respective systems (Keys 1 and 40). Temporary ventilation may be used to replace fire damaged HVAC and heat loads may be reduced.

The TDAFW pump room is provided with a DC operated exhaust fan (Key 37N) sized to provide the required air flow in the room for the volume method of cooling The fan is a roof ventilator type with intake and venting to the general area of the Auxiliary building. The fan will automatically start upon the start the TDAFW pump.

The diesel generator HVAC systems serve each combination of diesel, generator and associated batteries and electrical boards. The diesel generator building HVAC system consists of various subsystems.

The subsystems for each combination include diesel generator room HVAC subsystems, generator and 111-14

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 electrical panel subsystems, battery hood exhaust subsystems, electric board room exhaust and heating subsystems, and muffler room exhaust systems. A fire in any combination of diesel generator and associated batteries and electrical boards, which are separate fire areas, will not affect the HVAC systems servicing the adjacent combinations of diesel generator and associated batteries and electrical boards.

All other areas of the plant which contain equipment required for safe shutdown per Appendix R have been evaluated and determined that acceptable temperatures will be maintained for the required equipment to perform its intended FSSD function if HVAC is lost. Some areas require operator action to turn out normal lighting and other electrical loads to reduce the heat load. (i.e. Auxiliary Instrument Room K37B, 480V Board and Battery Rooms K37F, AFW/CCS and AFW/BAT Space Coolers K370, CCS/SFP Space Cooler K37P).

4.10 Electrical Power System - Key 38, 39 The plant Emergency Power System (EPS) includes on-site, independent, automatically-starting emergency power sources that supply power to essential safe shutdown equipment if the normal off-site power sources are unavailable.

The emergency power sources consist of four 6.9kV diesel generators. Each consists of a single generator driven by two engines on a common shaft. Each diesel engine is equipped with its own auxiliaries.

"These include batteries, starting air, fuel oil, lube oil, cooling water, intake and exhaust system, speed regulator (governor) and controls. Cooling water is provided from the ERCW system.

4.10.1 6.9KV Shutdown Power System Each of the four 6.9kV shutdown boards is normally fed from 16lkV/6.9kV common station service transformers (CSSTs) that receive power from offsite sources. Each of four 6.9kV shutdown boards can also be fed from the corresponding 6.9kV diesel generator. Loss of offsite power to the 6.9kV boards is sensed by.

undervoltage relays. Upon sensing an undervoltage, the master relay(s) automatically start the emergency generators, trip the normal feed switchgear breakers and trip all motor feeder breakers on the boards. The gentrators can also be fihanually started locally, frorfi the MCR, or from the ACR. For shutdown scenari that do not require MCR abandonment, a switchgear breaker on each board is automatically closed when its diesel generator is at rated speed and rated voltage and reenergizes the bus. The essential loads are sequentially connected to the bus. For shutdown scenarios from the ACR, breaker closure and diesel generator loading is done manually. The diesel generators will then supply all equipment which must operate under emergency conditions for the respective safeguard train.

4.10.2 480V AC Shutdown Power System "The 480V shutdown power system distributes power for low voltage station service demands. The normal source of power is the 6.9kV shutdown boards via the 6.9kV/480V transformers.

The 480V shutdown power system consists of eight boards, two per unit per train. Each 480V board is fed from the associated unit/train 6.9kV shutdown board through the normal or spare 6.9kV/480V transformers. The 480V shutdown boards feed 480V loads and various MCCs. The MCCs in turn feed various motor operated valves and other loads required for safe shutdown. Each MCC has a normal and alternate power source that can be utilized when needed.

111-15

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 4.10.3 120V AC Vital Instrument Power System The 120V AC Vital Instrument Power System consists of four separate vital boards per unit. Each 120V AC Vital Bus is supplied by an independent inverter. Eachvital battery supplies two inverters (one per unit of the same channel) plus a standby spare shared between units for each channel. Each inverter is normally supplied by the 480V AC power system of the associated traipiwhich is rectified andauctioneered using diodes with its respective 125Vdc battery board.The spare inverter can be manually aligned as a replacement for either of the normal inverters. The spare inverter can be supplied 480V AC fromither train via a manual transfer switch.

The output of each inverter is connected to its 120V AC vital instrument power board. The vital instrument power board can be supplied from its normal inverter orthe spare inverter via a manual transfer switch located on the board.The vital instrument power boards supply all of the required normal safe shutdown instrumentation per channel.

4.10.4 125V DC Power System The 125V dc power system consists of four battery banks, four normal chargers, two spare chargers, and four main dc battery boards. The 125V dc power system supplies power for control of 6.9kV/480V shutdown boards, operation of vital inverters, pneumatic-operated solenoid controlled valves, and selected emergency lights. The battery system consists of four separately located sets of batteries powering four channels of dc boards. Each normal vital battery has its own normal charger. Each vital battery board can also be supplied from one of two spare chargers. The battery chargers are energized from normal or alternate MCCs via a manual transfer switch. A fifth vital battery may be used as an installed spare and can be placed into service in place of any of the four normal vital batteries. The fifth vital battery is maintained by its own charger until connected to one of the normal vital battery boards.

During normal operation, the 125V dc loads are fed from the battery chargers, with the batteries being supplied a "trickle" charge floating on the system. Upon loss of ac power, the entire dc load is drawn from the batteries. However, the battery chargers can be manually aligned to alternate power sources to take over the load and recharge their associated batter:"

All direct current loads associated with engineered safeguards equipment are fully redundant. These loads are arranged so that each battery supplies its associated channel.

4.10.5 250V DC Power System The 250V dc power system consists of two battery banks, two normal chargers spare charge; and two 250V dc battery boards. Control power for nonsafety-related power circuit breakers and associated protective relays is distributed from the 25 OV dc supply via circuit breakers on the turbine building dc distribution boards. The 250V dc power system provides power for non-safety-related loads and, for Appendix R fire scenarios, is used to operate steam load trip circuits and to provide capabilities to trip the RCPs.

4.11 Operator Integrity - Key 41 Sufficient operator communication channels, emergency lighting, and security system access has been guaranteed for the FSSD.

111-16

SQN FIRE PROTECTION REPORT PART 11 - SAFE SHUTDOWN CAPABILITIES Rev. 9 4.12 Reactor Trip - Key 29 A fire inside or outside of the control building may require a reactor trip to bring the plant to hot standby. Reactor trip breaker A or B may be tripped by the handswitches in the MCR. Also, the reactor may be tripped using the motor-generator set breaker A and B. The reactor trip provides sufficient initial reactivity control. Long term reactivity control is accomplished by preventing boron dilution and assuring that injected makeup water is at least the boron concentration of the RWST.

The reactor can be manually shut down from the main control room, or if the fire damages the reactor trip breakers, the reactor can be manually shut down by de-energizing the control rod drive motor-generators There are four paths to trip the reactor. For each of two trains, there is a shunt trip path and an undervoltage trip path. The shunt trip path trips the reactor by energizing the shunt trip coil in the reactor trip switchgear through a handswitch contact in the main control room. The undervoltage trip path trips the reactor by de energizing the undervoltage trip coil in the reactor trip switchgear through a handswitch contact in the main control room. For an undervoltage trip path to fail, a perfect short to another power source must occur. For a shunt trip path to fail, the path must open without shorting. It is, therefore, considered incredible that all four paths will fail in the specific manner to disable each respective path, particularly in light of the fact that the trip handswitches in the main control room each utilize all four paths simultaneously when placed in the TRIP position. In addition, the reactor may be tripped locally at the reactor trip switchgear and the motor-generator set supply breaker. Procedure FR-S. 1, "ATWS", covers operator actions that may be required in the highly b". -:">

unlikely event that all four paths fail in the manual trip circuits. The reactor protection system will not be specifically protected from fire damage. The fail-safe design of the reactor protection system and diversity of input signals which can detect a given event provide additional protection should an event occur before the operator could manually insert the control rods. The input signal cables are run in conduit which makes them less susceptible to fire damage. Fires which occur in the control building which are more threatening to the reactor protection system are fires for which the operator will manually insert the rods quickly to allow evacuation of the main control room.

5.0 IDENTIFICATION OF SAFE SHUTDOWN SYSTEM COMPONENTS

"-For eich system, plant flow diagrains (P&IDs), system descriptions and one-line diagramts were used to identify the precise primary flow paths and operational characteristics that must be established to accomplish the desired safe shutdown function. From this information, a list was compiled in reference 11.2.1 of the components which participate in the system's performance of its safe shutdown function. These components are:

(1)

Active components that reed to be powered to establish, or assist in establishing, the primary flow path and/or the system's operation.

(2)

Active components in the primary flow path that normally are in the proper position whose power loss will not result in a change of position, but may be affected by open, short, or ground faults in control or power cabling.

(3)

Power-operated components that need to change position to establish or assist in establishing the primary flow path, whose loss of electrical or air supplies result in the component adopting the required safe shutdown position but which may be affected by open, short or ground faults in control or power cabling.

III-17

SQN FIRE PROTECTION REPORT PART IlI - SAFE SHUTDOWN CAPABILITIES Rev. 9 (4)

Major mechanical components that support safe shutdown.

From the analysis of the safe shutdown system flow paths, those components whose spurious operation would threaten safe shutdown system operability were also identified in reference 11.2.1. This identification included those branch flow paths that must be isolated and remain isolated to assure that flow will not be suibstantially diverted from the primary flow path. See Section 7 for the detailed discussion of spurious operations A list was generated for safe shutdown devices including device identification and operating requirements for the various shutdown keys (ref. 11.2.1).

6.0 IDENTIFICATION OF SAFE SHUTDOWN CIRCUITS AND CABLES The equipment list developed during the SQN safe shutdown system analysis (ref. 11.2.1) was the basic input for the identification of electrical circuits essential to ensure adequate equipment performance.

Essential safe shutdown electrical circuits were identified for the electrically-dependent devices (ref. 11.2.2).

However, for some equipment, either *a subset of cables or no cables were identified. For example, cables were not selected for valves where local manual operation is allowed during cooldown. The circuits identified included power, control, and instrumentation. Type II associated circuits as addressed in Section 7 were also treated as required circuits.

The identification and analysis of these essential electrical circuits was based on one-line diagrams, schematics, and wiring diagrams from which the necessary circuit cables were selected for the subsequent cable routing and separation analysis Circuit evaluation and identification considers equipment operability requirements. Circuits are identified for active and passive equipment Circuit identification for high/low pressure boundary components considered the possibility of more conservative cable faults (e.g., 3 phase to 3 phase faults.)

For each electrical component, circuits and cables were identified which (1) are required for safe shutdown to ensure operability or (2) failure of which would be detrimental. The circuits not included per the above criteria included annunciator, compifler, motor hdaters ahd external monitoring circtrits. Those circuits which are electrically isolated from the electrical circuits of concern, or where failure of these circuits would not affect operability, were not included in the separation analysis.

For each safe shutdown key, cable block diagrams were developed (ref. 11.2.2) for each safe shutdown component to identify cables required to ensure that the component can perform its safe shutdown function. Once the required cables were identified, the cable and conduit schedules were used to identify the individual cable physical routings in the plant on a raceway basis. Field routed conduit was located and evaluated where necessary. Reference 11.2.3 contains the physical routings.

7.0 ASSOCIATED CIRCUITS OF CONCERN 7.1 Introduction The separation and protection requirements of 10CFR50, Appendix R apply not only to safe shutdown circuits but also to "associated" circuits which could prevent operation or cause maloperation of shutdown systems and equipment. The identification of these associated circuits of concern was performed in 111-18

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 accordance with NRC Generic Letter 81-12, the Staffs clarification to Generic Letter 81-12, and Generic Letter 86-10. The generic letters defined associated circuits of concern as those which have a physical separation less than that required by Section III.G of Appendix R, and have one of the following:

Type I A common power source with the shutdown equipment and the power source is not electrically protected from the circuit of concern by coordinated breakers, fuses, or similar devices; Type II A connection to circuits of equipment whose spurious operation would adversely affect the shutdown capability; Type IIlA common enclosure with the shutdown cables, and, (a) are not electrically protected by circuit breakers, fuses or similar devices, or (b) will allow propagation of the fire into the common enclosure.

111-19

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 7.2 Associated Circuits by Common Power Supply and Common Enclosures The electrical distribution system was reviewed to assure that Type I associated circuits by common power supply are addressed by providing selective protective trip coordination for all FSSD power supplies.

Type III associated circuits by common enclosures were addressed by ensuring that all existing circuits in Category 1 buildings are electrically protected with a fuse or breaker that will actuate prior to the jacket of existing faulted cables from reaching their auto-ignition temperature.

Electrical circuit fault protection was designed to provide protection for plant electric circuits via protective relaying, circuit breakers and fuses. Protective equipment was designed and applied to ensure adequate protection of electrical distribution equipment, including cables, from electric faults and overload conditions in the circuits. The selection and application of these devices was in accordance with TVA design practices (ref. 11.2.4) and is documented in engineering calculations (ref. 11.2.5). The protective equipment ensures that electrical fault and overloads will not result in any more cable degradation than would be expected when operating conditions are below the set point of the protective equipment. This will also limit cable damage and prevent cable faults from resulting in internal cable temperatures which could cause ignition of cable insulation.

An integral part of the original electric system protection was the proper coordination of these electrical protective devices. Such coordination assures that the protective device nearest (in an electrical sense) to the fault operates prior to the operation of any "upstream" protective devices, and provides interruption of electrical service to a minimum amount of equipment The electrical protection design (ref.

11.2.4) required coordination of such electrical protective devices and is documented in engineering calculations (ref. 11.2.5).

7.3 Associated Circuits by Spurious Operation Cables that are not part of safe shutdown circuits may be damaged by the effects of postulated fires.

This cable damage may consequently prevent the correct operation of safe shutdown components, or result in the maloperation of equipment which would directly prevent the proper performance of the safe shutdown systems. The effects of spurious operations may be conceptually divided into two subclasses as follows (1)

Maloperation of safe shutdown equipment due to control circuit electrical interlocks between safe shutdown circuits and other circuits; for example, the numerous safe shutdown equipment automatic operation interlocks from process control and instrument circuits.

(2)

Maloperation of equipment that is not defined as part of the safe shutdown systems, but that could prevent the accomplishment of a safe shutdown function; for example, inadvertent depressurization of the RCS or the MS system by spurious opening of boundary valves The evaluation of Appendix R events ensures that any failure of associated circuits of concern by spurious operation (Type II) will not prevent safe shutdown (refer to Part X). Credible electrical faults considered in the analysis included open circuit, short circuit (conductar-to-conductor), short to ground, and cable-to-cable (hot-short) including 3-phase hot-shorts for high/low pressure interface valves (ref. 11.2.6).

Type II associated circuits of concern outside of containment are analyzed in accordance with Appendix R Sections III.G.2a, III.G.2b, and/or III.G.2c criteria as required circuits. Inside containment, Type II associated circuits of concem are analyzed in accordance with Appendix R Sections III.G.2d, III.G.2e, 111-20

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 and/or III.G.2f criteria as required circuits.

In order for cable faults that generate spurious operation to occur, the following conditions must exist synergistically at the cable fault location:

(1)

Sufficient energy must exist due to the fire to create failure of the cable jacket and insulating material.

(2)

The failure of the jacket and insulating material must occur in a way that directly exposes the cable conductors.

(3)

For each short, two or more specific conductors must come into direct contact causing low impedance conductor-to-conductor connections.

(4)

For certain types of spurious operation, multiple electrically independent shnrts must occur.

(5)

No additional conductors that would cause circuit fault currents and operation of circuit protective devices may participate in the short condition.

(6)

No ground faults that would cause operation of circuit protective devices must occur.

The spurious operation analysis performed (ref. 11.2.7) recognized the extremely low probability of "certain types of these faulted conditions. The following cable short conditions causing spurious operation were considered of sufficiently low likelihood that they were assumed not to require additional analysis or modification (unless it involves high-low pressure boundary interfaces) :

CASE 1)

Three phase-ac power circuit cable-to-cable faults (6.9kV and 480V)

CASE 2)

Two wire ungrounded-dc power circuit cable-to-cable faults (125V)

CASE 3)

Two wire ungrounded-ac control circuit cable-to-cable faults (120V)

"With respect to Cases 1), 2), and 3), no conductor-to-conductor faults within the same power cable can cause spurious powering of the associated device. Only power cable-to-cable connections between one deenergized and one energized power circuit could permit operation. For the case of the three-phase-ac circuit, three electrically independent cable-to-cable shorts must occur without grounds in order to power the associated device. Similarly, for the two-wire ungrounded dc power circuit, two electrically independent cable-to-cable shorts without grounds must occur. The likelihood of such occurrences has been acknowledged by the NRC Staff to be sufficiently low to permit excluding such faulted conditions from consideration except for high/low pressure boundary components. Therefore, for the above identified spurious operations caused by cable faults, only 3-phase hot-shorts for high/low pressure boundary interface valves have been incorporated into the analysis (ref. 11.2.7).

The fundamental basis of excluding the remaining shorts from consideration is based on the need for multiple cable-to-cable electrically independent faults in order for spurious operation to occur.

Concerning Case 2), all dc control circuits at SQN are ungrounded. In order for spurious operation 111-21

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 to occur due to circuit-to-circuit faults between dc circuits supplied from different sources, at a minimum, two electrically independent cable-to-cable shorts without grounds must occur.

For the ungrounded ac control circuits in Case 3), the identical consideration exists. Most MCC transformer secondary 120V ac control circuits are ungrounded. Therefore, at a minimum, two cable-to-cable shorts must simultaneously occur in order for spurious operation to result for circuits supplied from different sources.

8.0 HIGHILOW PRESSURE BOUNDARY INTERFACES Special considerations for high/low pressure interfaces to meet the requirements of IOCFR50 Appendix Rare described in Generic Letters 81-12 and 86-10 and Information Notice 87-50. Per Generic Letter 81-12, the following information is required for high/low pressure boundary interfaces in order to ensure that they are adequately protected for the effects of a single fire.

1)

Identify each high/low pressure interface that uses redundant electrically controlled devices (such as two series motor operated valves) to isolate or preclude rupture of any primary coolant boundary.

2)

Identify the essential cabling for each device

3)

Identify each location where the identified cables are separated by a barrier having less than a 3-hour fire rating

4)

For the areas identified in [3] above (if any), provide the bases and justification Per Generic Letter 86-10, the possibility of getting a hot short on all three phases of three phase ac circuits in the proper sequence to cause spurious operation of a motor is only required to be evaluated for cases involving high/low pressure interfaces. The same applies to ungrounded dc circuits regarding two hot shorts of proper polarity without grounding resulting in spurious operation of high/low pressure interfaces.

Per Information Noticd 87-50, for those low pressure systems that connect to the reactor coolant system (a high pressure system) at least one isolation valve must remain closed despite any damage that may be caused by-fire, because the high pressure from the reactor coolant system could result in failure of the low pressure piping.

Based on the above, a review of the systems credited for safe shutdown was conducted to identify potential high/low pressure interfaces. These interfaces were evaluated to identify valves that, if spuriously opened, would expose low pressure piping to high pressure resulting in potential failure of the low pressure system. The results are included in Keys 7 and 8 of reference 11.2.1.

The control system for RHR valves has been designed to prohibit opening unless the reactor coolant pressure is low enough to prevent RHR piping failure. However, if these valves opened spuriously, exposure.

of RHR piping to high pressure may cause failure of the RHR system piping and render the system inoperable. Therefore, the RHR/RCS isolation valves (1-FCV-74-1, 2) are considered high/low pressure interface valves.

Excess letdown is not specifically required for safe shutdown. However, spurious opening of these 111-22

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 valves could expose downstream piping to excess pressure that may cause failure resulting in the rupture of the primary coolant boundary. Therefore, the excess letdown isolation valves (1-FCV-62-55, -56) are considered high/low pressure interface valves.

Normal letdown is not specifically required for safe shutdown. However, spurious opening of these valves may cause failure to maintain RCS inventory control. Therefore, the normal letdown isolation valves are considered high/low pressure interface valves.

The pressurizer PORV and reactor head vent isolation valves are designed to function at high RCS operating pressure. They provide two safe shutdown functions: 1) to initially remain closed for RCS inventory control purposes, and; 2) to provide a means of depressurizing the RCS to the point that the RHR system can be initiated to bring the plant to a cold shutdown condition. Discharge from the RCS through these valves is directed to the pressurizer relief tank (PRT). The inlet lines are sized to accommodate vent/relief discharge flow without piping or component failure. Continuous letdown to the PRT may eventually cause spillage of excess coolant to containment through the PRT rupture disks Therefore, the pressurizer PORVs and block valve combinations, and reactor head vent isolation valves, are required for RCS inventory control (and RCS letdown) and are considered high/low interface valves.

9.0 LOCATION OF SAFE SHUTDOWN EqUIPMENT, CABLES AND RACEWAYS The safe shutdown equipment list (Table 111-2) identifies the equipment, components, and

{, i?.'

subcomponents relied on for fire safe shutdown (ref. 11.2.1). Safe shutdown cables were identified on block "diagrams (ref. 11.2.2). The routing (conduits and tray nodes) of each safe shutdown cable was obtained from the cable and conduit schedules as needed. The route of each safe shutdown cable was plotted on physical drawings and used as part of the separation as needed (ref. 11.2.3).

10.0 SAFE SHUTDOWN SYSTEM SEPARATION EVALUATION METHODOLOGY 10.1 Overview of Evaluation Methodology The safe shutdown analysis first established the systems, components, and cables required for fire safe shutdown purposes. The locations of equipment and routing of cables were determined as described in previous sections. The separation criteria of Appendix R were evaluated on a fire area basi'-to meet the safe shutdown performance goals as identified in NRC generic letters and guidance documents.

The Appendix R analysis (refer to Part X) evaluated fire areas that contain systems, components, and cables required for fire safe shutdown. Plant structures that do not contain systems, components, or cables associated with FSSD capabilities were not included in the separation analysis. The adequacy of barriers separating safe shutdown-related buildings was evaluated.

The fire safe shutdown analysis was based on the evaluation of separation in the auxiliary, control, diesel generator, reactor building, and intake pumping station. The auxiliary building, diesel generator buildings, and the intake pumping station, were evaluated against the requirements of Appendix R Sections III.G.1, III.G.2a, III.G.2b, and III.G.2c For purposes of this analysis, the entire control building was evaluated as a single alternative shutdown location under the criteria of Appendix R Section III.G.3 and III.L.

Fire safe shutdown activities take place outside of the control building in the ACR and other manual action locations (ref. 11.2.9). The reactor building was analyzed in accordance with the criteria of Appendix R Sections III.G.2d, III.G.2e, and III.G.2f. Detailed procedures have been developed to ensure fire safe shutdown capability in case of an Appendix R fire (ref. 11.2.10).

111-23

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES Rev. 9 Interactions between redundant safe shutdown paths were identified based on the location of the components and cables of redundant safe shutdown paths. Interactions are defined as locations where components of redundant shutdown paths did not meet Appendix R separation criteria. These interactions were evaluated for their impact on the safe shutdown capability of the plant and the resolutions have been implemented. The resolutions may consist of modifications, use of radiant energy shielding, fire detection and suppression in the area, alternate equipment, manual operator actions, fire barrier installation, pre-fire actions, post-fire repairs (ref. 11.2.11), engineering evaluations prepared in accordance with the guidance of Generic Letter 86-10, or deviation requests (refer to Part VIII).

10.2 Fire Area Evaluation Methodology Separation analyses were initially evaluated for viability on a fire area basis. The fire area separation analysis was effective where only a single room constituted a fire area, and where redundant capability existed outside of the fire area Large rooms and specific fire areas containing redundant trains of safe shutdown systems, components, or cables were further evaluated for purposes of separation. Where multiple rooms exist in the fire area, regulatory barriers with a 1-1/2-hour fire rating have been credited under Appendix R Section III.G.2c criteria. Where the 1-1/2-hour fire rated barriers have been credited, automatic detection and suppression capabilities on both sides of the barriers have been evaluated per Section III.G.2c criteria.

Credit has been taken for a minimum of 20 feet of separation under Appendix R Section III.G.2b criteria in those fire areas that contain multiple rooms not separated by regulatory fire barriers.Section III.G.2b criteria has also been utilized in large rooms that contain redundant trains of safe shutdown capability.Section III.G.2c criteria has been applied where 20 feet of separation was not available.Section III.G.2b criteria has been used in the large open areas of the auxiliary building and adjacent rooms which are not enclosed by regulatory fire barriers.

The fire area analysis is documented in Part X with deviations and evaluations documented in Part VII.

11.0 REFERENCES

11.1 Regulatory Documents 11.1.1 IOCFR50AppendixR 11.1.2 Generic Letter 81-12, Enclosure 1 11.2 TVA Documents 11.2.1 SQN-SQS4-0127, "Equipment Required for Safe Shutdown per 10CFR50 Appendix R!'

11.2.2 Electrical Equipment Block Diagrams Calculation Series, BD-K1 through BK-K..

11.2.3 TVA Drawing 45E890 Series 11.2.4 Electrical Design Criteria: SQN-DC-V-10.7, SQN-DC-V-1 1.2, SQN-DC-V-1 1.2.2, SQN DC-V-11.4.1, SQN-DC-V-1 1.6, SQN-DC-V-1 1.6.1 Ili-24

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 11.2.5 Calculations: D2SDJ-P213350, SQN-APS-006, DS-APPR-Series 11.2.6 SQN Detailed Design Criteria, SQN-DC-V-10.7, "10CFR50, Appendix R, Type II Items" 11.2.7 Calculations: SQN-CSS-023, SQN-CSS-024 11.2.8 SQN-DC-V-24.0, "Design Criteria for Fire Protection of Safe Shutdown Capability" 11.2.9 AOP-C.04, "Control Room Inaccessibility" 11.2.10 O-GO-08, "Fire Interaction Manual" 11.2.11 SMI-0-317-8, "Appendix R-Casualty Procedures" 11.2.12 AOP-N.01 "Plant Fire" 11.2.13 DCN D20071A/P20872A " Vitl Inverter Modification" 111-25

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE HI-1 SAFE SHUTDOWN SYSTEMS AND SUBSYSTEMS BY KEY Key 1 Key 2 Key 3 Key 4 Key 5 Key 6 Key 7 Key 8 Key 9 Key 11 Key 12 Key 13 Key 14 & 15 Key 16 Key 17 Key 19 Key 20 Key 21 Key 22 Key 23 Key 24 Key 25 Key 26 Key 28 Key 29 Key 30 Key 31 Key 34 Key 36 Key37A Key 37B Key 37C Key 37F Key 37K Key 37P Key 37N Key 370 Key 38 Key 40 Key 41 Key.48 Centrifugal Charging Pump and Component Cooling System Charging Flow Control Path Emergency Raw Cooling Water Path Volume Control Tank Suction RWST Suction ECCS Charging Path RCS Pressure Boundary Isolation Reactor Coolant Pressure Boundary Isolation Excess Letdown Isolation RCP Thermal Barrier Cooling Motor Driven Auxiliary Feedwater Pumps Steam Generator Level Control Using MDAFW Pump Control Air Turbine-Driven Auxiliary Feedwater Pump Steam Generator Level Control using TDAFW Pump Suction From Condensate Storage Tank Suction from ERCW To AFW Pump Suction Main Steam Isolation Steam Load Isolation Feedwater Isolation Feedwater Pump Turbine Steam Generator Blowdown Isolation Secondary Safety Valves Secondary Relief Valves RCS Pressure Control Reactor Trip RHR Shutdown Coolhg Flow Paths RHR Pumps Key Normal Charging Path.

Accumulator Isolation Nliain Control'Room'HVAC Auxiliary Inst Rm HVAC Diesel Generator Building HVAC 480V Bd Rm & Battery Rm HVAC 480V Transformer Rooms HVAC CCS/SFP HVAC TDAFW PUMP ROOM HVAC CCS/AFW Pump Coolers and AFW/BAT Pump Coolers Electrical Power (includes Onsite and Offsite and Distribution)

RHR Pump Rm Coolers Operator Integrity (communications/lighting/access)

RCS Letdown 111-26 Rev. 9

SQN FIRE PROTECTION REPORT PART 11 - SAFE SHUTDOWN CAPABILITIES TABLE III-2 SHUTDOWN LOGIC COMPONENT LIST MAIN STEAM (1)

Reference flriuinq Descrintion I&2-PI-1-2A I&2-PI-1-2B I&2-FCV-1-4 l&2-FSV-1-4A I&2-FSV-1-4B I&2-FSV-1-4D I&2-FSV-1-4E I&2-FSV-1-4F 1&2-FSV-1-4G I&2-FSV-1-4H I&2-FSV-1-4J l&2-P-1-5 I&2-PCV-1-5 I&2-FCV-1-7 l&2-P-1-9A 1&2-P-1-9B I&2-FCV-I-1I 1&2-FSV-I-11A 1&2-FSV-I-11B I&2-FSV-l-11D I&2-FSV-I-IIE 1&2-FSV-I-iiF 1&2-FSV-I-11G 1&2-FSV-I* 1lH I&2-FSV-I-1 I 26 26 20 20 20

-20 20 20 20 20 20 26 26 24 26 26 20 20 20 20 20 20 20 20 20 47W610-1-1 47W610-1-1 47W801-1 47W610-1-1 47W610-1-1 47W610-I-1 47W610-1-I 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 47W801-1 47W80 1-2 47W610-1-1 47W610-1-1 47W801-1 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 47W610-1-1 Main Steam Pressure Indication Loop I Main Steam Pressure Indication Loop 1 MSIV-Loop 1 Loop 1 MSIVAir Supply Solenoid Loop 1 MSIV Air Supply Solenoid Loop I MSIV Air Vent Solenoid Loop 1 MSIV Air Vent Solenoid Loop 1 MSIV Test Solenoid Loop 1 MSIV Air Vent Solenoid Loop 1 MSIV Air Vent Solenoid Loop 1 MSIV Test Solenoid Loop 1 Atmospheric.Relief Valve Control Loop 1 Atmospheric Relief Valve Steam Generator 1Blowdown Isolation Valve Main Steam Pressure Indication Loop 2 Main Steam Pressure-Indication Loop 2 MSIV-Loop 2 Loop 2 MSIV Air Supply Solenoid Loop 2 MSIV Air Supply Solenoid Loop 2 MSIV Air Vent Solenoid Loop 2 MSIV Air Vent Solenoid Loop 2 MSIV Test Solenoid Loop 2 MSIV Air Vent Solenoid Loop 2 MSIV Air Vert-Solenoid Loop 2 MSIV Test Solenoid III-27 Key

('nm~nn Onrt Rev. 9 47 rý

^"Ant

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST MAIN STEAM (1) rence

.vin*

Descriotion

%..U1LLJJLUILýI inf io l&2-P-l-12 I&2-PCV-I-12 I&2-FCV-1-14 1&2-FCV-1-15 1&2-FCV-1-16 l&2-FCV-1-17 1&2-FCV-I-18 1&2-P-1-20A I&2-P-1-20B 1&2-FCV-1-22 1&2-FSV-1-22A l&2-FSV-1-22B 1&2-FSV-1-22D 1&2-FSV-1-22E 1&2-FSV-1-22F 1&2-FSV-1-22G 1&2-FSV-1-22H 1&2-FSV-1-22J 1&2-P-1-23 1&2-PCV-1-23 1&2-FCV-1-25 26 26 24 14,15 47W610-1-1 47W801-1 47W801-2 47W803-2 14,15 47W803-2 14,15 47W803-2 14,15 47W803-2 26 26 20 20 20 20 20 20 20 20 20 26 26 24 47W610-1-2 47W610-1-2 47W801-1 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W801-1 47W801-2 Loop 2 Atmospheric Relief Valve Control Loop 2 Atmospheric Relief Valve Control SG 2 Blowdown Isolation Valve AFPT Steam Supply from SG No. I AFPT Supply from SG No. 4 Steam Flow Isolation to AFPT Steam Flow Isolation to AFPT Main Steam Pressure Indication Loop 3 Main Steam Pressure Indicdtmn Loop 3 MSIV-Loop 3 Loop 3 MSIV Air Supply Solenoid Loop 3 MSIV Air Supply Solenoid Loop 3 MSIV Air Vent Solenoid Loop 3 MSIV Air Vent Solenoid Loop 3 MSIV Test Solenoid Loop 3 MSIV Air Vent Solenoid Loop 3 MSIV Air Vent Solenoid Loop 3 MSIV Test Solenoid Loop 3 Main Steam Pressure Indication Loop 3 Atmospheric Relief Valve Steam Generator 3Blowdown Isolation Valve 111-28 Rev. 9 Key Refe

" rnxr,

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST MAIN STEAM (1)

Key Reference Thrnw~iiu Dl-crintinn 1&2-P-1-27A 1&2-P-1-27B 1&2-FCV-1-29 l&2-FSV-1-29A l&2-FSV-1-29B l&2-FSV-1-29D l&2-FSV-1-29E l&2-FSV-1-29F 1&2-FSV-1-29G 1&2-FSV-1-29H l&2-FSV-l-29J l&2-P-1-30 1&2-PCV-1-30 1&2-FCV-1-32 l&2-FCV-1-36 l&2-FCV-1-37 l&2-FCV-1-38 l&2-FCV-1-39 1&2-FCV-1-43 1&2-FCV-1-44 1&2-FCV-1-45

• &2-FCV-1-46 I&2-FCV-1-51 l&2-FCV-1-52 1&2-FCV-1-61 26 47W610-1-2 26 20 20 20 20 20 20 20 20 20 26 26 24 21,23 21,23 23 23 21,23 47W610-1-2 47W801-1 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W610-1-2 47W801-1 47W801-2 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 21,23 47W801-1 23 47W801-1 23 47W801-1 14,15 47W803-2 14,15 47W610-1-1 21 47W801-1 Loop 4 Main Steam Pressure Indic~ain Loop 4 Main Steam Pressure Indication MSIV - Loop 4 Loop 4 MSIV Air Supply Solenoid Loop 4 MSIV Air Supply Solenoid Loop 4 MSIV Air Vent Solenoid Loop 4 MSIV Air Vent Solenoid Loop 4 MSIV Test Solenoid Loop 4 MSIV Air Vent Solenoid Loop 4 MSIV Air Vent Solencd Loop 4 MSIV Test Solenoid Loop 4 Main Steam Pressure Indication Loop 4 Atmospheric Relief Valve SG 4 Blowdown Isolation Valve High Pressure Stop Valve to MFPT A High Pressure Control Valve to MFPT A Low Pressure Control Valve to MFPT A Low Pressure Stop Valve to MFPT A High Pressure Stop Valve to MFPT B High Pressure Control Valve to MFPT B Low Pressure Control Valve to MFPT B "ELow Pressure 6top Valve to MFPT B AFPT Trip & Throttle Valve AFPT Governor Valve Main Steam Stop and Control Valve to High Pressure Turbine 111-29 Rev. 9 Co.,,

n

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l--.,---,

.. r..

