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{{#Wiki_filter:American Electric Power                                                NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                      Rev.4 NFPPM                                                                                                        Page 1 COOK NUCLEAR PLANT NFPA 805 FIRE PROTECTION PROGRAM MANUAL (NFPPM)
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Rev. 4 Preparer:            Pfc=                                            Allen James                  u/r{,,
Signature                                  Print                      Date Reviewer:
Signature Matthew Goddard Print
                                                                                                  ,1/,1 /t, Date
*Supervisor\
Manager Apprevak /
                          /n                                            Bob May                    /1'/Z Print                      Date t The Supervisor/ Manager, responsible for the oversight of Fire Protection Engineering, approval signature serves to signify that the qualifications of the individual(s) assigned as Preparer and Reviewer were verified in the Plant Qualification Matrix.
Page 1 of 315
 
American Electric Power                                                              NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                                                        Rev. 4 NFPPM                                                                                                                                            Page 2 Table of Contents
 
==1.0        INTRODUCTION==
............................................................................................................................ 3 1.1  Executive Summary .................................................................................................................. 3 1.2  NFPPM Description .................................................................................................................. 3 1.3  Revision Summary .................................................................................................................... 3 2.0        FIRE PROTECTION PROGRAM BASIS....................................................................................... 6 2.1 Historical Background............................................................................................................... 6 2.2 Licensing ................................................................................................................................... 9 3.0        FIRE PROTECTION PROGRAM ................................................................................................... 9 3.1 Purpose ...................................................................................................................................... 9 3.2 Scope ......................................................................................................................................... 9 3.3 Plant Fire Protection Policy ..................................................................................................... 10 3.4 Fire Protection Program Philosophy ....................................................................................... 10 3.5 Fire Protection Program Administration ................................................................................. 10 3.6 Other Documents:.................................................................................................................... 11 3.7 Fire Protection Program Changes............................................................................................ 12 3.8 Organization ............................................................................................................................ 14 3.9 Administrative Controls and Procedures ............................................................................... 14 3.10 Control of Ignition Sources ................................................................................................... 15 3.10.1    Welding, Burning, and Grinding Activities .................................................................... 15 3.11 Fire Rated Assemblies (Barriers) ............................................................................................ 15 3.12 Plant Modifications and Program Changes ............................................................................ 16 3.13 Controls and Compensatory Measures ................................................................................... 16 3.14 Fire Brigade ............................................................................................................................. 16 3.15 Outside Assistance (Mutual Aid) Agreement........................................................................ 17 3.16 Fire Protection Systems .......................................................................................................... 17 3.17 Quality Assurance................................................................................................................... 17 4.0        FIRE PROTECTION ENGINEERING AND SYSTEM DESIGN................................................ 18 4.1 System Descriptions (SD) ....................................................................................................... 18 4.2 Fire Protection Specifications ................................................................................................. 24 4.3 Nuclear Safety Capability Assessment (NSCA) ..................................................................... 24 4.4 Fire Safety Analysis (FSA) ..................................................................................................... 25 5.0        FIRE PROTECTION LICENSE CONDITION ............................................................................. 25 5.1 Fire Protection Program .......................................................................................................... 26 6.0        FUNDAMENTAL FIRE PROTECTION PROGRAM AND DESIGN ELEMENTS REVIEW .. 28 7.0        NATIONAL FIRE PROTECTION ASSOCIATION CODE COMPLIANCE REVIEWS ........... 42 8.0        RADIOACTIVE RELEASE REVIEW .......................................................................................... 42 9.0        ENGINEERING EQIVALENCY EVALUATIONS ..................................................................... 42 10.0        EXISTING LICENSING ACTION REVIEW ............................................................................... 42 11.0        NON-POWER OPERATIONAL MODES REVIEW .................................................................... 43 ATTACHMENTS: : NFPA 805 Chapter 3 Fundamental FP Program and Design Elements 1-1 : NFPA Codes of Record Summary 2-1 : Radioactive Release Review.. 3-1 : Engineering Equivalency Evaluations and Technical Evaluations 4-1 : Existing Licensing Action Transition.... 5-1 : Wrapped Raceways.... 6-1 Page 2 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                  Page 3
 