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Rev. 9 Description l&2-FCV-1-62 l&2-FCV-1-64 1&2-FCV-1-65 1&2-FCV-1-67 1&2-FCV-1-68 I&2-FCV-1-70 I&2-FCV-1-71 l&2-FCV-1-75 l&2-FCV-1-77 l&2-FCV-1-79 1&2-FCV-1-84 I&2-FCV-1-91 1&2-FCV-1-98 1&2-FCV-1-103 I&2-FCV-I-104 1&2-FCV-1-105 1&2-FCV-1-106 1&2-FCV-1-107 1&2-FCV-1-108 1&2-FCV-I-109 I&2-FCV-I-ll0 1&2-FCV-I-111 1&2-FCV-I-112 I&2-FCV-I-113 I&2-FCV-I-1 rt 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine Main Steam Stop and Control Valve to High Pressure Turbine Main Steam Stop and Control Valve to High Pressure Turbine Main Steam Stop and Control Valve to High Pressure Turbine Main Steam Stop and Control Valve to High Pressure Turbine Main Steam Stop and Control Valve to High Pressure Turbine Main Steam Stop and Control Valve to High Pressure Turbine Main Steam to MSR A2 Main Steam to MSR B2 Main Steam to MSR C2 Main Steam to MSR Al Main Steam to MSR-BI Main Steam to M;R CI Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve Main Steam Dump Valve 111-30 Key rnninn n~nt MAIN STEAM (1)

Reference Drawine Y-L* iel

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE HI-2 SHUTDOWN LOGIC COMPONENT LIST Rev. 9 MAIN STEAM (1)

Key Reference T)rn-tvuini 1le~erintion ComponenII~tL.

1&2-FCV-1-147 1&2-FCV-1-148 1&2-FCV-1-149 1&2-FCV-1-150 1&2-FCV-1-181 1&2-FCV-1-182 1&2-FCV-1-183 1&2-FCV-1-184 l&2-FCV-1-275 1&2-FCV-1-277 1&2-FCV-1-279 1&2-FCV-1-284 l&2-FCV-1-291 1&2-FCV-1-298 1&2-VLV-1-512 1&2-VLV-1-513 1&2-VLV-1-514 1&2-VLV-1-515 1&2-VLV-1-516 1&2-VLV-1-517 1&2-VLV-1-518 1&2-VLV-1-519 1&2-VLV-1-520 1&2-VLV-1-521 1&2-VLV-1-522 1&2-VLV-1-523 1&2-VLV-1-524 1&2-VLV-1-525 1&2-VLV-1-526 1&2-VLV-1-527 1&2-VLV-1-528 1&2-VLV-1-529 1&2-VLV-1-530 1&2-VLV-1-531 1&2-VLV-1-868 1&2-VLV-1-869 20 20 20 20 24 24 24 24 21 21 21 21 21 21 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 24 24 47W801-1 47W801-1 47W801-1 47W801-1 47W801-2 47W801-2 47W801-2 47W801-2 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1,1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-1 47W801-2 47W801-2 MSIV Bypass Valve MSIV Bypass Valve MSIV Bypass Valve MSIV Bypass Valve S G 1 Blowdown Containment Isolation Valve SG 2 Blowdown Containment Isolation Valve SG 3 Blowdown Containment Isolation Valve SG 4 Blowdown Containment Isolation Valve MSR A2 Low Power Bypass Valve MSR B2 Low Power Bypass Valve MSR C2 Low Power Bypass Valve MSR Al Low Power Bypass Valve MSR B 1 Low Power Bypass Valve MSR C1 Low Power Bypass Valve Main Steam Safety Valve from SG 3 Main Steam Safety Valve from SG 3 Main Steam Safety Valve from SG 3 Main Steam Safety Valve from SG 3 Main Steam Safety Valve from SG 3 Main Steam Safety Valve from SG 2 Main Steam Safety Valve fun SG 2 Main Steam Safety Valve from SG 2 Main Steam Safety Valve from SG 2 Main Steam Safety Valve from SG 2 Main Steam Safety Valve from SG I Main-gteam,Safety Valve from SG 1.,

Main Steam Safety Valve from SG I Main Steam Safety Valve from SG 1 Main Steam Safety Valve from SG 1 Main Steam Safety Valve from SG 4 Main Steam Safety Valve from SG 4 Main Steam Safety Valve from SG 4 Main Steam Safety Valve from SG 4 Main Steam Safety Valve from SG 4 S G Blowdown Heat Exchanger Isolation Valve SG Blowdown Heat Exchanger Isolation Valve 111-31

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Key Reference Component Drwing AFW motor driven pump AA AFW motor driven pump tB AFW turbine driven Pump A-S 1&2-FCV-3-33 1&2-FCV-3-35 1&2-FCV-3-35A 1&2-L-3-39 1&2-L-3-43 1&2-FCV-3-47 1&2-FCV-3-48 1&2-FCV-3-48A 1&2-L-3-52 1&2-L-3-56 1&2-FCV-3-87 1&2-FCV-3-90 1&2-FCV-3-90A 1&2-L-3-94 1 &2-L-3-98 I&2-FCV-3-100 1&2-FCV-3-103 1&2-FCV-3-103A 1&2-L-3-107 l&2-L-3-1 11 1&2-FCV-3-116A 1&2-FCV-3-116B 11 47W803-2 11 47W803-2 14&15 47W803-2 22 47W803-1 22 22 12,16 12,16 22 22 22 12,16 12,16 22 22 22 12,16 12,16 22 22 22 12,16 12,16 19 19 47W803-1 47W610-3-1 47W610-3-1 47W610-3-1 47W803-1 47W803-1 47W610-3-1 47W610-3-1 47W610-3-1 47W803-1 47W803-1 47W610-3-2 47W610-3-2 47W610-3-2 47W803-1 47W803-1 47W610-3-2 47W610-3-2 47W610-3-2 47W803-2 47W803-2 Motor Driven Auxiliary Feedwater Pump Motor Driven Auxiliary Feedwater Pump Turbine Driven Auxiliary Feedwater Pump SG 1 Main Feedwater Isolation Valve S G 1 Main Feedwater Control Valve Feedwater Low Load Bypass to SG 1 SG No. 1 NR Level Loop SG No. 1 WR Level Loop SG 2 MFW Isolation Valve SG 2 MFW Control Valve Feedwater Low Load Bypass to SG 2 SG 2 NR Level Loop SG 2 WR Level Loop SG 3 MFW Isolation Valve SG 3 MEW ControlValve Feedwater Low Load Bypass to SG 3 SG 3 NR Level Loop SG 3 WR Level Loop SG 4 MEW Isolation Valve SG 4 MFW Isolation Valve Feedwater Low Load Bypass to SG 4 SG 4 NR Level Loop SG 4 WR Level Loop ERCW Header A Isolation Valve ERCW Header A Isolation Valve 111-32 Rev. 9 MAIN & AUXILIARY FEEDWATER (3)

Description I

A

SQN FIRE PROTECTION REPORT PART Ifl - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Key Main & Auxiliary Feedwater (3)

Reference r~wln*,De~cdntion 1&2-FCV-3-126A 1&2-FCV-3-126B l&2-FCV-3-136A 1&2-FCV-3-136B 1&2-P-3-138A

.1&2-P-3-138B 14,15,16 19 47W803-2 19 47W803-2 19 47W803-2 19 47W803-2 47W610-3-3 16 47W610-3-3 ERCW Header B Isolation Valve ERCW Header B Isolation Valve ERCW Header A Isolation Valve ERCW Header A Isolation Valve Turbine Driven AFW Pump Outlet Pressure 14,15 47W610-3-3 1&2-F-3-142 1&2-L-3-148 l&2-LSV-3-148 1&2-LCV-3-148 1&2-P-3-148 1&2-L-3-156 1&2-LCV-3-156 1&2-LSV-3-156 1&2-P-3-156 l&2-L-3-164 12 12 12 12 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 12 47W610-3-3 12 12 12 47W610-3-3 47W610-3-3 47W610-3-3 12 1' 47W610-3-3 TDAFWP Flow Loop SG 3 Level Loop Solenoid for Loop 3 MDAF WP Level Control Valve SG 3 MDAF WP Level Control Valve SG 3 Level Bypass Pressure Switch Loop SG 2 Level Loop SG 2 MDAFWP Level Control Vhe Solenoid for Loop MDAFWP Level Control Valve SG 2 Level Bypass Switch Loop SG 1 Level Loop

- NX PS-3-140A, -140B, -150B, -160A, and-160B have been deleted by ECNL5883 111-33 Rev. 9 Co poncrit 13 T) r'n win Descrinti6n

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Main & Auxiliary Feedwater (3) (Continued)

Key lanmnnnant Reference Drnwing Description 1&2-LSV-3-164 l&2-LCV-3-164 1&2-P-3-164 l&2-L-3-171 I&2-LCV-3-171 1&2-LSV-3-171 1&2-P-3-171 l&2-L-3-172 1&2-LCV-3-172 1&2-LSV-3-172 1&2-L-3-173 l&2-LCV-3-173 1&2-LSV-3-173 1&2-L-3-174 1&2-LSV-3-174 1&2-LCV-3-174 1&2-L-3-175 1&2-LCV-3-175 1&2-LSV-3-175 "T

1&2-FCV-3-179A 12 12 12 12 12 12 12 16 16 16 16 16 16 16 16 16 16 16 16 19 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W6 10-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 47W610-3-3 Solenoid for Loop 1 MDAF WP Level Control Valve SG 1 MDAF WP Level Control Valve SG 1 Level Bypass Pressure Switch Loop SG Level Loop 4 SG 4 MDAF WP Level Control Valve Solenoid for Loop 4 MDAF WP Level Control Valve SG 4 Level Bypass Pressure Switch Loop SG 3 Level Loqp SG 3 TDAF WP Level Control Valve Solenoid for Loop 3 TDAF WP FeecReg Valve SG 2 Level Loop SG 2 TDAF WP Level Control Valve Solenoid for Loop.2 TDAF WP Level Control Valve SG 1 Level Loop Solenoid for Loop 1 TDAF WVP Level Control Valve SG 1 TDAF WP Level Control Valve SG 4 Level Control Loop SG 4 TDAF WP Level Control Valve Solenoid for Loop 4 TDAF WP Level Control Valve ERCW Header B Isolatioiv Valve PS-3-165A and-165B have been deleted by ECNL5883.

111-34 Rev. 9

y.

j!

d L.

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE III-2 SHUTDOWN LOGIC COMPONENT LIST Main & Auxiliary Feedwater (3) (Continued)

Key Component 1,2-FCV-3-179B 1,2-FCV-3-400 1,2-FCV-3-401 1,2-VLV-3-826 1,2-VLV-3-827 1,2-VLV-3-828 1,2-VLV-3-829 1,2-VLV-3-834 1,2-VLV-3-835 1,2-VLV-3-836 1,2-VLV-3-837 19 12 12 12 12 12 12 12 12 12 12 Reference Drawing 47W610-3-3 47W803-2 47W803-2 47W803-2 47W803-2 47W803-2 47W803-2 47W803-2 47W803-2 47W803-2 47W803-2 Description ERCW Header B Isolation Valve Air operated Auxiliary Feedwater Pump AA Recirculation Air operated Auxiliary Feedwater Pump tB Recirculation valve Manual Isolation of Auxiliary Feedwater Pump-B to SG 3 Manual Isolation of Auxiliary Feedwater Pump-A to SG 2 Manual Isolation of Auxiliary Feedvtar Pump A-A to SG 1 Manual Isolation of Auxiliary Feedwater Pump-B to SG 4 Manual Isolation of Auxiliary Feedwater Pump-B to SG 3 Manual Isolation of Auxiliary Feedwater Pump-A to SG 2 Manual Isolation of Auxiliary Feedwater Pump 1-A to SG 1 Manual Isolation of Auxiliary Feedwater Pump 1-B to SG 4 Ventilation (30)

Key Reference 1,2-T-30-175 1,2-T-30-176 1,2-T-30-182 1,2-T-30-183 1,2-TS-30-214 1,2-HS-30-214 40 40 1

37N 37N 47W866-8 47W866-8 47W866-8 47W866:8 47W610-30-6 47W610-30-6 RHR Pump Room Coolers Temperature Loop RHR Pump Room Coolers Temperature Loop CCP Rm Clr Temp Control Loop CCP Rm Clr Temp Control Loop Turbine Driven Auxiliary Feedwater Pump Room Vent Fan Temp Switch Turbine Driven Auxiliary Feedwater Pump Room Vent FanHandswitch 111-35 Rev. 9 Component Tnicrintinn S........ A

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Key Reference rtnii n

itilation (30) (Continued)

Description 1-FCO-30-443 2-FCO-30-444 1-FCO-30-445 2-FCO-30-446 1-FCO-30447 HS-30-447B 1-TS-30-447B 2-TS-30-447B HS-30-447C 2-FCO-30-448 2-TS-30-448B HS-30-448B HS-30-448C 2-FCO-30-449 2-TS-30-449B HS-30-449B HS-30-449C 2-FCO-30-450 HS-30-450B HS-30-450C 2-TS-30-450B FCO-30-451 2-TS-30-451B HS-30-451B HS-30-451C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 37C 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 DG Building Intake Damper DG Building Intake Damper DG Building Intake Damper DG Building Intake Damper DG Building Exhaust Damper DG Building Exhaust Fadiandswitch DG Building Exhaust Temperature Switch DG Building Exhaust Temperature Switch DG Building Exhaust Fail-andswitch DG Building Exhaust Damper DG Building Exhaust Temperature Switch DG Building Exhaust FaiHandswitch DG Building Exhaust Fawandswitch DG Building Exhaust Damper DG Buildng Exhaust Temperature Switch DG Building Exhaust FaiHandswitch DG Building Exhaust Fadiandswitch DG Building Exhaust Damper DG Building Exhaust FaiHandswitch DG Building Exhaust Fadiands-witch DG Building Exhaust Temperature Switch DG Building Exhaust Damper DG Building Exhaust Temperature Switc DG Building Exhaust FaflIandswitch DG Building Exhaust FaflIandswitch V

111-36 Rev-9 Descrintion 0

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE fI-2 SHUTDOWN LOGIC COMPONENT LIST Rev. 9 Ventilation (30) (Continued)

%-,U lI IIJ I 11.,A1 I.

2-TS-30-452B FC0-30-452 HS-30-452B HS-30-452C I-FCO-30-453 1-TS-30-453B HS-30-453B HS-30-453C 2-FCO-30-454 HS-30-454B 2-TS-30-454B HS-30-454C K.

1-FCO-30-459 HS-30-459B HS-30-459C 2-FCO-30-460 HS-30-460B HS-30-460C 1-FCO-30-461 HS-30-461B HS-30-461C 2-FCO-30-462 HS-30-462B HS-30462C Key Reference Drawing 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 37C 37C 37C 37C 37C 37C 37C 37C 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 47W866-9 Description DG Building Exhaust Temperature Switch DG Building Exhaust Damper DG Building Exhaust Fadiandswitch DG Building Exhaust FaiHandswitch DG Building Exhaust Damper D G Building Exhaust Temperature Switch DG Building Exhaust Temperature Fan Handswitch DG Building Exhaust Temperature Fan Handswitch DG Building Exhaust Damper Switch DG Building Exhaust Fadiandswitch DG Building Exhaust Temperature Switch D G Building Exhaust Faifandswitch DG Electric Board Room Exhaust Damper DG Electric Board Room Exhaust Fan Handswitch" DG Electric Board Room Exhaust Fan Handswitch DG Electric Board Room Exhaust Damper DG Electric Board Room Exhaust Fan Handswitch DG Electric Board Room Exhaust Fan Handswitch DG Electric Boad Room Exhaust Damper DG Electric Board Room Exhaust Fan Handswitch DG Electric Board Room Exhaust Fan Handswitch DG Electric Board Room Exhaust Damper DG Electric Board Room Exhaust Fan Handswitch DG Electric Board Room Exhaust Fan Handswitch 1I-37

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 11-2 SHUTDOWN LOGIC COMPONENT LIST Ventilation (30) (Continued)

Key Reference 1hpcr-rntinn Elec Panel/

Gen Fan Elec Board Room Exhaust Fan Exhaust Fan 1 Exhaust Fan 2 37C 47W866-9 37C 47W866-9 37C 47W866-9 37C 47W866-9 DG Room 1A-A, 2A-A, 1B-B, 2B-B Electrical Board Room Unit 1AA, 2A-A, lB-B, 2B-B Diesel Generator Room Exhaust Fan Diesel Generator Room Exhaust Fan DC Powered TDAFW Pump Room Exhaust Fan37N RHR Pump 1A Cooling RHR Pump lB Cooling RHR Pump 2A Cooling RHR Pump 2B Cooling RHR Pump Room Cooler Fans 1A-A,1B-B, 2A-A,2B-B

@A flnmnonent 47W866-11 Emergency Exhaust-Fan 40 40 40 40 40 A/C (Cooling & Heating) (31)

Key Reference Drawing Description HS-3 1A-20A HS-31A-20B 0-FCO-31A-20 0-FSV-31A-20 0-T-31 A-22 0-FSV-31A-22A 0-FSV-3 1A-22B 37A 37A 37A 37A 37A 37A 37A 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 MCR Air Handling UniHandswitch MCR Air Handling UniHandswitch MCR Air Handling Unit Inlet Damper MCR Air Handling Unit Solenoid Valve MCR AHU Temperature Control Loop MCR AHU Cooling Fluid Solenoid Valve MCR AHU Cooling Fluid Solenoid Valve 111-38 Rev. 9 l,

OlllD~ll~ll x~an dry ttl xsot qnn Comnonent

SQN FIRE PROTECTION REPORT PART 1II - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST A/C (Cooling & Heating) (31) Continued Key Reference Drawincq Description 0-FCO-31A-23 0-FSV-31A-23 HS-31A-23A HS-31A-23B 0-T-31A-39 0-FSV-31A-39A 0-FSV-31A-39B 0-TCV-31 A-47&Loop 0-TCV-31A-48 0-TCV-31A-49 0-TCV-31A-50 37A 37A 37A 37A

.37A 37A 37A 37A 37A 37A 37A 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 MCR AHU Inlet Damper MCR AHU Solenoid Valve MCR Air Handling Unit Handswitch MCR Air Handling Unit Handswitch MCR AHU Temperature Control Loop MCR AHU Cooling Fluid Solenoid Valve MCR AHU Cooling Fluid Solenoid Valve MCR AHU Cooling Fluid Control MCR AHU Cooling Fluid Control MCR AHU Cooling Fluid Control MCR AHU Cooling Fluid Control U.

1IH-39 Comoonent Rev. 9

ýk COMmne.

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST A/C (Cooling & Heating) (31) (Continued)

Key Reference Dlrnwinn 0-T-31A-52 0-TCV-31A-65 & Loop 0-TCV-31A-66 & Loop 0-TCV-31A-67 & Loop 0-TCV-31A-68 & Loop 0-T-31A-70 O-P-31A-126 0-P-31A-127 0-T-31A-128 0-T-31A-129 0-LG-31 A-1 30 Loop 31A-131 0-T-31 A-1 32 0-T-31A-133 Loop 31A-134 O-ET-31A-136 0-P-31A-141 0-P-31A-142 0-T-31A-143 0-T-31A-144 0-LG-31 A-1 45 Loop 31A-146 0-T-31 A-1 47 0-T-31A-148 O-ET-31A-151 Loop 31A-149 37A 37A 37A 37A 37A 37A 37A 37A 37A 37A 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-2 47W867-4 47W867-4 47W867-4 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 37A 37A 37A 37A 37A 47W867-4 47W867-4 47W867-4 47W867-4 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 37A 47W867-4 MCR AHU Air Controls MCR AHU Cooling Fluid Control MCR AHU Cooling Fluid Control MCR AHU Cooling Fluid Control MCR AHU Cooling Fluid Control MCR AHU Air Control MCR AHU Condensing Unit Pressure Control MCR AHU Condensing Unit Pressure Control MCR AHU Condensing Unit Temperature Control MCR AHU Condensing Unit Temperature Control MCR AHU Condensing Unit Oil Sump Level Glass MCR AHU Condensing Unit A-A MCR AHU Condensing Unit Oil Pump Motor Temperature Oil Cooler MCR AHU Condensing Unit Control MCR AHU Condensing Unit A-A MCR AHU Condensing Unit Liquid Pressure MCR AHU Condensing Unit Liquid Pressure MCR AHU Condensing Unit Liquid Pressure MCR AHU Condensing Unit Temperature Controls MCR AHU Condensing Unit Temperature Controls MCR AHU Condensing Unit Oil Sump Level Glass MCR AHU Condensing Unit B-B MCR AHU Condensing Unit Oil Pump Motor Temperature Oil Cooler MCR AHU Condensing Unit Control MCR AHU Condensing Unit Comp. Mtr. Power Supply MCR AHU Condensing Unit B-B A/C (Cooling & Heating) (31) (Continued)

Key Reference O-P-31 A-1 72 0-P-31A-173 0-FCO-31A-176 37A 47W867-4 37A 47W867-4 37A 47W867-2 II40 MCR AHU Condensing Unit Liquid Pressure MCR AHU Condensing Unit Liquid Pressure MCR AHU Inlet Damper

(.nrnnn~nt*n Rev. 9 Descridtion F1crnt inn C om Ip...

t

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u IgnLt t

0-T-31 A-1 76 0-FCO-31A-177 0-T-31A-177 NC U A-A A/C U B-B 37; 37; 37; 37 37 SQN FIRE PROTECTION REPORT PART I1 - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST rA 47W867-2 MCR AHU Inlet Damper Control rA 47W867-2 MCR AHU Inlet Damper 7A 47W867-2 MCR AHU Inlet Damper Control 7A 47W867-2 MCR Air Conditioning Unit 7A 47W867-2 MCR Air Conditioning Unit Control Air (32)

Key Component 0-FSV-32-37 0-FSV-32-42 O-FSV-32-61 0-FSV-32-62 0-FCV-32-82 O-PS-32-82 0-FCV-32-85 O-PS-32-85 0-FSV-32-87 Reference Drawing 13 13 13 13 13 13 13 13 13 Description 47W845-5Station Air Compressor B Coolant Water Inlet Valve 47W845-5Station Air Compressor A Coolant Water Inlet Valve 47W845-6Auxiliary Air Compressor A-A Cooling Water Inlet 47W848-1 Auxiliary Air Compressor A-A Unloader Valve 47W848-1 Auxiliary Air Compressor A-A Auxiliary Building Isolation 47W848-1Auxiliary Air CompressorA-A Auxiliary Building Isolation Control 47W848-1Auxiliary Air Compressor B-B Auxiliary Building Isolation Valve 47W848-1 Auxiliary Air Compressor B-B Auxiliary Building Isolation Control 47W848-1 Auxiliary Air Compressor B-B Auxiliary Building Isolation 11141 Rev. 9

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMIPONENT LIST Component 0-FSV-32-88 Key Reference Drawing 13 Station Air Compressor A Station Air Compressor B Aux Air Compressor A Aux Air Compressor B Control Air Supply Path 1 Control Air Supply Path 2 Control Circuit for Air Comp A Control Circuit for Air Comp B Control Circuit for Aux Air Comp A Control Circuit for Aux Air Comp B Control Air (32) (Continued) 13 13 13 13 12, 16 12,16 13 13 13 13 Description 47W848-1 47W846-1 47W846-1 Auxiliary Air Compressor B-B Unloader Valve Compressor Compressor 47W848-1 Compressor 47W848-1 Compressor 47W846-1 47W846-1 47W846-1 47W846-1 47W848-1 47W848-1 Service Air (3ý)

Component 0o-VLV-33-500 O-VLV-33-501 Key Reference Drawing 13 13 Description 47W846-1 47W846-1 Station Air to Control Air Manual Isolation Station Air to Control Air Manual Isolatioh 11142 Rev. 9

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE HI-2 SHUTDOWN LOGIC COMPONENT LIST Feedwater Control System (46)

Component Loop FIC-46-57 Loop SC-46-57 Key Reference Drawing 14,15 14,15 Description 47W610-46-1TDAF WP Flow Control 47W610-46-1TDAF WP Speed Control Chemical and Volume Control System (62)

Component 1 &2-FCV-6:

I &2-FCV-6:

1 &2-FCV-6 1 &2-FCV-6 Key Reference Drawing 2-9 48 2-22 48 2-35 48 2-48 48 Description 48W809-1 47W809-1 47W809-1 47W809-1 RCP Seal Return Isolation Valve RCP Seal Return Isolation Valve RCP Seal Return Isolation Valve RCP Seal Return Isolation Valve 1 &2-FCV-62-54 1 &2-FCV-62-55 "1

&2-FCV-62-56 1 &2-FCV-62-69 1 &2-FCV-62-70 1 &2-FCV-62-72 1 &2-FCV-62-73 1 &2-FCV-62-74 8,48 8,48 8,48 7,48 7,48 7,48 7,48 7,48 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 Excess Letdown Isolation Valve Excess Letdown Isolation Valve Excess Letdown Isolation Valve RCS Loop 3 Letdown Flow Valve RCS Loop 3 Letdown Flow Valve Regen Heat Exchanger Letdown Isolation Valve Regen Heat Exchanger Letdown Isolation Valve Regen Heat Exchanger Letdown Isolation Valve 111-43 Rev. 9

SQN FIRE PROTECTION REPORT PART IIH - SAFE SHUTDOWN CAPABILITIES TABLE I1-2 SHUTDOWN LOGIC COMPONENT LIST Chemical and Volume Control System (62) (Continued)

Reference n rln;nn 1 &2-FCV-62-84 1 &2-FCV-62-85 1 &2-FCV-62-86 1 &2-FCV-62-89 1 &2-FCV-62-90 1 &2-FCV-62-91 1 &2-FCV-62-93 1-FCV-62-98 2-FCV-62-98 1-FCV-62-99 2-FCV-62-99 PCV-62-119 PCV-62-120 FSV-62-125 PCV-62-126 1 &2-L-62-129A 1&2-L-62-130A 1 &2-FCV-62-132 1 &2-FCV-62-133 1 &2-LCV-62-135 1 &2-LCV-62-136 1 &2-FCV-62-77 1 &2-PCV-62-81 VLV-62-672 I &2-TCV-62-79 1 &2-FCV-62-59 1 &2-FCV-62-61 1 &2-FCV-62-63 34 34 34 34 34 34 2,34 1

1 5

5 5

5 4,5 4,5 4,5 4,5 4,5 4,5 48 48 48 48 48 48 48 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 Auxiliary Spray Isolation Valve Alternate Charging Flow RCS CL loop 1 Isolation Valve Normal Charging Flow RCS CL Loop 4 Isolation Valve Charging Flow Control Valve Charging Flow Isolation Valve Charging Flow Isolation Valve Charging Header Flow Control Valve Centrifugal Charging Pump Minimum Flow Isolation Valve Centrifugal Charging Pump Minimum Flow Isolation Valve Centrifugal Charging Pump Isolation Valve Centrifugal Charging Pump Isolation Valve VCT Isolation From Nitrogen VCT Isolation From Hydrogen VCT Vent Isolation VCT Vent Isolation VCT Level Loop VCT Level Loop VCT Outlet Isolation Valve VCT Outlet Isolation Valve Charging Pump Flow from RWST Charging Pump Flow from RWST Normal Letdown Isolation Valve VCT Letdown Pressure Control Valve PCV by-pass valve VCT Letdown Temp. Control Valve Excess Letdown Three-way Valve Excess Letdown Isolation Valve Excess Letdown Isolation Valve Chemical and Volume Control System (62) (Continued)

Key r1

^nnf nf Reference

'*rnwinn np.,nrintion 11144 Key I ai npti,-an an

• it Rev. 9 I.,i.U I

IfI.Il IoI 1 I.,S

• 1 i I*r, Hnfinn

SQN FIRE PROTECTION REPORT PART I11 - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST 1 &2-VLV-62-526 1 &2-VLV-62-527 I &2-VLV-62-533 1 &2-VLV-62-534 VLV-62-538 VLV-62-689 VLV-62-692 VLV-62-693 1 &2-Centrifugal Charging Pump A-A I &2-Centrifugal Charging Pump B-B 1&2 CCP Room Cooler 1 Fan A-A CCP Room Cooler Fan B-B CCP Aux Lube Oil Pump A-A CCP Aux Lube Oil Pump B-B 1 &2-LCV-62-118 1 &2-RV-62-662 1 &2-VLV-62-723 1 &2-RV-62-636 1 &2-VLV-62-715 2,34 2

2 2,34 34 5

5 5

1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 47W809-1 Charging Flow Manual Bypass Valve CCP A Manual Isolation to Charging B Manual Isolation to Charging Charging Flow Manual Bypass Valve RCS Makeup Manual FCV Bypass VCT Gas Sample Manual Isolation Manual VCT Isolation From Nitrogen Manual VCT Isolation From Hydrogen Key 1 Key I 47W809-1 Key 1 1

1 48 48 48 48 48 47W61 0-62-2 47W610-62-2 47W809-1 47W809-1 47W809-1 47V809-1 47W809-1 Oil Supply for CCP A Oil Supply for CCP B VCT Level Control Valve Normal Letdown to PRT Normal Letdown Header Isolation Valve Excess Letdown Relief Valve to PRT Excess Letdown Header Isolation Valve 11145 Rev. 9

.1

SQN FIRE PROTECTION REPORT PART 11 - SAFE SHUTDOWN CAPABILITIES TABLE HI-2 SHUTDOWN LOGIC COMPONENT LIST Safety Injection System (63)

Reference rflp*r~rintinn 1 &2-FCV-63-1 1 &2-FCV-63-5 1 &2-FCV-63-6 1 &2-FCV-63-7 1 &2-FCV-63-8 1 &2-FCV-63-11 1 &2-FCV-63-25 1 &2-FCV-63-26 1 &2-FCV-63-39 1 &2-FCV-63-40

"*1 &2-FCV-63-41

"*1 &2-FCV-63-42 I &2-FCV-63-47 FCV-63-63 FCV-63-65 FCV-63-67 1 &2-FCV-63-72 1 &2-FCV-63-73 FCV-63-80 FCV-63-87 1 &2-FCV-63-93 5

4,5 4,5 4,5 30 30 6

6 6

6 6

6 4,5 36 36 36 5,

30 5,

30 36 36 30 47W811-1 47W811-1 47W811-1 47WB11-1 47W811-1 47W81 1-1 47W811-1 47W811-1 47W811-1 47W811-1 47W811-1 47W811-1 47W811-1 47W811-1 47W830-6 47W811-1 47W811-1 47WB11-1 47W811-1 47W811-1 47W811-1 RWST to RHR Pump Flow Control RWST to SIS Pump Flow Control SIS Pump Inlet to CVCS Charging Pump SIS Pump Inlet to CVCS Charging Pump RHR Pump Supply to CCPs Flow Control RHRP Outlet to SIP Inlet Isolation Valve SIS CCPIT Shutoff SIS CCPIT Shutoff SIS CCPIT Shutoff SIS CCPIT Shutoff SIS CCPIT to CVCS Boric Acid Tank SIS CCPIT to CVCS Boric Acid Tank SIS Pump 1A-A Inlet Valve AT No. 4 Nitrogen Isolation Valve AT No. 4 Nitrogen Vent Valve AT No. 4 Flow Isolation Valve Containment Sump Flow Isolation Valve Containment Sump Flow Isolation Valve AT No. 3 Flow Isolation Valve AT No. 3 Nitrogen Isolation Valve RHR Pump A-A Discharge to Cold Leg 2 & 3

• These valves are normally locked closed with powerremoved.

111-46 Key Rev. 9

'.UII IFUI IUI IL L

I

'4.....rption

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE I[I-2 SHUTDOWN LOGIC COMPONENT LIST Safety Injection System (63) (Continued)

Component 1 &2-FCV-6 FCV-63-98 FCV-63-10" FCV-63-11 FCV-63-12 1 &2-FCV-6 1 &2-VLV-6:

Key Reference Drawing 3-94 30 36 7

36 8

36 7

36 3-172 30 3-574 6

Description 47W811-1 RHR Pump B-B Discharge to Cold Leg 1 & 4 47W811-1 AT No. 2 Flow Isolation Valve 47W811-1 AT No. 2 Nitrogen Isolation Valve 47W811-1 AT No. 1 Flow Isolation Valve 47W811-1 AT No. 1 Nitrogen Isolation Valve 47W811-1 RHR Hot Leg Injection Isolation Valve 47W811-1 SIS CCPIT Outlet Valve to Boric Acid and CVCS Holdup Tanks Essential Raw Cooling Water (67)

Key Component 0-FCV-67-12 0-FCV-67-14 I-FCV-67-22 2-FCV-67-22 1 -FCV-67-24 2-FCV-67-24 1 &2-FCV-67-66 1 -FCV-67-162 1 -FCV-67-164 2-FCV-67-217 2-FCV-67-219 Reference Drawing 3

3,9 3

3 3

3 3

370 370 370 370 Description 47W845-1 47W845-1 47W845-1 47W845-1 47W845-1 47W845-1 47W845-1 47W845-6 47W845-6 47W845-4 47W845-4 ERCW Header A Return Discharge Canal Shutoff Valve ERCWHeaderA Return Discharge Canal Shutoff Valve ERCW HDR 1A/2A Cross-tie ERCW 2A/1 A Cross-tie ERCW HDR 1 B/2B Cross-tie ERCW HDR 2B/1B Cross-tie DG Heat Exchanger Isolation Valve CCS & AFW Pump Space Cooler Isol. Valve CCS & AFW Pump Space Cooler Isol. Valve BA & AFW Pump Space Cooler Isol. Valve BA & AFW Pump Space Cooler Isol. Valve II147 Rev. 9

SQN FIRE PROTECTION REPORT PART Il - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Essential Raw Cooling Water (67) (Continued)

Component 1 &2-FCV-67-67 1-FCV-67-81 2-FCV-67-81 1-FCV-67-82 2-FCV-67-82 1-FCV-67-123 2-FCV-67-123 1 -FCV-67-124 2-FCV-67-124 1-FCV-67-125 2-FCV-67-125 1-FCV-67-126 2-FCV-67-126 1 -FCV-67-127 2-FCV-67-127

" Description (ey Reference Drawing 3

3 3

3 3

3,19 3,19 3,19 3,19 3,19 3,19 3,19 3,19 3,13 3

DG Hx Isolation Valve Auxiliary Building ERCW Supply Header 1A Isolation Valve Auxiliary Building ERCW Supply Header 2A Isolation Valve Auxiliary Building ERCW Supply Header 1 B Isolation Valve Auxiliary Building ERCW Supply Header 2B Isolation Valve Containment Spray Heat Exchanger 1 B Supply Control Valve Containment Spray Heat Exchanger 2B Supply Control Valve Containment Spray Heat Exchanger 1 B Discharge Valve Containment Spray Heat Exchanger 2B Discharge Valve Containment Spray Heat Exchanger 1A Supply Control Valve Containment Spray Heat Exchanger 2A Supply Control Valve Containment Spray Heat Exchanger 1A Discharge Valve Containment Spray Heat Exchanger 2A Discharge Valve Supply Valve for ERCW Flow to Air Conditioning Equipment 1A, and Service Air Compressor Supply Valve for ERCW Flow to Air Conditioning Equipment 2A 11148 Rev. 9 47W845-1 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Essential Raw Cooling Water (67) (Continued)

Key Reference Drawina 1 -FCV-67-128 2-FCV-67-128 1-FCV-67-146 2-FCV-67-146 1-FCV-67-147 2-FCV-67-147 0-FCV-67-151 0-FCV-67-152 1-FCV-67-168 2-FCV-67-168 1-FCV-67-170 2-FCV-67-170 1 -FCV-67-188 2-FCV-67-188 1-FCV-67-190 2-FCV-67-190 3,13, 3,13 1,9 1,9 3

3,19 1

1 3

3 3

3 40 40 40 40 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-2 47W845-6 47W845-4 47W845-6 47W845-4 47W845-6 47W845-4 47W845-6 47W845-4 Supply Valve for ERCW Flow to Air Conditioning Equipment IB, and Service Air Compressor Supply Valve for ERCW Flow to Air Conditioning Equipment 2B Component Cooling System Heat Exchanger 1Al/1A2 Discharge Control Valve Component Cooling System Heat Exchanger 2A1/2A2 Discharge Control Valve Cross Connect Valve, Main Supply Control Header 1A Cross Connect Valve, Main Supply Header 2B Component Cooling System Heat Exchanger OB1/0B2 Discharge Control Valve Component Cooling System Heat Exchanger OB1/0B2 Discharge Control Valve Supply Valve for ERCW Flow to Centrifugal Charging Pump Room Cooler 1A Supply Valve for ERCW Flow to Centrifugal Charging Pump Room Cooler 2A Supply Valve for ERCW Flow to Centrifugal Charging Pump Room Cooler 1B Supply Valve for ERCW Flow to Centrifugal Charging Pump Room Cooler 2B Supply Valve for ERCW Flow to RHR Pbmp Room Cooler 1A Supply Valve for ERCW Flow to RHR Pump Room Cooler 2A Supply Valve for ERCW Flow to RHR Pump Room Cooler 1 B Supply Valve for ERCW Flow to RHR Pump Room Cooler 2B 11149 Comnonent Rev. 9 Description C om..po..

t

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Essential Raw Cooling Water (67) (Continued)

Key Reference DrawinQ Description 0-TCV-67-197 0-TCV-67-201 0-FCV-67-205 FS-67-206 PS-67-206 0-FCV-67-208 FS-67-209 PS-67-209 1 &2-FCV-67-223 0-FCV-67-364 0-FCV-67-365 1-FCV-67-424 0-FCV-67-478 1.9.19 1-FCV-67-489 2-FCV-67-489 I &2-FCV-67-490A 1 &2-FCV-67-490D 1&2-FCV-67-491A 1 &2-FCV-67-491 D 1-FCV-67-492 2-FCV-67-492 37A 37A 13 13 13 13 13 13

3.

19 3

3, 9

3, 19 47W845-2 3

3 3

3 3

3 3

3 47W845-6 47W845-6 47W845-5 47W61 0-67-5 47W610-67-5 47W845-5 47W610-67-5 47W610-67-5 47W845-2 47W845-1 47W845-1 47W845-2 MCR A/C Discharge Isolation MCR A/C Discharge Isolation Station Service and Control Air Compressor Supply Header A Isolation Valve ERCW to Station Air Comp Train A ERCW to Station Air Comp Train A Station Service and Control Air Compressor Supply Header 1 B Isolation Valve ERCW to Station Air Comp Train B ERCW to Station Air Comp Train B Supply Header 1B to Header 2A Isolation Valve Header A Return Discharge Canal Shutoff Valve Header A Return Discharge Canal Shutoff Valve ERCW HDR 1B to HDR 2A ISOL VLV Supply Valve ERCW to Component Coolant Heat Exchanger 1A1/1A2 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 ERCW Strainer B1B-B Isolation Valve ERCW Strainer B2B-B Isolation Valve Strainer B Backwash Isolation Valve Strainer B Backwash Isolation Valve Strainer A Backwash Isolation Valve Strainer A Backwash Isolation Valve ERCW Strainer A1A-A Isolation Valve ERCW Strainer A2A-A Isolation Valve IHI-50 Comoonent Rev. 9 I

I

SQN FIRE PROTECTION REPORT PART II - SAFE SHUTDOWN CAPABILITIES TABLE HI-2 SHUTDOWN LOGIC COMPONENT LIST Essential Raw Cooling Water (67) (Continued)

Key Reference Drawina ERCW Pump J-A ERCW Pump K-A ERCW Pump Q-A ERCW Pump R-A ERCW Pump L-B ERCW Pump M-B ERCW Pump N-B ERCW Pump P-B ERCW Strainer A1A-A ERCW Strainer A2A-A ERCW Strainer B1B-B ERCW Strainer B2B-B ERCW Header 2A&1 B ERCW Header 2B&IA Screen Wash Pump A-A 3 Screen Wash Pump B-B 3 Screen Wash Pump C-B 3 Screen Wash Pump D-A 3 Traveling Screen A-A 3 Traveling Screen B-B 3 Traveling Screen C-B 3 Traveling Screen D-A 3 3

3 3

3

3.

3 3

3 3

3 3

3 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 I1, 3,9 1,3 Delivers ERCW Cooling to Header 1A Delivers ERCW Cooling to Header 1A Delivers ERCW Cooling to Header 2A Delivers ERCW Cooling to Header 2A Delivers ERCW Cooling to Header 1B Delivers ERCW Cooling to Header 1 B Delivers ERCW Cooling to Header 2B Delivers ERCW Cooling to Header 2B Strainer for ERCW Header 1A Strainer for ERCW Header 2A Strainer for ERCW Header 1B Strainer for ERCW Header 2B 47W845-5 47W845-5 47W845-5 "47W845-5 47W845-5 47W845-5 47W845-5 47W845-5 111-51 C*nmnonent Rev. 9 Description Com..pon.....

t

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE I1-2 SHUTDOWN LOGIC COMPONENT LIST Reactor Coolant (68)

Key Reference Drawing Description 1 &2-T-68-1 1 &2-T-68-18 1 &2-T-68-24 1 &2-T-68-41 1 &2-T-68-43 1 &2-T-68-60 1 &2-T-68-6 5 1 &2-P-68-66 1 &2-P-68-69 1 &2-T-68-83 1 &2-L-68-320 1 &2-FCV-68-332 1 &2-FCV-68-333 1,2-PCV-68-334 1 &2-L-68-335 1 &2-L-68-339 1 &2-PCV-68-340A 1 &2-PCV-68-340B 1,2-PCV-68-340D 1 &2-P-68-342C 1 &2-FSV-68-394 1 &2-FSV-68-395 1 &2-FSV-68-396 1 &2-FSV-68-397 28 28 28 28 28 28 28 28 28 28 2

4 28,48 28,48 7,28,48 2

4 2

4 7,28,48 28 28 28 7,48 47W610-68-1 47W610-68-1 47W610-68-2 47W610-68-2 47W610-68-3 47W610-68-3 47W610-68-4 47W610-68-7 47W610-68-7 47W610-68-4 7W61 0-68-5 47W813-1 47W813-1 47W813-1 7W61 0-68-5 7W610-68-5 47W813-1 47W813-1 47W813-1 47W610-68-5 47W813-1

" 7,48 47W813-1 7,48 7,48 47W813-1 47W813-1 Loop 1 Hot Leg Temperature Indicator Loop 1 Cold Leg Temperature Indicator Loop 2 Hot Leg Temperature Indicator Loop 2 Cold Leg Temperature Indicator Loop 3 Hot Leg Temperature Indicator Loop 3 Cold Leg Temperature Indicator Loop 4 Hot Leg Temperature Indicator RCS Pressure Loop for PI-68-66A RCS Pressure Loop for PR-68-69 Loop 4 Cold Leg Temperature Indicator Pressurizer Level Loop Pressurizer Relief Block Valve Pressurizer Relief Block Valve Pressurizer PORV RCS Pressurizer Water Level RCS Pressurizer Water Level Pressurizer PORV Pressurizer Spray Valve Pressurizer Spray Valve Pressurizer Pressure Instrument Loop for PI-68-342A Reactor Vessel Head Vent Isolation Valve ReactoFVessel Head Vent Isolation Valve Reactor Vessel Head Vent Throttle Valve Reactor Vessel Head Vent Throttle Valve HI-52 Comoonent Rev. 9 COMInen

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Component Cooling Water System (70)

Key Reference n r~winn

').crintin 0-FCV-70-1 1 &2-FCV-70-2 1 &2-FCV-70-3 1 &2-FCV-70-4 1 -FCV-70-8 1-FCV-70-9 1-FCV-70-1 0 0-FCV-70-11 0-FCV-70-12 1-FCV-70-13 2-FCV-70-14 S"-

2-FCV-70-15 "2-FCV-70-16 2-FCV-70-18 0-FCV-70-22 I-FCV-70-23 1-FCV-70-25 1-FCV-70-26 1-FCV-70-27 2-FCV-70-28 2-FCV-70-29 0-FCV-70-34 0-FCV-70-39 0-FCV-70-40 0-FCV-70-41 1,31 1

1 9

1,9 1,9 1,9 1,31 1

1,9 1,9 1,9 1,9 1,9 1

1,9 1,9 1,9 1,9 1,9 1,9 1,9 1,

1,31 1,31 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 SFPCS HX B Outlet Isolation Valve RHR HTX A Inlet Valve RHR HTX B Inlet Valve Miscellaneous Equipment Header Inlet Valve CCS HTX 1A1/1A2, Outlet Isolation Valve CCS HTX 1A1/1A2 & OB1/0B2, Outlet Isolation Valve CCS HTX 1A1/1A2 & OB1/0B2, Outlet Isolation Valve SFPCS Hx A Outlet Isolation Valve CCS HTX OB1/OB2 Outlet Isolation Valve CCS HTX 1A1/1A2 & 031/082, Inlet Isolation Valve CCS HTX 2A1/2A2 & OB1/0B2, Inlet Isolation Valve CCS HTX 2A1/2A2 Outlet Isolation Valve CCS Hx 2A1/2A2 Inlet Isolation Valve CCS HTX 2A1/2A2 & 0131/02, Inlet Isolation Valve CCS HTX OB1/0B2 Inlet Isolation Valve CCS HTX IA1/1A2 & OBI1/OB2, Inlet Isolation Valve CCS HTX 1AI/1A2 Inlet Valve CCS Pumps IA-A and 1B-B to C-S Outlet Isolation Valve CCS Pumps 1A-A and 1B-B to C-S Outlet Isolation Valve I

CCS Pump 2A-A and 28-B to C-S Outlet CCS Pump 2A-A and 28-B to C-S Outlet Isolation Valve CCS Pump 1A-A to 1B-B Inlet Isolation Valve CCS Pump 2A-A to 2B-B Inlet Isolation Valve SFPCS Hx A Inlet Isolation Valve SFPCS Hx B Inlet Isolation Valve 111-53 Rev. 9 t"*n~l n fln~fl r

U,

• UIIi; I

v;

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE III-2 SHUTDOWN LOGIC COMPONENT LIST Component Cooling Water System (70) (Continued)

Component 1 -FCV-70-64 1 -FCV-70-74 1 &2-FCV-70-7 2-FCV-70-76 2-FCV-70-78 I &2-FCV-70-8 1 &2-FCV-70-9 1 &2-FCV-70-1 1 &2-FCV-70-1 1 &2-FCV-70-1 1 &2-FCV-70-1 0-FCV-70-193 1 &2-FCV-70-8 1 &2-FCV-70-1 1 &2-TCV Key Reference Drawing 1

9 1

9

'5 1

1 9

1 9

17 9

0 9

133 9

34 9

153 1,31 156 1

9,31 1,

9, 31 35 48 143

48.

192 48 Description 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-2,3 47W859-2,3 47W859-2,3 47W859-2,3 47W859-4 47W859-4 47W859-1 47W859-2,3 47W859-2,3 47W859-2,3 CCS Pumps 1A-A and 1B-B to C-S Inlet Isolation Valve CCS Pumps 1A-A and 1B-B to C-S Inlet Isolation Valve RHR Heat Exchanger B Return Header Isolation Valve CCS Pumps 2A-A and 2B-B to C-S Inlet Isolation Valve CCS Pumps 2A-A and 2B-B to C-S Inlet Isolation Valve Reactor Coolant Pump Thermal Barrier Return Isolation Valve Reactor Coolant Pump Thermal Barrier Return ISOL Valve Reactor Coolant Pump Thermal Barrier Coolant Isolation Valve Reactor Coolant Pump Thermal Barrier Coolant Isolation Valve RHR Heat Exchanger B Outlet Valve RHR Heat Exchanger A Outlet Valve SFPCS Heat Exchanger A & B Inlet Valve CCS to Excess Letdown HX CCS to Excess Letdown HX CCS to Letdown HX 111-54 Rev. 9

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Component 0-FCV-70-194 2-FCV-70-195 2-FCV-70-196 0-FCV-70-197 0-VLV-70-529A 0-VLV-70-529B 1-VLV-70-531 0-FCV-70-198 1 &2-VLV-70-545A 1 &2-VLV-70-545B 1 &2-VLV-70-546A 1 &2-VLV-70-546B O-VLV-70-574 0-VLV-70-587 0-VLV-70-601 0-VLV-70-636 0-VLV-70-637 0-VLV-70-661 CCS Pump B-B CCS Pump A-A CCS Pump C-S RCP Thermal Barrier Booster Pump A-A Booster Pump B-B Component Cooling Water System (70) (Continued)

Key Reference Drawing 1,

9, 31 1

9 1

9 1,31,9 1,31,9 1,31,9 1,31 1,9,31 1,9 1

1,9 1

31 31 31 31 31 31 1,9 1,9 1,9 9

9 Description 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-1 47W859-4 47W859-4 47W859-4 47W859-4 47W859-2&3 47W859-1 &2 47W859-2 47W859-2 47W859-2,3 47W859-2,3

-47W859-1 47W859-1 47W859-1 47W859-2,3 47W859-2,3 SFPCS Heat Exchanger A & B Inlet Valve CCS HTX 2A1/2A2 & OBI/0B2, Outlet Isolation Valve CCS HTX 2A1/2A2 & OB1/OB2, Outlet Isolation SFPCS HTX Supply Header Valve SFPCS HTX A Outlet Manual Isolation Valve SFPCS HTX B Outlet Manual Isolation Valve SFPCS HTX Return Manual Isolation Valve SFPCS HTX Supply Header Valve RHR A Inlet Isolation Valve RHR B Inlet Isolation Valve RHR HTX A Outlet Valve RHR HTX 1A-A Outlet Valve Non Regen Letdown HTX Manual Inlet Non Regen Letdown HTX Manual Outlet Comp Cooling to ERCW Manual Isolation Outlet ERCW Cooling to CCS Inlet GAE&GS Inlet Isoltion Valve BAE&GS Outlet Isolation Valve 111-55 Rev. 9

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Containment Spray (72)

Key Reference Drawing 1 &2-FCV-72-2 1 &2-FCV-72-20 1 &2-FCV-72-21 I &2-FCV-72-22 1 &2-FCV-72-23 1 &2-FCV-72-39 1 &2-FCV-72-40 1 &2-FCV-72-41 CS Pump A-A CS Pump B-B 4,5 5

5 5

5 4,5 4,5, 30 4,5, 30 4,5 4,5 47W812-1 47W812-1 47W812-1 47W812-1 47W812-1 47W812-1 47W812-1 47W812-1 Containment Spray Header B Isolation Valve Containment Sump Isolation to CSPs Containment Spray Pump RWST Isolation Containment Spray Pump RWST Isolation Containment Sump Isolation to CSPs Containment Spray Header A Isolation Valve RHR Spray Header A Isolation Valve RHR Spray Header B Isolation Valve 47W812-1 47WR12-1 Residual Heat Removal (74)

Key Reference Drawing 1 &2-FCV-74-1 1 &2-FCV-74-2 1 &2-FCV-74-3 1 &2-FCV-74-12 1 &2-FCV-74-16 I &2-FC\\'-74-21 1 &2-FCV-74-24 1 &2-FCV-74-28 1 &2-FCV-74-32 1 &2-FCV-74-33 1 &2-FCV-74-35 1 &2-HCV-74-36 1 &2-HCV-74-37 RHR Pump A-A RHR Pump B-B 7,30 7,30 30 5,30 30 30

" 5*

30 30 30 30 30 30 31,4,5 31,4,5 47W81 0-1 47W81 0-1 47W81 0-1 47W810-1 47W81 0-1 47W81 0-1 47W810-1 47W810-1 47W810-1 47W81 0-1 47W810-1 47W810-1 47W81 0-1 47W81 0-1 47W81 0-1 RHR System Isolation Valve RHR System Isolation Valve RHR Pump A-A Inlet Flow Control Valve RHR Pump A-A Min Flow Valve RHR HTX A Outlet Flow Control Valve RHR B-B Pump B-B Inlet Flow Control Valve RHR Pump B-B Mini Flow Valve RHR HTX B Outlet Flow Control Valve RHR HTX Bypass Flow Control Valve RHR HTX A Bypass Valve RHR HTX B Bypass Valve RHR HTX A Bypass Valve RHR HTX B Bypass Valve 111-56 Component Rev. 9 Description ComDonent Description S..

. n C....

o--

enn

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES TABLE 111-2 SHUTDOWN LOGIC COMPONENT LIST Rev. 9 Waste Disposal System (77)

Key Reference t

Drawino 5

Key Reference Drawing Descriotion 47W830-4 Waste Gas Compressor Isolation From VCT Vent Path Neutron Monitoring System (92) and Reactor Protection System (99)

Description HS-RT-1 or HS-RT-2 XI-92-5001 B XI-92-5002B

(. -,Reactor Trip Breaker A Reactor Trip Breaker B Rod Drive Motor Generator Set Breaker A&B 47W611-99-1 29 29 29 29 29 47W611-99-1 47W611-99-1 47W611-99-1 29 111-57 C*nmnnna~nt PCV-77-89 Component Component Drawino I

m

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES TABLE HI-3 INSTRUMENTATION LIST FOR MAIN CONTROL ROOM Indicator LI-68-339 LI-68-320 One of three LI-68-335A PI-68-342A PI-68-66A One of three PR-68-69 PI-1-2A Either one PI-1-2B PI-1-9A Either one P1-1-9B PI-1-20A Either one PI-1-20B PI-1-27A Either one PI-1-27B.

LI-3-43 LI-3-174 LI-3-164 LI-3-38*

Either one L;-3-39 LI-3-56 LI-3-156 LI-3-173 LI-3-51*

Eitherone LI-3-52 Description Pressurizer Water Level Pressurizer Water Level Pressurizer Water Level RCS WR Pressure RCS WR Pressure RCS WR Pressure SG-1 Steam Press SG-1 Steam Press SG-2 Steam Press SG-2 Steam Press SG-3 Steam Press Loops SG-3 Steam Press Required SG-4 Steam Press SG-4 Steam Press Two SG-1 NR Level SG-1 NR Level SG-2 NR Level SG-2 NR Level LI-3-98 LI-3-172 LI-3-148 LI3-93*

Either one LI-3-94 LI-3-111 LI-3-175 LI-3-171 LI-3-106* Either one LI-3-107 SG-3 NR Level SG-3 NR Level SG-4 NR Level SG-4 NR Level III-58 Rev. 9

SQN FIRE PROTECTION REPORT PART Ill - SAFE SHUTDOWN CAPABILITIES TABLE 111-3 Rev. 9 INSTRUMENTATION LIST FOR MAIN CONTROL ROOM Indicator Description TI-68-1 RCS Loop 1 Hot Leg TI-68-18 RCS Loop 1 Cold Leg TI-68-24 RCS Loop 2 Hot Leg TI-68-41 RCS Loop 2 Cold Leg Two loops TI-68-43 required RCS Loop 3 Hot Leg TI-68-60 RCS Loop 3 Cold Leg TI-68-65 RCS Loop 4 Hot Leg TI-68-83 RCS Loop 4 Cold Leg Source Range Flux Monitor XI-92-5001 B Either one XI-92-5002B Condensate Storage Tank Level 1

LI-2-230A Either one for Tank A (Note 1)

2.

LI-2-230D

3.

LI-2-233A Either one for Tank B (Note 1)

4.

LI-2-233D Chemical and Volume Control

1.

LI-62-129 (Tank Level-VCT)

Note 2

2.

FI-62-93A (Charging Flow)

Note 3 Note 1:lf MCR indication is not available, local monitorifri of tank level or AFW suction pressure is acceptable Note 2:

Refer to key 4 for actions if this level indication is not available.

Note 3:This indicator is only required if the normal charging path is chosen in key 2.

• Denotes steam generator level transmitters whose sense lines have been verified as being unaffected by a fire inside containment (Reference 11.21).

Only the sense lines are Appendix R equipment (i.e., the cabling was not evaluated).

111-59

SQN FIRE PROTECTION REPORT PART III - SAFE SHUTDOWN CAPABILITIES Rev. 9 TABLE II-3 SECUOYAH MUCLEAR PLANT FIGURE Ill-I APPENoIX R SAFE SHUTDOWN LOGIC DIAGRAM III-60

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION

1.0 INTRODUCTION

This part documents the methodology used to satisfy 10CFR50 Appendix R Section IIIJ & 111.0.

III.J requires emergency lighting units with at least an 8-hour battery power supply in all areas needed for operation of safe shutdown equipment and in access and egress routes thereto.

Section 111.0 requires the reactor coolant pump to be equipped with an oil collection system if the containment is not inerted during normal operation.

2.0 EMERGENCY LIGHTING Emergency lighting units with at least an 8-hour battery power supply are provided in areas needed for operation of safe shutdown equipment and in access and egress routes as required by 10CFR50 Appendix R, Section III.J. Emergency lighting is provided for Appendix R fire scenarios that require manual operator actions (ref. 4.1.1) within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in order to ensure safe shutdown capability. Portable lanterns are also available for performance of manual actions (ref. 4.1.2) and in the event access is required to remote areas of the site (e.g. yard, DGB, ERCW pumping station, Reactor Building). Additionally, although cable separation analysis has not beeh included in the safe shutdown analysis, permanently installed standby lighting powered by the shutdown boards (LS lighting cabinets) and emergency lighting powered by vital batteries (LD lighting cabinets) will contribute to the lighting levels in the plant. The DGB has lighting provided by lighting cabinets that are three hour separated. The security system provides lighting for the yard areas.

Plant walkdowns have been conducted to assess the adequacy of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> emergency lighting units in access/egress routes to manual action locations in the plant and at the manual action locations. The adequacy of this emergency lighting was evaluated by fire protection engineers and/or plant operators who would be responsible for performing the manual actions during an Appendix R event (ref. 4.1.3). Walkdown checklists for the emergency lighting units provided for manual action locations and access/egress routes were performed (ref. 4.1.4). Additional lighting units were added and existing units modified/adjusted to achieve additional lighting (ref. 4.1.5).

Functional tests are specified by the Surveillance Requirements (Part II, Section 14.7) and are detailed in approved instructions (ref. 4.1.6), which are performed on the emergency battery lighting units by simulating a loss of power. FOR 3.7.14, SR 4.7.14 and the Bases for Section 14.7 of Part II of the FPR provide the operating and surveillance requirements, and the technical bases for those requirements.

Emergency lighting units with 8-hr battery supply are provided with unique identification numbers in the locations listed in Table V-1. The illuminated components and/or areas are also listed.

V-1

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION 3.0 REACTOR COOLANT PUMP OIL COLLECTION The reactor coolant pumps (RCPs) are equipped with an oil collection system. The oil collection system is designed, engineered, and installed such that failure of oil containing components on the RCPs will not lead to fire during normal or design basis accident conditions. Additionally, there is reasonable assurance that the system will with-stand the Safe Shutdown Earthquake.

The oil collection system is capable of collecting lube oil from all potential pressurized and unpressurized leakage sites in the reactor coolant pump lube oil system. The oil leakage is safely collected and drained to a vented closed sump.

The drain piping located between the oil collection basins (around the pump) and the containment floor (oil drains to the auxiliary reactor building sump), is designed to category I (L) requirements so the piping will not fail during a safe shutdown earthquake and damage nuclear safety-related equipment. The drain piping has not been designed to maintain its pressure boundary integrity after the event. The RCP lubricating oil system, and the auxiliary reactor building sump are designed to seismic category I requirements so they will not fail during a safe shutdown earthquake (ref. 4.1.7). The total system provides more than reasonable assurance that a RCP lubricating oil fire will not occur as a result of a seismic event.

The RCP oil collection system does not have the capacity to hold the entire contents from all four RCP lubricating oil systems. The ireactor coolant pump motors, the lubricating oil systems, and the auxiliary "reactor building (pocket) sump are all designed to seismic category I requirements so they will not fail during a safe shutdown earthquake. Therefore, assuming only a single random failure, the oil collection system would only be required to hold the oil resulting from the largest spill due to such a single failure. The largest single failure is the rupture of the upper bearing oil system of one RCP, which contains 240 gallons of oil.

The auxiliary reactor building sump holds approximately 200 gallons. Additional storage capacity of 140 gallons is available in the embedded piping systems for a total of 340 gallons of capacity (ref. 4.1.8).

Annunciator response instructions require the operator to pump the auxiliary reactor building sump down in the event of a RCP high/low oil reservoir alarm in order to ensure adequate capacity is available for oil collection (4.1.9).

The sump vents do not require the installation of flame arresters because the high flashpoint characteristics of the reactor coolant pump lube oil preclude the hazard of fire flashback.

Refer to Part VII of this FPR for deviations to Section 111.0.

V-2

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION

4.0 REFERENCES

4.1 TVA Documents 4.1.1 SQN-SQS4-0127, "Equipment Required for Safe Shutdown per 10CFR50 Appendix R" 4.1.2 AOP-C.04, "Control Room Inaccessibility" 4.1.3 Appendix R Project Documentation of Emergency Lighting: S01 85906 823, S01 851223 916, SOl 860214 805, S53 850822 916, S01 850517 892, S01 850424 819, S01 860507 949 4.1.4 Memo from R. S. Egli to I. M. Heatherly, dated May 9, 1994, "Walkdown of Emergency Lighting Required for Appendix R Fire Safe Shutdown Manual Actions", (B38 940509 800) 4.1.5 Modifications to Add Additional Appendix R Lights: ECN L5984, ECN L6287, DCN M00558D, DCN M0961 IB, DCN F10041A, DCN F11358A, DCN F12153ADCN M 12538A for the aiming and remote locating of 10 lampý and DCN D20071A/P20872A for remote locating 2 lamps and -he aiming of 6 lamps.