==1.0    INTRODUCTION==
 
1.1    Executive Summary The NFPA 805 Fire Protection Program Manual (NFPPM) provides a description of the risk-informed, performance-based Fire Protection Program for the Cook Nuclear Plant (CNP),
including references to the documents that comprise the Fire Protection Program.
The NFPPM describes the overall Fire Protection Program at Cook Nuclear Plant, provides a single reference to the documents that comprise the licensing basis of the Fire Protection Program, and includes the studies and evaluations that support the Fire Protection Program.
Engineering evaluations provide the basis for demonstrating issues of compliance with NFPA 805 at CNP. Other evaluations that support issues with the Fire Protection Program are also referenced in the NFPPM.
1.2    NFPPM Description The NFPPM describes the Cook Nuclear Plant and American Electric Power Service Corporation (AEPSC) procedures, evaluations, and other documents used by AEPSC and Indiana Michigan Power Company (I&M) to ensure that the Cook Nuclear Plant complies with federal regulations governing fire protection. It is not intended, however, that the NFPPM, by reference to these procedures, controls them. When differences exist between the NFPPM and the procedures, the procedures shall govern. The intent of the NFPPM is to serve as a guide regarding the overall Fire Protection Program structure.
AEPSC has established an Independent Spent Fuel Storage Installation (ISFSI) at the Cook Nuclear Plant to implement dry fuel storage under the General License provisions of 10 CFR 72.210. As used in this Fire Protection Program Manual, the terms Cook Nuclear Plant and Plant include both the two units operating under the provisions of 10 CFR 50 and the ISFSI operating under the provisions of 10 CFR 72.210. Unless specifically delineated otherwise, the Fire Protection Program applies to both the operating units and the ISFSI.
The Cook Nuclear Plant Fire Protection Program ensures that a fire will not diminish the ability to maintain the plant in a safe and stable hot standby condition and minimize the release of radioactivity through the defense-in-depth concept. Defense-in-depth is intended to prevent fires from starting, quickly detect and suppress a fire should it occur, limit the extent of damage caused by fire, and preserve the capability to utilize the required functions in the event of a fire. Putting this concept into practice is the Fire Protection Programs primary objective.
1.3    Revision Summary Revision 0 represents the initial issue of this document.
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American Electric Power                                      NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 4 Revision 1 was updated based on the plant at the time of transition to NFPA 805. This document was reorganized and now includes the content of Technical Evaluation 12.28, Technical Evaluation for Fundamental Fire Protection Program and Design Elements Review, Technical Evaluation 12.31, Technical Evaluation for Radioactive Release Review, and Technical Evaluation 7.1, Technical Evaluation for Licensing Action Review. These Technical Evaluations are superseded by this document. Technical changes are noted by the use of revision bars (except as noted within the text of selected attachments).
Revision 2 updates to incorporate NFPA 805 Fire Protection Program Changes as implemented by:
FPPR 2014-0009, UFSAR 9.8.1 Update for NFPA 805 FPPR-2015-0002, Revise PMP-2270-CCM-001 AR 2015-3026 IACE FPPR-2015-0010, Update Reference Documents to NFPPM Attachment 1 elements 3.5.3 and 3.5.4 to include reference to Report R2527-001-001 FPPR-2015-0074, FPPR-2016-0006, AR 2016-1349, AR 2016-1463 Update NFPPM FPPR-2016-0007, AR 2016-1349, AR 1463 Update NFPPM FPPR-2016-0010, GT-2016-12344-17 Replace 12-EHP-2270-FPPR-001 with 12-EHP-2270-FPIR-001 and 12-EHP-2270-FPCE-001 FPPR-2016-0011, NFPPM Rev. 2 update for minor corrections and changes from the last submittal of the Updated Final Safety Analysis Report (UFSAR) to support the new UFSAR submittal in accordance with 10 CFR 50.71(e), UFSAR Update and PMP-2350-COM-001, Communications with the Nuclear Regulatory Commission and Other Regulatory Agencies.
Revision 3 updates to incorporate NFPA 805 Fire Protection Program Changes as implemented by:
FPCE-2018-0007 Updates made to Attachment 1 section 3.3.8 to clarify compliance basis.
FPCE-2017-0008 Update made to Attachment 1 section 3.11.3(1), Attachment 2 section NFPA 80, and  to include reference to EEE-11-72.
FPCE-2017-0011 Update made to Attachment 1 section 3.11.3(1), Attachment 2 section NPFA 80, and  to include reference to EEE-11-71.
FPCE-2017-0001 Updates made to reflect changes from EHP series procedures to FPE series procedures resulting from consolidation of Fire Protection under the Operations department. Reference also CDI GT-2017-10673-1.
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American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                              Page 5 FPCE-2017-0018 Updates made to reflect transition of Technical Evaluation 11.69 to EEE-11-69.
Reference GT 2016-1960-7.
FPCE-2017-0021 Updates made to Attachment 1 3.3.1.2(4) to reflect changes to PMP-2270-CCM-001 to allow for a graded approach based on multiple factors including the risk significance of the room, current in-situ combustible loading and potential to exceed the combustible loading limits of the FSA.
FPCE-2017-0024 Updates made to Attachment 1 3.11.3(1) to reflect EEE-11-69.
FPCE-2017-0025 Updates to the NFPPM Section 3.7.1 and Attachment 1, Elements 3.2.3(4) and 3.3.1.1(3) to change reference from 12-EHP-5040-MOD-009, Engineering Change Reference Guide to IP-ENG-001, Standard Design Process.
FPCE-2018-0006 Update Attachment 1 section 3.9.1(1) reference documents to delete incorrect references to Technical Evaluation-N, O, and P.
FPCE-2017-0004 and FPCE-2017-0017 Updated the compliance basis for NFPA 805 design element 3.5.15 to reflect the use of a mobile means of delivering fire hose and equipment in the lieu of storage of hose in fire hose house. Removed reference specific to the fire truck as a mobile means of delivering fire hose and equipment.
FPCE-2016-0014 Updated attachment 6 to list wrapped cables.
FPCE-2016-0017 and FPCE-2016-0017A updated Appendix A section 3.3.5.1 to reflect installation of EC-0000054707 and EC-0000054824.
Corrected section 4.1 to indicate system descriptions are historical documents.
Updated to reflect revision of EEE-11-44 per AR 2016-1829-4.
Updated section 2.1 to explain the use of defense in depth equipment and procedures that previously required by the Appendix R program.
Added Section 6.2.3 to discuss compliance by NRC approval. Sections were added to describe license amendments that allow existing instances of cables over suspended ceilings, and the use of thin walled metal conduit and embedded plastic conduit. These updates are also reflected in Attachment 1 Sections 3.3.5.1 and 3.3.5.2.
Revision 4 FPCE-2018-0017 documents NRC approval for the use of flexible metallic conduit in configurations other than to connect components, and in lengths greater than short lengths.
FPCE-2019-0001 updated the title of EEE-11-18 in Attachment 1 section 3.11.2 and Attachment 4.
GT 2017-0785-8 update reference for design element 3.11.2.
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American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                  Page 6 Reference to FAQ 06-0022 was added as an editorial change to Compliance Section 3.3.5.3 to document the use of equivalent flame spread tests to IEEE-383.
FPCE-2019-0013 updated the title of EEE-11-19, Rev. 1 in Attachment 4.
Section 4.1.5, Emergency Lighting, was updated per FPCE-2019-0014 Per FPCE-2019-0015, EEE-11-49 was removed as a reference from Attachment 1 sections 3.11.4, 3.11.4(a), and 3.11.4(b). EEE-11-79 and EEE-11-80 were added as referenced to Attachment 1 sections 3.11.4. EEE-11-49 was marked as superseded and removed as a credited EEE in Attachment 4. EEE 79 and EEE-11-80 were added to Attachment 4 and marked as credited EEE.
Updated sections 4.1.3, 4.1.4, and 4.1.8 to include information previously contained in the FHA.
Made numerous editorial corrections and reference updates to Attachment 1.
2.0    FIRE PROTECTION PROGRAM BASIS 2.1    Historical Background Following the Brown's Ferry Nuclear Plant fire in 1975, the NRC concluded that measures should be instituted to decrease the frequency and severity of fires. In 1976, the Auxiliary Power Conversion and System Branch (APCSB) issued Branch Technical Position (BTP) APCSB 9.5-1, "Guidelines for Fire Protection for Nuclear Power Plants," and its Appendix A, with a request that utilities respond in writing to the NRC describing how the utility implemented the guidelines therein. Cook Nuclear Plant responded to this request by letter to the NRC dated January 31, 1977. The NRC had 53 initial questions regarding the submittal. The initial questions were followed by a second round of questions and five questions concerning administrative controls and quality assurance. These were answered by AEPSC letters dated August 19, 1977, September 30, 1977, October 27, 1977, and November 22, 1977. A schedule for completion of modifications to the fire protection system was submitted on February 3, 1978. Results of fire barrier penetration sealing tests were submitted on June 12, 1978 (AEP:NRC:004) and responses to questions on the fire test were submitted on August 16, 1978 (AEP:NRC:067). These responses and submittals formed the basis for the 1979 SER provided by the NRC. On November 19, 1980, the NRC issued 10 CFR 50.48 and Appendix R to 10 CFR 50 as a clarification to BTP APCSB 9.5-1 and Appendix A. However, the adoption of this rule imposed new, more stringent fire protection regulations on nuclear utilities. This new regulation, 10 CFR 50.48 and Appendix R to 10 CFR 50, was geared towards upgrading fire protection at nuclear power plants by requiring resolution of certain contested generic issues. Plants licensed to operate prior to January 1, 1979, were only required to comply with Sections III.G, III.J, and III.O of Appendix R as well as to maintain their compliance with BTP APCSB 9.5-1, Appendix A. In addition, Section III.L of 10 CFR 50 Appendix R is also applicable to plants taking credit for alternative shutdown capabilities as a compliance strategy.
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American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 7 On July 16, 2004, the NRC amended 10 CFR 50.48, Fire Protection, to add a new subsection, 10 CFR 50.48(c), which establishes new risk-informed, performance-based (RI-PB) fire protection requirements. 10 CPR 50.48(c) incorporates by reference, with exceptions, the National Fire Protection Association's NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, as a voluntary alternative to 10 CFR 50.48 Section (b), Appendix R.
As stated in 10 CFR 50.48(c)(3)(i), any licensee's adoption of a RI-PB program that complies with the rule is voluntary. For operating nuclear power plants, this program may be adopted as an acceptable alternative method for complying with either 10 CFR 50.48(b), for plants licensed to operate before January 1, 1979, or the fire protection license conditions for plants licensed to operate after January 1, 1979.
The Nuclear Energy Institute (NEI) developed NEI 04-02 to assist licensees in adopting NFPA 805 and making the transition from their current fire protection program to a program based on NFPA 805. The NRC issued Regulatory Guide (RG) 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light Water Nuclear Power Plants, which endorses NEI 04-02 with exceptions, in December 2009.
I&M submitted a letter of intent to the NRC on December 28, 2005 (ML060090370) for CNP to adopt NFPA 805 in accordance with 10 CFR 50.48(c). In that letter of intent, I&M stated its understanding that the letter would initiate a period of enforcement discretion during which no enforcement actions would be taken for non-safety-significant non-compliances discovered as a result of evaluations performed during the transition process. The NFPA 805 Transition License Amendment Request (LAR) was submitted on July 1, 2011 and supplemented by letters dated September 2, 2011, April 27, 2012, June 29, 2012, August 9, 2012, October 15, 2012, November 9, 2012, January 14, 2013, February 1, 2013, May 1, 2013, June 21, 2013, and September 16, 2013. The LAR was approved in the Safety Evaluation (SE) dated October 24, 2013.
The D.C. Cook Nuclear Plant Fire Protection Program transitioned to a NFPA 805 compliant program in October 2014 and thereby is no longer required to meet the requirements of Appendix R to 10 CFR 50. Under the requirements of 10 CFR 50 Appendix R, CNP was required to go to cold shutdown during a fire event. The NFPA 805 Fire Protection Program does not require that CNP go to cold shut down as we have shown that CNP can meet the nuclear safety performance goal by maintaining hot stand-by conditions. Therefore there are a number of procedures, equipment labels and other supporting documents no longer required to meet the program requirements. Although not required, CNP has kept and maintained the ability to go to cold shutdown as defense-in-depth during fire event. Therefore the Appendix R designation remains a valid basis for many procedures, equipment labels and other supporting documentation for those defense-in-depth actions.
Cook Nuclear Plant uses the following major requirements and guidance documents to provide the framework for its NFPA 805 fire protection program:
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American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                              Page 8 2.1.1  NFPA 805 Requirements The US Code of Federal Regulations 10 CFR 50.48(c), which allows licensees to adopt National Fire Protection Association standard 805 (NFPA 805).
NEI 04-02, Guidance for Implementing a Risk-informed, Performance-based Fire Protection Program Under 10 CFR 50.48(c)
NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition Regulatory Guide (RG) 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light Water Nuclear Power Plants, Revision 1 NUREG/CR 6850, EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, as guidance and a revision to the Internal Events PRA to support the Fire PRA LAR - Indiana Michigan Power, Donald C. Cook Nuclear Plant Units 1 & 2, Docket Nos. 50-315 and 50-316, Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition SE - Donald C. Cook Nuclear Plant, Units 1 And 2 - Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program In Accordance With 10 CFR 50.48(c) (Tag Nos. ME6629 and ME6630) 2.1.2  Compliance with these regulations and implementation of NRC guidance is described and/or maintained by the following NFPA 805 documents:
D. C. Cook Nuclear Plant Fire Safety Analysis (FSA)
NFPA 805 Fire Protection Program Manual (NFPPM) *this document Nuclear Safety Capability Assessment (NSCA)
Technical Requirements Manual (TRM) [Unit 1/Unit 2]
Updated Final Safety Analysis Report (UFSAR)
Evaluation of Fire and Explosion Hazards for ISFSI (EFEH)
The applicability and purpose of the UFSAR and licensing reference information are described in subsections 2.2.1 and 2.2.2, respectively, while applicability and purpose of the NFPPM has already been introduced in Section 1.0. The NSCA, FSA, and TRM are discussed in Section 3.6.
Federal law requires that all commercial nuclear power plants have nuclear property and liability insurance. These insurance guidelines form a further basis for the fire protection program and are implemented through various procedures and specifications. Nuclear Electric Insurance Limited (NEIL) provides guidelines for the implementation of insurance requirements into the fire protection program. These guidelines, combined with NEIL representative consultations and inspections, form the basis for the Cook Nuclear Plant Fire Protection Program compliance with NEIL requirements. The NFPPM does not address these requirements except where overlap exists between regulatory and insurance requirements.
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American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                                Page 9 2.2    Licensing 2.2.1  Operating License and Fire Protection License Conditions The Cook Nuclear Plant has an operating license for Units 1 and 2 and a general license for the ISFSI. Fire protection license conditions place additional operational constraints upon the Cook Nuclear Plant. Consequently, the Fire Protection License Conditions are an important part of the overall Cook Nuclear Plant licensing scheme.
2.2.2  UFSAR The UFSAR Section 9.8.l addresses the principal design criteria for the fire protection system, stating in part how the requirements of 10 CFR 50, Appendix A, Criterion 3, are to be met. It describes and/or references supporting documents that describe the fire detection, fire alarm and fire suppression systems used at Cook Nuclear Plant. It also discusses and/or references supporting documents that discuss the conduct of operations, organization and responsibilities, training, standards and procedures, records, and review and audit of operations for all areas including fire protection. The UFSAR is also a part of Cook Nuclear Plant's license basis for operation.
2.2.3  Technical Specifications The requirements formerly contained in the Technical Specifications related to the fire protection program are now contained in the Cook Nuclear Plant Technical Requirements Manual (TRM).
2.2.4  Quality Assurance The Fire Protection Quality Assurance Program is specified in the Donald C. Cook Nuclear Plant Quality Assurance Program Description (QAPD).
3.0    FIRE PROTECTION PROGRAM 3.1    Purpose The purpose of the D.C. Cook Fire Protection Program is to incorporate, identify and discuss the applicable commitments, documents, controls, departments and activities which together form the D.C. Cook Fire Protection Program.
3.2    Scope The Fire Protection Program is the mechanism through which D.C. Cook Nuclear Plant integrates the activities and elements of the Fire Protection Program required by 10 CFR 50.48(c), NFPA 805. These activities and elements include the following:
Organizations and positions that are responsible for the Fire Protection Program, Page 9 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                  Page 10 Qualifications of fire protection personnel, Specific features necessary to adequately implement the Fire Protection Program, Implementation of fire and emergency activities, and Fire Protection Quality Assurance.
Operating requirements/limitations, surveillance requirements and compensatory measures for fire protection identified by the Fire Protection Program must be followed to assure an acceptable level of protection is provided.
3.3    Plant Fire Protection Policy It is the policy of D. C. Cook Nuclear Plant to implement a Fire Protection Program that provides assurance, through a defense-in-depth design, that a fire will not:
Adversely impact the health and safety of the general public and plant employees.
Prevent the performance of necessary nuclear safety functions.
Increase the risk of radioactive releases to the environment Adversely impact the Station's investment in facilities and equipment.
3.4    Fire Protection Program Philosophy The Fire Protection Program uses the Defense-In-Depth concept to achieve a high degree of fire safety at Cook Nuclear Plant by:
Preventing fires from starting, Detecting and quickly controlling and suppressing those fires that do occur, while limiting their damage, and Providing protection for structures, systems, and components important to safety so that a fire that is not promptly extinguished by fire suppression activities will not prevent maintaining the plant in a safe and stable condition.
3.5    Fire Protection Program Administration This Plan was developed and is maintained to satisfy 10 CFR 50.48(a), which requires each operating nuclear plant to have a Fire Protection Program that satisfies Criterion 3 of 10 CFR 50 Appendix A.
3.5.1  Licensing Documents 3.5.1.1      Safety Evaluation Reports The NFPA 805 Safety Evaluation Report (Unit 1 Amendment 322 and Unit 2 Amendment 305, dated October 24, 2013) is a summary of the NRC's review of D.C. Cook Nuclear Plant's NFPA 805 fire protection program analysis including a physical inspection of the plant's Page 10 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 11 safety related components, systems, and structures and their relationship with combustibles and the associated fire detection/suppression systems.
3.5.1.2      Updated Final Safety Analysis Report The Updated Final Safety Analysis Report (UFSAR) incorporates Safety Evaluation Reports issued by the NRC and describes the approved fire protection program as it applies to the nuclear safety capability of the plant.
The UFSAR references specific documents that address different facets of the Fire Protection Program in greater detail. These documents are:
: a. Engineering Equivalency Evaluation 14.1.1, NFPA Code Conformance Report
: b. Nuclear Safety Capability Assessment (NSCA)
: c. NFPA 805 Fire Protection Program Manual (NFPPM) *this document
: d. D. C. Cook Fire Safety Analysis (FSA)
: e. PMI-2270, Fire Protection Program 3.6    Other Documents:
3.6.1  D. C. Cook Fire Safety Analysis (FSA)
This document demonstrates the achievement of the nuclear safety and radioactive release performance criteria of NFPA 805 as required by 10 CFR 50.48(c). The Fire Safety Analysis is a key part of compliance with Section 2.7.1.2, Fire Protection Program Design Basis Document, of NFPA 805.
3.6.2  Nuclear Safety Capability Assessment (NSCA)
This document identifies the safe and stable hot standby system requirements of the plant relative to the fire protection guidelines of NFPA 805, as described by NEI 04-02. It provides a listing of system components and a discussion of how the specific functions necessary to satisfy NFPA 805 are achieved.
3.6.3  Technical Requirements Manual (TRM)
The Technical Requirements Manual provides a means of tracking and maintaining control of important operational requirements and station commitments which are not included in, or have been removed from, the plant Technical Specifications.
3.6.4  Evaluation of Fire and Explosion Hazards for ISFSI (EFEH).
The EFEH report (13090401-R-M-009) documents the review of potential D.C. Cook Nuclear Plant site specific fire and explosion hazards that could affect spent fuel storage operations at the ISFSI and/or ISFSI cask transport operations along the ISFSI haul route, and demonstrates that Page 11 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 12 fire and explosions which could occur at the D.C. Cook Nuclear Plant site are enveloped by the parameters considered in the HI-STORM 100 FSAR and related NRC SER.
3.7    Fire Protection Program Changes Fire Protection program changes shall be reviewed in accordance with applicable CNP Procedures as allowed by the CNP NFPA 805 License Condition (Section 5.0):
: a. IP-ENG-001, Standard Design Process [FPCE-2017-0025]
: b. 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation [
 