4.1.6 MI-1 0.56, "Emergency Lighting (Appendix R)"

4.1.7 Design Criteria, DC-V-3.0, "The Classification of Piping, Pumps, Valves, and Vessels."

4.1.8 Memo from J. H. Sullivan to Appendix R Project Files, "RCP Oil Collection System", S01 841206 919 4.1.9 1- & 2-AR-M5-B, "Annunciator Response" V-3

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-i, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-ROO1 0-LGT-247-R002 0-LGT-247-R003 0-LGT-247-R004 0-LGT-247-R005 O-LGT-247-R006 0-LGT-247-R007 O-LGT-47-R008 0-LGT-247-R009 O-LGT-247-R010 0-LGT-247-RO1 1 0-LGT-247-R012 O-LGT-247-RO13 0-LGT-247-R014 0-LGT-247-RO15 0-LGT-247-RO16 0-LGT-247-RO17 0-LGT-247-RO18 0-LGT-247-RO19 DESCRIPTION 749.0, Stair #8 749.0, A3/r-s 749.0, A8/s 749.0, A8/s 749.0, A13/r-s 749.0, Stair #7 749.0, A13/s-t 749.0, A8/s-t 749.0, A8/s-t 749.0,A3/s-t 749.0, A14/q 749"0, A14/s 749.0, A14/t 749.0, A14/u 759.0, A12/v 759.0, A12/w 759.0, Stair #9 759.0, A4/v 759.0, A4/w ILLUMINATED COMPONENTS Up/Dn Stairs & Doors RX MOV BD 1B1-B, 1B2-B, Vital Battery Charger I and its Transfer switch, Inverters 0-I, 1-I and 2-I Vital Battery Charger II and its Transfer switch, Spare Charger 1-S and its Transfer switches, Inverters 0-IT, 1-II and 2-1I Vital Battery Charger III and its Transfer switch, Spare Charger 2-S and its Transfer switches, Inverters 0-III, 1-Ill and 2-I11 RX MOV BD 2B 1-B, 2B2-B, Vital Battery Charger IV and its Transfer switch, Inverters 0-IV, I -V and 2-IV Up/Dn Stairs & Doors RX MOV BD 2A1-A, 2A2-A General Area General Area RX MOV BD 1A1-A, 1A2-A 2A-A Exh Fan Dampers 2A-A Exh Fan Dampers 2B-B Exh Fan Dampers 2B-B Exh Fan Dampers Stair S3 CRDM MG SET BKR A & B Up/Dn Stairs & Doors CRDM MG SET BKR A & B, General Area CRDM MG SET BKR A & B, General Area V-4

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-I, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID O-LGT-247-R020 0-LGT-247-R021 0-LGT-247-R022 0-LGT-247-R023 0-LGT-247-R024 0-LGT-247-R025 0-LGT-247-R026 0-LGT-247-R027 0-LGT-247-R028 0-LGT-247-R029 0-LGT-247-R030

• "2 0-LGT-247-R031 0-LGT-247-R032 0-LGT-247-R033 O-LGT-247-R034 0-LGT-247-R035 0-LGT-247-R036 0-LGT-247-R037 0-LGT-247-R038 0-LGT-247-R039 0-LGT-247-R040 0-LGT-247-R041 0-LGT-247-R042 0-LGT-247-R043 0-LGT-247-R044 DESCRIPTION 732.0, C2/n 732.0, Stair C1 732.0, C4/p 732.0, C5/n 732.0, C5/n 732.0, C6/n 732.0, C6/n 732.0, C7/n 732.0, C7/n 732.0, C8/n 732.0, C8/n 732.0, C8/n 732.0, C9/n 732.0, C10/n-p 732.0, C9/q 732.0, C8/q 732.0, C7/q 732.0, C6/q 732.0, C6/q 732.0, C5/q 732.0, Stair C2 732.0, C 11/n-p 732.0, C13/n 732.0, C13/p 732.0, C2/p-q ILLUMINATED COMPONENTS General Area, Chiller Package B, TCV-67-201 Up/Dn Stairs & Doors General Area, PNL l-M-9 Req by OPS Req By OPS, PNL l-M3 Req By OPS, PNL-1-M-2 Req By OPS, PNL l-M-1 Up/Dn Corridor Req By OPS, PNL-0-M-12 OPS Req, MID MCR Desk Up/Dn Corridor Req by OPS, PNL 2-M-6 Req by OPS, PNL 2-M-6 Req by OPS, PNL 2-M-5 General Area, PNL 2-M-9 Rq by OPS OPS Req, PNL 2-M-1 & 2 -M-2 General Area Req by OPS, PNL 2-M-l Req by OPS, PNI:5I-M-6 General Area OPS Req, PNL l-M-5 & l-M-6 Up/Dn Stairs & Doors Corridor, Doors C51 & C60 General Area General Area 0-FCO-3 IA-20,-23,-176,-177 V-5

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-1, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-R045 0-LGT-247-R046 0-LGT-247-.R047 0-LGT-247-R048 0-LGT-247-R049 0-LGT-247-R050 0-LGT-247-R051 0-LGT-247-R052 0-LGT-247-R053 0-LGT-247-R054 0-LGT-247-R055 0-LGT-247-R056 0-LGT-247-R057 0-LGT-247-R058 0-LGT-247-R059 0-LGT-247-R060 0-LGT-247-R061 0-LGT-247-R062 0-LGT-247-R063 0-LGT-247-R064 0-LGT-247-R065 0-LGT-247-R066 0o-LGT-247-R067 0-LGT-247-R068 DESCRIPTION 732.0, C4/n 734.0, A12/q-r 734.0, Al3s 734.0, A14/q 734.0, A14/r 734.0, A14/t 734.0, A15/u 734.0, A13/s-t 734.0, A12/u 734.0, Al 1/s 734.0, A10/s 734.0, A lI/r 734.0, A8/r 734.0, A8/q 734.0, A5/r 734.0, A6/s 734.0, A5/s 734.0, A3/s 734.0, A3/q 734.0, A2/r 734.0, A2/t 734.0, A2/u 734.0, A3/s-t 734.0, A4/u ILLUMINATED COMPONENTS Corridor, DRS C56 & C39 General Area 6.9kV SD BD lB-B, 2B-B 480V SD BD 2A2-A 480V SD BD 2A1-A 480V SD BD 2B1-B 2-PCV-1-5 Handwheel 480V SD BD 2B2-B General Area 6.9kV SD BD IB-B, 2B-B 6 9kV SD BD 1B-B, 2B-B General Area General Area General Area General Area 6.9kV SD BD lA-A, 2A-A 6.9kV SD BD lA-A, 2A-A 6.9kV SD BD IA-A, 2A-A 480V SD BD 1B2-B 480V SD BD 1BI-B 480V SD BD lAl-A 1-PCV-1-5 Handwheel 480V SD BD 1A2-A General Area, CCS PMP C-S Transfer switch via open door V-6

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-1, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0o-LGT-247-R069 O-LGT-247-R070 O-LGT-247-R071 O-LGT-247-R072 0-LGT-247-R073 0-LGT-247-R074 O-LGT-247-R075 0-LGT-247-R076 0-LGT-247-R077 0-LGT-247-R078 0-LGT-247-R079 O-LGT-247-R080 0-LGT-247-R081 0-LGT-247-R082 0-LGT-247-R083 0-LGT-247-R084 0-LGT-247-R085 0-LGT-247-R086 0-LGT-247-R087 0-LGT-247-R088 O-LGT-247-R089 0-LGT-247-R090 0-LGT-247-R091 0-LGT-247-R092 0-LGT-247-R093 DESCRIPTION 734.0, A5/u-v 734.0, A4/u 734.0, A3/u-v 734.0, A8/u 734.0, Al 1/u-v 734.0, A12/v 734.0, A4/q 734.0, A5/q 734.0, A2/u 734.0, A3/q 734.0, Al 1/q 734.0, A12/q 734.0, A13/u 734.0, A6/q 734.0, A6/r "734.0, A:I0/q 734.0, A1O/r 706.0, T2/k 706.0, T8/k-m 706.0, T8/m 706.0, Stair Cl 706.0, Stair C2 714.0, A12/s 714.0, A8/s 714.0, A5/s ILLUMINATED COMPONENTS General Area General Area General Area General Area General Area General Area VBB Rm I (bkrs & rear of Pnl 4)120V AC Vital Instrument Power Board 1-I (switch)

VBB Rm II (bkrs & rear of Pnl 4)120VAC Vital Instrument Power Boafcqslvltch)

I-PCV-1-30 Handwheel General Area VBB Rm III (bkrs & rear of Pnl 4)120V AC Vital Instrument Power Board 1-III (switch)

VBB Rm IV (bkrs & rear of Pnl 4)120V AC Vital Instrument Power Board 1 -IV (switch) 2-PCV-1-30 Handwheel PNL l-L-11A PNL l-L-11B PNL 2-L-I-A PNL 2-L-11 B General Area General Area Up/Dn Stairwell Up/Dn Stairs & Doors Up/Dn Stairs & Doors General Area FCV-70-193, -194, -197, -198 General Area V-7

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-1, 8 HOUR EMERGENCY LIGHTING UNITS O-LGT-247-R094 714.0, A3Mt 1-VLV-3-827 & -828 V-8

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-i, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-R095 0-LGT-247-R096 0-LGT-247-R097 0-LGT-247-R098 0-LGT-247-R099 0-LGT-247-R100 0-LGT-247-R101 0-LGT-247-R102 0-LGT-247-R103 0-LGT-247-R1 04 0-LGT-247-R105 0-LGT-247-R106 0-LGT-247-R107 0-LGT-247-R108 0-LGT-247-R109 0-LGT-247-R1 10 0-LGT-247-R1 11 0-LGT-247-R1 12 0-LGT-247-R1 13 0-LGT-247-R1 14 0-LGT-247-R1 15 0-LGT-247-RI 16 0-LGT-247-RI 17 0-LGT-247-R1 18 0-LGT-247-R1 19 0-LGT-247-R120 DESCRIPTION 714.0, A5/t 714.0, A12/t 714.0, Stair A13/u 714.0, A13/v 714.0, Al l/v-w 714.0, A8/v 714.0, A7/w 714.0, A5/v-w 714.0, A3/v 714.0, Stair A3/u 706.0, A2/v 706.0, A2/u 714.0, A3/s 714.0, A13/s 706.0, A14/u-v 706.0, A14/u-v 706.0, A14/v 706.0, A2/u 714.0, A5/w 714.0,'AlOt 714.0, A10/s 714.0, A12/w 706.0, T4/m 706.0, T12/m 706.0, C4/n 706.0, C4/p ILLUMINATED COMPONENTS General Area General Area Up/Dn Stairs & Doors 2-VLV-3-835,-834, 2-FCV-3-172,-173 General Area General Area General Area General Area 1-VLV-3-835,-834, 1-FCV-3-172,-173 Up/Dn Stair & Doors 1-LCV-3-175, -174, 1-FCV-1-18 General Area 1-VLV-3-826,-829 2-VLV-3-827,-828 General Area General Area 2-LCV-3-175,-174, 2-FCV-1-18 General Area HSs on JB 3801 1-FCV-67-146, 0-FCV-67-152 0-FCV-67-151, 2-FCV-67-146 HSs on JB 3804 Gen Area, Doors C28 & C29 Gen Area, Doors C34 & C35 Corridor, Doors C30 & C58 Gen Area, Doors C29 & C58 V-9

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-i, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-R121 0-LGT-247-R122 O-LGT-247-R123 0-LGT-247-R124 0-LGT-247-RI25 0-LGT-247-RI26 0-LGT-247-R127 0-LGT-247-R128 0-LGT-247-R129 0-LGT-247-R130 0-LGT-247-R131 O-LGT-247-R132 0-LGT-247-R133 0-LGT-247-R134 0-LGT-247-R135 0-LGT-247-RI36 0-LGT-247-R137 O-LGT-'-247-R138 0-LGT-247-R139 O-LGT-247-R140 0-LGT-247-R141 O-LGT-247-R142 O-LGT-247-RI43 0-LGT-247-R144 DESCRIPTION 706.0, C 10/n 685.0, T5/j 685.0, T6/k 685.0, T8/k 685.0, T9/n 685.0, T12/j 685.0, Stair C2 685.0, C7/n 685.0, Stair Cl 685.0, C9/n 685.0, C5/n 685.0, T2/k 685.0, T8/j-k 690.0, Al/q 690.0, A2/s 690.0, A3/t-u 690.0, A4/s 690.0, A5/s 690.0, ABA 690.0, A10/t 690.0, All/s 690.0, A13/t 690.0, A15/v 690.0, A13/u ILLUMINATED COMPONENTS Door C34 & Gen Area 1-VLV-1-868 Station Air Compressor A & B General Area, 0-33-500, -501 Stairwell 2-VLV-1-868 Up/Dn Stairs & Doors Corridor, Doors C22 & C24 Up/Dn Stairs & Doors General Area General Area Stairs, 685.0 to 706.0 N-S Aisle between J-K General Area General Area, 0-FCV-67-205, -208, 1-FCV-67-162 1-FCV-3 -116A,-116B, Door A62, 1-FCV-67-164, 1-PI-3-117 1-FCV-3-126A,-126B, 1-PI-3-127 Ceneral Area-General Area, 1-FCV-70-153, -156 General Area, 2-FCV-70-153, -156 General Area, 2-PI-3-117 2-FCV-3-126A,-126B, DoorA75 General Area General Area V-IO

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-1, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-R145 0-LGT-247-RI46 0-LGT-247-RI47 0-LGT-247-R148 0-LGT-247-R149 0-LGT-247-R150 0-LGT-247-R151 0-LGT-247-R152 0-LGT-247-R153 6-LGT-247-RI54 0-LGT-247-R155 0-LGT-247-R156 0-LGT-247-RI57 0-LGT-247-RI 58 0-LGT-247-R159 0-LGT-247-RI60 0-LGT-247-RI61 0-LGT-247-RI62 O-LGT-247-R163 O-LGT-247-RI 64 0-LGT-247-R165 0-LGT-247-R166 0-LGT-247-R1 67 0-LGT-247-RI68 DESCRIPTION 690.0, A 13/v 690.0, A12/v-w 690.0, A9/v 690.0, A4/v 690.0, A3/v 690.0, A3/u 690.0, Al/v 690.0, Al l/w 690.0, Al /w 690.0, A12/t 690.0, A5/w 690.0, A5/w 690.0, A4/u 690.0, A12/u 669.0, A4/s 669.0, A6/t 669.0, A12/s 669.0, A14/t 669.0, A13/t 669.0, A13-14/u-v 669.0, A 12/u-v 669.0, A13/t 669.0, Al 1/t-u 669.0, A9/v ILLUMINATED COMPONENTS 2-LCV-62-132,-133, VCT Rm entrance General Area General Area General Area 1-LCV-62-132,-133,VCT Rm entrance General Area General Area 2-FCV-62-63 2-FCV-62-77, 2-FCV-70-85,-143 2-FCV-3-116A, -116B, 2-PI-3-127, 2-FCV-67-217, 219 1-FCV-62-63 1-FCV-62-77, I-FCV-70-85,-143 1-VLV-62-692, -693 2-VLV-62-692, -693 General Area, l-L-1 12A General Area General Area 2-FCV-3-136A,-136B,179A,-179B, 2-PCV-3-183, 2-PI-3-137, -184 General Area, 2-XS-46-57 2-LCV-62-136, Sump Valve Box 2-VLV-62-537, 538, 539, Sump Valve Box 2-VLV-62-526, -527 2-VLV-62-533, -534 General Area V-11

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-I, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-RI69 0-LGT-247-R170 0-LGT-247-R171 0-LGT-247-R172 0-LGT-247-R173 0-LGT-247-R174 0-LGT-247-R175 0-LGT-247-RI76 0-LGT-247-R177 0-LGT-247-R178 0-LGT-247-R179 0-LGT-247-R180 0-LGT-247-R181 0-LGT-247-R182 0-LGT-247-R1 83 0-LGT-247-R184

"*0-LGT-247-R185 0-LGT-247-R186 0-LGT-247-R187 0-LGT-247-R188 0-LGT-247-R189 0-LGT-247-R190 0-LGT-247-R191 0-LGT-247-R192 0-LGT-247-R193 DESCRIPTION 669.0, A4/u-v 669.0, A2-3/s-t 669.0, Al/t 669.0, A2/t-u 669.0, A4/u 669.0, A4/u 669.0, A2/u 669.0, A15/t 669.0, A14/u 669.0, Al 1/s 669.0, A13/u 653.0, A7/u 653.0, A9/u-v 722.0, Stair D1 722.0, 722.0-1 722.0, 722.0-2 722.0, 722.0-9 722.0, 722.0-9 722.0, 722.0-9 722.0, 722.0-7 722.0, 722.0-7 722.0, 722.0-6 722.0,722.0-6 722.0, 722.0-5 722.0, 722.0-5 ILLUMINATED COMPONENTS 1-VLV-62-537, -538,,539, Sump Valve Box 1-LCV-62-135, -136, Sump Valve Box 1.FCV-3-l36A,-136B,-l79A,-l7 9 B, 1-VLV-3-918,-919, 1-FCV-1-51 cntrls, "l-PCV-3-183, 1-PI-3-137,-184 PNL 1-L-381, 1-XS-46-57 1-VLV-62-526,-527 1-VLV-62-533,-534 1-LCV-62-135,-136 PNL 2-L-381 2-FCV-1 -51 Ctrls, 2-VLV-3-918, -919 PNL 2-L-1 12A, General Area 2-LCV-62-135,-136 General Area General Area Up/Dn Stair & Doors General Area General Area General Area General Area General Area Gen Area, PNL 2-L-163 General Area Gen Area, PNL 1-L-163 General Area Gen Area, PNL 2-L-272 General Area V-12

SQN FIRE PROTECTION REPORT PART V - EMERGENCY LIGHTING AND REACTOR COOLANT Rev. 9 PUMP OIL COLLECTION TABLE V-I, 8 HOUR EMERGENCY LIGHTING UNITS COMP. ID 0-LGT-247-R194 0-LGT-247-R195 0-LGT-247-RI96 0-LGT-247-R197 0-LGT-247-R198 0-LGT-247-R199 0-LGT-247-R200 0-LGT-247-R201 0-LGT-247-R202 0-LGT-247-R203 0-LGT-247-R204 0-LGT-247-R205 DESCRIPTION 722.0, 722.0-4 722.0, 722.0-4 740.5, 740.5-1 740.5, 740.5-4 740.5, 740.5-7 740.5,740.5-10 740.5, 740.5-13 732.0, C 10/n 749.0, A2/u 749.0, A2-3/s-t 759.0,.A12/v 714.0, A13/t ILLUMINATED COMPONENTS Gen Area, PNL 1-L-272 General Area General Area 480V BD RM IA 480V BD RM 2A 480V BD RM lB 480V BD RM 2B Corridor, Doors C53 & C55 1A-A Exh Fan Dampers 1A-A Exh Fan Dampers CRDM M-G SetBkrA&B 2-VLV-3-826 & -829 V-13

TVAN FIRE PROTECTION REPORT APPROVAL PAGE SEQUOYAH NUCLEAR PLANT FIRE PROTECTION REPORT Revision No.

10 Effective Date:

11/28/01 Revision Sponsor.

FPU Dan Johnson urganizaron Name Change Approval Action Type of Impacts Action Complete Organization Needed?

Action (see note 1)

(Name/Signature)

Date 1

FPU N/A Change Initiator N/A wa Curator

/vIa Curator via Curator (C D.Pditchard)

(7127101)

SE - M/N Program ws3 Yes El via Curator I/Ha Curator via Curator Owner No

[

(Brenda SImral)

(8/27/01)

SE - EE Program Yes T & I Reviews 2 Yes l

via Curator

/vIa Curator va Curator Owner No 0

(Rebecca Travis)

(8/6/01) 4 OPS Procedures Yes T & I Reviews 2 Yes 0 vfa Curator I/wa Curator va Curator 4

PNo El (Jim Dvorak)

(8/8/01)

OPS Fire 2

Yes El va Curator I/va Curator via Curator Protection YesNo (Dan Johnson)

(8&24i01) 6 OPS FP System Yes T & I Reviews 2 Yes 0 va Curator I/wa Curator via Curator Engineer No

[E (Steve Frazier)

(8/7/01) 7 OPS FP System Note 4 T & I Reviews 2 Yes El N/A N/A N/A Engineer No 0 Yes El 8

N/A Note 3 Impact Review No

[E N/A N/A N/A PORC Chairman eva Curator Afa Curator via Curator 9

Yes Approval N/A (Ed Freeman)

(9/15101)

(Meeting #6027)

5_Curator aCurator 10 Plant Manager Yevprvai/

a Curator

/ via Curator via Curator 10 es AproalN/

(Dennis Koehl)

(9125101)

Record any impacts of the FPR change on form FPDP-3-2, TVAN FPR Revision Impacts Technical review of the FPR change and also impact review if change is outside the design change process.

Additional impact reviews - as determined needed by sponsor or technical reviewers. N/A rows not needed If more than one system/system engineer is affected by the change TVA 40706 [07-2001]

1.

2.

3 4.

F Page I of I FPDP-3-1 [07-25-2001]

SQN FIRE PROTECTION REPORT Rev. 10 TABLE OF CONTENTS Page i Page Rev.

REVISION LOG i

10 TABLE OF CONTENTS i

10 PART I - INTRODUCTION I-1 1.0

Background

I-1 2.0 Purpose M-1 3.0 Scope I-1 4.0 References-Appendix A Program 1-4 5.0 References-Appendix R Prog-am 1-7 6.0 References-Fire Protection Improvement Program (FPIP)

I-11 PART II - FIRE PROTECTION PLAN IH-1 10

1.0 Purpose and Scope

11-1 2.0 Objectives of the Fire Protection Plan II-1 3.0 Basis of the Fire Protection Plan II-1 4.0 References 11-2 5.0 Definitions 11-5 "6.0 Fire Protection Quality Assurance 11-13 7.0 Fire Protection Organization/Programs 11-14 8.0 Fire Protection Program Administrative 11-18 and Technical Controls 9.0 Emergency Respcnse 11-20 10.0 Control of Combustibles 11-24 11.0 Control of Ignition Sources 11-25 12.0 Description of Fire Protection Systems and Features 11-26

SQN FIRE PROTECTION REPORT Rev. 10 TABLE OF CONTENTS Page ii PART II - FIRE PROTECTION PLAN(Continued)

Page Rev.

13.0 Fire Protection System Impairments and Compensatory Actions 11-36 14.0 Fire Protection Systems and Features, Operating Requirements 11-39 (OR's) and Surveillance Requirements (SR's)

PART III - SAFE SHUTDOWN CAPABILITIES II-1 9

1.0 Introduction 1-1 2.0 Safe Shutdown Functions 111-2 3.0 Analysis of Safe Shutdown Systems 11I-3 4.0 Safe Shutdown Systems 111-8 5.0 Identification of Safe Shutdown System Components 111-17 6.0 Identification of Safe Shutdown Circuits and Cables II-18 7.0 Associated Circuits of Concern 111-18 8.0 High/Low Pressure Boundary Interfaces 111-22 9.0 Location of Safe Shutdown Equipment, Cables 111-23 and Raceways 10.0 Safe Shutdown System Separation Evaluation Methodology 111-23 11:0 References 111-24 PART IV - ALTERNATE SHUTDOWN CAPABILITY IV-1 1.0 Introduction IV-1 2.0 Discussion IV-1 3.0

,Alternate Control Room Capabilities IV-1 4.0 References IV-4

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS PART V - EMERGENCY LIGHTING AND REACTOR COOLANT PUMP OIL COLLECTION 1.0 Introduction 2.0 Emergency Lighting 3.0 Reactor Coolant Pump Oil Collection 4.0 References PART VI - NFPA CODE EVALUATION 1.0 Introduction 2.0 Scope 3.0 Applicable NFPA Codes PART VII - DEVIATIONS AND EVALUATIONS 1.0 Introduction 2.0 Deviations to 10CFR50 Appendix R 3.0 SQN 86-10 Evaluations for IOCFR50 Appendix R 4.0 Deviations to BTP 9.5-1 Appendix A 5.0 NFPA Code Deviations - Sprinkler System Criteria for Resolving Intervening Combustible Concerns PART VIII - CONFORMANCE TO APPENDIX A TO BTP 9.5-1 GUIDELINES PART IX - APPENDIX R COMPLIANCE MATRIX PART X - FIRE HAZARDS ANALYSIS Rev. 10 Page iii Rev.

9 Page V-1 V-1 V-1 V-2 V-3 VI-1 VI-1 VI-1 VI-2 VII-1 VII-1 VII-1 VII-39 VII-91 VII-99 VII-105 VIII-1

'IX-1 X-1 10 5

4 1

I I

SQN FIRE PROTECTION REPORT Rev. 10 TABLE OF CONTENTS Page iv LIST OF TABLES PART II - FIRE PROTECTION PLAN Table 5.1 Operational Modes 11-12 Table 3.3-11 Minimum Fire Detector Instruments Operable 11-43 Table 3.7-5 Fire Hose Stations II-57 PART III-SAFE SHUTDOWN CAPABILITIES Table III-1 Safe Shutdown Systems and Subsystems by Key III-26 Table 111-2 Shutdown Logic Component List III-27 Table 111-3 Instrumentation List For Main Contrd Room 111-58 PART V - EMERGENCY LIGHTING AND REACTOR COOLANT PUMP OIL COLLECTION Table V-I 8-Hour Emergency Lighting Units V-4 PART VII - DEVIATIONS AND EVALUATIONS Table 2.0-1 Process Control Requirements for Validating VII-33

• Appendix R Deviation Bases Table 2.2-1 Control Building Rooms Containing Redundant Safe VII-34 Shutdown Equipment, without Fire Detection and/or Automatic Suppression Table 2.12-1 Auxiliary Building Rooms Containing Redundant Safe VII-35 Shutdown Equipment, without Fire Detection and/or Automatic Suppression Table 2.12-2 Auxiliary Building Rooms Containing Redundant Safe VII-38 Shutdown Equipment, with only Partial Fire Detection and/or Automatic Suppression Table VII-1 Auxiliary Building Special Purpose Doors VII-107 Table VII-2 Main Control Room Bullet Resistant Security Doors VII-108

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS Added Auxiliary Building Fire Rated Doors Alarmed Security Doors Certified Fire Dampers Equivalent Fire Dampers Certification/Equivalent Construction Features Added Fire Dampers in HVAC Ducts Rev. 10 Page v Table VII-3 Table VII-4 Table VII-5 Table VII-6 Table VII-7 Table VII-8 VII-108 VII-109 VII-1 10 VII-112 VII-1 13 VII-1 14 m

I

SQN FIRE PROTECTION REPORT Rev. 10 TABLE OF CONTENTS Page vi LIST OF FIGURES PART II - FIRE PROTECTION PLAN (All drawings will be current active version)

Figure 11-1 1,2-47W850-1 Flow Diagram Fire Protection Figure 11-2 1,2-47W850-2 Flow Diagram Fire Protection Figure 11-3 1,2-47W850-3 Flow Diagram Fire Protection Figure 11-4 1,2-47W850-4 Flow Diagram Transformer Fire Protecalh System Figure H1-5 1,2-47W850-5 Flow Diagram Transformer, Yard & MWTP HPFP Figure 11-6 1,2-47W850-6 Flow Diagram Fire Protection Figure 11-7 1,2-47W850-7 Flow Diagram Fire Protection Figure 11-8 1,2-47W850-8 Flow Diagram Fire Protection Figure 11-9 1,2-47W850-9 Flow Diagram Fire Protection Figure II-10 1,2-47W850-10 Flow Diagram Fire Protection Figure I-11 1,2-47W850-11 Flow Diagram Fire Protection Figure 11-12 1,2-47W850-12 Flow Diagram Fire Protection Figure 11-13 1,247W850-20 Flow Diagram Fire Protection Figure II-14a 1,2-47W850-24 Flow Diagram Fire Protection Figure II-14b 1,247W850-'26 Flow Diagram Fire Protection Figure II-14c 1,2-47W850-27 Flow Diagram Fire Protection Figure 11-15 1,2-47W843-1 Flow Diagram CQ Storage, Fire Protection and Purging System Figure 11-16 1,2-47W843-2 Flow Diagram CQ Storage and Fire Protection Figure 11-17 1,2-47W610-26-1 Mechanical Control Diagram High Pressure Fire Protection System

,Figure 11-18 1,247W610-26-2 Mechanical ControDiagram High Pressure Fire Protection System Figure 11-19 1,247W611-26-1 Mechanical Logic Diagram High Pressure Fire Protection Figure 11-20 1,2-47W611-26-2 Mechanical Logic Diagram High Pressure Fire Protection

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS LIST OF FIGURES PART II - FIRE PROTECTION PLAN (Continued)

Figure 11-21 1,2-47W610-39-1 Figure 11-22 Figure 11-23 Figure 11-24 Figure 11-25 Figure 11-26 Figure 11-27 Figure 11-28 Figure II-29 Figure 11-30 Figure 11-31 Figure 11-32 Figure 11-33 Figure 11-34 Figure 11-35 Figure 11-36 Figure 11-37 Figure 11-38 Figure 11-39 Figure 11-40 1,2-47W610-39-2 1,2-47W611-39-1 1,2-47W611-39-2 1,2-47W611-13-1 1,2-47W611-13-2 1,2-47W611-13-3 1,2-47W611-13-4 1,2-47W611-13-5 1,2-47W611-13-6 1,2-47W611-13-7 1,2-47W600-245 1,2-47W600-246 1,2-47W600-247 1,2-47W600-248 1,2-47W600-249 1,2-47W600-250 1,2-47W600-251 1,2-47W600-252 1,2-47W600-253 Rev. 10 Page vii Mechanical Control Diagram C02 Storage Fire Protection and Purging System Mechanical Control Diagram C02 Storage Fire Protection and Purging System Logic Diagram C02 Storage, Fire Protection Purging System Logic Diagram C02 Storage, Fire Protection and Purging System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instuments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls I

SQN FIRE PROTECTION REPORT TABLE OF CONTENTS LIST OF FIGURES PART II - FIRE PROTECTION PLAN (Continued)

Figure 11-41 1,2-47W600-254 Mechanical Instrume Figure 11-42 1,2-47W600-255 Mechanical Instrunme Figure 1143 1,2-47W600-256 Mechanical Instrunme Figure 11-44 1,2-47W600-257 Mechanical Instrume Figure 11-45 1,2-47W600-258 Mechanical Instrume Figure H-46 1,2-47W600-259 Mechanical Instrume Figure 11-47 1,247W600-260 Mechanical Instrume Figure 1148 1,2-47W600-270 Mechanical Instrume PART mI - SAFE SHUTDOWN CAPABILITIES Figure III-1 Appendix R Safe Shutdown Logic Diagram PART X - FIRE HAZARDS ANALYSIS Figure X-1 1,2-47W494-1 Auxiliary Building Compartmentation EL 653 & 669 Figure X-2 1,2-47W494-2 Auxiliary Building and Reactor Building Compartmentation EL 685 & 690 Figure X-3 1,2-47W494-3 Auxiliary Building Compartmentation EL 706 & 714 Figure X-4 1,2-47W494-4 Auxiliary Building Compartmentation EL 732 & 734 Figure X-5 1,2-47W494-5 Auxiliary Building Compartmentation EL 749, 759, & 763 Figure X-6 1,2-47W494-6 Control Building Compartmentation EL 669 & 685 Figure X-7 1,2-47W494-7 Control Building Ompartmentation EL 706 & 732 Figure X-8 1,247W494-8 Diesel Generator Building Compartmentation EL 722 & 740.5 Figure X-9 1,247W494-9 ERCW Pumping Station Compartmentation EL 625 & 688 Figure X-10 1,2-47W494-10 ERCW Pumping Station Compartmentation EL 704 & 720 Rev. 10 Page viii rots and Controls nts and Controls nts and Controls

nts and Controls

• nts and Controls

nts and Controls

nts and Controls nts and Controls I

SQN FIRE PROTECTION REPORT Rev. 10 REVISION LOG II Revision DESCRIPTION OF REVISION Date No.

Approved 0

Initial Issue 8/23/96 Revision 1 to the Fire Protection Report (FPR) is a complete revision of the 11/19/98 document. The previously issued change packages (FPR-01-1 thru -13) have all been incorporated and interfiled with this revision. These change packages have been approved by PORC independently. Besides minor editorial changes (e.g.,

correction of typographical errors, clarification of wording, etc.), the only new change to the FPR is to Part II, Section 14, in which the surveillance requirements (SR) for hose station inspections and valve position verification of valves in the Reactor Buildings have been revised. Also, a new SR has been added for valve actuation of hose station standpipe valves.

All significant changes made by Revision 1 (e.g., change package revisions, the above mentioned surveillance requirements, etc.) are designated by revision bars.

2 Revision 2 to the FPR is to incorporate Fire Detection Zones 547 and 548 into 12/17/98 Part II, Table 3.3-11. These zones are being added by DCN M-14226-A, which is installing automatic fire suppression and detection into the general area of Elevation 690.0, above the Boric Acid Tanks.

Pages Changed: Coversheet, i, ii, iii, 11-48 Pages Added: 11-67 Pages Deleted: None Note: Sections with page(s) affected by this change are being included in their entirety and issued with this change package. Therefore, the entire sections will be issued as Rev. 2, with the specific changes denoted by revision bars.

i I

I

SQN FIRE PROTECTION REPORT Rev. 10 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

Approved 3

Revision 3 to the FPR affects Part VII and Part II, Sections 5.0 and 14.0. For 2/11/99 continuity and consistency in pagination, the sections are being issued in their entirety as Rev. 3, with the actual changes denoted by revision bars.

The changes to Part Vii of the FPR were made as part of the corrective action plan for resolution of CAQ SQ962075PER. The PER was originally initiated due to a discrepancy between actual plant configuration and the justification for an NRC approved deviation to 1 OCFR50 Appendix R. The changes made in Rev. 3 of the FPR include resolution of documentation discrepancies involving combustible loading values, updates of cable rerouting, raceway barrier installations, procedure changes, etc. -The nature of the discrepancies were all documentation only, and did not represent any unanalyzed configurations in the plant. Also, minor changes to existing evaluations in Part VII were done as enhancements.

Changes to Part II of the FPR included the addition of the defirition of "in-situ Combustible Loading," and the allowance for exceeding the compensatory measure time requirements, as specified by the Fire Operating Requirements (FORs), for fire suppression/detection equipment and fire barriers taken out of service during outages. The compensatory measures (i.e., backup fire suppression and/or fire watches) will remain in place until the equipment is placed back in service after the necessary outage-related work is completed.

4 Revision 4 to the FPR is in support of DCN D-20152. The change to the FPR involves deleting the discussion on the smoke detection in the ventilation intake ducts in the Main Control Room from Part VIII, pages 53 and 54. The DCN abandons the detectors in place, and disconnects the annunciation circuits to the MCR.

Pages Changed: Coversheet, i, ii, iii, v, VIII-53, VIII-54 Pages Added: None Pages Deleted: None Note: Section VIII is being included in its entirety in the R4 change package, with the specific changes denoted by revision bars.

ii I

I

SQN FIRE PROTECTION REPORT Rev. 10 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

Approved 4

Minor format change to support electronic filing (Curator) conversion.

8/19/99 5

Revision 5 to the Fire Protection Report (FPR) was performed to incorporate the following changes:

Added Part II, Section 14.7 to incorporate new Fire Operating Requirement (FOR) 3.7.14 and Surveillance Requirement (SR) 4.7.14 for Emergency Battery Lighting (EBL) units, including compensatory actions and testing frequencies. Also revised Part V "Emergency Lighting and Reactor Coolant Pump Oil Collection" to address new FOR and SR; Revised Part II, Section 14.5 (FOR/SR 3/4.7.11.4) for Fire Hose Stations to allow use of portable hose packs and removal of fire hoses from the hose stations inside the Reactor Buildings; Clarified definitions for continuous and roving fire watchesin Part II, Section 13.0; Clarified compliance with NFPA-72D regarding exception to G-73 for bypassing the audible annunciation system in the Main Control Room (MCR),

Panel 0-M-29, under the direct supervision of a dedicated operator at the console.