==Reference:==
FPPR-2016-010, and FPCE 2017-0001]
: c. 12-FPE-2270-RICE-001, NFPA 805 Fire Protection Program Risk Informed Change Evaluation 3.7.2  Reporting Requirements Two categories of reporting requirements are applicable to the Fire Protection Program. The first is the reporting of Fire Protection Program changes, and the second is reporting of Fire Protection Program non-conformances.
3.7.3  Non-conformances The Fire Protection Program Manager is responsible for the interpretation of Fire Protection Program documents. This position may use whatever resources are available to aid in the determination of significance of a nonconformance (i.e. Operations, Licensing Department, Engineering, etc.).
Documentation of nonconformance to the Fire Protection Program may be accomplished in accordance with the D.C. Cook Corrective Action Program, or any other procedurally controlled nonconformance documentation system applicable to fire protection.
3.7.4  Special Reports and Licensee Event Reports Nonconformances to the Fire Protection Operational Requirements of the Technical Requirements Manual shall be evaluated for reportability to the NRC in a special report per 10 CFR 50.72(b).
Any fire that posed an actual threat to the safety of the nuclear plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the plant is reported in accordance with the requirements of 10 CFR 50.73, Licensee Event Report System.
Nonconformances to the Fire Protection Program that impact the ability to achieve and maintain a safe and stable plant condition are reported in accordance with the requirements of 10 CFR 50.73, Licensee Event Reports System.
Page 12 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                              Page 13 3.7.4.1    Records The Fire Protection Program and subsequent revisions are to be maintained for the life of the plant.
3.7.4.2    Reviews, Inspections and Audits
: a. Review of the Fire Protection Program The Fire Protection Program is to be reviewed once every 24 months for content and accuracy by the Fire Protection Program Manager or a designee knowledgeable of the Fire Protection Program.
: b. Biennial Inspection of the Fire Protection Program A fire protection inspection shall be performed at least once every 24 months, utilizing either qualified offsite/independent licensee personnel or a qualified outside fire protection consultant. A fire protection inspection shall be performed using an outside independent fire protection consultant at least once every 36 months.
The inspection shall consist of:
: 1. Inspections of representative safety related areas of the Plant to verify conformance with the Fire Safety Analysis. [
 
==Reference:==
GT 2015-5725 and FPPR-2014-0009]
: 2. A review of the fire brigade organization, training and drills to verify conformance to the requirements applicable to the D.C. Cook Nuclear Plant.
: 3. A review of compliance with the Fire Protection Quality Assurance Program.
: 4. A review of implementing procedures to assure that the requirements for design, procurement, fabrication, implementation, testing, maintenance and administrative controls continue to be included in the QA/QC program for fire protection; and that the Fire Protection Program continues to meet the criteria of the QA/QC program.
: c. Triennial Inspection:
A fire protection inspection shall be performed at least once every thirty-six (36) months by the NRC, the Authority Having Jurisdiction (AHJ).
The purpose of this inspection is to verify that the fire protection program commitments, modifications, and procedure revisions have not decreased the level of safety in the plant.
The review should include inspection of plant areas for which fire protection is provided and in particular, examine fire barriers, fire detection systems, and fire suppression systems provided for safety-related equipment.
Page 13 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 14 3.8    Organization 3.8.1  Responsibilities and Authorities Responsibilities and Authorities within the fire protection program are defined in Section 3, Responsibilities, of Procedure PMI-2270, Fire Protection Program.
3.8.2  Qualifications Minimum qualifications for personnel are defined in Section 4.1, Personnel Qualifications, or Procedure PMI-2270, Fire Protection Program.
3.9    Administrative Controls and Procedures 3.9.1  Control of Combustible Materials Administrative controls, implemented through procedures, are designed to control the type, amount, use and location of combustibles at D.C. Cook Nuclear Plant. Proper control of combustibles minimizes the possibility of starting, spreading, or contributing to a fire.
Combustibles are classified as either in-situ or transient.
Additional details on control of combustible materials can be found in Procedure PMP-2270-CCM-001, Control of Combustible Materials.
3.9.1.1  In-Situ Combustibles In-situ combustibles are the permanent fire loading comprised of fixed plant features and are evaluated and documented as contributors to the fire loading in their respective fire areas and zones. In-situ combustibles in the respective fire analysis areas/zones are maintained in the SAFE Database.
3.9.1.2  Transient Combustibles Transient combustibles represent the variable fire loading present at D.C. Cook Nuclear Plant.
Administrative and functional controls include the following:
Handling and limitation on the use of combustibles, flammable, and explosive hazards and assurance that these items are not stored in safety related areas.
Review of the quantity of transient fire loads introduced during maintenance and modifications. Addition of fire protection and suppression equipment for excessive loading.
Removal of all transient combustibles resulting from work activities following completion of the activity.
Page 14 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 15 3.10  Control of Ignition Sources Many areas are vital to the safe and orderly shutdown of the plant. It is imperative that these areas be protected from fire as a normal course of plant operation. Any work in these areas must also be carefully planned to ensure that adequate controls are established prior to starting work and during the progress of the job.
Refer to 12-FPP-2270-066-011, Fire Watch Activities, and PMP-2270-WBG-001, Welding, Burning and Grinding Activities, for additional details regarding control of ignition sources.
3.10.1 Welding, Burning, and Grinding Activities The use of open flames, welding, burning, or grinding is controlled by a permit system.
Areas surrounding the work area are surveyed by the responsible work supervisor to verify combustible material below and within a 35-foot radius of the ignition source has been removed, all immovable combustible materials below and within that radius are thoroughly protected by appropriate firefighting equipment, a trained fire watch is present throughout any operations where there is potential for fire that might damage safety related equipment, and all equipment is in a safe, working condition.
The Facilities Maintenance Department, Fire Protection Section, monitors welding, burning, and grinding activities and the control of ignition sources for those activities being conducted outside permanent shop areas.
3.10.2 Smoking Restrictions Smoking is not allowed on AEPNGG property, which includes the entire D.C. cook plant site geographic boundary, except for designated areas and employees personal vehicles while on the way to work or when exiting plant parking facilities.
3.10.3 Leak Testing Methods The use of open flames as a testing medium is prohibited.
3.11  Fire Rated Assemblies (Barriers)
Fire rated assemblies have been installed to ensure that fire damage will be limited. These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment.
When any fire rated assembly is rendered inoperable, the Fire Protection Section shall be notified to establish the required compensatory actions. Discovery of a non-functional fire rated assembly by site personnel requires that the Fire Protection Section be notified that the assembly is inoperable.
Page 15 of 315
 
American Electric Power                                      NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 16 3.12  Plant Modifications and Program Changes All plant modifications and program changes are reviewed for their impact on the Fire Protection Program.
3.13  Controls and Compensatory Measures 3.13.1 System/Component Operability The operability or inoperability of a fire protection system or component is determined through periodic surveillance.
3.13.2 Procurement When parts and materials for fire protection equipment/systems are required per Design Change Packages (DCPs) and/or work requests, these items are procured in accordance with plant procedures that maintain the proper fire protection system configuration.
3.14  Fire Brigade 3.14.1 Fire Brigade Composition and Support The Fire Brigade at D.C. Cook Nuclear Plant is organized to extinguish any fire that might occur at the plant site. Fire Brigade organization is consistent with licensing bases commitments.
A dedicated Fire Brigade of at least five (5) members is maintained on site at all times.
If the number of brigade members falls below the required number of five, it must be restored to a full complement within 2 hours as required by the Technical Requirements Manual and Section 3.1.1.4 of the NFPA 805 Safety Evaluation.
The Operations Department provides one person with a reactor operator's license or equivalent training to act as an advisor to the Brigade Leader on nuclear safety capability and general plant systems in the fire area.
Fire Brigade Training and the Fire Brigade Training Staff requirements are contained in procedure TPD-600-FP, Fire Protection Training Program Description.
3.14.2 Fire Pre-Plans The Fire Pre-Plans exist to describe the facility layout, access, contents, construction, hazards, hazardous materials, types and locations of fire protection systems, radioactive release concerns and other information pertinent to the formulation and planning of emergency fire response.
Page 16 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 17 3.15  Outside Assistance (Mutual Aid) Agreement An Outside Assistance (Mutual Aid) Agreement exists with the Bridgman/Lake Township Volunteer Fire Department. In the event of fire at Cook Nuclear Plant, the Bridgman/Lake Township department will respond to assist in firefighting activities. In the event that fire occurs within the protected area, the Fire Brigade Leader will be the on-scene commander and the volunteer force will report to him. The volunteer department fire chief will assume the on-scene commander's position for firefighting activities outside of the protected area.
3.16  Fire Protection Systems Fire suppression systems consisting of water, carbon dioxide (CO2) and Halon systems have been installed throughout the plant to provide protection for life safety, and plant equipment.
Systems protecting safety-related equipment, systems required for NFPA Chapter 4 Separation, systems required for a Licensing Action, and systems determined to have a high safety significance in the NFPA 805Monitoring program, a r e controlled by plant Technical Requirements Manual (TRM).
Fire detection systems are located throughout the plant and some areas of the office buildings.
Permanently mounted plant fire extinguishers are positioned to meet NRC commitments, the requirements of NFPA codes and the occupancy of the area in which they are located.
The D. C. Cook Fire Safety Analysis (FSA) contains a listing of fire protection systems and features in each fire area.
3.17  Quality Assurance Fire Protection Quality Assurance requirements are in place to assure that the quality assurance requirements specified in NFPA 805, 2001 Edition, as explained in the NFPA 805 Safety Evaluation dated October 24, 2013, are satisfied. The following quality assurance functions apply within the scope of the fire protection program, as outlined in Section 2.7.3 of NFPA 805.
Independent reviews: Analyses, calculations, and evaluations performed in support of compliance with 10 CFR 50.48(c) have been and will be performed in accordance with CNP procedures that require independent review.
CNP Procedure 12-EHP-5040-DES-003, which addresses independent review of calculations for 10 CFR 50 Appendix B, is applied to the PRA model calculations Reviews of engineering changes (physical modification or procedural change) require independent review per 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation .
Page 17 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                              Page 18 Verification and validation of calculational models and numerical methods:
Calculational models and numerical methods used in support of compliance with 10 CFR 50.48(c) have been and will be verified and validated as required by Section 2.7.3.2 of NFPA 805.
Limitations of use (appropriate use of engineering methods and numerical models): Engineering methods and numerical models used in support of compliance with 10 CFR 50.48(c) were used and will be used appropriately as required by Section 2.7.3.3 of NFPA 805.
Qualification of users: Cognizant personnel who use and apply engineering analysis and numerical methods in support of compliance with 10 CFR 50.48(c) shall be competent and experienced as required by Section 2.7.3.4 of NFPA 805. This requirement was met and will continue to be met by adherence to CNP procedures and project management of contractor support staff.
Uncertainty analysis performed: Uncertainty analyses have been and will be performed as required by 2.7.3.5 of NFPA 805 and the results have been and will be considered in the context of the application.
4.0    FIRE PROTECTION ENGINEERING AND SYSTEM DESIGN This section begins with a description of the fire protection systems and features which may be found at Cook Nuclear Plant in support of the defense-in-depth concept of fire protection under the NFPA 805 risk-informed, performance-based concept of a Fire Protection Program.
Specific details regarding the particular uses of these systems and features may be found in the Nuclear Safety Capability Assessment (NSCA) and Fire Protection System Descriptions (SD).
Fire-protection-related engineering evaluations are an important compliance mechanism used at the Cook Nuclear Plant to demonstrate how actual physical conditions in the plant, which differ from strict compliance to the requirements, provide an equivalent measure of protection.
Evaluations credited for compliance are listed in Attachment 4.
4.1    System Descriptions (SD)
Cook Nuclear Plant employs features that are designed to prevent, detect and suppress fires. In addition, these systems will help to minimize the level of damage to nuclear safety equipment should a fire occur. The fire protection system descriptions presented in this section are categorized as either automatic, manual, or passive fire protection features. An historical description of the systems may be obtained by referring to the following Fire Protection System Descriptions for the NFPA-805-based Fire Protection Program:
SD-12-FIRA-100, "Fire Detection and Alarm Systems" SD-12-FIRE-100, "Automatic Fire Suppression System" SD-12-FIRE-110, "Fire Protection System - Water Supply System" SD-12-FIRE-120, "Fire Protection Miscellaneous System" Page 18 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 19 SD-12-COAUX-100, "Low Pressure Carbon Dioxide Fire Fighting System" SD-12-HALON-100, "Fire Protection - Halon Systems" 4.1.1  Automatic Fire Alarm Systems Automatic fire alarm systems are actuated by either detectors that sense fire conditions or through manual pull stations. Fire detectors that may be used include ionization smoke detectors, heat detectors, infrared flame detectors, and air duct ionization smoke detectors.
The fire suppression system alarm signaling capabilities that may be used involve automatic sprinkler waterflow supervisory alarms, fire pump monitoring, carbon dioxide system monitoring, and halon system monitoring.
Fire alarm detection devices generally transmit signals to the local fire alarm panels and then to the control room annunciators, or they transmit signals directly to the control room annunciators.
In some cases, they will also actuate automatic fire suppression systems to control a fire prior to the response of the plant's fire brigade.
4.1.2  Automatic Water Fire Suppression Systems The automatic water fire suppression systems include all equipment or systems necessary for sprinkler or spray system protection. There are four basic types of automatic and manual water suppression systems used at Cook Nuclear Plant: wet pipe sprinkler systems, deluge water spray systems, pre-action water spray systems and pre-action sprinkler systems.
Water necessary for firefighting is provided by three primary fire pumps (one 2,500 gpm at 155 psi electric motor-driven horizontal centrifugal pump and two 2,500 gpm at 155 psi diesel engine-driven horizontal centrifugal pumps). The primary fire pumps take suction from either of two fire water storage tanks. The source of water to fill the dedicated fire protection water storage tanks is Lake Township drinking water. Each tank is nominally sized at 685,000 gallons, and the normal tank water level is between 612,000 gallons and 621,000 gallons. The minimum tank water level is set at 565,000 gallons.
The primary water pumps are arranged for (1) automatic sequential starting by operation of pressure sensing devices, (2) remote manual start of the fire pumps in either control room and (3) local starting at each pump. They cannot be shut down until extinguishment of a fire is verified by control room operators. Shutdown must be performed at the local fire pump control panels.
The fire water system provides water in sufficient quantity and pressure for fire hydrants and water-based suppression systems throughout the site. The water from the fire pumps is discharged into an underground 12" ring header located around the outside of the plant. Isolating valves with post indicators or curb boxes are installed in this header so that the entire loop interior header is connected to the outdoor loop header by valved connections routed through the turbine building, screenhouse, service building, auxiliary building and the yard. This arrangement forms a series of Page 19 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                              Page 20 smaller interior-exterior loops. The interior piping network is equipped with isolating valves and supplies water to the fixed fire protection and standpipe systems.
4.1.3  Carbon Dioxide Suppression Systems Cook Nuclear Plant has automatic and manual low pressure carbon dioxide systems to suppress fires in specified areas that are normally unoccupied. Distribution of carbon dioxide within each system is accomplished by means of valves and piping extending from the storage unit to the protected area.
The carbon dioxide storage unit consists of a pressure vessel, refrigeration system, gauges, alarm system, and a safety vent assembly. All of these components are enclosed within a steel housing on a single welded base.
The refrigeration system automatically maintains the carbon dioxide in the pressure vessel in a liquid state. Cook Nuclear Plant has a 17-ton storage unit for the auxiliary and turbine buildings.
Individual Cardox system panels are located at the entrances to protected areas. Each automatic suppression system has an isolation switch that may be used to prevent the local electrical actuation of the carbon dioxide system during zone occupation by plant personnel. A manual means for actuating each system is available for emergency use or if the automatic feature fails.
Fire Areas and Zones that are protected by Carbon Dioxide systems have boundary penetrations (i.e., dampers, seismic gaps and openings around cables, conduits and pipes) sealed to ensure retention of the Carbon Dioxide concentrations. In some fire areas, however, dampers have not been provided for duct work that communicates directly with the plant exterior or that pass through other areas within rated construction boundaries to the plant exterior. For the CO2 systems in these fire areas, concentration tests have been performed that demonstrate that the required concentration levels can be maintained without dampers. The affected fire zones in which this situation exists are 40A, 40B, 42A, 45, 46A, 47A and 47B.
4.1.4  Automatic Halon Fire Suppression System Cook Nuclear Plant has several locations protected by automatic Halon 1301 total flooding systems. Halon 1301 cylinders are provided to supply a minimum five percent concentration to the protected areas. Penetration seals have been provided to ensure that the required concentration of the agent is maintained.
4.1.5  Emergency Lighting Portable hands-free lighting is provided to operators to support access to safe shutdown equipment and components that must be manually operated or maintained during and after a fire, if normal area lighting is lost. The portable hands-free lighting is able to provide a minimum of 2 hour of continuous light. 2 hours of continuous light is evaluated as exceeding the duration to complete necessary recovery actions, but spare batteries are provided for the unlikely event that the portable lighting fails prior to the completion of the recovery actions.
Page 20 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                              Page 21 Fixed emergency lighting is available throughout the plant and was installed to support the previous 10CFR50, Appendix R, section III.J requirements (or exemptions granted). These lights are energized upon failure of the normal AC lighting system and de-energized when the normal AC lighting system is returned to service. The existing emergency lighting system, together with portable lighting (e.g., miners hats), will be maintained under NFPA 805.
Recovery actions credited under NFPA 805 are required to be feasible and must be evaluated to ensure sufficient lighting is available to perform the intended action, including operation of the components and for access and egress routes. Ongoing review and modifications will be performed as part of the NFPA 805 recover action related implementation items documented in Technical Evaluation R1900-0026-001, Recovery Action Transition in Support of NFPA 805.
[
 