Revised Section 3.31 of Part VII to replace summary of superseded calculation MDQ0026-980017, "Fire Barrier Rating Evaluati6n for Hollow Block and Partially Filled 8" Concrete Block Walls" with calculation SCG1S591, "Fire Ratings of Hollow Core Masonry Walls."

Corrected minor documentation discrepancy in Part II, Table 3.3-11, in which the number of ionization fire detectors for Zone 230 was listed as 9, instead of the correct number of 10 detectors in the zone.

Revised Part II, Secflon 14.0 to reference Calculation SQN-SQS2-203, which addresses processes for restoring inoperable Appendix R equipment that is not currently bounded by existing Tech Specs to operable status.

Minor administrative change to Revision 4 Rev Log description to delete statement regarding MCR HVAC duct smoke detector abandonment in response to a recommendation from QA audit SSA0001. The recommendation was to remove the statement, "The duct detectors have been determined unnecessary based on the absence of industry in the vicinity that could be capable of producing significant enough smoke to affect the habitability in the MCR, and the detectors in the El. 732.0' Mechanical Equipment Room which will detect smoke entering the MCR ventilation system intake and subsequently alarm in the MCR," because it provided unnecessary detail that was not discussed in the FPR.

iii==

I I

SQN FIRE PROTECTION REPORT Rev. 10 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

Approved Changed required testing frequency for inaccessible detectors from "each COLD 6

SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 month" to 10/18/00 every 18 months during cold shutdowns (page 11-42). Related editorial changes to this page, FPR cover sheet, and the table of contents.

Changed the compensatory actions for LCO 3.3.3.8 to delete fire watches and 7

temperature monitoring inside primary containment upon failure of a detector 1/29/01 inside primary containment (page 11-42). The bases for the LCO compensatory (effective actions for inoperable detectors inside primary containment were also changed.

2/1/01)

(pages 11-65 and 66).

This revision incorporates the following changes to part I1:

8 Changes the testing frequency for detectors which require removing plant 2/26/01 equipment from service from 6 to 18 months and deletes the requirement to perform the 18 month detector tests during cold shutdowns from Surveillance Requirement 4.3.3.8.1 on page 11-42.

Adds a fire detection basis on page 11-66 for the above change in test frequency which gives examples of the equipment which must be removed from service for detector testing (EGTS, ABGTS, CREVS and containment purge). They two above changes are corrective action for PER-00-006637 000.

"* Adds a definition for"accessible" on page 11-5.

"* Adds an existing heat detector to zone 466 in Table 3.3-11 on page 11-49.

"* Adds a end-of-quarter "grace period" to the annual fire brigade medical examination requirement on page 11-20.

"* Deletes three references to raw service water flow diagrams and adds five references to fire protection flow diagrams on page 11-73 (added diagrams are for the fire pumps/tanks, yard piping, the ERCW Bldg. and two cable tray water spray systems).

Related editorial changes were made to this Rev. Log, the FPR coveirsheet, and the table of contents.

This revision incorporates the following changes to the FPR Parts III and V, due 9

to the Vital Inverter System modification per DCN D20071A/P20872A as 10/12/2001 applicable:

"* Added references to DCN D20071A/P20872A, see section 11.2.13 of Part III and section 4.1.5 of Part V.

"* Revised the description of the 126VAC Vital Instrument and 250Vdc Power System, see section 4.10.3 and 4.10.5 respectively, of Part Ill.

"* Added Components to the illuminated list of Part V, see Table V-I, pages V 4 and V-7.

Related editorial changes were made to this revision log, the FPR cover sheet and the table of contents.

The Nuclear Safety Assessment for the above changes is in the "Fire protection (Appendix R)" section of Block 15 in DCN D20071A iv I

I

SQN FIRE PROTECTION REPORT Rev. 10 REVISION LOG Revision DESCRIPTION OF REVISION Date No.

I Approved 10 Changed Part II, Section 14.1 (page 11-42) as follows:

9/25/01 Extended the frequency for fire detector testing required by Surveillance (effective Requirement (SR) 4.3.3.8.1 from 6 to 12 months.

11/28/01)

Added a requirement to test required fire detection zones each 6 months to existing SR 4.3.3.8.3.

Changed SR 4.3.3.8.2 by limiting supervision testing to the wiring between required local alarm panels and the alarm receiving console. The previously required testing of zone supervision was deleted.

Changed LCO action 3.3.3.8c by providing actions to take in the event the supervision tested via revised SR 4.3.3.8.2 fails or a loop failure trouble is annunciated. Previously, this action required a corrective action/reportability review if inoperable detectors are not restored to operation within 14 days.

This action is no longer needed since it is already included in actions 3.3.3.8a and b.

Changed LCO action 3.3.3.8b to make it explicit that it is the loss of automatic suppression system actuation which requires implementation of the action.

Changed Part II, fire detection bases (page 11-66), by adding bases for the fire suppression system actuation testing, the new zone testing and for the revised supervision testing. The later includes a discussion of the application of the LCO actions in the event of a supervision test failure or a failure of the circuits between required panels and the alarm receiving console.

Changed Part VI as follows:

Section 1.0 (page VI-1)- added a requirement that future significant deviations from NFPA testing, inspection, maintenance and testing requirements will be addressed in Part VI.

Section'3.3.11 (page VI-13)- added a detector testing deviation (12 vs. 6

" month frequency).

Related editorial changes were made to this Revision Log, the Cover Sheet, and the Table of Contents.

V I

I

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 1.0 PURPOSE AND SCOPE Part II of the Sequoyah Nuclear Plant (SQN) Fire Protection Report describes the Fire Protection Plan (Plan) developed for SQN to ensure compliance with the requirements of 10 CFR 50.48 paragraphs (a) and (e),

10 CFR 50, Appendix R, Sections III.G, J, L, and 0 and the guidelines of Appendix A to Branch Technical Position (BTP) APCSB 9.5-1.

The Plan is applicable to Unit 1, Unit 2, and common areas needed for safe operation of SQN. Part II provides drawings for information only to more fully describe the Fire Protection Systems available.

Compartmentation drawings are provided for information in Part X.

The latest drawings and associated change paper should be obtained when necessary. Fire protection features are described in the fire hazards analysis (refer to Part X).

2.0 OBJECTIVES OF THE FIRE PROTECTION PLAN The Plan describes the controls associated with the SQN Fire Protection Program (FPP); identifies the organizations and positions that are responsible for the FPP; describes the authority of positions responsible for implementing the FPP; and outlines the plans for fire protection, fire detection and suppression capability, and limitation of fire damage. The Plan describes the features necessary to implement the FPP such as: administrative controls; personnel requirements for fire prevention and manual fire suppression activities; automatic and manually operated fire detection and suppression systems; and the means to limit fire damage to structures, systems, and components important to safety so that the capability to safely shutdown the plant is ensured.

The Plan describes the measures that are established at SQN to extend the concept of defense-in-depth to fire protection in areas important to safety. These measures are established:

to prevent fires from starting, to rapidly detect, control, and promptly extinguish those fires that do occur, and to provide protection for systems important to safety so that a fire that is not promptly extinguished by the fire suppression activities will not prevent the safe shutdown of the plant.

3.0 BASIS OF THE FIRE PROTECTION PLAN The Plan at SQN has been developed to comply with and is based upon the requirements of General Design Criterion 3 in Appendix A to 10 CFR 50, 10 CFR 50.48, paragraphs (a) and (e), and TVA's commitment to implement Sections Ill.G, III.J, and 111.O to 10 CFR 50, Appendix R and Appendix A to Branch Technical Position APCSB 9.5-1, "Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976" (August 23, 1976). The requirements contained in Section III.L of Appendix R to 10 CFR 50 are also applicable to areas where alternate shutdown capability is selected. This Plan establishes the policy for and describes the manner in which TVA conforms with these requirements and the guidelines which have been promulgated to describe acceptable implementation methods. The applicable guidelines used as the basis for the Plan are listed in Section 4.1, Regulatory Documents.

11-1

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10

4.0 REFERENCES

4.1 Regulatory Documents 4.1.1 Branch Technical Position (Auxiliary Power and Control Systems Branch) 9.5-1, Appendix A 4.1.2 10 CFR 50.48 - Fire Protection 4.1.3 10 CFR 50, Appendix A, Criterion 3 - "Fire Protection" 4.1.4 10 CFR 50 Appendix R - Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 4.1.5 NRC letter dated August 29, 1977 -Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance 4.1.6 Generic Letter 81 Fire Protection Rule and NRC Memorandum of Clarification for Genenic Letter 81-12, dated March 22, 1982 4.1.7 Generic Letter 82 Technical Specifications for Fire Protection Audits 4.1.8 Generic Letter 83-33 -NRC Positions on Certain Requirements of Appendix R to 10 CFR 50.

4.1.9 Generic Letter 86 Implementation of Fire Protection Requirements 4.1.10 Generic Letter 86 Supplement 1 - Fire Endurance Acceptance Criteria for Fire Barrier Systems Used to Separate Redundant Safe Shutdown Trains within the Same Fire Area 4.1.11 Generic Letter 88 Removal of Fire Protection Requirements from Technical Specifications 4.1.12 Generic Letter 91 Information to Licensees regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability.

4.1.13 NUREG-0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors, Revision 4 (referred to as standard Technical Specifications).

4.1.14 USNRC Regulatory Guide 1.75, "Physical Independence of Electric Systems" 4.2 TVA Documents 4.2.1 SQN Engineering Design Criteria, Drawings, Appendix R Key Calculations 4.2.2 NP-STD-12.15, 'Tire Protection" 4.2.3 NP-STD-3.2, "Augmented Quality Assurance" 11-2

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 4.2.4 TVA-NQA-PLN89-A, "Nuclear Quality Assurance Plan" 4.2.5 General Engineering Specification G-73, 'Installation, Modification, and Maintenance of Fire Protection Systems and Features" 4.2.6 General Engineering Specification G-96, "Installation, Modification, and Maintenance of Penetration Seals" 4.2.7 General Engineering Specification G-98, 'Installation, Modification, and Maintenance of Electrical Raceway Fire Barrier Systems" 4.2.8 Mechanical Design Standard DS-M17.2.2, "Electrical Raceway Fire Barrier Systems" 4.2.9 System Description Document N2-302-400, 'Penetration Seals" (formerly Engineering Report No. 0006-00902-0 1, "Penetration Seal Program Assessment Report").

4.2.10 TVA Calculation SQN-SQS2-203, 'Evaluation of Fire Safe Shutdown Equipment for IE Notice 97-048."

4.3 Other Documents 4.3.1 ASTM E84 - Test for Surface Burning Characteristics of Building Materials 4.3.2 ASTM El19 - Fire Tests of Building Construction and Materials 4.3.3 ASTM E814 - Standard Test Method for Fire Tests of Through-Penetration Fire Stops 4.3.4 Fire Protection Handbook, 14" Edition, National Fire Protection Association.

4.3.5 Fire Protection Handbook, 17h Edition, National Fire Protection Association:

4.3.6 Report of the Test of Internal Conduit Seals 4.3.7 Conduit Fire Protection Research Program (Wisconsin Test Report), 5/18/87 4.4 NFPA Codes and Standards NOTE:

Part VI of this Fire Protection Report documents the level of compliance with the NFPA codes and standards identified in Section 4.4. Other codes and standards referenced in Appendix A to BTP 9.5-1 are also addressed in Part VI. Deviations from code criteria that impact operational capability of the systems are documented in Part VII of the FPRt 4.4.1 NFPA 10-1975, "Portable Fire Extinguishers" 4.4.2 NFPA 12-1973, "Carbon Dioxide Extinguishing Systems" 4.4.3 NFPA 13-1975, "Installation of Sprinkler Systems" 11-3

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 4.4.4 NFPA 14-1974, "Standpipe and Hose Systems" 4.4.5 NFPA 15-1973, "Water Spray Fixed Systems for Fire Protection" 4.4.6 NFPA 20-1973, "Centrifugal Fire Pumps" for electric driven fire/flood mode pumps 4.4.7 NFPA 20-1993, "Centrifugal Fire Pumps", for dedicated UL/FM electric motor driven and diesel engine driven pumps.

4.4.8 NFPA 24-1973, "Outside Protection" 4.4.9 NFPA 30-1973, "Flammable and Combustible Liquids" 4.4.10 NFPA 72D-1975, "Proprietary Protective Signaling Systems" 4.4.11 NFPA 72E-1974, Automatic Fire Detectors" 4.4.12 NFPA 80-1981, "Fire Doors and Windows" 4.4.13 NFPA 90A-1975, "Air Conditioning and Ventilating Systems" 4.4.14 NFPA 194-1974, AFire Hose Connections" 4.4.15 NFPA 196-1974, AFire Hose" 4.4.16 NFPA 220-1985, "Types of Building Construction" 4.4.17 NFPA 251-1985, "Fire Tests of Building Materials" 11-4

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 5.0 DEFINITIONS Accessible - Equipment not located in an inaccessible area (see definition).

Action - ACTION shall be the part of a Specification which prescribes remedial measures required under designated conditions (FPR Preparer)

Approved -Tested and accepted for a specific purpose or application by a nationally recognized testing laboratory or acceptable to the authority having jurisdiction.

(FPR Preparer)

Authority Having Jurisdiction (AHJ) -The organization, office, or individual responsible for "approving" equipment, an installation, or a procedure. (For TVA nuclear power facilities, the Corporate Engineering Chief Engineer is the AHJ per NP STD 12.15 and serves as the central point of contact with other organizations) (NRC, Insurance Carrier). (G-73)

Automatic - Self-acting, operated by its own mechanism when actuated by some impersonal influence such as a change in current, pressure, temperature or mechanical configuration. (G-73)

Barrier -A feature of construction provided to separate or enclose various occupancies to create a boundary limit based on functional requirements, or a flexible material designed to withstand the penetration of water, vapor, grease, or harmful gases. (G-96)

Channel Functional Test - A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILIY including alarm and/or trip functions.

b. Bi-stable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

c.

Digital channels - the injection of a simulated signal into the channel as close to the sensor input to the process racks as practicable to verify OPERABILITY including alarm and/or trip functions. (FPR Prepareir)

Combustible Material - Material which does not meet the definition of noncombustible.- Any material which in the form in which it is used and under the conditions anticipated will ignite and bum (e.g., cable insulation, lube oil, plastic sheeting, charcoal, paper, etc.) (G-73)

Combustible Liquid - A liquid having a flash point at or above 100 TF (37.8 'C). (G-73)

Electrical RacewaU Fire Barrier System (ERFBS)- A special type of Fire Barrier System designed to protect electrical raceways (e.g., conduits, cable trays, junction boxes, etc.) containing FSSD circuits required for Appendix R safe shutdown. (DS-M17.2.2)

Engineering - The organization responsible for the design basis of the plant. (G-73)

Fire Area (FA) - That portion of a building or plant that is separated from other areas by boundary fire barriers. (G-73) These FAs are defined on the compartmentation drawings and supported by the Fire Hazards Analysis. One room or several rooms may constitute a single fire area. A fire area may be further subdivided by additional barriers. (FPR Preparer) 11-5

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 Note:

For the purposes of fire watch compensatory actions, fire Areas have 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire barriers.

Fire areas are further subdivided into 1.0- or 1.5-hour fire area and/or zones. These 1.0- or 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> compartments are analogous to the fire zones in earlier definitions and the Basis for Technical Specification 3.7.12. (FPR Preparer)

Fire Barrier - Those components of construction walls, floors, ceilings, and their supports including beams, joists, columns, penetration seals or closures, fire doors, and fire dampers that are rated by approving laboratories in hours of resistance to fire and are used to prevent the spread of fire. (G-73)

ERFBS and radiant energy shields are also considered as fire barriers. Fire barriers that are not rated may be used when approved in accordance with a NRC Generic Letter 86-10 evaluation or equivalent.

This definition does not include those barriers installed for RG 1.75 for less than 3' horizontal or 5' vertical separation of redundant cable trays. (FPR Preparer)

Fire Damper -A device, installed in the air distribution system, designed to close upon detection of heat or release as the result of a signal from a sensing device such as a CO 2 discharge signal or a smoke detector, to interrupt migratory air flow, and to restrict the passage of flame. A combination fire and smoke damper shall meet the requirements of both. (G-73)

Fire Detector - A device designed to automatically detect the presence'of fire and initiate an alarm system and other appropriate action (see NFPA 72E, "Automatic Fire Detectors"). (G-73)

Fire Door - The door component of a fire door assembly. (G-73)

Fire Door Assembly - Any combination of a fire door, frame, hardware, and other accessories, that together provide a specific degree of fire protection to the opening. (G-73)

Fire Hazards Analysis (FHA) - An analysis performed by fire protection and systems engineers to consider potential in situ and transient fire hazards; determine the consequences of fire in any location in the plant on the ability to safely shutdown the reactor or on the ability to minimize and control the release of radioactivity to the environment and specify measures for fire prevention, fire detection, fire suppression and fire containment and alternative shutdown capabilities as required for each fire area containing structures, systems and components important to safety that are in conformance with NRC guidelines and regulations. The FHA demonstrates that the plant will maintain the ability to perform safe

• shutdown functions and minimize radioactive release to the environment in the event of i fire, and shbuld verify that NRC FPP guidelines or equivalent level of protection have been met. (G-73)

Fire Loading - The amount of combustibles present in a given situation, expressed in BTUs per square foot. (G-73)

Fire Rated Assembly - A passive fire protection feature that ig used to separate redundant fire safe shutdown capabilities. A fire rated assembly includes fire rated walls, floors, ceilings, ERFBSs, equipment hatches, stairwells, doors, dampers, and penetration seals. (FPR Preparer)

Fire Rated Penetration Seal - An opening in a fire barrier for the passage of pipe, cable, etc., which has been sealed so as not to reduce the integrity of the fire barrier.

(DS-M17.2.2)

H1-6

SQN FIRE PROTECTION REPORT PART 1I - FIRE PROTECTION PLAN Rev. 10 Fire Resistance Rating - The time that materials or assemblies have withstood a fire exposure in accordance with the test procedures of NFPA 251, Standard Methods of Fire Tests ofBuilding Construction and Materials. (G-73)

Fire Safe Shutdown (FSSD) Equipment - Structures, systems, or components required to shutdown the reactor and maintain it in a safe shutdown condition in the event of a fire. Structures, systems, and components used to satisfy fire safe shutdown requirement commitments do not have to be safety-related.

(FPR Preparer)

Fire Severity - A unit of measure, in terms of time (hours or minutes) that is used to quantify the hazards associated with the fire loading in a given plant area. It is based on an approximate relationship between fire loading and exposure to a fire severity equivalent to the standard time-temperature curve, as defined by ASTM E-1 19. The fire loading of ordinary combustibles such as wood, paper, and similar materials with a heat of combustion of 7000 to 8000 Btu per lb. is related to hourly fire severity. It should not be used with combustibles having a high heat-release rate. The following Fire Severity Index is used to qualify the hazards associated with the combustible loading and was developed based on information from Section 6 / Chapter 6, 17 edition of the Fire Protection Handbook. (FPR Preparer)

FIRE SEVERITY COMBUSTIBLE EQUIVALENT INDEX LOADING FIRE SEVERITY Insignificant

< 6,500 BTU/sq. ft.

< 5 minutes Low

< 80,000 BTU/sq. ft.

< 60 minutes Moderate

< 160, 000 BTU/sq. ft.

< 120 minutes Moderately Severe

< 240,000 BTU/sq. ft

< 180 minutes Severe

> 240,000 BTU/sq. ft.

> 180 minutes Fire Suppression - Control and extinguishing of fires. Manual fire suppression is the use of hoses, portable extinguishers, or manually-actuated fixed systems by plant personnel. Automatic fire suppression is the use of automatically actuated fixed systems such as water, Halon, or carbon dioxide systems. (G-73)

Fire Wall - A wall having adequate fire resistance and structural stability under fire conditions to accomplish the purpose of subdividing buildings to restrict the spread of fire. (DS-M.17.2.2)

Fire Watch -A fire watch is a compensatory action used when fire protection systems or features are inoperable or impaired as required by Operating Requirements (ORs). Additionally, fire watches may be utilized for compensatory actions when limits are exceeded in administrative controls for areas (e.g.,

excessive transient fire loads).

(FPR Preparer)

Fire Watch-Hourly - Hourly fire watch patrols require that a trained individual be in the specified area at intervals of 60 minutes with a margin of 15 minutes. (FPR Preparer)

Fire Watch-Continuous - A continuous fire watch requires that a trained individual be in the specified area at all times, that the specified area contain no impediment to restrict the movements of the continuous fire watch, and that each compartment within the specified area is patrolled at least once every 15 minutes with a margin of 5 minutes. A specified area for a continuous fire watch is one or more fire 11-7

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 zones within a single fire area, which are easily accessible to each other and can be patrolled within 15 minutes. Easy access is defined as: no locked doors or inoperable card reader, no C-Zone entry required, or no hazards that will interfere with the continuous fire watch activity being performed within the 15 minute period. (FPR Preparer)

Fire (Protection) Water Distribution System - The piping and appurtenances on TVA property between a source of fire protection water and the base of the riser (flange of flange and spigot piece or base tee) for automatic sprinkler systems, fixed water spray systems, standpipe systems, and other water based fire suppression systems. (G-73)

Flammable Liquid -A liquid having a flash point below 1 00T1 and having a vapor pressure not exceeding 40 lbs/in2 (absolute) at 100°F shall be known as a Class I Liquid.

(G-73)

Frequency - Each Surveillance Requirement (SR) has a specified Frequency in which the SR must be met in order to meet the associated Operating Requirement (OR). The "specified frequency" is referred to in Section 14. (FPR Preparer)

Functional Test - The injection of a simulated signal into the sensor or device to verify the operability, including alarm and/or activation functions. (FPR Preparer)

Inaccessible Area - Those areas defined by the FSAR Chapter 12.1 as a High Radiation Area or a Very High Radiation Area. Areas may be designated as inaccessible by the Fire Protection Manager because operating conditions that pose immediate danger to life and health from environmental or operational conditions. (FPR Preparer)

In-Situ Combustible Loads - Combustible material permanently located in a room or fire area. The total amount of in-situ combustibles in a fire area is used to determine the fire severity rating. The combustible loading values and fire severity ratings are included in the Fire Hazards Analysis. (FPR Preparer).

Internal Conduit Seals

a.

Smoke and Hot Gas Seals -Noncombustible seals installed inside conduit openings to prevent the passage of smoke and hot gasses through fire barriers. These seals may be located at the fire barrier or at the nearest conduit entry on both sides of the fire barrier. Smoke and hot gas seals are not required to have a fire resistance rating equal to the fire barrier they are installed in. (G

96)

b.

Heat and Fire Seals - Fire rated seals installed inside conduits at or in close proximity to the fire barrier. Heat and fire seals have the same or greater fire resistance rating as the fire barrier they are installed in. (G-96)

Labeled - Equipment or materials to which has been attached a label, symbol or other identifying mark of an organization acceptable to the authorities having jurisdiction and concemed with product evaluation, that maintains periodic inspection of production of labeled equipment or materials and by whose labeling the manufacturer indicates compliance with appropriate standards or performance in a specified manner.

(G-73) 11-8

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 Limited Combustible Material - As applied to a building construction material, a material not complying with the definition of noncombustible material, which, in the form in which it is used, has a potential heat value not exceeding 3500 Btu per lb. (8141 IJ/Kg), and complies with one of the following paragraphs (a) or (b). Materials subject to increase in combustibility or flame spread rating beyond the limits herein established through the effects of age, moisture, or other atmospheric condition shall be considered combustible.

(a) Materials having a structural base of noncombustible material, with a surfacing not exceeding a thickness of 1/8 in. (3.2mm) which has a flame spread rating not greater than 50.

(b) Materials, in the form and thickness used, other than as described in-(a), having neither a flame spread rating greater than 25 nor evidence of continued progressive combustion and of such composition that surfaces that would be exposed by cutting through the material on any plane would have neither a flame spread rating greater than 25 nor evidence of continued progressive combustion. (NFPA 220)

Listed - Equipment or materials included in a list published by an organization acceptable to the authority.

having jurisdiction and concerned with product evaluation, that maintains periodic inspection of production of listed equipment or materials and whose listing states either that the equipment or material meets appropriate standards or has been tested and found suitable for use in a specified manner. (G-73)

Noncombustible Material - 1) A material which in the form in which it is -used and under the conditions anticipated, will not ignite, bum, support combustion, orrelease flammable vapors when subjected to fire or heat; having a structural base of noncombustible material, as defined above, with a surfacing not over 1/8-inch thick that has a flame spread rating not higher than 50 when measured using ASTM E84 Test, "Surface Burning Characteristics of Building Materials". (G-73)

2) A material which, in the form in which it is used and under the conditions anticipated, will not ignite, bum, support combustion, or release flammable vapors, when subjected to fire or heat.

Materials which are reported as passing ASTM E136, Standard Test Method for Behavior of Materials in a Vertical Tube Furnace at 750°C, shall be considered noncombustilble materials. (NFPA 220)

Operable-Operability - A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s). (FPR Preparer)

Operational Mode - Mode - An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 5.1. (FPR Preparer)

Operating Requirement (OR) - The lowest level functional capabilities or performance levels of equipment required to ensure adequate fire protection capability is established and maintained to protect safety-related and FSSD equipment from the effects of fire. When an OR is not met, action statements are provided to describe remedial action until the OR can be met. (FPR Preparer)

II-9

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 Penetration - An opening through structural members or barriers such as walls, floors, or ceilings for passage of penetrating components. (G-96)

Penetration Seal - Materials, devices, or assemblies installed in communicating spaces across barriers, which provide effective sealing against defined environmental exposure criteria to achieve the same functional requirement as that originally intended by the structural member or the barrier.

(G-96)

Portable Fire Extinguisher - A portable device containing powder, liquid, or gases which can be expelled under pressure for the purpose of suppressing or extinguishing a fire.

(FPR Preparer)

Pre-action Sprinkler System - A system employing automatic sprinklers attached to a piping system connected to a water supply containing air that may or may not be under pressure, with a supplemental fire detection system installed in the same area as the sprinklers. Actuation of the fire detection system (as from a fire) opens a valve that permits water to flow into the sprinkler piping system and to be discharged from any sprinklers that may be open. (G-73)

Primary Containment - A structure that acts as a barrier to the release of radioactive fission products or other radioactive substances. Primary containment is a gas-tight shell that receives and contains the water, steam, and fission products that flow from any break in the reactor coolant pressure boundary located within primary containment. (FPR Preparer)

Safety-Related - Items that meet the following criteria:

a.

Those functions that are necessary to ensure:

(1) The integrity of the reactor coolant pressure boundary.

(2) The capability to shut down the reactor and maintain it in a safe condition.

(3) The capability to prevent or mitigate the consequences of an incident which could result in potential offsite exposures comparable to those specified in 10 CFR 100.

(G-73)

Safety-Related Area - Any area containing safety-related equipmenC Safety-related areias include: Unit 1 Reactor Building, Unit 2 Reactor Building, Auxiliary Building (including Unit 1 & 2 Additional Equipment Buildings), Control Building, Intake Pumping Station, Essential Raw Cooling Water Pump Station, Diesel Generator Building, cable/conduit duct banks between safety-related buildings, and portions of the Yard containing safety-related equipment. (FPR Preparer)

Secondary Containment - The structures (annulus and auxiliary building) that provides a plenum for the temporary, low pressure retention of gaseous leakage from primary containment. (FPR Preparer)

Smoke Detector - A device which detects the visible or invisible particles of incomplete combustion. (G

73)

Sprinkler System - A network of piping connected to a reliable water supply that will distribute the water throughout the area protected and will discharge the water through sprinklers in sufficient quantity either to extinguish the fire entirely or to prevent its spread. The system, usually activated by heat, includes a controlling valve and a device for actuating an alarm when the system is in operation.

Specific systems are manually actuated and do not contain a device for actuating an alarm when the system is in operation.

(FPR Preparer) 1I-10

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 Staggered Test Basis -A STAGGERED TEST BASIS shall consist of:

a. A schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals,

b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval. (FPR Preparer)

Standpipe and Hose System - An arrangement of piping, valves, hose connections, and allied equipment installed in a building with the hose connections located in a manner that the water can be discharged in streams or spray patterns through attached hose and nozzles, for the purpose of extinguishing a fire and so protecting a building and its contents in addition to protecting its occupants. This is accomplished by connections to water supply systems or by pumps, tanks and other equipment necessary to provide an adequate supply of water to the hose connections. (G-73)

Testable Valves - Refers to valves such as Outside Screw and Yoke (OS&Y), butterfly, and gate, (with or without automatic operators) that are designed to be cycled or exercised to ensure operation and prevent binding. This does not refer to valves such as check valves, solenoid valves, alarm test valves, or suppression system water flow alarm valves. (FPR Preparer)

Thermal Detector -A device that detects abnormally high temperature or rate of temperature rise. (FPR Preparer)

Transient Fire Loads - Any combustible material that is not permanently present in a given area, and may be introduced during maintenance, repair, rework, or may be transported to a final destination for permanent installation or maintenance, repair, rework of equipment systems and components present there. (G-73)

Water Spray Nozzle - A normally open water discharge device which, when supplied with water under pressure, will distribute the water in a special, directional pattem peculiar to the particular device. (G

73)

Water Spray System - A special fixed piping system connected to a reliable source of fire protection water supply and, equipped with water spray nozzles for specific water discharge and distribution connected to the water supply through an automatically or manually actuated valve which initiates the flow of water. An automatic valve is actuated by operation of automatic detection equipment installed in the same areas as the water spray nozzles (in special cases the automatic detection equipment may also be located in another area). (G-73)

Water Supply - An arrangement of pumps, piping, valves, and associated equipment necessary to provide an adequate, reliable supply of water for the extinguishment of fires.

(FPR Preparer)

IU-1I

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 5 1 OPERATIONAL MODES MODE

1. POWER OPERATION

2. STARTUP

3. HOT STANDBY

4. HOT SHUTDOWN

5. COLD SHUTDOWN

6. REFUELING**

REACTIVITY CONDMON, Kj

>0.99

>0.99

<0.99

<0.99

<0.99

_<0.95

% RATED THERMAL POWER*

>5%

_<5%

0 0

0 0

AVERAGE COOLANT TEMPERATURE

Ž_350 0°F

>_350 0°F

_350 0F 350°F>Tag>2000F

-<200°F

-<1400F Excluding decay heat.

• Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed 11-12 Rev. 10

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 6.0 FIRE PROTECTION QUALITY ASSURANCE TVA has developed an augmented Quality Assurance (QA) Program for fire protection which satisfies the guidelines for QA for Fire Protection established by Appendix A to Branch Technical Position APCSB 9.5-1 and the Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance letter (dated August 29, 1977) for fire protection features that provide protection for safety-related structures, systems or components and fire safe shutdown systems. Refer to Part VIII of the FPR for a comparison of the SQN Fire Protection Program with Appendix A guidelines.

The QA program for fire protection uses the applicable parts of the TVA Nuclear Quality Assurance Plan (TVA-NQA-PLN89-A). More stringent QA requirements may apply to fire protection features that also perform nuclear safety-related functions such as containment isolation. This QA program is described in corporate Standards and implemented in SQN procedures.

f-13

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 7.0 FIRE PROTECTION ORGANIZATIONIPROGRAMS 7.1 TVA Nuclear (TVAN) Corporate Management The Senior Vice President, Nuclear Operations, TVAN, his/her equivalent or designee, has the overall responsibility for establishing policies and programs related to fire protection. The General Manager, Operations Services, his/her equivalent or designee, establishes fire protection programs and fire brigade training and qualification requirements and assesses their effectiveness. Agreements are maintained between the TVAN and TVA Fossil and Hydro Power organizations for providing training and qualification of fire brigade and Incident Commander personnel. The Senior Vice President, Nuclear Operations, TVAN, assumes or delegates the responsibility for "Authority Having Jurisdiction" (AHJ) for Operational fire protection matters.

The Vice President, Engineering and Technical Services, TVAN, has the overall responsibility for establishing the design basis of the plant systems and features related to fire protection. The Corporate Engineering Chief Engineer assumes or delegates the responsibility as the "Authority Having Jurisdiction" (AHJ) for the design basis fire protection matters.

TVAN has on staff or as a consultant, an individual(s) who meet the eligibility requiirements as a Member Grade in the Society of Fire Protection Engineers.

7.2 Site Vice President (VP)

The Site VP is responsible for the development, implementation, and administration of the Fire Protection Program. Authority and accountability for overview and implementation of the program have been further delegated to the Plant Manager. Specific requirements and responsibilities related to tasks such as administrative control of fire hazards, manual fire suppression, and maintenance of fire protection equipment have been delegated to various site organizations. The Site VP also provides design, engineering, and construction resources for fire protection systems and features.

7.3 Plant Manager

- The Plant Manager is responsible for management o~versight of tht development and implementatioffof the SQN Fire Protection Plan.

7.4 Operations Manager The Operations Manager is responsible for the development, implementation, and control of the S QN Fire Protection Plan. The Operations Manager provides senior management assistance and departmental interface for the resolution of fire protection-related issues referred by the Fire Protection Manager.