==Reference:==
FPCE-2019-0014]
4.1.6  Portable Manual Fire Fighting Features Portable manual fire protection is available as a backup to automatic or manual fixed fire suppression systems or as the primary suppression method in various areas throughout the plant.
Manual features include hydrants, standpipe hose stations, firefighting tools, protective clothing, self-contained breathing apparatus (SCBA), portable fire extinguishers, and smoke removal equipment. The plant also utilizes a fire truck, which is stationed on site.
Fire hydrants are equipped with three hose connections. The largest connection is 41/2 inches and is used in combination with the fire truck soft suction hose and pump when operating from the underground fire header. The two smaller connections are 21/2 inches and can be used for the same purpose or for direct connection of 21/2-inch fire hose. For the latter use, gate valves are provided on the 21/2-inch outlets to better control the hose lines.
The plant is equipped with standpipes and fire hose stations, which provide manual fire suppression capability in plant buildings. The usual hose station is equipped with either 75 or 100 feet of 11/2-inch hose; however, in isolated cases, several hose stations have up to 125 feet of available hose. In other cases, the hose station has also been provided with a second hose reel with up to 100 feet of either 11/2-inch or 21/2-inch hose.
Firefighting tools, protective clothing, self-contained breathing apparatus and smoke removal equipment are provided for the fire brigade at designated locations throughout the plant. These locations are reviewed with the fire brigade during training sessions and fire drills.
Portable fire extinguishers are provided throughout the plant for use in fighting small fires. These fire extinguishers include dry chemical types for fighting Class A, B, C fires and B, C type fires.
Carbon dioxide fire extinguishers are also provided for fighting B, C type fires.
Class A fires involve ordinary combustible materials such as wood, paper, plastics, rubber, cloth, etc. Class B fires involve flammable or combustible liquids and flammable gases. Class C fires Page 21 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                  Page 22 involve live electrical equipment. The type of portable fire extinguisher chosen for an area is dependent on the type of hazard anticipated, its location and availability of other firefighting equipment.
4.1.7  Communications Plant personnel are notified that a fire emergency exists through the use of a fire horn alarm system. The preferred communication method during a fire is portable hand-held radios supported by a repeater system within the plant. Sound-powered telephones and a public address (PA) system are available as backup methods of interplant communication. The standard fire system monitoring devices, such as horns, alarms, bells, bells, and lights, provide fire condition notification in areas protected by Halon and CO2.
4.1.8  Passive Fire Protection Features Passive fire protection features are those plant configurations and special systems designed to provide fire protection but which are not part of an active or manual fire suppression system.
Passive features include fire barriers, fire barrier penetration seals, separation distances between plant components, and the reactor coolant pump lube oil collection system.
Separation is used as a passive fire protection criterion to isolate redundant safe shutdown systems from unacceptable fire hazards, and to separate redundant safe shutdown systems from each other so that both are not damaged by a single fire.
An alternative, passive method of fire protection allows the use of one-hour fire rated material to enclose the cables, trays, or conduits necessary for safe shutdown. Fire barrier material is used as a cable tray, conduit and cable fire wrap to provide separation between redundant divisions of equipment and cables outside of containment. Another method of passive fire protection is the installation of fire stops, perpendicular to the run of an electrical cable tray, to prevent the spread of fire along cables.
Fire barriers provide a physical separation to delay or prevent the spread of fire from one space to another. Fire barriers include walls, floors, ceilings, and their structural supports that are rated by approved laboratories in hours of resistance to fire.
Fire barriers are penetrated by doors, ventilation systems, piping systems (including tubing), and electrical conduits and cable trays. The fire rating of barriers is maintained by sealing resulting openings at these penetrations. Fire barrier penetrations are sealed by rated fire doors, fire dampers, or mechanical penetration seals. Fire door assemblies include any combination of a fire door, frame, hardware, and other accessories that together provide a specific degree of fire protection to an opening and are labeled by an independent testing laboratory (typically Underwriter's Lab and/or Factory Mutual).
Page 22 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                  Page 23 Rated fire dampers are installed in HVAC systems to interrupt air flow and restrict the passage of flame and smoke. These fire dampers are rated and labeled by an independent testing laboratory.
Mechanical penetration seals are installed around piping, cable trays, and conduit and in and around cable trays to provide a fire resistant barrier when required. Under certain situations, one end of double open ended conduits are sealed to prevent the passage of fire through the conduit to the other side of the fire barrier. A variety of seal types is used; however, most employ silicone foam. Specification ES-FIRE-0601-QCF, Fire Rated Seals, governs mechanical penetration seals at CNP.
4.1.8.1 RCP Lube Oil Collection System The four RCP motors in each unit have a common oil collection system that terminates in an oil collection tank. Each RCP motor is provided with oil collection enclosures to capture oil from potential pressurized and unpressurized leakage sites in the lube oil system. The oil collection system is designed to prevent RCP lube oil from making contact with hot RCS piping and other ignition sources. Leakage is collected and drained to a vented collection tank located at the basement level of containment.
The oil is drained through carbon steel piping which has been seismically supported. Threaded fittings which have been seal welded and socket weld fittings were used in the design. Tygon tubing is also used in the RCP oil collection piping system. The tubing acts as a flexible pipe connector and as a non-conductive connector intended to insulate the upper portion of the motor from ground, thereby preventing a shorting of the upper motor bearing electrical insulation. Refer to Section 12.9 for a future discussion of the tygon tubing and its seismic qualifications.
The collection tank has been reinforced to meet DBE seismic criteria and has a design capacity of 275 gallons. The tank capacity is designed to hold the oil from only one motor (approximately 265 gallons). The collection tank is arranged such that if a failure of more than one RCP motor lube system occurred, the oil will overflow through a two inch pipe above the tank and onto the lower containment floor. Once on the floor, it will then drain to the lower containment sump.
There are no ignition sources at the floor level of the lower containment.
In the event of a RCP lube oil leak occurring under normal operating conditions, the oil collection system will function to contain the oil and drain it to the oil collection tank. The oil collection system will prevent the lube oil from making contact with hot RCS piping and other external ignition sources. In addition, the containment spray system is available as an effective fire suppression system.
The RCP motor lube oil system is capable of withstanding the safe shutdown earthquake. Since the RCP lube oil system is designed to withstand the safe shutdown earthquake, the oil collection system need only be designed to handle random oil leaks as indicated in NRC Generic Letter 86-10 (Enclosure 2, Section 6.1). As a result, the system is only required to be sized to channel the Page 23 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                Page 24 quantity of oil from one pump to a vented closed container. Generic Letter 86-10 provides an additional basis for the acceptability of the Cook Nuclear Plant oil retention tanks.
The RCP oil collection system was originally provided to meet our commitments of Appendix A to BTP APCSB 9.5-1. This system also fulfilled the requirements of Appendix R to 10CFR50, Section III.0. However, the RCP motor lube oil system does not comply with Section III.0 because the oil collection tank is not sized to contain the entire lube oil system inventory. The design of the RCP oil collection system has been reviewed by the NRC. A safety evaluation report (SER dated 12/23/83) was prepared by the NRC for the exemption from the requirements of Appendix R Section III.0. Refer to Section 6.2.1 for additional details regarding this prior approval.
4.1.9  Repair of NFPA 805 Equipment NFPA 805 requires that nuclear utilities be able to achieve and maintain a safe and stable hot standby. With a mission time of 24 hours, plant operation beyond that time will be governed by the EOPs. Temporary repairs for NFPA 805 equipment are allowed to be credited in support of the EOPs. These repairs are performed with special equipment and procedures that are reserved for the express purpose of accomplishing the necessary repair actions.
4.1.10 Attachment 6 provides information regarding raceways that are wrapped with fire retardant materials. This table was added directly from the Fire Protection Program Manual (FPPM),
Revision 13 dated September 3, 2013. Updates to the table found in this document are marked with revision bars.
4.2    Fire Protection Specifications CNP engineering specifications are controlled in accordance with CNP Procedures. There are several specifications applicable to fire protection for the Cook Nuclear Plant. These include:
ES-FIRE-0601-QCF, Fire Rated Seals DCC-FP-103-QCF, Fire Protection Equipment and Systems QA Requirements DCC-PV-110-QCF, Shop and Field Fabrication and Erection of Fire Protection Piping ES-CABLE-0221-QCN, Design and Installation Criteria for Cable, Trough, and Conduit ES-HVAC-0803-QCN, Fire Dampers 4.3    Nuclear Safety Capability Assessment (NSCA)
Nuclear facilities are required to perform a fire safety analysis to (1) consider potential in-situ and transient hazards, (2) determine the consequences of fire in any location in the plant and the ability to maintain the reactor in a safe and stable hot standby condition, and (3) address measures Page 24 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                  Page 25 for fire prevention, detection, suppression and containment, as required for each fire area containing nuclear safety-related items per NRC regulations and guidelines. Cook Nuclear Plant has chosen to respond to these requirements by performing a fire safety analysis (FSA) for each fire area and a Nuclear Safety Capability Assessment (NSCA) separately.
The NSCA documents the analysis of the ability to successfully maintain the plant in a safe and stable hot standby condition in the event of a fire. The NSCA also identifies the fire areas that contain the equipment and cables necessary to achieve a safe and stable hot standby of the Cook Nuclear Plant. The method and selection of the NFPA 805 systems, equipment, and cables is also delineated. Transition from hot standby to the EOPs within 24 hours after the event's initiation, at which time temporary repairs may be performed, if required.
The NSCA is updated and maintained as part of continued compliance with NFPA 805.
4.4    Fire Safety Analysis (FSA)
The FSA is a comprehensive evaluation of the fire hazards that exist for all fire areas at the Cook Nuclear Plant. The FSA is updated and maintained by a fire protection engineer. A typical analysis is performed on a fire area basis and discusses the following items:
Identify significant fire hazards in each fire area based on an NFPA 805 approach to analyze the plant from an ignition source and fuel package perspective.
Summarize Nuclear Safety Capability Assessment (NSCA) compliance strategies.
Summarize Non-Power Operational Modes compliance strategies.
Summarize Radioactive Release compliance strategies.
Provide Fire Probabilistic Risk Assessment summary based on the results from the plant Fire PRA.
Perform risk-informed, performance-based evaluations if needed for the performance based approach.
Summarize Defense-in-Depth strategy for each fire area.
Determine key analysis assumptions which are candidates to be included in the NFPA 805 monitoring program.
Provide conclusions relative to NFPA 805 compliance.
The Fire Safety Analysis Report designates "fire areas" within the plant that are separated from other areas by fire-rated walls, floors, or ceilings. The fire safety analysis evaluates the effects of a fire within each separate fire area of the plant.
The FSA is updated and maintained as part of continued compliance with NFPA 805.
5.0    FIRE PROTECTION LICENSE CONDITION This section briefly describes the Fire Protection License Conditions and NRC Safety Evaluations (SEs) that form part of the licensing basis for the DC Cook NFPA 805 Fire Protection Program.
Page 25 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                              Page 26 The following subsections are quoted from the D.C. Cook NFPA 805 Safety Evaluation dated October 24, 2013.
(Note: sections are renumbered to be consistent with this document.)
5.1    Fire Protection Program Indiana Michigan Power Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee's amendment request dated July 1, 2011, as supplemented by letters dated September 2, 2011, April 27, 2012, June 29, 2012, August 9, 2012, October 15, 2012, November 9, 2012, January 14, 2013, February 1, 2013, May 1, 2013, June 21, 2013, and September 16, 2013, and as approved in the Safety Evaluation dated October 24, 2013. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
5.1.1  Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed Fire PRA (FPRA) model, methods that have been approved by NRC through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.
5.1.1.1      Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
5.1.1.2      Prior NRC review and approval is not required for individual changes that result in a risk increase less than 1E-07/year (yr) for CDF and less than 1E-08/yr for LERF. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
5.1.2  Other Changes that May Be Made Without Prior NRC Approval Page 26 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM                                                                                              Page 27 5.1.2.1    Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program and Design Elements Prior NRC review and approval are not required for changes to the NFPA 805, Chapter 3, fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805, Chapter 3, element is functionally equivalent. to the corresponding technical requirement. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.
The licensee may use an engineering evaluation to demonstrate that changes to certain NFPA 805, Chapter 3, elements are acceptable because the alternative is "adequate for the hazard."
Prior NRC review and approval would not be required for alternatives to four specific sections of NFPA 805, Chapter 3, for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is adequate for the hazard. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the. change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard. The four specific sections of NFPA 805, Chapter 3, are as follows:
                  "Fire Alarm and Detection Systems" (Section 3.8);
                  "Automatic and Manual Water-Based Fire Suppression Systems" (Section 3.9);
                  "Gaseous Fire Suppression Systems" (Section 3.10); and, "Passive Fire Protection Features" (Section 3.11).
This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805.
5.1.2.2    Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRC review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRC Safety Evaluation dated October 24, 2013, to determine that certain fire protection program changes meet the minimal criterion. The licensee shall ensure that fire protection defense-in-depth and safety margins are maintained when changes are made to the fire protection program.
5.1.3  Transition License Conditions 5.1.3.1    The letter from the NRC dated October 24, 2013 contains the NFPA 805 Safety Evaluation.
Enclosure 1 to the letter is License Amendment No. 322 to DPR-58, Donald C. Cook Nuclear Page 27 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 28 Plant Unit 1 Renewed Operating License. Enclosure 2 to the letter is License Amendment No. 305 to DPR-74, Donald C. Cook Nuclear Plant Unit 2 Renewed Operating License.
Section 2.C.(4)(c) of the amended DPR-58 and Section 2.C.(3)(o)(III) of the amended DPR-74 contain the Unit 1 and Unit 2 transition license conditions.
6.0    FUNDAMENTAL FIRE PROTECTION PROGRAM AND DESIGN ELEMENTS REVIEW 6.1    Compliance with Chapter 3 of NFPA 805 is documented in Attachment 1, NFPA 805 Fundamental FP Program and Design Elements (NFPA 805 Chapter 3).
6.2    The D. C. Cook NFPA 805 Safety Evaluation (SE) dated October 24, 2013 finds acceptable Complies via Previous NRC Approval and Submit for NRC Approval compliance strategies stated in Attachment 1. The following text is adapted from the SE dated October 24, 2013.
6.2.1  Compliance Strategy -- Complies via Previous NRC Approval Certain NFPA 805 Chapter 3 requirements were supplanted by an alternative that was previously approved by the NRC. NRC approval was documented in (1) an SE dated July 31, 1979, supporting Amendments Nos. 31 and 12 to the CNP Unit 1 and 2, operating licenses; (2) an exemption dated December 23, 1983, approving the use of the reactor coolant pump (RCP) motor lube oil system that is not sized to contain the entire lube oil system inventory; (3) a Safety Evaluation (SE) dated June 16, 1988, approving the installation of carpet in the control room having a flame spread greater than that recommended by NRC staff guidance; (4) an SE dated April 9, 1991, approving the use of a minimum fire brigade shift crew size of four members for up to 2 hours under certain conditions; (5) an SER dated January 24, 1995, approving the installation and use of certain unsupervised circuits; (6) an exemption dated August 27, 1985, approving the use of 22 Auxiliary Building undampered ventilation duct penetrations; and (7) an SER dated April 26, 1990, approving the internal conduit seal program.
In each instance, the licensee evaluated the basis for the original NRC approval and determined that, in all cases, the bases were still valid. The NRC staff reviewed the information provided by the licensee and concluded that previous NRC approval had been demonstrated using suitable documentation that meets the approved guidance contained in RG .1.205, Revision 1. Based on the licensee's statements for the continued validity of the previously approved alternatives to the NFPA 805 Chapter 3 requirements, the NRC staff concludes that the licensee's statements of compliance in these instances are acceptable.
The following NFPA 805 sections identified in Attachment 1 as complying via this method required additional review by the NRC staff:
6.2.1.1    3.3.12 Reactor Coolant Pumps NFPA 805 Section 3.3.12 provides requirements for the reactor coolant pump (RCP) oil Page 28 of 315
 