7.5 Fire Protection Manager The Fire Protection Manager has overall responsibility for SQN fire protection program and related activities at the site. The Fire Protection Manager has available an individual who meets the eligibility requirements as a "member grade" in the Society of Fire Protection Engineers to support the fire protection administrative program.

Fire Protection Engineers are provided, for fire protection systems and features, to provide technical 11-14

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 leadership to plant personnel for assigned fire protection systems and features, proactive identification and resolution of technical issues affecting fire protection systems and features, initiation of fire protection-related design modifications, and technical assistance to fire protection management, operations, and maintenance organizations.

The Fire Protection Manager has the following responsibilities:

a. Ensures that the assigned sections of the Fire Protection Report are maintained.

b. Provides oversight to the Appendix R fire protection program.

c. Represents SQN management concerning site fire protection-related issues -with regulators, insurance representative, state and local authorities, and other outside agencies such as the local fire department.

d. Ensures that fire protection systems and features are tested, inspected, and maintained in accordance with provisions set forth in this Plan.

e.

Supervises SQN's fire protection emergency response organization.

f. Ensures appropriate modification (design changes) and other complex work packages are evaluated for compliance with established fire protection codes and standards and regulatory commitments.

g. Ensures the overall readiness of the fire protection organization and site personnel, to combat, suppress; and report fires, perform tests, and provide technical programmatic oversight.

h. Ensures that pre-fire plans and procedures for fire emergencies are maintained.

i.

Ensures periodic fire protection inspections are performed as required.

j.

Administers the process that confrols fire protection systems and feature impairments and restorations, and associated compensatory actions to ensure compliance with regulatory requirements.

k. Develops and implements administrative and physical controls of transient combustibles and ignition sources.

1. Ensures that work initiating documents (WID) are reviewed for impact on the elements of the Fire Protection Plan.

m. Provides advice and assistance to plant personnel on fire protection matters.

n. Ensures the fire protection system/equipment surveillance and maintenance program and its associated instructions are developed and maintained.

o. Ensures fire protection system test and surveillance results are evaluated for determination of operability status and deficiencies are correctly dispositioned.

11-15

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10

p. Establishes and implements the periodic site training and drill requirements as outlined in this plan.

q. Ensures that fires are investigated.

r. Ensures the implementation of the augmented Quality Assurance Program for Fire Protection.

s.

Ensures adequate staff and fire fighting equipment are available on site forthe onsite emergency response organization.

7.6 Nuclear Enrineerin2 The Engineering & Materials Manager is responsible for fire protection related design activities at the site. Nuclear Engineering has available an individual who meets the eligibility requirements as a "Member Grade" in the Society of Fire Protection Engineers to assist in fire protection design. Nuclear Engineering:

a. Maintains responsibility for the technical adequacy of the SQN Fire Protection Report.

b. Reviews and evaluates applicability of regulations and standards to fire protection system design activities.

c.

Reviews the design, installation and modification of plant fire protection equipment and systems for conformance to regulatory requirements, general industry fire protection standards, and soliciting and integrating operational considerations into these documents.

d. Provides technical advice and assistance toplant personnel on fire protection engineering design activities.

e. Reviews design activities for impacts on Appendix R Safe Shutdown and the Fire Hazards Analysis.

f.

Establishes design bases for fire suppression, fire barrier, fire detection, and alarm system.

g. Ensures the technical adequacy of permanent fire protection features installed in nuclear power plants.

h. Ensures that plant and system design considers the safety to life from fire in buildings and structures.

I. - Coordinates the development of positions to generic fire protection-related engineering issues and provides support in the development of positions to site-specific licensing and insurance issues.

j.

Participates in fire protection presentations, submittals, and commitments made to the NRC that involve engineering.

11-16

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 7.7 Nuclear Assurance Nuclear Assurance ensures annual, biennial, and triennial audits are performed in accordance with the SQN Fire Protection Plan, Section 8.3.

7.8 Site Personnel The SQN Fire Protection Plan applies to Nuclear Generation employees and contractors performing activities at SQN.

Site personnel who have duties or perform work activities at SQN are responsible for being familiar with procedures applicable to them during a fire emergency and conducting day-to-day work activities in accordance with plant fire protection administrative procedures.

General employee's fire protection-related responsibilities and requirements are provided in the plant access training program. As part of their instruction, Employees are familiarized in the following areas of fire protection:

1)

Fire Protection transient combustibles and hazard identification.

2)

Fire Detection and the proper procedure to report a fire in the plant.

3)

Fire extinguishing systems installed in the plant.

4)

Compartmentation and its importance to fire protection.

Employees are instructed in the proper procedure for reporting a fire emergency. Employees are not trained or required to combat fires. Manual fire suppression is performed by personnel specifically trained in fire suppression (i.e., Fire Brigade).

11-17

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 8.0 FIRE PROTECTION PROGRAM ADMINISTRATIVE AND TECHNICAL CONTROLS This section of the SQN Plan provides the administrative process and controls for implementation of the Fire Protection Program.

8.1 Program Changes and Associated Review and Approval

a.

Nuclear Engineering is responsible for the technical accuracy of the SQN Fire Protection Report (FPR). Changes to the FPR are initiated similar to the UFSAR change process and require a 10CFR50.59 review.

b.

The Fire Protection Manager reviews proposed changes to the Fire Protection Report and fire protection administrative procedures to ensure adequacy and compliance with established regulatory commitments

c.

The Plant Operations Review Committee (PORC) reviews changes to the Fire Protection Report (excluding the figures in the FPR that are issued design drawings and Part X, Fire Hazards Analysis, which is controlled in accordance with NEP-3.1, Calculations) and SSP-12.15, Fire Protection.

d.

The Nuclear Safety Review Board (NSRB) functions to provide for independent review and audit activities in the area of the site Fire Protection Program.

e.

SQN may make changes to the approved Fire Protection Report without prior approval of the NRC only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

e.

The Fire Protection Report is updated in accordance with 10CFR50.71.

8.2 Modification Control A fire protection evaluation is perfoirmed (when required) for plant modifications in accordance with established Nuclear Engineering procedures. This evaluation is performed to ensure that adequate fire protection measures are maintained, combustible loading considerations are addressed, the overall Fire Protection Program is not degraded, and requirements and guidelines of regulatory agencies have been considered. The evaluation also addresses specific commitments to the applicable sections of 10CFR50, Appendix R.

8.3 Audits/Inspections of the Fire Protection Program In accordance with Generic Letter No. 82-21, "Technical Specifications for Fire Protection Audits" the following system of audits are conducted to assess the SQN fire protection equipment and FPP implementation to verify continued compliance with NRC requirements and TVA commitments:

a.

An annual fire protection and loss prevention inspection and audit utilizing either qualified offsite TVA personnel or an outside fire protection firm,

b.

A biennial audit of the FPP and implementing procedures, and 11-18

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10

c.

A triennial fire protection and loss prevention inspection and audit utilizing an outside qualified fire protection consultant.

8.4 Assessment of Information Notices. Generic Letters, Bulletins, etc.

The Sequoyah Nuclear Experience Review (NER) Program and Licensing Staff ensures that NRC Information Notices, Generic Letters, Bulletins, and other relevant documents that provide information on generic or specific fire protection and/or fire safe shutdown issues are assessed for applicability to SQN. The responsible organizations (i.e., licensing, engineering, operations, etc.) for addressing the applicable issues are determined upon assessment of the subjects identified in the documents.

8.5 Nonconformance and Reportability Nonconformance with the requirements described in Section 14.0 shall be evaluated for reportability and corrective actions performed in accordance with site administrative procedures.

Nonconformance occurs when the limits of the Surveillance Requirements (SR) (including allowable extensions) are exceeded or conditions of the associated action statement are not met.

11-19

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 9.0 EMERGENCY RESPONSE 9.1 Fire Brizade Staffing Effective handling of fire emergencies is an important aspect of the SQN Fire Protection Program. This is accomplished by trained and qualified emergency response personnel. The fire response organization is staffed and equipped for fire fighting activities. The fire brigade is comprised of a fire brigade leader and four fire brigade members.

A fire brigade of at least 5 members shall be maintained onsite at all times. The fire brigade shall not include the Shift Manager and 2 other members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency. Additional support is available when needed through an agreement with a local fire department.

An Incident Commander is available to direct each shift fire brigade. The Incident Commander is an Unit Supervisor (or equivalent) and has sufficient training in or knowledge of plant safety-related systems to understand the effects of fire and fire suppressants on safe shutdown capability.

The fire brigade composition may be less than the minimum requirements for a period of time not to exceed two hours, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions. A life-threatening medical emergency, requiring the plant ambulance and EMT responders to leave the site for transport of the patient, is an example of an emergency that would prevent the full fire brigade from being available onsite. This is expected to be a rare occurrence.

9.2 Fire Brigade Support Personnel

a.

Site Nuclear Security provides access to the security controlled area for the fire brigade and offsite fire response personnel during fire emergencies. This includes traffic, emergency vehicle, and crowd control, when necessary.

b.

Site Radiological Control (RAD CON) personnel provide radiological support for the fire brigade to advise the brigade on radiological hazards and assist in radiological decontamination efforts if necessary. RADCON personnel provide radiological support for offsite fire response personnel.

9.3 Trainingz and Qualifications S QN fire brigade training ensures that the fire brigade's capability to combat fires is established and maintained. Prior to training and annually thereafter (with a grace period to the end of the quarter in which the evaluation is due), each fire brigade member and leader receives a medical evaluation to ensure the ability to perform strenuous physical activity, to wear special respiratory equipment, and for unescorted access to nuclear plants.

The training program consists of initial (classroom and practical) training and recurrent training which includes periodic instruction, fire drills and annual fire brigade training.

a.

Initial training Initial training consists of classroom instruction and practical exercises to include actual 11-20

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 fire extinguishment and use of fire fighting and related equipment under strenuous fire fighting conditions. Training includes:

1)

Identification of the fire hazards and associated types of fires that could occur in

• the plant and an identification of the location of such hazards.

2)

Identification of the location of fire fighting equipment for each fire area, and familiarization with layout of the plant including access and egress routes to each area.

3)

The proper use of available fire fighting equipment, and the correct method of fighting each type of fire. The types of fires covered include electrical fires, fires in cables and cable trays, hydrogen fires, flammable liquid fires, waste/debris fires, and record file fires.

4)

Indoctrination of the plant fire fighting plan with specific coverage of each individual's responsibilities.

5)

The proper use of communication, lighting, ventilation, and emergency breathing apparatus.

6)

The toxic characteristics of expected products of combustion.

7)

The proper methods for fighting fires inside buildings and tunnels

8)

Detailed review of Pre-Fire Plans and procedure changes.

9)

Review of latest plant modifications and changes in fire fighting plans.

10)

The direction and coordination of the fire fighting activities (fire brigade leaders only).

In addition, fire brigade leaders receive additional training that provides the fire brigade leader with the knowledge and skills necessary to supervise and direct the activities of the fire brigade during an incident.

b.

Recurrent training Training and qualification will be scheduled with a maximum allowed extension of 25 percent of the listed frequency interval.

1)

Periodic Classroom Instruction Regular planned meetings will be held every three months. These planned meetings will repeat the initial training subject matter over a two-year period.

2)

Fire Drills IH-21

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 Drills are pre-planned to establish the objectives and are conducted by the fire training instructor or designated representative. Drills are conducted as follows:

a)

A minimum of one drill per shift every 92 days.

b)

A minimum of one unannounced drill per shift per year.

c)

At least one drill per shift per year is performed on a "backshift" for each fire brigade.

d)

At three-year intervals, a randomly selected, unannounced drill critiqued by qualified individuals performing a triennial audit of the fire protection plan.

e)

An annual fire drill, which includes participation by the offsite fire department organization(s) that has an active agreement(s) to provide fire fighting and equipmefit response to the plant.

f)

Fire brigade members including leaders shall participate in at least two drills per year.

g)

When assigned as the shift Incident Commander, the Incident Commander shall attend all fire drills occurring during that shift.

Performance deficiencies of the fire brigade or individual brigade members are remedied by scheduling additional training.

3)

Annual Fire Brigade Training Annual Fire Brigade Training will be held for the fire brigade on the proper method of fighting various types of fires similar in magnitude, complexity, and difficulty as those that could occur. This training will include actual fire extinguishmient and the use of emergency breathing apparatus under strenuous conditions.

Annual briefings are provided to the local fire departments to assure their continued understanding of their role in the event of a fire emergency at the plant.

The annual briefings are required for only those local fire departments that have aid agreements with the plant.

11-22

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 9.4 Fire fighting Equipment Fire fighting equipment is provided throughout the plant. The availability of fire fighting equipment is such that delays in obtaining equipment by the fire brigade for fire emergencies will be minimized.

Fire fighting equipment may, alternatively, be staged adjacent to or at the access to areas/locations to facilitate equipment availability.

Examples of the types of fire fighting equipment available are as follows:

mobile apparatus portable ventilation equipment fire extinguishers self-contained breathing apparatus and reserve air bottles fire hose nozzles, gated wyes, fittings, and foam applicators personal protective equipment such as turn-out coats, boots, gloves, and helmets communication equipment portable lights ladders for fire fighting use 9.5 Fire Emergency Procedures and Pre-fire Plans Fire emergency procedures and pre-fire plans specify actions taken by the individual discovering a fire and actions considered by the emergency response organization. Included in these procedures are operational instructions for response to the fire detection system annunciation. These procedures provide different levels of response based on the type of alarms received. An annunciation may or may not carry the same level of response as the report of a fire by site personnel. '

Pre-fire plans are developed to support fire fighting activities in safety-related areas, in fire safe shutdown system areas, and areas which may present a hazard to safety-related or FSSD equipment. Pre-fire plans are not intended to establish a procedure or step-by-step process but to provide guidance, depending upon the particular circumstances, to aid idi fire fighting efforts. It is recognized that many diffeient fire fighting techniques or strategies exist which would be acceptable for fire suppression efforts.

The pre-fire plans include the following information, as appropriate:

N Identification of plant equipment N

Access and egress routes for fire areas N

Fire fighting strategy and tactics N

Location of fire protection features N

Identification of special fire, toxic material, and radiological hazards N

Special consideration of hazards N

Ventilation methodology Safe shutdown procedures are available in the event a fire occurs in safety-related or FSSD equipment areas of the plant.

11-23

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 10.0 CONTROL OF COMBUSTIBLES Combustibles are controlled to reduce the severity of a fire which might occur in a given area and to minimize the amount and type of material available for combustion.

The use and application of combustible materials at SQN are controlled utilizing the following methods:

Instructions/guidelines provided during general employee training/orientation programs The chemical traffic control program.

Periodic plant housekeeping inspections/tours by management and/or the plant fire protection organization.

Design/modification review and installation process.

Administrative procedures..

The fire protection organization performs a periodic fire safety inspection of the safety-related areas of the plant to identify and minimize potential fire hazards.

The use and handling of combustible materials such as fire retardant-treated lumber, paper, plastic, and

.-. flammable/combustible gases and liquids are controlled in safety-related areas. The use of untreated lumber in safety-related areas requires specific approval of the fire protection organization.

Combustible materials (e.g., combustible packing materials, flammable and combustible liquids) necessary for maintenance work activities are properly stored at the conclusion of the work activity, unless alternative conditions are implemented in accordance with administrative procedures.

The control of hazardous waste and hazardous materials is conducted in accordance with the chemical control and hazardous material processes. Materials containing or collecting significant radioactivity are stored in closed metal containers in the radwaste area Design considerations in the control of combustibles is utilized when appropriate. For example, these considerations include the application of noncombustible or limited combustible construction materials or components, use of noncombustible fluids in operating equipment, dikes, or containments provided for equipment containing combustible liquids, etc.

11-24

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 11.0 CONTROL OF IGNITION SOURCES The use of ignition sources such as welding, flame cutting, thermite welding, brazing, grinding, arc gouging, torch applied roofing, and open flame soldering within safety-related areas are controlled through the approval and issuance of an ignition source permit.

Fire watch systems are established for all ignition source work activities that are performed in safety related areas.

11-25

SQN FIRE PROTECTION REPORT PART 1I - FIRE PROTECTION PLAN Rev. 10

12.0 DESCRIPTION

OF FIRE PROTECTION SYSTEMS AND FEATURES Fire protection systems and related features consist of the following subsystems:

water supply standpipes, hoses and hydrants automatic and manual fire suppression equipment fire detection lightning protection, emergency lighting, and communications reactor coolant pump lube oil collection system, and fire-rated assemblies The following subsections are summary discussions of these fire protection systems and related features 12.1 Water Supply The High Pressure Fire Protection (HPFP) system water supply is common to both units and consists of one electric motor driven fire pump and one diesel engine driven fire pump. Each pump takes suction from its own 300,000 gallon potable water storage tank which is supplied by the local municipal utility. The pump supply piping is interconnected such that either or both pumps can take suction from either tank. The electric pump is the lead pump and the diesel pump is a 100% backup. Each pump is capable of supplying the water required for all Appendix R fires and most general plant fires. The pumps are located in the HPFP pump house in their own room separated by a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire wall. Each pump is connected to the HPFP system looped yard main by a separate supply line which can be isolated.

The fire pumps automatically start on low HPFP system header pressure. The HPFP system is normally pressurized when the fire pumps are not running by a cross connect to the fire tank potable water supply and two jockey pumps which automatically start if the potable water supply cannot maintain system header pressure. The cross connect is downstream of the potable water backflow preventer and contains a pressure regulator and check valve to isolate the fire protection system from a failure of the potable water supply and prevent recirculation back to the fire tanks during fire pump operation. If the HPFP header pressure drops below the fire pump start pressure for approximately 1 to 3 seconds the electric fire pump will start. If the pressure remains below the fire pump start pressure for approximately 8 to 10 seconds the diesel fire pump will start. The fire pumps can be manually started locally or from the main control room but can only be shut off from the local control panel.

The electric fire pump is powered from the 6900VAC Yard Area Common Board. The diesel fire pump and instrumentation is powered by a battery system and will operate on a loss of AC power. The electric fire pump has control room alarms which indicate pump motor running, loss of line power, phase reversal, and motor failed to start. The diesel fire pump has control room alarms which indicate engine running, engine failed to start, and controller not in automatic start position. Each pump also has a common alarm in the control room for adverse environmental conditions and equipment failures effecting pump operation.

The HPFP system is also connected to the two fire/flood mode pumps (old fire pumps) which can be utilized by opening the normally closed valves which isolate them from the system. These are electric pumps which take suction from the forebay and arepowered from separate (Class 1E) 480 VAC shutdown boards.

These pumps are not required for the HPFP system to fulfill its design bases.

Strainers are provided at the IPS and inside the AB on the fire pump headers. These strainers were 11-26

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 installed because the original system was supplied by river water. The strainer at the IPS is normally bypassed unless a fire/flood mode pump is being used to supply river water to the HPFP system.

In addition, fire protection water strainers are located in the flow path just upstream of the flow control valves for the various sprinkler and water spray systems supplying safety-related areas. The fire pump strainers and the flow path strainers are inspected and maintained in accordance with the SQN Periodic Inspection Program. A fire protection water distribution system is provided to serve both units. Sectional isolation valves are provided so that maintenance may be performed on portions of the loop while maintaining fire fighting capability.

The sectional isolation valves in the underground loop are locked or sealed in position and surveillance is performed to ensure proper system alignment. The fire protection water distribution system is cross-tied between units.

12.2 Standpipes, Hose Stations, and Hydrants Interior manual hose installations are provided throughout the plant typically as back up for the automatic suppression systems and, in some cases, as the primary suppression system.

Selected hazards in the Reactor Buildings have automatic suppression systems as primary protection.

These hazards include closed head, pre-action water spray systems installed for each reactor coolant pump (RCP) and pre-action sprinklers in the annulus that serve as water spray on select cable concentrations and to prevent c.:;!'

specific cable interactions. These automatic suppression systems are the primary suppression for these hazards with the standpipes as the backup.

For lower containment areas of the Reactor Buildings, the primary suppression system is the Reactor Building standpipes with the Auxiliary Building standpipes serving as the backup system. Upper containment areas utilize auxiliary building hose stations.

The standpipe systems in the IPS serve as the primary system, with yard hydrants and mobile apparatus providing the backup system. Hydrants are appropriately located throughout the yard in the vicinity of the IPS.

The ERCW Pumping Station is provided with two independent standpipe systems (supplied by train A and Train B ERCW Pumps).

Selected areas in the Diesel Generator Building (DGB) have automatic C0 2 and pre-action sprinkler systems as primary protection with the standpipe system serving as the backup system in these areas. In areas of the DGB without automatic suppression, the standpipe system serves as the primary system, with yard hydrants providing the backup system.

Class II and Ill Hose stations are equipped with nozzles rated for the hazards present and with a sufficient amount of hose to support fire fighting needs in that area. Water spray or fog is not permitted in the new fuel storage vault. Portable extinguishers are acceptable in this area due to the low combustible loading and the metal covers over the new fuel vault.

Hose station equipment may, alternatively, be staged adjacent to or at the access to areas/locations to facilitate equipment availability. This may be necessary to address equipment concerns relative to personnel safety, ALARA practices, and logistical response needs.

11-27

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 The auxiliary building, control building, diesel generator building, intake pumping station, and ERCW pumping station are provided with a wet standpipe system. These systems have supply valves open and water pressure to the hose rack isolation valve. The Reactor Building (including the Annulus) is provided with a dry standpipe system. The standpipe systems within the RB are normally dry and are arranged to admit water into the systems through manual operation of push buttons located at each hose station.

The reactor building systems are controlled by electrically or manually operated flow control valves which are located in the AB. These systems are provided with automatic containment isolation capabilities for primary containment to address nuclear safety concerns where appropriate. In case a fire in primary containment causes a spurious containment isolation signal, flow to these systems can be reestablished by resetting the phase A isolation signal and opening the containment isolation valves.

12.3 Automatic Fire Suppression Systems The automatic fire suppression systems are designed to extinguish a fire or control and minimize the effects of a fire until the fire brigade can respond and extinguish it. The automatic suppression systems consist of water based systems and total flooding C0 2 systems. In addition, manually actuated fixed water suppression systems are also addressed in this section.

There are typically four types of automatic suppression systems provided in safety-related areas at SQN:

a.

automatic pre-action sprinkler systems

b.

automatic fire suppression systems with closed water spray heads

c.

automatic total flooding C0 2 systems

d.

automatic pre-action water spray systems (see Part VI)

The annulus area of the Reactor Building has automatic pre-action sprinklers that serve as water spray on select cable concentrations to prevent specific cable interactions.

12.3.1 Pre-action Sprinkler Systems "Automatic pre-action sprinklei systems generally are provided in areas where it is important to prevent accidental discharge of water. In a pre-action sprinkler system, the piping network is maintained dry until water is needed for fire suppression. A deluge valve (sometimes referred to as a pre-action valve when used in a pre action system) is used to control the water when the water is introduced into the piping network.

Operation of the pre-action sprinkler system is initiated by a signal from a detection system in the protected area. This signal causes the pre-action valve to open and fill the piping network. Actuation can also be initiated manually by mechanical operation at the pre-action valve. Selected pre-action sprinkler systems have manual actuation stations at strategic locations remote from the pre-action valve.

Water is then applied to the fire when the heat from the fire melts the fusible element in the sprinkler head. Water flow is stopped by manually closing the associated isolation valve.

11-28

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 12.3.2 Fire Suppression Systems with Closed Water Spray Heads See Part VI.

12.3.3 Carbon Dioxide Suppression Systems Automatic total flooding CO2 suppression systems have been provided for the Auxiliary Instrument Rooms and Computer Room in the Control Building, and the Lube Oil Storage Room, each Diesel Engine Room (4), Fuel Oil Transfer Room, and each 480-V Board Rooms (4) in the Diesel Generator Building. See Part VI.

A signal from either the fire detection system or a push button station activates the area alarms, C02 discharge timer which actuates the master control valve and the area selector valve permitting the CO2 to be discharged into the selected area. In addition, the system can be manually operated via the electro-manual pilot valve.

Personnel safety is considered by providing the pre-discharge alarm to notify anyone in the area that CO2 is going to be discharged and by the addition of an odorizer to the CO2 to warn personnel that CO2 has been discharged. Additionally, abort switches are strategically located in the Unit LAuxiliary Instrument Room (685.0-Cl), Unit 2 Auxiliary Instrument Room (685.0-C4), and Computer Room (685.0-C3) to allow for the discharge to be terminated by personnel in the area.

Actuation of the CO2 system causes selective closure of dampers and doors to the area protected. HVAC fans to the protected areas in the diesel generator building are shutdown. This prevents spread of the fire and ensures that the minimum concentration of CO2 is maintained. The duration of the discharge is determined by the area requirements and is controlled by the discharge timer.

The carbon dioxide system providing protection for the diesel generator building is stored in a tank at the diesel generator building. The diesel generator units are protected from the effects of a postulated failure of this storage tank by an 18-in thick reinforced concrete wall. Therefore, any missiles or pressure buildup generated by a rupture of the carbon dioxide storage tank would not damage safety-related equipment. The vent path for the storage tank compartment is through one set of double doors into a stainvell then, if needed, through another set of double doors which open to the atmosphere from the 'tairwell.

Carbon dioxide for the powerhouse areas is supplied from another storage tank in an underground vault in the yard; therefore, rupture or explosion of the tank cannot pose a threat to any safety-related structure.

12.3.4 Pre-action Water Sorav Systems 11-29 See Part VI.

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 12.4 Manual Suppression Systems and Features 12.4.1 Portable Extinguishers Portable fire extinguishers of a size and type compatible with specific hazards are located throughout the plant. Extinguishers may, alternatively, be staged adjacent to or at the access to areas/locations to facilitate equipment availability. This may be necessary to address personnel safety concerns, ALARA practices, and logistical response needs.

12.4.2 Manual Sprinkler Systems Manually activated sprinkler systems are provided for the Post Accident System facility, Post Accident System filters, and the 125-volt vital battery and battery board rooms I, II, III, and WV. The piping network isolation valve is maintained in the closed position. Personnel are alerted to a problem in these areas by the fire detectionsystem. After confirming there is a fire, personnel then open the appropriate isolation valve to allow water to the system. Water is applied to the fire when the heat from the fire melts the fusible element in the sprinkler head.

In the event of a fire in the elevation 669' corridor of the Control Building, manual initiation of the pre action valve is required.

12.5 Fire Detection Systems Fire detection is installed to provide for prompt detection of a fire in its incipient stage and provide early warning capability. Prompt detection of a fire will reduce the potential for damage to structures, systems and equipment and is an important part of the overall fire protection program at SQN. The fire detection systems at SQN are designed to be operable with or without offsite power.

The fire detection systems consist of initiating devices, proprietary protective signaling devices, local control panels, remote transmitter/receiver units which provide remote multiplex (MUX) functions, and computerized multiplex central control equipment.

The system processes the following signal types:

1.

Alarm - A signal indicating the actuation of smoke or heat detectors or the sensing of flow through fire suppression systems. Also, some suppression supervision monitoring devices transmit an alarm signal.

2.

Trouble - A signal indicating the occurrence of a fault condition in the proprietary protective signaling system.

3.

Supervisory - A signal indicating a change in status of a zone.: Several zones at Sequoyah Nuclear Plant are monitored with a supervision module that indicates a change in the status of the local zone without impacting normal operations of its associated local panel. This signal is indicated on the alarm console as a trouble condition.

One of the two central processor units (CPU) of the computerized multiplex central control equipment located in the main control room communicates with the local control panels via the remote transmitter/receiver 11-30

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 units over looped circuits. Only one of the CPU=s provided is required to be OPERABLE. A second CPU is installed and available for use in the event that the operating CPU fails. The CPU polls each panel connected to the multiplexor loop and has the capability to transmit panel commands and receive data from the panels.

When an initiating device changes from normal to a trouble or alarm status, it is detected at the local control panel and the remote transmitter/receiver will transmit this status change.

The status change is evaluated by the CPU and visual and audible indications are provided. The computerized multiplex central control equipment is located in a constantly attended location.

Where detection is provided for the protection of safety-related or FS SD equipment, Class A, four wire, supervised circuits link the fire detectors to the local control panels.

A status change generally results in the following system responses:

1.

Audible and visual annunciation by the computerized multiplex central control equipment. This annunciation includes identification of the zone/area alarm panel location and the time of receipt of the status change on a cathode ray tube (CRT) and a printer. Trouble indication is for the panel only. The local panel provides further details on the alarm condition.

2."

Illumination of indicating lamps on the local control panel indicating the status change.

3.

Actuation of local control panel circuits for the control of automatic suppression systems, fire pumps, fire dampers, or ventilation equipment as appropriate for selected alarm status changes.

4.

An alarm status change can be reset at the local control panel. Local control panel reset, in safety related areas, can also be achieved through the computerized multiplex central control equipment.

A redundant printer is located in the Unit 2 Auxiliary Instrument Room.

The fire detection system for safety-related areas is comprised of different types of devices, components, or parts that provide the system functions of detection, annunciation', and/or activation of automatic suppression systems. The devices used are:

I.

Smoke Detectors

a.

Ionization

b.

Photoelectric

2.

Thermal Detectors The thermal detectors are the rate compensation/fixed temperature type and are self restoring. They have temperature ratings appropriate for the area environment. Protecto-wire has been added to the cable trays in selected areas of the 480VAC Shutdown Board Rooms. This thermal detector is not self restoring.

3.

Air Duct Detectors The air duct detectors are specifically designed to sense the presence of smoke or combustion 11-31

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 products in HVAC ducts.

4.

Monitoring Devices The fire detection system utilizes the following devices to monitor the fire suppression systems status.

a. Pressure Switch - piping integrity

b. Pressure Switch - for water flow

c. Pressure Switch - C0 2 discharge

d. Relay contacts - C0 2 abort and disablement

5.

Manual Pull Stations

6.

Power Supply Two sources of 120V AC power are provided to the portion of the fire detection system protecting the safety-related equipment. The primary power supply is from Class 1E power sources with a high degree of reliability and adequate capacity for the intended service. The standby power is from the diesel generator.

Electrical isolation is provided between the fire detection system and the Class 1E power source from which it is supplied.

12.6 Liahtnin2 Protection The basic principle to protecting life and property from damage or loss due to lightning is to provide a direct low impedance path for the lightning to travel to ground rather than through structures and/or equipment.

The lightning protection system consists of three basic parts which provide the low impedance path:

1.

The air terminals on roofs and other elevated locations.

2.

The ground grid.

3.

The conductors connecting the air terminals to the ground grid.

12.7 Emerzency Liehting See Part V.

12.8 Communications There are several means of communication available to Operations staff such as telephones; code, alarm, and paging; sound powered phones; and two-way radios. The in-plant radio repeater system will be the primary means of communication for performing manual actions and for the fire brigade use.

The in-plant radio repeater system consists of multiple VHF radio repeaters, remote control units, portable radios, and redundant antenna systems.

A sound powered phone system connects the auxiliary control room and various local control stations to 11-32

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 supplement the VHF radio during alternative shutdown.

12.9 Reactor Coolant Pump Oil Collection See Part V.

12.10 Fire-Rated Assemblies Fire rated assemblies at SQN are part of the passive fire protection features which ensure that the function of one set of redundant fire safe shutdown components necessary to achieve and maintain FSSD remains free of fire damage. Fire rated assemblies consist of fire barriers, Electrical Raceway Fire Barrier Systems (ERFBS), equipment hatches and stairwells, fire doors, fire dampers, radiant energy shields, penetration seals, walls, floors, and ceilings. Fire barriers and fire doors are identified on the compartmentation drawings in Part X of the FPR.

12.10.1 Walls, Floors, and Ceilings Fire areas are separated by 1.0, 1.5-or 3-hour equivalent fire barriers that are bounded by UL rated designs or equivalent. Rooms within each fire area may be separated from other rooms in the same area by FSSD or non-FSSD fire barriers. Where fire barriers are used to separate rooms in the same area, the barriers have equivalent 1.0 or 1.5-hour fire ratings. If the FSSD separation between rooms in the same fire area is less than

+._,

3-hour, then automatic suppression and detection systems are provided or deviations justified (see Part VII for the discussion of deviations and evaluations).

12.10.2 Raceway Protection Cable raceways that require separation by Electrical Raceway Fire Barrier Systems (ERFBS) are provided with one-hour rated ERFBS (subject to Thermo-Lag upgrade and deviation request) and automatic suppression and detection in the area (except as allowed by approved deviations). Inside the reactor building, which includes primary containment and secondary containment (i e., annulus), a combination of radiant energy shields and automatic detection and suppression are used to obtain separation where fire could potentially damage redundant safe shutdown components.

12.10.3 Equipment Hatches and Stairwell Equipment hatches in floor or ceiling fire barriers fall into three categories:

a)

Pre-cast concrete plugs which overlap mating surfaces for support - These plugs are usually associated with radiation shielding and provide a fire barrier equivalent to the floor or ceiling in which they are located.

b)

Steel covers that overlap mating surfaces for support -These covers are of substantial construction and provide an effective barrier to prevent fire from propagating from one side of the barrier to the other.

However, since they are not fire rated, they are either provided with a fire barrier coating, evaluated in accordance with GE 86-10, or redundant safe shutdown components on either side have been separated from each other by a cumulative horizontal distance of 20 or more 11-33

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 feet. In either case, automatic fire suppression and detection are provided on both sides of the equipment hatch cover, if appropriate, or an engineering evaluation has been performed.

See Part VII for justifications of deviations and/or evaluations.

c)

Open hatches and stairwells - Redundant safe shutdown components located on each side of the opening have been identified. If separated by less than a cumulative distance of 20 feet horizontally, either the hatch/stairwell has been provided with a water curtain to separate elevations, or a one hour fire barrier has been provided on the cables for one of the redundant paths. In either case automatic fire suppression and detection has been provided on both sides of the opening, except for the refueling area and the 653 ft elevation of the Auxiliary Building. See Part VII for justifications for deviations and/or evaluations.

12.10.4 Fire Doors Fire door assemblies (doors, frames, and hardware) are generally provided in door openings in required fire barriers. These assemblies are UL listed as either "A" label (3-hour rated) or "B" label (1-1/2 hour rated).

"A" label doors are provided in 3-hour or less rated fire barriers and "B" label doors are provided in barriers that require a 2-hour or less fire rating.

Sliding fire doors are provided in selected locations. These sliding fire doors are closed by heat melting a fusible link and in selected CO2 protected areas, a CO2 system pressure-activated, or electrical release, or a combination of both.

In some cases, such as air lock doors, equipment doors, submarine type doors, etc., the doors cannot be purchased as labeled fire doors. These doors have been evaluated by a Fire Protection Engineer for their ability to prevent the propagation of a fire. These evaluations are documented in Part VII, Deviations, or in other Engineering documentation.

Modifications to fire doors must be within accepted criteria or approved by a Fire Protection Engineer.

Fire doors can be repaired under defined criteria and with the approval of the Fire Protection Engineer through the design output process.

12.10.5 Fire Dampers Fire dampers are normally provided in fire barriers and in HVAC ducts that penetrate required fire barriers to prevent the propagation of a fire through the barrier. Some duct penetrations, shown on the compartmentation drawings as unprotected openings without dampers, have been evaluated as acceptable barrier openings, acceptable partial barriers, or equivalent fire barriers. In some cases, the fire damper is also used to isolate an area prior to CO2 discharge. Fire dampers are provided with appropriately rated fusible links based on

-the ambient temperatures in the location.

Some dampers are also supplied with electro - thermo links (ETL) that are electrically activated in response to a signal from the fire detection system. The fire dampers provided with CO2 suppression system isolation capability are actuated by CO 2 system pressure activated release mechanism and/or by thermal link.

Fire dampers in safety-related HVAC systems may have double fusible links installed if required by a single failure analysis.

11-34

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 12.10.6 Penetration Seals When plant commodities (i.e., pipe, cable trays, conduits, etc.) must pass through required fire barriers, the openings are provided with seals that meet or exceed the fire protection requirements of the barrier. The majority of mechanical and electrical penetration seals used at Sequoyah have been bounded by fire tests. For the remaining population of penetration seals, evaluations have been performed in accordance with USNRC Generic Letter 86-10 to determine the acceptability of the seals in their "as-built" configuration. The fire protection design basis for the penetration seal program is contained in Reference 4.2.9, System Description Document N2 302-400, "Penetration Seals" (formerly issued as "SQN Penetration Seal Program Assessment Report, No. 0006 00902-01"). The system description provides-verification of conformance to the required standards for each of the fire endurance tests used to qualify the penetration seals; schematics and evaluations for the limiting parameters of each typical detail; and general discussions of pertinent penetration seal issues.

In addition to fire protection capabilities, some penetration seals may be required to meet other plant design bases requirements such as radiation shielding, HVAC pressure differential, and/or flood.

12.10.6.1 Electrical Penetrations Conduit penetrations typically require only internal seals since most conduit penetrations were poured-in place during plant construction. Internal seal materials, design, and locations in walls and floor/ceiling assemblies have been evaluated as equiyalent to tested configurations. If a conduit requires an external seal (e.g., the conduit passed through a sleeve larger than the conduit), the external seal will meet the same criteria as stated in the above paragraph. The criteria for internal conduit seals are provided by site-specific drawings.

11-35

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 13.0 FIRE PROTECTION SYSTEM IMPAIRMENTS AND COMPENSATORY ACTIONS Fire protection impairments are controlled to maximize the availability of the active and passive fire protection systems and features. Fire protection systems and features are intended to remain fully operational to the maximum extent possible. However, it is expected that outages or impairments will occur to support plant or fire protection-related modifications or maintenance.

Compensatory actions for impaired fire protection systems are defined in the applicable sections of this plan. When fire watches are assigned as compensatory measurers for fire protection systems or features, their principle purpose/responsibilities are to:

1.

Detect fire or conditions of potential fire (i.e. smoke, flames, etc.).

2.

Communicate observation of detected fire or conditions of potential fire to the control room.

3.

Notify personnel in the immediate area of the fire to evacuate the immediate area, if time permits.

Alternate compensatory actions for fire watch such closed circuit television may be utilized on a case by' case basis. This alternative action is considered when the primary methods create further hazards or represent personnel safety concerns.

A summary of each of these primary and alternate compensatory actions are as follows:

A.

Fire Watch - Continuous (Primary)

A continuous fire watch is required when the potential exists for a single fire to damage redundant trains of the minimum fire safe shutdown (FSSD) equipment necessary to achieve and maintain cold shutdown conditions in the event of a fire. 10CFR Appendix R, Section mI G. 1 states: "Fire protection features shall be provided for stmctures, systems and components important to safe shutdown. These features shall be capable of limiting fire damage so that:

a. One train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station(s) is free of fire damage; and

b. Systems necessary to achieve and maintain cold shutdown from either the control room or emergency control station(s) can be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />."

A single fire is a fire that is postulated to occur in any plant area that is separated from other plant areas by boundary fire barriers or substantial spatial separation. Each area of the plant is assigned a fire area or fire zone designation such as FAA-1, FAA-2, FAC-1, FAC-2, etc. As an example, a fire is postulated to occur in FAA-1 or FAA-2 but not in FAA-1 and FAA-2 simultaneously.

The fire areas/zones are separated from each other by minimum 1-1/2 hour fire rated boundaries, with approved deviations, or in some cases, substantial spatial separation such as between the Auxiliary Building and the CCW Pump Station or the ERCW Pump Station. Therefore, an hourly fire watch is considered adequate detection capability to prevent an otherwise undetected fire from breaching the boundary fire barriers and spreading to an adjacent fire area/zone where redundant FSSD equipment may be located.

11-36

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 When redundant trains of FSSD equipment are located within the same fire area/zone the protection that has generally been provided is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rated Thermo-Lag Electrical Raceway Fire Barrier Systems (ERFBS), or a minimum of 20 feet of horizontal separation with no intervening combustibles, and an automatic fire detection and suppression system. Other protection arrangements for redundant FSSD equipment located in the same fire area/zone are described in approved deviations to IOCFR50 Appendix R requirements (i.e. Counting Room). In all of these cases, an hourly fire watch is not considered adequate detection capability to prevent an otherwise undetected fire from damaging both trains of redundant FSSD equipment.

A continuous fire watch requires that individual(s) inspect the specified area at least once every 15 minutes with a margin of 5 minutes.

B.

Fire Watch - Roving (Primary)

All hourly fire watch patrols require that a trained individual be in the specified area at intervals of 60 minutes with a margin of 15 minutes.

C.

Closed Circuit Television -CCTV (Altemative)

CCTV equipment consists of CCTV cameras and monitors. Cameras may be placed in more than one room or more than one elevation of the plant. CCTV systems are similar to the ones used by other utilities for monitoring of inoperable fire barriers as well as CCTVs previously utilized at Browns Ferry Nuclear Plant in inaccessible tunnels. An evaluation will be performed by the plant fire protection staff and documented with the impairment process (appropriate administrative process) or work initiation document for use of CCTV equipment (cameras and monitors) to demonstrate technical equivalency to standard compensatory actions identified in Section 14, "Fire Protection Systems and Features Operating Requirements (OR)."

CCTV monitors are monitored by trained personnel at a frequency consistent with standard compensatory actions identified in Section 14, "Fire Protection Systems and Features Operating Requirements (OR)." CCTV is used in instances where conditions may present risks to personal safety, operational conditions in high heat areas such as the main steam vault, or ALARA concerns in high radiation areas preclude using a human fire watch in the area.

D.

Procedural Controls (Strict Administrative Measures)

Procedural controls as discussed in GL 91-18 may be utilized as compensatory measures to require immediate actions to be taken to restore a system or feature back to OPERABLE status in the event of a fire emergency in an affected area. These controls will further require strict administrative measures to ensure the system or feature is not left unattended unless either the system or feature is restored back to operable status or a fire watch is established. In the event procedural controls are utilized as compensatory measures, an evaluation will be performed by the plant fire protection staff and documented as part of the affected procedure change and revision process.

11-37

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 The evaluation will demonstrate the technical equivalency to standard compensatory actions identified in Section 14, Fire Protection Systems and Features Operating Requirements (OR).

11-38

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN SECTION 14.0 - OPERATING REQUIREMENTS TABLE OF CONTENTS 11-39 Rev. 10 Associated SECTION FOR SR Table Section 14.1 - FIRE DETECTION INSTRUMENTATION 3.3.3.8 4.3.3.8 3.3-11 Section 14.2 - FIRE SUPPRESSION WATER 3.7.11.1 4.7.11.1 N/A SYSTEM Section 14 SPRAY AND/OR SPRINKLER 3.7.11.2 4.7.11.2 N/A SYSTEMS Section 14.4 - C0 2 SYSTEMS 3.7.11.3 4.7.11.3 N/A Section 14.5 - FIRE HOSE STATIONS 3.7.11.4 4.7.11.4 3.7-5 Section 14.6 - FIRE BARRIER PENETRATIONS 3.7.12 4.7.12 N/A Section 14.7 - EMERGENCY BATTERY LIGHTING 3.7.14 4.7.14 N/A UNITS

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.0 FIRE PROTECTION SYSTEMS AND FEATURES OPERATING REQUIREMENTS (OR) AND SURVEILLANCE REQUIREMENTS (SR)

The OR established in this section have been developed to ensure adequate fire protection capability is available and maintained, to detect, control, and extinguish fires occurring in any portion of the plant where safety-related or Fire Safe Shutdown (FSSD) equipment are located. Calculation SQN-SQS2-203, "Evaluation of Fire Safe Shutdown Equipment for IE Notice 97-048," addresses equipment required for FSSD which is not bounded by existing Technical Specifications. Since these components are not fire protection equipment, they are also not controlled by an existing FOR-Based on a review of each component determined to be required for FSSD, the calculation determines that the FSSD equipment not covered through existing Surveillance Instructions is equipment essential for normal operation of the plant, and as such, receives high priority for maintenance and return to operable status, which will ensure that they are available for FSSD purposes.

Fire protection systems and features at SQN are not assumed to be operable to mitigate the consequences of a Design Basis Accident (DBA) or plant transient in conjunction with a fire. The bases for this assumption are contained in Section I of Appendix R which states that the need to limit fire damage to systems required to achieve and maintain FSSD conditions is greater than the need to limit fire damage to those systems required to mitigate the consequences of DBAs. As a result, Section L of I OCFR5 0, Appendix R, identifies that fire protection features must be capable of limiting fire damage so that:

1.

One train of systems necessary to achieve and maintain hot shutdown conditions from either the control room, auxiliary control room, or emergency control stations is free of fire damage; and

2.

Systems necessary to achieve and maintain cold shutdown from either the control room, auxiliary control room, or emergency control stations can be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

3.

Alternate shutdown capability is provided when needed to achieve and maintain cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Testing of the fire protection systems involve manually disabling portions of them to prevent unwanted responses. These responses can be in the form of excessive starting of pumps, discharging water in a radiologically controlled area, excessive alarming of devices/components, and undesirable actuation of systems/components. In many cases when test personnel are actively performing the test (system under control of test performers), compensatory measures (i.e., fire watches) will not be required. The test personnel may be credited for returning the system under test to normal operational alignment in the event of a fire that would require the system to function. These situations are controlled by the procedure governing the test or by other administrative controls established for the performance of the test. Factors considered in determining when test personnel may be credited for manual action to restore a system to operational status include ability of test personnel to recognize input signals, communications between test personnel, and timing required to restore the system to functional status.

11-40

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.0.1 Compliance with the Operating Requirements (OR) contained in the succeeding Specifications is required during the APPLICABILITY or other conditions specified therein, except that upon failure to meet the Limiting Conditions for Operations, the associated ACTION requirements shall be met.

14.0.2 Noncompliance with a Specification shall exist when the requirements of the Operating Requirements (OR) and associated ACTION requirements are not met within the specified time intervals. If the OR is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

14.0.3 Entry into an OPERATIONAL MODE or other specified condition may be made with reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION requirements.

14.0.4 When a system, subsystem, train, component or devise is determined to be inoperable solely because its emergency power source in inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE forthe purpose of satisfying the requirements of its applicable Limiting Condition of Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s), trains(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this Specification.

14.0.5 Surveillance Requirements (SR) shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operations unless otherwise stated in an individual SR.

14.0.6 Each SR shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed twenty-five percent (25%) of the specified surveillance interval.

14.0.7 Failure to perform a SR within the allowed surveillance interval, defined by Section 14.0.5, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition of Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a SR has not been performed. The ACTION requirements may be delayed for up to twenty-four (24) hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less'than twenty-four (24) hours. SR's do not have f6 be performed on inoperable equipment.

11-41

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.1 FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.*

ACTION:

a. With the alarm function associated with the fire detection instruments INOPERABLE:

1. For areas other than Primary Containment:

a.

For fire detection instrumentation that is associated with fire suppression systems required to be OPERABLE per LCO 3.7.11.2 or 3.7.11.3, within one hour establish a continuous fire watch in areas where redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b. For fire detection instrumentation that is not associated with fire suppression systems required to be OPERABLE per Section 3.7.11.2 or 3.7.11.3, within one hour establish an hourly fire watch patrol.

c.

Restore the inoperable instrument(s) to OPERABLE status within 14 days. If not restored to OPERABLE within 14 days, perform corrective action/reportability reviews in accordance with site administrative procedures.

2.

For inoperable equipment inside Primary Containment, restore the inoperable instrument(s) to OPERABLE status within 14 days If not restored to OPERABLE within 14 days, perform corrective action/reportability reviews in accordance with site administrative procedures.

b.

With the automatic suppression system actuation function of the fire detection instrumentation INOPERABLE, enter the applicable LCO of Section 3.7.11 2 and/or 3.7.11.3 for those automatic suppression systems with no automatic actuation available

c.

If the circuit supervision verified by SR 4.3.3.8.2 fails or a loop failure trouble is annunciated, correct the problem within 14 days. If not corrected within 14 days, perform corrective action/reportability reviews in accordance with site administrative procedures.

SURVEILLANCE REQUIREMENTS (SR) 4.3.3.8.1 Each of the above required fire detection instruments which are accessible and do not require removing plant equipment from service shall be demonstrated OPERABLE at least once per 12 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detection instruments which are not accessible or which require removing plant equipment from service during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.

4.3.3.8.2 The supervision of the circuits between required local panels and the alarm receiving console shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.8.3 Each zone serving required fire detection instruments(s) and the non-supervised circuits between the local fire protection panels and actuated fire suppression equipment shall be demonstrated OPERABLE at least once per 6 months.

The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

11-42

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE Rev. 10 "FIRE PHOTO ZONE INSTRUMENT LOCATION IONIZATION ELECTRIC THERMAL INFRARED 1

Diesel Gen Rm. 2B-B, El. 722 5

2 Diesel Gen. Rm. 2B-B, El. 722 5

3 Diesel Gem Rim lB-B, El. 722 5

4 Diesel Gen Rm. lB-B, El. 722 5

5 Diesel Gem. Rm. 2A-A, El. 722 5

6 Diesel Gem Rm. 2A-A, El. 722 5

7 Diesel Gem Rm. lA-A, El. 722 5

8 Diesel Gem Rm. lA-A, El. 722 5

9 Lube Oil Storage Rm. El. 722 1

10 Lube Oil Storage PRm El. 722 1

11 Fuel Oil Transfer Pan. El. 722 1

12 Fuel Oil Transfer Rm El. 722 1

13 Diesel Gen Corridor, El. 722 6

14 Air Intake & Exhaust Rm 2B, E1. 740.5 9

15 Airlntake & Exhaust Rm. 11, El. 740.5 9

16 Air Intake& Exhaust Rm 2A, El. 740.5 9

17 Air Intake & Exhaust PRm. IA, El. 740.5 9

18 Diesel Gen. 2B-B Relay Bd., El. 722 3

19 Diesel Gen. lB-B Relay Bd., El. 722 3

20 Diesel Gen. 2A-A Relay Bd, El. 722 3

21 Diesel Gen. lA-A Relay Bd., El. 722 3

22 Diesel Gen. Bd. Rm. 2B-B, El. 740.5 2

23 Diesel Gem Bd. Rm. 2B-B, El. 740.5 2

24 Diesel Gem Bd. PRm. lB-B, El. 740.5 2

25 Diesel Gen. Bd. Rm. lB-B, El. 740.5 2

26 Diesel Gen. Bd Rrm 2A-A, El. 740.5 2

27 Diesel Gem Bd Ram. 2A-A, El. 740 5 2

28 Diesel Gem. Bd Rm. lA-A, El. 740.5 2

29 Diesel Gen. Bd Rm. lA-A, El. 740.5 2

30 Cable Spreading RPn. C7-Cll, El. 706 14 31 Cable Spreading Rm. C7-Cll, El. 706 14 32 Cable Spreading Rm. C7-C11, El. 706 14 33 Cable Spreading PRm. C7-C11, El. 706 14 34 Cable Spreading Rm. C3-C7, El. 706 14 35 Cable Spreading Pn.m C3-C7, El. 706 14 39 Cont Spray Pump IA-A, El. 653 2

40 Cont. Spray Pump lB-B, El. 653 2

41 Cont. Spray Pump 2A-A, El. 653 2

42 Cont. Spray Pump 2B-B, El. 653 2

43 RHR Pump 1A-A, El. 653 2

44 RHR Pump 1B-B, El. 653 2

45 RHR Pump 2A-A, El. 653 2

46 RHP Pump 2B-B, El. 653 2

47 Aux. Bldg. Corridor, El. 653 10 48 Corridor, Control Bldg El. 669 4

11-43

SQN FIRE PROTECTION REPORT PART Il - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE I

1 I

T 1N'TRITMENT I C) CATION IONIZATION PHOTO ELECTRIC THERMAL Rev. 10 INFRARED 49 Corridor, Control Bldg. El. 669 4

50 Mech. Equip. Rm. Col. Cl, El. 669 2

51 Mech. Equip. Rm. Col. Cl, El. 669 2

52 Mechl Equip. Rm. Col. C3, El. 669 2

53 Mech. Equip. Rm. Col. C3, El. 669 2

54 250-V Batt. Rm. 1, El. 669 3

55 250-V Batt. Rm 1, El. 669 3

56 250-V Batt. Bd. Rm. 1, El. 669 2

57 250-V Batt. Bd. Rm. 1, El. 669 2

58 250-V Batt. Bd. Rm. 2, El. 669 2

59 250-V Batt. Bd. Rm. 2, El. 669 2

60 250-V Batt. Rm. 2, El. 669 3

61 250-V Batt. Rm. 2, El. 669 3

62 24-V & 48-V Batt. Rm. El. 669 3

63 24-V & 48-V Batt. Rm. El. 669 3

64 24-V & 48-V Batt. Bd. Rm., El. 669 2

65 24-V & 48-V Batt. Bd. Rm., El. 669 2

66 Communications Rm. El. 669 4

67 Communications Rm. El. 669 4

68 Mech. Equip. Rnm El. 669 2

S...

tL Mk,"*h Fa~ni, Pm T.1 f69 70 Aux. Bldg. A5-Al, CoL.W-X, El. 669 5

71 Aux. Bldg. A5-All, CoL.W-X, El. 669 5

72 Aux. FW Pump Turbine 1A-S, El. 669 1

73 Aux. FW Pump Turbine l A-S, El. 669 1

74 Aux. FW Pump Turbine 2A-S, El. 669 1

75 Aux. FW Pump Turbine 2A-S, El. 669 1

76 S. I. & Charging Pump PRns. El 669 5

77 S. 1. Pump Rm. 1A, El. 669 1

78 S.I. Pump Rm. 1B, El. 669 1

79 Charging Pump Rm. 1C, El. 669 1

-80 Charging Pump Rm. 1B, El. 669 1

81 Charging Pump Rm. 1A, El 669 1

82 S. I. & Charging Pump Rms. El. 669 5

83 S. I. Pump Rm. 2A, El. 669 1

84 S.I. Pump Rm. 2B, El. 669 1

85 Charging Pump Rm. 2A, El. 669 1

86 Charging Pump Rm. 2B, El. 669 1

87 Charging Pump Rm. 2C, El. 669" 1

88 Aux. Bldg. Corridor Al-A8, El. 669 8

89 Aux-Bldg. Corridor Al-A8, El. 669 8

90 Aux. Bldg. Corridor A8-A15, El. 669 8

91 Aux. Bldg. Corridor A8-A15, El. 669 8

92 Aux. Bldg. Corridor Col. U-W, El. 669 4

93 Aux. Bldg. Corridor Col. U-W, El. 669 4

11-44 FIRE

'AVNTr

,-

I

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE r

T T

I m1TDTT1jrVTT T Ar' ATTATJ TO'NI7AT ATIrN PHOTO EI,FC'TRIC THERMAL Rev. 10 INFRARED 94 Valve Galley, El. 669 2

95 Valve Galley, El. 669 2

96 U/2 Valve Galley, El. 669 2

97 U/2 Valve Galley, El. 669 2

98 U/i Cntmt Purge Air Fltr., El. 690 2

2 99 U/1 Cntmt Purge Air Fltr., El. 690 2

2 100 U/2 Cntmt Purge Air Fltr., El. 690 2

2 101 U/2 Cntmt Purge Air Fltr. El. 690 2

2 102 U/1 Pipe Gallery, El. 690 4

103 U/1 Pipe Gallery, El. 690 4

104 U/2 Pipe Gallery, El. 690 4

105 U/2 Pipe Gallery, El 690 4

106 Aux. Bldg., El. 690 8

107 Aux. Bldg., El. 690 8

108 Radio Chemical Lab. Area, El. 690 3

109 Radio Chemical Lab. Area, El. 690 3

110 Aux. Bldg. A1-A8, Col. Q-U, El. 690 10 111 Aux. Bldg. Al-A8, Col. Q-U, El. 690 10 112 Aux. Bldg. A8-A15, Col. Q-U, El. 690 9

113 Aux. Bldg. AS-A15, Col. Q-U, El. 690 9

1 114 Waste Pkg. Area, El. 706 3

" 115 Waste Pkg. Area El. 706 3

116 Cask Loading Area El. 706 4

117 Cask Loading Area El. 706 4

118 New Fuel Storage Area El. 706 2

119 New Fuel Storage Area El. 706 2

120 Aux. Bldg. Gas Trtmt. Fltr. El. 714 1

1 121 Aux. Bldg. Gas Trtmt. Fltr. El. 714 1

1 122 Add Eqpt. Bldg, El. 706 & 717.5 6

123 Volume Cont. Tank Rm. 1A, El. 690 1

1 124 Additional Equip. Bldg. El. 706 6

125 Volume Cont. Tank Rm. IA, El. 690 1

1 126 ABGTS Rm. El. 714 2

127 ABGTS Rm. El. 714 2

128 ABGTS Rm. El. 714 2

129 ABGTS Rm. El. 714 2

130 Ventilation & Purge Air Rm El. 714 3

131 Ventilation & Purge Air Rm. El. 714 3

132 Ventilation & Purge Air Rm. El. 714 3

133 Ventilation & Purge Air Rm. El. 714 3

134 Aux. Bldg. A5-All, Col. U-W, El. 714 7

135 Aux. Bldg. A5-A1l, Col. U-W, El. 714 7

136 Heating & Vent Rm-El. 714 4

137 Heating & Vent. Rm. El. 714 4

lqR T-bqtincrR'Vpnt Rm Fl 714 4

11-45 FIRE 1 115Z 14-ab

&Vent Rm El 714

SQN FIRE PROTECTION REPORT PART Il - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE

-FIRE ZONE 7

7 1

1 INSTRUMENT LOCATION IONIZATION PHOTO ELECTRIC THERMAL Rev. 10 INFRARED 139 Heating & Vent. Rm. El. 714 5

140 Above Hot Instr. Rm. El. 714 1

141 Above Hot Instr. Rm. El. 714 1

142 Aux. Bldg. Al-A8, Col. Q-U, El. 714 12 143 Aux. Bldg. A1-A8, Col. Q-U, El. 714 12 144 Aux. Bldg. A8-A15, Col. Q-U, El. 714 9

145 Aux. Bldg. A8-Al5, Col. Q-U, El. 714 9

146 N Storage Area, El. 706 4

2 147 ABGTS filter, El. 714 1

1 148 ABGTS Filter, El. 714 1

1 149 Cable Spreading Rm. C3-C7, El. 706 15 150 Cable Spreading Rm. C3-C7, El. 706 15 151 VCT Room 2A, EL. 690 1

1 152 VCT Room 2A, EL. 690 1

1 153 Add Eqpt. Bldg El. 740.5 4

154 Add. Eqpt. Bldg El. 740.5 6

155 Refuel Rm. El. 734 19 156 U/1 RB Access Rm. El. 734 2

157 U/I RB Access in. El. 734 2

158 U/2 RB Access Rm. El. 734 2

159 U/2 RB Access RPm. El. 734 2

160 SG Blwdn. Rm. El. 734 4

161 SG Blwdn. Rm. El. 734 4

162 EGTS Rm. El. 734 3

163 EGTS Rim El. 734 3

164 EGTS Fltr. A El. 734 1

2 165 EGTS Fltr. A El. 734 1

2 166 EGTS Fltr. B El. 734 1

2 167 EGTS Fltr. B El. 734

,2_,

1 2

172 Mech. Eqpt. Rm. El. 734 1

173 Mech. Eqpt. Rm. El. 734 1

174 Mech. Eqpt. Rm. El. 734 1

175 Mech. EqpL Rm. El. 734 1

176 480-V Shtdn. Bd. RPm. 1A1, El. 734 2

177 480-V Shtdn. Bd. Rm. lA1, El. 734 2

178 480-V Shtdn. Bd. PRm. 1A2, El. 734 2

179 480-V Shtdn. Bd. Rm. 1A2, El. 734 2

180 480-V Shtdn. Bd. Rm. IB1, El. 734 2

181 480-V Shtdn. Bd. RPm. 1B1 El. 734 2

182 480-V Shtdn. Bd. Rm. 1B2 El. 734 3

183 480-V Shtdn. Bd. Rm. 1B2 El. 734 3

184 6.9-KV Shtdn. Bd. Rm. A 7

185 6.9-KV Shtdn. Bd Rm. A 7

186 6.9-KV Shtdn. Bd. Rm. B 7

187.

6.9-KV Shtdn. Bd. RPm. B 7

11-46 J

SQN FIRE PROTECTION REPORT PART 1I - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE INSTRUMENT LO CATION IONIZATION PHOTO ELECTRIC

-T T

THERMAL INFRARED 188 480-V ShtdrL Bd. Rm. 2A1 El. 734 2

189 480-V Shtdn. Bd. Rm. 2A1 El. 734 2

190 480-V Shtdn Bd. Rm. 2A2 El. 734 3

191 480-V Shtdn. Bd. Rm. 2A2 El. 734 3

192 480-V Shtdn Bd. Rm. 2B1 El.734 2

193 480-V Shtdn. Bd. Rm. 2B1 El. 734 2

194 480-V Shtdn Bd. Rn. 2B2 El. 734 2

195 480-V Shtdn. Bd. Rm. 2B2 El. 734 2

196 125-V Batt. Bd. Rm. I El. 734 1

197 125-V Batt. Bd. Rm. I El. 734 1

198 125-V Batt. Bd. Rm. II El. 734 1

199 125-V Batt. Bd. RPn. 1I El. 734 1

200 125-V Batt. Bd. Rm. III El. 734 1

201 125-V Batt. Bd. Rm. III El. 734 1

202 125-V Batt. Bd Rm. IV El. 734 1

203 125-V Batt. Bd Rm. IV El. 734 1

204 Aux. CR El. 734 2

205 Aux. CR El. 734 2

206 Aux. CR Inst. Rm 1A El. 734 1

207 Aux. CR Inst. Rm. 1A El. 734 1

208 Aux. CR Inst. Rm. lB El. 734 1

209 Aux. CR Inst. Rm. 1B El. 734 1

210 Aux. CR Inst. Rm. 2A El. 734 1

211 Aux. CR Inst. Rn. 2A El. 734 1

212 Aux. CR Inst. Rm. 2B El. 734 1

213 Aux. CR Inst. Rm. 2B El. 734 1

214 Mech Eqpt. Rm. El. 732 5

215 Mech Eqpt. Rm. El. 732 5

216 CR Fltr. B El. 732 1

1 217 CRFltr. B El. 732 1

1 218 CR Fltr. A E1. 732 1

1 219 CR Fltr. A E1. 732 1

1 220 Main CR El. 732 25 221 Technical Support Center, El. 732 5

222 Technical Support Center, El. 732 5

225 Relay Bd. Rn. El. 732 13 226 Electric Cont. Bds. El. 732 11 227 Oper. Living Area El. 732 7

1 228 Oper. Living Area El. 732 8

229 Main Cont. Bds El. 732 9

230 Aux. CR Bds. L-4A, 4C, 11A & 10, El. 734 10 233 Ctrl. Rod Dr. Eqpt. Rm. El. 759 4

234 Ctrl. Rod Dr. Eqpt. Rm. El. 759 4

235 Ctrl. Rod Dr. EqpL Rm. El. 759 4

Ctrl. Rod Dr. Eant. Rm. El. 759 4

11-47 FIRE ZONE Rev. 10 236 23 Ctl Rod_______

Dr.

_____RmE_1._75

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE Rev. 10 FIRE PHOTO ZONE INSTRUMENT LOCATION IONIZATION ELECTRIC THERMAL INFRARED 237 Mech Eqpt. Rm. El. 749 1

238 Mech. Eqpt. Rm El. 749 1

239 Mech. Eqpt. Rrnm El. 749 2

240 Mech. Eqpt. Rm. El. 749 2

241 480-V XFMRRm. IA El. 749 3

242 480-VXFMR Rm. 1AEl. 749 3

243 480-VXFMRRm. 1B El. 749 3

244 480-VXFMRRm. 1B El. 749 3

245 480-VXFMR nRm 2AEl. 749 3

246 480-VXMFR Rm. 2A El. 749 3

247 480-VXMFRRm 2B El. 749 3

248 480-VXMFR Rm. 2B El. 749 3

249 125-V Batt. Rm. I El. 749 1

250 125-V Batt. Rm. I E1. 749 1

251 125-V Batt. Rm. II El. 749 1

252 125-V Batt. Rm. II E1. 749 1

253 125-V Batt. Rm. III El. 749 1

254 125-V Batt Rm. III El. 749 1

255 125-V Batt. Rm. IV El. 749 1

256 125-VBatt. Rm. IVE1. 749 1

480-V Bd. Rm. lB El. 749 4

258 1 480-lVTril Pm -R~ I 7t P IN

-7A0A 259 480-VBd Rm. 1AE1.749 4

260 480-VBd Rm. 1AEl.749 4

261 480-V Bd. Rm. 2A El. 749 4

262 480-V Bd. Rm 2A El. 749 4

263 480-V Bd. Rm. 2B El. 749 4

264 480-V Bd. Rm. 2B El. 749 4

267 Aux. Inst. Rm. El. 685 8

268-Aux. Inst. Rm. El. 685 4,.