American Electric Power                                      NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 29 collection system. By {{letter dated|date=October 11, 2012|text=letter dated October 11, 2012}}, the NRC staff issued request for additional information (RAI) 57 to correct a reference listed in the basis of LAR Attachment K associated with Exemption 7.5. By {{letter dated|date=November 9, 2012|text=letter dated November 9, 2012}}, the licensee responded to the RAI and indicated that the licensing action described in LAR Attachment K, associated with Exemption 7.15, contains a typographical error. The discussion in the Basis section should have referred to NFPA 805 Section 3.3.12(2).
The NRC staff concludes that the licensee's statements of compliance in this instance are acceptable.
6.2.1.2    3.4.1 On-Site Fire-Fighting Capability NFPA 805 Section 3.4.1 provides requirements for the fire brigade members including a minimum crew size of five. The licensee had originally claimed to comply with a clarification that there was a prior approval to use a reduced fire brigade crew size.
During the NRC staff's review, NRC FAQ 12-0063, "Fire Brigade Make-Up," was issued and provided additional guidance regarding the reduction in minimum crew size for up to 2 hours under certain conditions, and provisions for the appropriate compliance strategy. The licensee's response, dated April 27, 2012, to RAI 10, dated January 27, 2012, identified that its current FPP allows for the same minimum crew size under similar conditions and limitations. In response to the RAI, the licensee changed its compliance strategy from "complies with clarification" to "complies by previous NRC approval." The licensee quoted its Technical Requirements Manual (TRM)
Section 10.1, which stated "the composition of the fire brigade may be less than the minimum requirements for a period of time not to exceed 2 hours, in order to accommodate unexpected absence provided immediate action is taken to fill the required positions." This provision was approved by the NRC staff in Section 2.0(3) of the SE dated April 9, 1991, for Amendment Nos. 154 and 138 for Unit 1 and Unit 2, respectively.
6.2.2  Compliance Strategy -- Submit for NRC Approval (at transition)
For two of the NFPA 805 Chapter 3 requirements, the licensee requested approval for the use of a performance-based method to demonstrate compliance with a fundamental FPP element. In accordance with 10 CFR 50.48(c)(2)(vii), the licensee requested that specific approval be included in the license amendment approving the transition to NFPA 805 at CNP. The NFPA 805 sections identified in Table B-1 as complying with this method are as follows:
6.2.2.1    3.2.3(1) Procedures - Inspection, Testing, and Maintenance In Table B-1, the 1icensee identified that EPRI Technical Report (TR)-1006756, "Fire Protection Surveillance Optimization and Maintenance Guide for Fire Protection Systems and Features," July 2003, may be used to determine performance-based Page 29 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM                                                                                            Page 30 surveillance frequencies. EPRI TR-1006756 is published by the Electric Power Research Institute and provides guidance for licensees to follow in order to optimize their fire protection surveillance and testing practices and frequencies for fire protection systems, structures, and components based upon performance. In RAI 05 dated January 27, 2012, and RAI 05.01 dated October 11, 2012, the NRC staff identified this compliance strategy as unacceptable and stated that if the licensee intends to use a performance-based alternative program for managing inspection, testing, and maintenance, then a request for approval must be submitted to the NRC in accordance with 10 CFR 50.48(c)(2)(vii). The licensee's response, dated October 15, 2012, provided a new Approval Request #2 in accordance with 10 CFR 50.48(c)(2)(vii). This request was evaluated by the NRC as described below:
As described by the licensee, performance-based inspection, testing, and maintenance frequencies would be established using the methods described in EPRI TR-1006756, "Fire Protection Surveillance Optimization and Maintenance Guide for Fire Protection Systems and Features," Final Report, July 2003.
The licensee stated that the use of this method for establishing inspection, testing, and maintenance frequencies will have no adverse impact on the ability to provide assurance that the availability and reliability of the fire protection systems and features are maintained to the levels assumed in the NFPA 805 engineering analyses.
The licensee stated that there will be no impact on the NFPA 805 nuclear safety performance goals, performance objectives, and performance criteria because the use of performance based test frequencies established per EPRI Technical Report TR-1006756 methods, combined with NFPA 805, Section 2.6, will provide assurance that the availability and reliability of the fire protection systems and features are maintained to the levels assumed in the NFPA 805 engineering analyses. This will ensure that there is no impact on the ability of the fire protection systems and features to perform its function.
The licensee also stated that the radiological release performance goals, objectives, and criteria are satisfied based on the determination of limiting radioactive release (LAR Attachment E). Fire protection systems and features are credited as part of that evaluation. Use of performance based test frequencies established per EPRI Technical Report TR-1006756 methods combined with NFPA 805, Section 2.6 Monitoring Program will ensure that the availability and reliability of the fire protection systems and features are maintained to the levels assumed in the NFPA 805 engineering analyses, which include those assumptions credited to meet the Radioactive Release performance criteria. Therefore, there will be no adverse impact to Radioactive Release performance criteria.
The licensee further stated that the proposed alternative maintains the safety margins of the licensee's analyses because it will provide assurance that the availability and Page 30 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 31 reliability of the fire protection systems and features are maintained to the levels assumed in the NFPA 805 engineering analyses, which includes those assumptions credited in the FRE safety margin discussions. In addition, the use of these methods in no way invalidates the inherent safety margins contained in the codes used for design and maintenance of fire protection systems and features. Therefore, the safety margin inherent and credited in the analyses will be preserved.
The three echelons of DID described in NFPA 805, Section 1.2 are (1) to prevent fires from starting (combustible/hot work controls); (2) rapidly detect, control and extinguish fires that do occur thereby limiting damage (fire detection systems, automatic fire suppression, manual fire suppression, pre-fire plans); and (3) provide adequate level of fire protection for systems and structures so that a fire will not prevent essential safety functions from being performed (fire barriers, fire rated cable, success path remains free of fire damage, RAs). Echelon 1 is not affected by the use of EPRI Technical Report TR-1006756 methods. Use of performance-based test frequencies established per EPRI Technical Report TR-1006756 methods, combined with NFPA 805, Section 2.6, will provide assurance that the availability and reliability of the fire protection systems and features credited for DID are maintained to the levels assumed in the NFPA 805 engineering analyses. Therefore, there will be no adverse impact to Echelons 2 and 3 of DID.
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed performance-based method is an acceptable alternative to the corresponding NFPA 805, Section 3.2.3(1) requirement because it satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains sufficient safety margin, and maintains adequate fire protection DID.
6.2.2.2    3.5.16 Water Supply - For Fire Protection Use Only Contrary to the requirements of NFPA 805 Section 3.5.16 and NFPA 24, Standard for the Installation of Private Fire Service Mains and their Appurtenances, Section 5-7, the fire protection water supply system at CNP may periodically be used to supply water for non-fire protection purposes. This request was evaluated by the NRC as described below:
By letters dated April 27 and October 15, 2012, in response to NRC staff RAIs 11 dated January 27, 2012, and 11.01 dated October 11, 2012, regarding the controls in place for uses of fire water for non-fire protection purposes, the licensee stated there are only two identified uses of non-fire protection purposes:
Permanently piped cooling water (approximately 240 gallons per minute (gpm) maximum) to the Security Diesel Generator jacket water coolers.
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American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 32 Tube sheet water lance cleaning of the Unit 1 or 2 Main Feed Pump Turbine Condensers via various fire hose stand pipe locations (approximately 100 gpm). This use is controlled as a proceduralized temporary plant modification in accordance with station procedures.
As described by the licensee, this usage is subject to the following conditions: (1) prior approval is obtained from the CNP fire protection staff and (2) personnel utilizing the fire protection water are in contact with the CNP Control Room. These controls are described as sufficient to ensure that the fire water system is not impaired and can be secured and restored to full capacity should a fire occur.
Additional controls in place for use of the fire water for non-fire use other than the two specific purposes described above are:
Engineering evaluation has concluded that there is sufficient pumping capacity to supply the largest demand as well as non-fire use operation.
Control Room Operations staff and fire brigade are notified of the non-fire uses, and contingencies established for prompt restoration in a fire event.
Should non-fire water use of the fire water system impact operability of any of the three primary fire pumps, station procedure[s] provides guidance for establishing backup fire water capability from specified local township fire hydrants and for refilling the fire water storage tanks.
A station procedure ensures that work activities on plant SSCs are conducted within the requirements of the station license, including TRM Section 8.7.5. All non-fire water uses of the fire water system are included in the Work Control Process, which includes proper planning, scheduling, execution, and risk assessment.
The licensee stated that the use of the fire protection water for non-fire protection system water demands would have no adverse impact on the ability of the fire protection system to provide required flow and pressure based on the following:
Controls in place, as described above, to cease the non-fire protection use should a fire condition occur.
The system, which consists of one 2,500 gpm electric motor driven fire pump and two redundant 2,500 gpm diesel engine driven fire pumps connected by a common header to two 685,000 gallon fire protection water storage tanks, is designed to provide water in excess of that required to suppress a fire.
During a largest demand fire scenario, a safety margin of approximately 1,300 gpm is maintained even with only two of the three pumps in operation.
The licensee concluded that the use of the fire protection water for non-fire protection uses does not impact the NSPC because the CNP fire water system has excess capacity to supply the combined demands of automatic and manual water-based fire suppression systems and non-fire protection uses in the event of a fire, even in the unlikely event of a delay in ceasing Page 32 of 315
 
American Electric Power                                          NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                                Rev. 4 NFPPM                                                                                                Page 33 the use the fire protection water for non-fire protection purposes. For this same reason, the licensee concluded that the use of the CNP fire water system for non-fire protection uses has no impact on maintaining fire protection defense-in-depth because suppression systems are not affected.
The licensee also stated that this alternative will have no effect on the NFPA 805 radiological release performance goals, performance objectives, and performance criteria, since use of the CNP fire water system for non-fire protection uses has no impact on the radiological release.
The licensee further stated that the proposed alternative maintains the safety margins of the licensee's analyses related to fire water use functions, because the proposed alternative will not alter the methods, input parameters, and acceptance criteria used in fire water demand.
The CNP fire water system has excess capacity to supply the combined demands of the automatic and manual water-based fire suppression systems and non-fire protection uses in the event of a fire. Finally, the licensee stated that fire protection defense-in-depth will be maintained because the fire water system pumps have excess capacity to supply demands of automatic and manual water-based fire suppression systems and non-fire protection uses in the event of a fire.
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed performance-based method is an acceptable alternative to the corresponding NFPA 805, Section 3.5.16 requirement because it satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains sufficient safety margin, and maintains adequate fire protection DID.
6.2.3  Compliance Strategy -- Submit for NRC Approval (post transition) 6.2.3.1      For two of the NFPA 805 Chapter 3 requirements, the licensee requested approval for the use of a performance-based method to demonstrate compliance with a fundamental FPP element.
Amendments were requested to approve deviation from the requirements of National Fire Protection Association Standard 805, Section 3.3.5.1, regarding the use of non-plenum listed cables above suspended ceilings, and Section 3.3.5.2, regarding the use of electric metallic tube and embedded/buried polyvinyl chloride conduit. The licensee submitted the proposed license amendment request in accordance with Title 10 of the Code of Federal Regulations, Section 50.48(c)(2)(vii), requesting to use a performance based method in a fire protection program element.
The NFPA 805 sections identified in Attachment 1 as complying with this method are as follows:
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American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                        Rev. 4 NFPPM                                                                                          Page 34 6.2.3.1.1 3.3.5.1 Electrical Wiring Above Suspended Ceiling Limitations Wiring above suspended ceiling shall be kept to a minimum. Where installed, electrical wiring shall be listed for plenum use, routed in armored cable, routed in metallic conduit, or routed in cable trays with solid metal top and bottom covers. Contrary to these requirements, CNP has wiring installed above suspended ceilings not routed in raceways that could not be verified as rated for plenum use. These cables are considered unverified cables and it is assumed that some population of these unverified cables is not listed for plenum use.
These unverified cables above suspended ceilings are located in the following areas:
Fire Analysis Area AA2:
Fire Zone 87 (Makeup Water Plant Office)
Fire Zone 126 (Shift Manager's Office (SMO) and Technical Support Center (TSC))
Fire Zone 129 (Auxiliary Equipment Operator (AEO) Break Room, Online Laboratory, and Turbine office)
Fire Analysis Area AA36/42:
Fire Zone 43 (Turbine/Auxiliary Building Access (TRPAC))
The licensee provided the following basis for its request, which it stated applies to all zones except when stated otherwise:
Suspended ceiling finishes comply [ ... ] with NFPA 805, Section 3.3.3, Interior Finishes. Their supports are noncombustible.
All NSCA cables in Fire Zone 43 meet the criteria defined in Section 3.3.5.1 of NFPA 805. The population of unverified cabling consists of low-voltage communications and data network cables, which are less susceptible to self-ignition and electrical shorts that could result in a fire in the enclosed space.
CNP areas currently with suspended ceilings inside the NFPA 805 defined power block include office areas and do not affect risk significant fire scenarios. The use of non-plenum cables does not impact any NSCA PB evaluations. Fire Zone 43 contains Variance from Deterministic Requirements (VFDRs) defined in the current license basis and a detailed evaluation is provided below.
Exposed, nonplenum-rated electrical wiring located above suspended ceilings is minimal, is sufficiently dispersed, and adds limited combustible loading. CNP complies[ ... ] to NFPA 805, Section 3.3.5.3, Electrical Cable Flame Propagation Limits. Although this is recognized as not equivalent to plenum rated cable, it does reflect that most non-plenum cables have some fire resistive capability.
Page 34 of 315
 