4, 9

269 Computer Rm. El. 685 4

270 Computer Rm. El. 685 4

271 Aux. Instr. Rm. El. 685 8

272 Aux. Instr. Rm. El. 685 9

273 Computer Rm. Corridor 3

276 Intk. Pump Sta. El. 690 & 670.5 15 277 ERCW Pump Sta. El. 704 21 8

296 Aux. CR Bds. L-4B, 4D, & 11B, El. 734 6

297 Main Cont Bds.

9 298 Common Main CR Bds. El 732 9

330 U/i Reactor Building Annulus 3

331 U/I Reactor Building Annulus 4

332 U/2 Reactor Building Annulus 3

333 U/2 Reactor Building Annulus 4

Uill Lwr. Comat C ole El. 693 4

11-48 A

S -- 257 352

_ 1___

__4

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE Rev. 10 FIRE PHOTO ZONE INSTRUMENT LOCATION IONIZATION ELECTRIC THERMAL INFRARED 353 U/2 Lwr. Compt. Coolers, El. 693 4

354 U/i Upr. Compt. Coolers, El. 778 4

355 U/2 Upr. Compt. Coolers, El. 778 4

356 U/i RCP 2, El. 693 2

357 U/i RCP 2, El. 693 2

358 U/2 RCP 2, El. 693 2

359 U/2 RCP 2, El. 693 2

360 U/i RCP 1, El. 693 2

361 U/I RCP 1, El. 693 2

362 U/2 RCP 1, El. 693 2

363 U/2 RCP 1, El. 693 2

364 U/i RCP 3, El. 693 2

365 U/i RCP 3, El. 693 2

366 U/2 RCP 3, El. 693 2

367 U/2 RCP 3, El. 693 2

368 U/i RCP 4, El. 693 2

369 U/i RCP 4, El. 693 2

370 U/2 RCP 4, El. 693 2

371 U/2 RCP 4, El. 693 2

372 U/1Reactor Bldg. Annulus 22 373 U/i Reactor Bldg. Annulus 21 374 U/2 Reactor Bldg. Annulus 20 375 U/2 Reactor Bldg. Annulus 19 387 Turbine Cont. Bldg. Wall, El. 706 19 427 125V Batt. Rrn. VEl. 749 2

428 125V Batt. Rm. V El. 749 2

458 Counting Room Ceiling El. 690 2

462 480V Sd Bd Rm 182 El. 734 1

463 480V Sd Bd Rm 2A2 El. 734 1

-`t465 Counting Room Ceiling El. 690 2

466 480V Sd Bd Rm 1B2 El. 734 1

467 480V Sd Bd Rm 1B2 El. 734 1

468 480V Sd Bd Rm 182 El. 734 1

469 480V Sd Bd Rm 2A2 El. 734 1

470 480V Sd Bd Rm 2A2 El. 734 1

471 480V Sd Bd Rm 2A2 El. 734 1

520 Ul AB General Supply Duct, El. 714 1

521 U1 AB General Supply Duct, El. 714 1

522 U2 AB General Supply Duct, El. 714 1

523 U2 AB General Supply Duct, El. 714 1

545 Hot Tool Rm. El. 669 4

547 BAT Area Rm AO1, El. 690 2

548 BAT Area Rm. AO1, El. 690 2

600 U1 Post Accident Sampling Facility E1706.0 1

601 U I Post Accident Sampling Facility El 706.0 1

11-49 j

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.3-11 MINIMUM INSTRUMENTS OPERABLE FIRE PHOTO ZONE INSTRUMENT LOCATION IONIZATION ELECTRIC THERMAL INFRARED 602 U2 Post Accident Sampling Facility El 706.0 1

603 U2 Post Accident Sampling Facility El 706.0 1

11-50 Rev. 10

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14 2 FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire protection water supply system shall be OPERABLE with:

a.

Two fire pumps, each with a capacity of 1648 gpm at 130 psid, with suction aligned to the water storage tanks, and discharge aligned to the distribution piping.

b.

Two water storage tanks, each with a minimum contained volume of 300,000 gals, and

c.

An OPERABLE flow path from the water storage tanks through distribution piping, sectionalizing control or isolation valves, up to but not including the first valve off the loop header that isolate:

1. Spray and/or sprinkler systems required to be OPERABLE per Section 3.7.11.2

2.

Hose standpipes required to be OPERABLE per Section 3.7.11.4.

APPLICABILITY: At all times.

ACTION:

a.

With one pump and/or one water storage tank INOPERABLE, restore the inoperable equipment to OPERABLE status within seven (7) days, or perform corrective actions / reportability reviews in accordance with site administrative procedures outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an'alternate backup pump or supply.

b. With no fire pumps or no water storage tanks OPERABLE:

1. Establish a backup fire protection water supply system within twenty-four (24) hours and perform' corrective actions / reportability reviews in accordance with site administrative procedures.

2.

When ACTION 3.7.11..b. I cannot be met, 'within one (1) hour action shall be initiated to place the unit(s) in:

a.

At least HOT STANDBY within the next six (6) hours,

b.

At least HOT SHUTDOWN within the following six (6) hour-and

c.

At least COLD SHUTDOWN within the subsequent twenty-four (24) hours.

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION maybe taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

c.

With the fire suppression water system INOPERABLE for reasons other than loss of fire pumps or water storage tanks:

1. Enter the applicable LCO of Section 3.7.11.2 and/or 3.7.11.4 for those systems with no OPERABLE flow path available.

11-51

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14 2 FIRE SUPPRESSION WATER SYSTEM SURVEILLANCE REQUIREMENTS 4.7.11.1.1 The fire suppression water system shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying the contained water supply volume,

b.

At least once per 31 days by starting the electric motor-driven pump and operating it fcr at least 15 minutes,

c.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.

d.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

e.

At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and.

1.

Verifying that each fire pump develops at least 1648 gpm at a pump differential pressure head of 130 psig,

2.

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and

3.

Verifying that each fire pump starts automatically to maintain Fire Protection Water System pressure.

f.

At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

4.7.11.1.2 The diesel-driven fire pump system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1)

The fuel storage tank contains at least 50% full volume,

2)

The diesel starts from ambient conditions and operates for at least 30 minutes,

b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within acceptable limits when checked for viscosity and water and sediment, and

c.

At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

II-52

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 4.7.11.1.3 The diesel-driven fire pump starting 24-volt battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1)

The electrolyte level if each battery is above the plates, and

2)

The overall battery voltage is greater than or equal to 24 volts.

b.

At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery, and

c.

At least once per 18 months by verifying that:

1)

The batteries, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration, and

2)

The battery-to-battery and terminal connections are clean, tight, free of corrosion, and coated with anticorrosion material.

H-53

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.3 SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 The following spray and/or sprinkler systems shall be OPERABLE:

a.

Reactor Building -

RC pump area, Annulus

b.

Auxiliary Building -Elev. 669, 690, 706, 714, 734, 749, 759, ABGTS Filters, EGTS Filters, Cont. Purge Filters, and 125V Battery Rooms.

c.

Control Building - Elev. 669, Cable Spreading Room, MCR air filters, and operator living area.

d. Diesel Generator Building - Corridor Area.

e.

Turbine Building -

Control Building Wall.

APPLICABILITY: Whenever equipment protected by the spray/sprinkler system is required to be OPERABLE.

ACTION:

a. With one or more of the above required spray and/or sprinkler systems inoperable, within one hour, establish backup fire suppression.

b. Restore the system to OPERABLE status within fourteen (14) days. If not restored to OPERABLE within fourteen (14) days, perform corrective actions / reportablilty reviews in accordance with site administrative procedures.

SURVEILLANCE REQUIREMENTS 4.7.11.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path, excluding those valves in the Reactor Buildings, is in its correct position.

b.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

11-54

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14 3 SPRAY AND/OR SPRINKLER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c.

At least once per 18 months:

1.

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct positions on a cross zone or single zone detection test signal as designed, and b)

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

c)

Verifying that each valve (manual, power operated or automatic) in the flow path, located in the Reactor Buildings, is in its correct position.

2.

By visual inspection of the dry pipe, spray and sprinkler headers to verify their integrity, and

3.

By visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed 11-55

SQN FIRE PROTECTION REPORT PART H - FIRE PROTECTION PLAN Rev. 10 14.4 CO2 SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.3 The following low pressure C02 systems shall be OPERABLE.

a.

Computer Room.

b.

Auxiliary Instrument Room.

c.

Diesel Generator Rooms.

d.

Fuel Oil Pump Rooms.

e.

Diesel Generator Building Electrical Board Rooms.

APPLICABILITY: Whenever equipment protected by the C0 2 systems is required to be OPERABLE.

ACTION

a. With one or more of the above required CO 2 systems inoperable, within one hour, establish backup fire suppression.

b. Restore the system to OPERABLE status within fourteen (14) days. If not restored to OPERABLE within fourteen (14) days, perform corrective actions / reportablilty reviews in accordance with site administrative procedures.

SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the above required CO. systems shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.

4.7.11.3.2 Each of the above required low pressure CO2 systems shall be demonstrated OPERABLE:

I

a.

At least once per 7 days by verifying the CO. storage tank level to be greater than 50% and pressure to be greater than 270 psig, and

b.

At least once per 18 months by verifying:

1.

The system valves and associated ventilation dampers and fire door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and

2.

Flow from each nozzle during a "Puff Test."

11-56

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.5 FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to the unprotected area(s) from an OPERABLE hose station within one (1) hour if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within twenty-four (24) hours. Fire hoses for the hose stations shown in Sections (a) - (d) of Table 3.7-5 shall be attached by the Fire Brigade as needed, and are not required to be permanently installed at the hose stations. For all hose stations shown in Table 3.7-5, restore the inoperable fire hose station(s) to OPERABLE status within fourteen (14) days.

If not restored to OPERABLE within fourteen (14) days, perform corrective actions /

reportablilty reviews in accordance with site administrative procedures.

SURVEILLANCE REQUIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve in the flow path, excluding those valves located in the Reactor Building, is in its correct position.

b. At least once per 92 days by visual inspection of the stations accessible during plant operations, excluding those stations located in the Reactor Buildings, to assure all required equipment is at the station.

c. At least once per 12 months by cycling each testable valve in the flow path, excluding those valves located in the Reactor Buildings, through at least one complete cycle of full travel.

d. At least once per 18 months by;

1.

Visual inspection of the stations located in the Reactor Buildings to assure all required equipment is at the station,

2.

Removing the hose for inspection and re-racking,

3.

Inspecting all gaskets and replacing any degraded gaskets in the couplings,

4.

Verifying that each valve in the flow path, located in the Reactor Buildings, is in its correct

position,

5.

Cycling each valve in the flow path, that is inaccessible during normal plant operation and is located in the Reactor Buildings, through at least one complete cycle of full travel.

6.

Verifying that the automatic valves in the flow path actuate to their correct positions, as designed.

e. At least once per 3 years by:

1.

Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

11-57

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.7-5 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK#

a.

Unit 1 Reactor Building - Annulus Area Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform Platform 778.5 778.5 778.5 778.5 759.5 759.5 759.5 759.5 740.5 740.5 740.5 740.5 721.5 721.5 721.5 721.5 701.5 701.5 701.5 701.5 679.78 679.78 679.78 679.78 1-26-1196 1-26-1197 1-26-1198 1-26-1199 1-26-1200 1-26-1201 1-26-1202 1-26-1203 1-26-1204 1-26-1205 1-26-1206 1-26-1207 1-26-1208 1-26-1209 1-26-1210 1-26-1211 1-26-1212 1-26-1213 1-26-1214 1-26-1215 1-26-1216 1-26-1217 1-26-1218 1-26-1219

b.

Unit 1 Reactor Building - RCP & Lowe Containment Air Filters Area Reactor Building Reactor Building Reactor Building Reactor Building Reactor Building Reactor Building Rev. 10 679.78 679.78 679.78 679.78 679.78 679.78 1-26-1220 1-26-1221 1-26-1222 1-26-1223 1-26-1224 1-26-1225 11-58

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 TABLE 3.7-5 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK#

c.

Unit 2 Reactor Building - Annulus Area Platform 778.0 2-26-1196 Platform 778.0 2-26-1197 Platform 778.0 2-26-1198 Platform 778.0 2-26-1199 Platform 759.0 2-26-1200 Platform 759.0 2-26-1201 Platform 759.0 2-26-1202 Platform 759.0 2-26-1203 Platform 740.0 2-26-1204 Platform 740.0 2-26-1205 Platform 740.0 2-26-1206 Platform 740.0 2-26-1207 Platform 721.0 2-26-1208 Platform 721.0 2-26-1209 Platform 721.0 2-26-1210 Platform 721.0 2-26-1211 Platform 701.0 2-26-1212 Platform 701.0 2-26-1213 Platform 701.0 2-26-1214 Platform 701.0 2-26-1215 Platform.

679.78 2-26-1216 Platform 679.78 2-26-1217 Platform 679.78 2-26-1218 Platform 679.78 2-26-1219

d.

Unit 2 Reactor Building - RCP & Lowe-i Containm~kt Air Filters Area Reactor Building 679.78 2-26-1220 Reactor Building 679.78 2-26-1221 Reactor Building 679.78 2-26-1222 Reactor Building 679.78 2-26-1223 Reactor Building 679.78 2-26-1224 Reactor Building 679.78 2-26-1225 11-59

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 TABLE 3.7-5 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK#

e.

Control Building Control Building 732 0-26-1186 Control Building 732 0-26-1191 Control Building 706 0-26-1187 Control Building 706 0-26-1192 Control Building 685 0-26-1188 Control Building 685 0-26-1193 Control Building 669 0-26-1189 Control Building 669 0-26-1194

f.

Diesel Generator Building Corridor 722 0-26-1077 Corridor 740.5 0-26-1080 Air Exhaust Rmn.

740.5 0-26-1082 Lube Oil Storage Room 722.0-2 722 0-26-2337

g.

Additional Equipment Building - Unit 1 South Wall 740.5 1-26-687 South Wall 706 1-26-686

h.

Additional Equipment Building - Unit 2 North Wall 740.5 2-26-687 North Wall 706 2-26-686 11-60

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN TABLE 3.7-5 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK#

i.

Auxiliary Building 759 759 749 749 734 734 734 734 734 Siamese Outlet 734 Siamese Outlet 734 734 714 714 714 714 706 690 690 690 Siamese Outlet 690 Siamese Outlet 690 669 669 669 669 669 653 653 1-26-669 2-26-669 2-26-664 1-26-664 2-26-670 0-26-684 1-26-670 0-26-682 1-26-671 and 1-26-672 2-26-671 and 2-26-672 1-26-665 2-26-665 0-26-660 1-26-666 2-26-666 0-26-677 0-26-658 0-26-690 0-26-661 1-26-674 and 1-26-675 2-26-674 and 2-26-675 1-26-667 2-26-667 1-26-668 2-26-668 0-26-662 0-26-680 0-26-663 0-26-691

j. CCW Intake Pumping Station Rev. 10 690 690 690 690 690 0-26-866 0-26-867 0-26-868 0-26-869 0-26-870 11-61

SQN FIRE PROTECTION REPORT PART H - FIRE PROTECTION PLAN TABLE 3.7-5 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK#

k. ERCW Pumping Station Rev. 10 688 688 688 704 704 704 720 720 720 0-26-927 0-26-926 0-26-930 0-26-931 0-26-925 0-26-928 0-26-929 0-26-924 0-26-932 11-62

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.6 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.12 All fire barrier penetrations (including cable penetration barriers, fire doors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional.

APPLICABILITY: At all times.

ACTION:

NOTE: For ERFBS (e.g., Thermo-Lag, Kaowool, etc.) an hourly roving fire watch with OPERABLE detection in the affected area, or continuous fire watch with no OPERABLE detection in the affected area shall be maintained until upgrade work is complete as described in DCN's M 12743 & M-12744 (Thermo-Lag upgrade), and M-12745 & M-12746 (Kaowool replacement).

a.

With one or more of the required fire barrier penetrations non-functional, within one hour restore the inoperable equipment or

1. Establish a continuous fire watch on at least one side of the affected barrier, where there is NO OPERABLE fire detection on either side of the affected barrier, or

2. Verify the OPERABILITY of fire detection on one side of the non-functional fire barrier and establish an hourly fire watch, or

3. If fire detection is OPERABLE on both sides of the effected barrier, then no compensatory actions are required.

b.

Restore the non-functional fire barrier penetration(s) to functional status within 30 days. If not restored to OPERABLE within thirty (30) days, perform a review in accordance with the site corrective action procedures.

SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be functional:

a.

At least once per 18 months by a visual inspection

b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspection of the affected fire barrier penetration(s).

11-63

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 14.7 EMERGENCY BATTERY LIGHTING UNITS LIMITING CONDITION FOR OPERATION 3.7.14 Emergency battery lighting units provided for FSSD shall be OPERABLE.

APPLICABILITY: Modes 1, 2, 3 or 4 on the Unit with the illuminated FSSD equipment required to be OPERABLE.

ACTION:

a.

With any of the emergency battery lighting units provided for FSSD Inoperable, restore the Inoperable units to Operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or ensure alternate lighting is available.

b.

Restore the Inoperable emergency battery lighting unit to Operable status within 14 days. If not restored to OPERABLE within 14 days, perform a review in accordance with site corrective action programs.

SURVEILLANCE REQUIREMENTS 4.7.14 Each of the above required emergency battery lighting units (EBL) shall be verified to be functional:

a.

At least once per 92 days by performing a functional test and visual inspection of each EBL to verify proper operation and correct alignment of the lamps of the EBL as a unit by simulating a loss of power.

b.

Periodically replace batteries as a function of their service life, environmental condition and as a safety factor.

11-64

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 BASES 14.1 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

The fire detection system provides the ability to detect and alarm to a constantly attended location the presence of a fire, and in some instances to automatically actuate automatic fire suppression equipment. If the alarm function of the fire detection system is INOPERABLE, fire watches are required to be established to monitor the affected areas for fire conditions since this is the only means available to provide for detection and notification. If the automatic actuation of fire suppression equipment is INOPERABLE but the alarm function of the system remains OPERABLE it is appropriate to enter the LCO for INOPERABLE automatic suppression and provide a back up means of fire suppression. Fire watches are not specified in this case since the ability of the fire detection system to detect and alarm to a constantly attended location remains OPERABLE. If both the alarm funfction and the automatic actuation function of the system is INOPERABLE it is necessary to establish fire watches in accordance with the requirements of section 3.3.3.8 and to enter the applicable requirements of LCO 3.7.11.2 and/or LCO 3.7.11.3 and provide a back up means of fire suppression.

In cases where the fire detection alarm and notification function is INOPERABLE to a constantly attended location but remains OPERABLE at the local fire detection panels it is appropriate to establish the required fire watch compensatory measures either at the local fire detection panels or in the actual areas protected. In cases where the fire detection alarm and notification function is INOPERABLE at the local fire detection panel the required fire watch compensatory measures must be established in the areas protected.

Output from the fire detection system also provide for the automatic shutdown of selected plant fans/air movers and dampers. This output is beyond the scope of this LCO for the fire detection system since this automatic shutdown doesnot affect the operations of the system as exhibited by the annunciation of the associated fire detection equipment.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of continuous or roving fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. The fire watch requirements for inoperable attendant fire detection equipment are for a continuous fire watch in areas where redundant systems or components could be damaged and an hourly fire watch in areas where redundant systems or components could not be damaged. An hourly roving fire watch is required for inoperable detection equipment that is alarm only, and does not have associated automatic suppression equipment.

The compensatory actions described in LCO 3.3.3.8 for loss of detection inside primary containment differ from those for other areas due to radiological conditions and potential hazards inside containment..

11-65

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire detection instrumentation are met. All hourly fire watch patrols require that a trained individual be in the specified area at intervals of 60 minutes with a margin of 15 minutes.

A continuous fire watch requires that a trained individual be in the specified area at all times, that the specified area contain no impediment to restrict the movements of the continuous fire watch, and that each compartment within the specified area is patrolled at least once every 15 minutes with a margin of 5 minutes. A specified area for a continuous fire watch is one or more fire zones within a single fire area, which are easily accessible to each other and can be patrolled within 15 minutes. Easy access is defined as: no locked doors or inoperable card reader, no C-Zone entry required, or no hazards that will interfere with the continuous fire watch activity being performed within the 15-minute period.

The restoration time of 14 days is reasonable based on the compensatory actions required for inoperable equipment. During unit outages it will sometimes be necessary to remove equipment from service for longer than 14 days to support outage related activities. These impairments will be excluded from the corrective action program review requirements for exceeding the 14 day restoration time during unit outages. The Fire Protection Unit (FPU) will review all impairments and documentthe justification for extension past the 14 day restoration time when necessary to support unit outage activities. All other requirements associated with the ACTION statements of 3.3.3.8 shall remain applicable.

Plant equipment such as EGTS, ABGTS, CREVS and containment purge which must be removed from service for fire detector testing is performed on an 18 month frequency to minimize outages of the equipment and to allow detector testing to be performed concurrent with outages of the equipment for other testing.

The supervision testing required by surveillance requirement 4.3.3.8.2 is needed since multiple faults on the looped, class A supervised wiring between the local panels and the alarm receiving console may prevent annunciation of alarms from one or more local panels. The testing verifies loop failure is annunciated when a single open is created, verifies alarm receipt capability when a single open or ground fault is created and verifies loss of communications is annunciated when communications between the console and a local panel is lost. The 6 month testing frequency is based on standard technical specifications and is adequate given the class A supervision provided and the two levels of trouble annunciation provided-loop failure and loss of communications. LCO action 3.3.3.8 a is not required to be established if the testing required by the surveillance requirement fails or if a loop failure is annunciated-instead, LCO action 3.3.3.8c is implemented.

A loss of communications requires implementation of LCO action 3.3.3.8a for all required local panels which have lost communications with the alarm receiving console. Since any detector alarms will still be annunciated at the local panels, required fire watches may be posted at the local panels.

The testing of zones and unsupervised actuation circuits required by surveillance requirement 4.3.3.8.3 ensures zone alarm conditions simulated at the local panel results in the required detection system functions of alarm to a constantly attended location and, when required, actuation of required fire suppression equipment. The testing frequency for the zones is based on the code of record requirements and the potentially severe consequences of a zone module failure. The testing frequency for unsupervised actuation circuits is based on standard technical specifications.

11-66

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 BASES 14.2, 14.3, 14 4, 14.5 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO2, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

The fire protection water supply system consists of water storage tanks, pumps, and the necessary piping and valves to provide a flow path from the pumps to the end devices which consist of sprinkler/spray systems and hose standpipe systems. The water distribution system is looped to provide redundancy of the flow path. The closing of a single valve on the looped distribution piping will not cause the end device(s) to become inoperable. The closing of multiple valves in the looped distribution piping can completely isolate or degrade the flow path to the sprinkler/spray systems and the hose standpipe systems. When this situation occurs it is appropriate to enter the applicable LCO and comply with the action statement for the system(s) that is made inoperable by the condition.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.

The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met. For fire suppression equipment located in the Reactor Buildings, the surveillance frequency of once per 18 months (refueling outage) is supported by the limited accessibility of this equipment, historical data from previous performances, ALARA and Industrial Safety concerns and is considered adequate.

J.

In the event the fire suppression water system described by 3.7.11.1 becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

Reportability reviews/corrective actions performed in accordance with administrative procedures provides for prompt evaluation of the corrective measurers to ensure adequate fire suppression capability for the continued protection of the nuclear plant.

The restoration time of 14 days described by 3.7.11.2, 3.7.11.3, and 3.7.11.4 is reasonable based on the compensatory actions required for inoperable equipment. During unit outages it will sometimes be necessary to remove equipment from service for longer than 14 days to support outage related activities. These impairments will be excluded from the corrective action program review requirements for exceeding the 14 day restoration time during unit outages. The Fire Protection Unit (FPU) will review all impairments and document the justification for extension past the 14 day restoration time when necessary to support unit outage activities. All other requirements associated with the ACTION statements of 3.7.11.2, 3.7.11.3, and 3.7.11.4 shall remain applicable.

11-67

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 All hourly fire watch patrols require that a trained individual be in the specified area at intervals of 60 minutes with a margin of 15 minutes.

A continuous fire watch requires that a trained individual be in the specified area at all times, that the specified area contain no impediment to restrict the movements of the continuous fire watch, and that each compartment within the specified area is patrolled at least once every 15 minutes with a margin of 5 minutes.

A specified area for a continuous fire watch is one or more fire zones within a single fire area, which are easily accessible to each other and can be patrolled within 15 minutes. Easy access is defined as: no locked doors or inoperable card reader, no C-Zone entry required, or no hazards that will interfere with the continuous fire watch activity being performed within the 15-minute period.

Fire hoses in the Annulus and Containment areas for both units (Sections (a) - (d) of Table 3.7-5) are not required to be permanently installed at the hose stations. Surveillance Requirement 4.7.11.4 ensures that all equipment associated with the hose stations is operable. If necessary, Fire Brigade members can connect hoses to the hose stations connections using portable hose packs. Since plant personnel not specifically trained for fire fighting situations are instructed to immediately evacuate an area in which a fire occurs, and are not expected or desired to perform fire fighting activities, the absence of the hoses on the racks does not delay fire fighting measures. The removal of hoses from the Containment and Annulus areas is a good ALARA practice, since the hoses do not have to be removed and replaced every refueling outage, as well as a cost-effective measure due to expenses from contaminated waste removal, and costs due to equipment replacement.

11-68

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 BASES 14 6 FIRE BARRIER PENETRATIONS The functional integrity of the fire barrier penetrations ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetrations are a passive element in the facility fire protection program and are subject to periodic inspections.

Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered functional when the visually observed condition is the same as the as-designed condition. For those fire barrier penetrations that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.

During periods of time when a barrier is not functional, either: 1) A continuous fire watch is required to be maintained in the vicinity of the affected barrier (if there is NO OPERABLE detection on either side of the affected barrier); or 2) The fire detectors on one side of the affected barrier must be verified OPERABLE and a hourly fire watch patrol established, until the barrier is restored to functional status. In cases where there is OPERABLE detection on both sides of the affected barrier, no fire watch is required. A fire watch is required for detection and notification of a fire to ensure early response, and with operable detection on both sides of an affected barrier, the placement of fire watches provides no additional fire protection function.

For ERFBS (e.g., Thermo-Lag, Kaowool, etc.) an hourly roving fire watch with OPERABLE detection in the affected area, or continuous fire watch with no OPERABLE detection in the affected area shall be maintained until upgrade work is complete as described in DCN's M-12743 & M-12744 (Thermo-Lag upgrade), and M 12745 & M-12746 (Kaowool replacement).

All hourly fire watch patrols require that a trained individual be in the specified area at intervals of 60 minutes with a margin of 15 minutes.

A continuous fire watch requires that a trained individual be in the specified area at all times, that the specified area contain no impediment to restrict the movements of the continuous fire watch, and that each compartment within the specified area is patrolled at least once every 15 minutes with a margin of 5 minutes.

A specified area for a continuous fire watch is one or more fire zones within a single fire area, which are easily accessible to each other and can be patrolled within 15 minutes. Easy access is defined as: no locked doors or inoperable card reader, no C-Zone entry required, or no hazards that will interfere with the continuous fire watch activity being performed within the 15-minute period.

11-69

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 BASES 14.6 FIRE BARRIER PENETRATIONS (cont)

The completion time of 30 days affords adequate time for the various cure times for the different fire barrier materials, procedural requirements for time between stages when multiple stages of installation are required, and inspection and/or testing of the barrier materials. This completion time is reasonable, based on the compensatory actions for continuous fire watches, or those pertaining to fire-rated assemblies/fire barriers used in conjunction with other fire protection features, such as fire detection.

The completion time of 30 days affords adequate time for the various cure times for the different fire barrier materials, procedural requirements for time between stages when multiple stages of installation are required, and inspection and/or testing of the barrier materials. This completion time is reasonable, based on the compensatory actions for continuous fire watches, or those pertaining to fire-rated assemblies/fire barriers used in conjunction with other fire protection features, such as fire detection.

During unit outages it will sometimes be necessary to breach some of the fire barriers for longer than 30 days for plant personnel and equipment access purposes These breaches will be excluded from the corrective action program review requirements for exceeding the 30 day restoration time during unit outages. The Fire Protection Unit (FPU) will review all breached fire barriers and document the justification for extension past the 30 day restoration time when necessary to support unit outage activities. All other requirements associated with the ACTION statements of 3.7.12 shall remain applicable.

11-70

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 BASES 14 7 EMERGENCY BATTERY LIGHTING UNITS Emergency battery lighting (EBL) units are required to support a unit shutdown in the event of a fire and coincident loss of offsite power.

An ability to access and operate fire safe shutdown systems is required as well as the protection of such systems. These tasks must be capable of being performed in conjunction with the loss of offsite power. To achieve this, emergency battery lighting units with 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> lighting capacity are provided.

FOR 3.7.14 uses the term "alternate battery lighting" for a temporary substitute for installed emergency battery lighting units. This "alternate battery lighting" generally refers to portable, hand-held lighting as addressed in Part V, Section 2.0, "Emergency Lighting" of this report.

The restoration of the equipment to OPERABLE status in 14 days is reasonable based on the type of equipment that is out of service.

The Surveillance Requirements (SR) verify proper operation of EBL units by simulating a loss of power.

When manually actuated, normal AC power is interrupted to the EBL at the primary or secondary side of the step-down transformer. Thus, the EBL's ability to go from the float charge mode to the discharge mode is fully exercised. This functional test also demonstrates:

1) The EBL is configured for automatic operation and is not in the standby mode

2) The load transfer circuitry is functional

3) The lamps are functional

4) Continuity exists between the battery and all lamps

5) The battery is functional

6) The charging circuit is functional

7) The status indicators are functional A visual inspection to assess the general condition of the EBL, to detect obvious signs of degradation, and to detect any damage to the unit that may affect Operability is included. The visual inspection can identify degradation mechanisms at an early stage, and in many cases, can warn personnel of an impending failure.

Included is a visual inspection to identify electrolyte leakage, and for vented cells, to determine whether water addition is needed. Early detection of battery leakage allows battery replacement before the leakage results in complete battery failure or in severe damage to other EBL components. The inspection verifies proper alignment of the lamps (or in the case of multiple components the capability to be aligned) to ensure illumination of the fire safe shutdown equipment and/or access/egress paths.

The frequency of 92 days for EBLs is based upon vendor recommendations and industry practice.

11-71

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 The SR requires periodic battery replacement as a function of its service life, environmental conditions the battery will experience, and as a safety factor. The service life and the environmental factors are based on information from the manufacturer. This manufacturer's information plus the safety factor results in the frequencies as shown below:

Type of Battery Service Life Replacement I

(Years)

Frequency Sealed lead acid and calcium alloy 15 8

Solid gel 4

3 The replacement method is preferred since a periodic, deep discharge (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) test is not recommended by the manufacturer. The frequency and criteria is based on vendor recommendations 11-72

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN LIST OF FIGURES (All drawings will be current active version)

FPR Figure#

Figure II-1 Figure 11-2 Figure 11-3 Figure 11-4 Figure 11-5 Figure 11-6 Figure 11-7 Figure 11-8 Figure 11-9 Figure II-10 Figure II-1I Figure 11-12 Figure 1I-13 Figure II-14a Figure II-14b Figure II-14c Figure 11-15 Figure 11-16 Figure 11-17 Figure 11-18 Figure 11-19 Figure 11-20 TVA Drawing 1,2-47W850-1 1,2-47W850-2 1,2-47W850-3 1,2-47W850-4 1,2-47W850-5 1,2-47W850-6 1,2-47W850-7 1,2-47W850-8 1,2-47W850-9 1,2-47W850-10 1,2-47W850-11 1,2-47W850-12 1,2-47W850-20 1,2-47W850-24 1,2-47W850-26 1,2-47W850-27 1,2-47W843-1 1,2-47W843-2 1,247W610-26-1 1,2-47W610-26-2 1,2-47W611-26-1 1,2-47W611-26-2 11-73 Rev. 10 Title Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection and Flow Diagram Transformer Fire Protection System Flow Diagram Transformer, Yard & MWTP HPFP Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram Fire Protection Flow Diagram CO 2 Storage, Fire Protection and Purging System Flow Diagram CO 2 Storage and Fire Protection Mechanical Control Diagram High Pressure Fire Protection System Mechanical Control Diagram High Pressure Fire Protection System Mechanical Logic Diagram High Pressure Fire Protection Mechanical Logic Diagram High Pressure Fire Protection

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN FPR Figure #

Figure 11-21 Figure 11-22 Figure 11-23 Figure H-24 Figure 11-25 Figure 11-26 Figure 11-27 Figure 11-28 Figure 11-29 Figure 11-30 Figure 11-31 Figure 11-32 Figure 11-33 Figure 11-34 Figure 11-35 Figure 11-36 Figure 11-37 Figure 11-38 Figure 11-39 Figure 11-40 11-74 Rev. 10 TVA Drawing 1,2-47W610-39-1 1,2-47W610-39-2 1,2-47W611-39-1 1,2-47W611-39-2 1,2-47W611-13-1 1,2-47W611-13-2 1,2-47W611-13-3 1,2-47W611-13-4 1,2-47W611-13-5 1,2-47W611-13-6 1,2-47W611-13-7 1,2-47W600-245 1,2-47W600-246 1,2-47W600-247 1,2-47W600-248 1,2-47W600-249 1,2-47W600-250 1,2-47W600-251 1,2-47W600-252 1,2-47W600-253 LIST OF FIGURES (Continued)

Title Mechanical Control Diagram C02 Storage Fire Protection and Purging System Mechanical Control Diagram C02 Storage, Fire Protection and Purging System Logic Diagram C02 Storage, Fire Protection Purging System Logic Diagram C02 Storage, Fire Protection and Purging System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Logic Diagram Fire Detection System Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls

SQN FIRE PROTECTION REPORT PART II - FIRE PROTECTION PLAN Rev. 10 FPR Figure #

Figure 11-41 Figure 11-42 Figure 11-43 Figure 11-44 Figure 11-45 Figure 11-46 Figure 11-47 Figure 11-48 TVA Draving 1,2-47W600-254 1,2-47W600-255 1,2-47W600-256 1,2-47W600-257 1,2-47W600-258 1,2-47W600-259 1,2-47W600-260 1,2-47W600-270 LIST OF FIGURES (Continued)

Title Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls Mechanical Instruments and Controls

(* Changes are to Figure Numbers Only) 11-75