American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                      Rev. 4 NFPPM                                                                                        Page 35 The NFPA 805 requirement to require plenum cable exceeds National Electrical Code (NEC) (NFPA 70) requirements for cables not in plenum spaces. Original fire protection installation criteria did not mandate plenum cables in suspended ceiling spaces as required by NFPA 805 (2001 ). Non-plenum spaces have stagnant air versus flowing air in plenum areas in which smoke filled air can travel through to other locations of the plant. The SMO (Fire Zone 126),
Turbine office (Fire Zone 129), on line Lab (Fire Zone 129), AEO Break Room (Fire Zone 129) and Make up Plant (Fire Zone 87) locations do not contain plenum spaces.
Based on walk downs and a review of CNP Technical Evaluations, no fixed ignition sources, per NUREG/CR-6850, were identified in the area above the suspended ceilings.
CNP modification procedures ensure that future cable installations above suspended ceilings will meet the requirements of NFPA 805 Section 3.3.5.1.
Fire barriers prevent propagation of fires to adjacent fire areas. Areas above suspended ceilings do not cross established fire barriers.
CNP procedures have been updated to specifically restrict the storage of combustible material, including extension cords above suspended ceilings.
For areas located within Fire Zone 129, areas above suspended ceilings are not used as plenum spaces and do not contain any NSCA related equipment.
There are no automatic suppression or detection systems within the suspended ceiling space for these locations. An automatic suppression system protects the exterior of the Makeup Water Plant Office (it is an enclosure. within Fire Zone 87). Ionization smoke detectors are installed below the ceilings in the AEO Break Room, the SMO and TSC, and TRPAC (Fire Zone 129, Fire Zone 43, and Fire Zone 126).
Fire barriers bound the Fire Areas comprising these zones. Hose streams are available throughout these Zones. These fire protection features, in combination with persons who routinely occupy these areas along with the dedicated fire brigade, are expected to detect and suppress fires prior to fire expanding and effecting cables/equipment in additional Fire Zones.
The licensee stated that Fire Zone 43, TRPAC, has some NSCA considerations that were evaluated further. The licensee provided a supplemental evaluation of the fire protection features and impacts on the NSCA. This included a description of the automatic fire detection system, fire doors, internal walls, and HVAC system. The licensee also described the detailed fire modeling that was performed for Fire Zone 43, Page 35 of 315
 
American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                      Rev. 4 NFPPM                                                                                        Page 36 which determined that the risk, safety margin, and DID met the acceptance criteria of NFPA 804 Section 4.2.4. The licensee stated, "There is no impact to this analysis due to the potential for minimal amounts of non-plenum exposed cables in the suspended ceiling."
The licensee stated that, in general, the presence of nonplenum-rated cables above suspended ceilings in the identified locations does not adversely affect nuclear safety capability, and that the wiring above the suspended ceilings is kept to a minimum. The licensee further stated that the low-voltage communications and data network cables are not prone to heat-generating overload faults, and that in the unlikely event of a fire occurring in the area above the suspended ceiling, there will be no impact on the ability of CNP to achieve and maintain the NSPC of NFPA 805.
The licensee stated that the location of nonplenum-rated wiring above suspended ceilings has no impact on the radioactive release performance criteria and that the radioactive release review was performed based on the potential location of radiological concerns and is independent of the type of wiring and locations of suspended ceilings. The licensee further stated that radioactive release performance criteria are satisfied based on the determination of limiting radioactive release, which is not affected by the cables above suspended ceilings that do not comply with the requirements specified in Section 3.3.5.1 of NFPA 805.
The licensee stated that power, control, and instrumentation cables are already in use in the plenum space above the Unit 1 and Unit 2 Main Control Room and complies with NFPA 805, Section 3.3.5.3, Electrical Cable Flame Propagation Limits. The licensee further stated that its fire probabilistic risk assessment (FPRA) uses historical fires and fire tests as the basis for many inputs, and, therefore, the inherent safety margin present in the FPRA methods is acceptable because NRC accepted methods are used to perform the FPRA. The licensee further stated that deviations are evaluated against the methods and criteria for the overall internal events of probabilistic risk assessment (PRA) and FPRA model development for consistency, or confirmation of bounding treatment, to confirm that the safety margin inherent in the PRA model is unaffected.
The licensee stated that the limited amount of low voltage communications/data cable above suspended ceilings is not susceptible to shorts that would result in a fire and thus, their presence above suspended ceilings has no impact on the analytical methods used in the FPRA to evaluate potential fire scenarios. Therefore, the inherent safety margin in these methods remains unchanged.
Page 36 of 315
 
American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                        Rev. 4 NFPPM                                                                                        Page 37 The licensee provided a discussion of the three elements of DID, which are: 1) prevent fires from starting, 2) rapidly detect, control and extinguish fires that do occur, thereby limiting damage, and 3) provide adequate level of fire protection for systems and structures so that a fire will not prevent essential safety functions from being performed.
With regard to preventing fires from starting, the licensee stated that the use of non-listed communication/data cables routed above the suspended ceilings does not impact the fire protection DID and that the cables do not pose an ignition hazard. The licensee further stated that its fire analysis supports the loss of all cables and equipment in the affected areas with no impact to the ability to meet the NFPA 805 performance goals.
With regard to detecting, controlling, and extinguishing fires, the licensee stated that the cables above suspended ceilings will have no effect on the performance of area suppression or detection, and that areas without automatic features are provided with manual suppression and fire brigade response. The licensee further stated that fire analysis has been performed to demonstrate any fire that does occur will be small and contained within the fire analysis area.
With regard to providing an adequate level of fire protection so that a fire will not prevent essential safety functions from being performed, the licensee stated that there are no essential safety functions impacted by a fire in any of the affected fire zones. The only exception is Fire Zone 43, which was modeled as whole room burnout with no loss in the ability to achieve or maintain the NFPA 805 Performance Goals.
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed PB method as described by the licensee in its request to use non-plenum listed cable above suspended ceilings, is an acceptable alternative to the corresponding NFPA 805, Section 3.3.5.1 requirement.
The proposed PB method is acceptable because it satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains safety margins, and maintains fire protection DID (fire prevention, fire detection, fire suppression, mitigation, and post-fire safe shutdown capability).
6.2.3.1.2 3.3.5.2 Electrical Raceway Construction Limits Page 37 of 315
 
American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                        Rev. 4 NFPPM                                                                                          Page 38 Only metal tray and metal conduits shall be used for electrical raceways.
Thin wall metallic tubing shall not be used for power, instrumentation, or control cables. Flexible metallic conduits shall only be used in short lengths to connect components. Contrary to these requirements, CNP has used electrical metallic tubing (EMT) extensively throughout the power block and that per CNP specification for cables, all exposed rigid metal conduit 2" or smaller inside the plant (excluding containment) is EMT, except as noted on drawings. Additionally, other sizes of EMT are not prohibited and EMT is used for power, instrumentation, and control cables. Further, per CNP specification, some conduit used in structural slabs is polyvinyl chloride (PVC) which is a plastic and is nonmetallic.
Regarding the use of EMT, the licensee stated that the use of EMT was not prohibited by original Fire Protection Design Guidelines, is impact resistant, and has been a basic conduit type for the life of plant at CNP.
The licensee stated that, based on a review of Corrective Action Program requests, its presence has not adversely affected NSPC, radiological release performance criteria, safety margin, or DID. Additionally, the licensee stated that the CNP cable installation specification provides installation criteria to prevent damage to cables, and limits installation of EMT in close proximity to equipment that may induce damage due to equipment vibration.
The licensee stated:
The NEC allows the use of EMT for both "exposed" and "concealed" work but the area must "not be subject to severe physical damage." Per the NFPA Report on Proposals for Revision to NFPA 805-2001, Section 3.3.5.2 of NFPA 805 was revised for consistency with the NEC (NFPA 70) to remove the requirement prohibiting thin-wall EMT. The current edition of NFPA 805 (2015), retains this change. Although the current edition of NFPA 805 is not within the CNP licensing bases, the change to NFPA 805 was made by the NFPA Technical Committee on Fire Protection for Nuclear Facilities, which is made up of experts representing varied viewpoints and interests concerning nuclear facility fire protection, through a consensus standards development process.
Regarding the use of plastic conduit, the licensee stated that the CNP cable installation specification requires that all concrete encased nonmetallic conduit be plastic, and that metallic conduit be used to extend plastic conduit runs out of the floor slabs, with the plastic not extending past the concrete surface. The nonmetallic conduit provides Page 38 of 315
 
American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                      Rev. 4 NFPPM                                                                                        Page 39 physical protection and separation for the conduit. The plastic conduit embedded in concrete is not subject to direct flame/heat impingement from an external source. The licensee stated that the NEC (NFPA 70),
allows use of rigid nonmetallic conduit for underground and embedded applications, and that no PB evaluations (i.e., use of fire modeling) were performed on VFDRs associated with embedded conduits during CNP's NFPA 805 transition on embedded conduit.
The licensee stated that the use of EMT does not affect NFPA 805 credited success paths, as conduit type is not credited to withstand the effects of fire, and, therefore, there is no impact on the NSPC.
The licensee stated that the use of nonmetallic conduit for raceways embedded in concrete is allowed by NFPA 70, NEC, and provides adequate physical and electrical protection for cables. The licensee further stated that the use of PVC conduit in embedded/buried locations does not affect nuclear safety, as the material in which conduits are run within an embedded location are not subject to the failure mechanisms that could potentially result in circuit damage or resultant damage to external targets and, therefore, there is no impact on the NSPC.
The licensee stated that the use of nonmetallic conduit in embedded/buried installations and EMT does not have any impact on the radiological release performance criteria, and that the radiological release review was performed based on the manual fire suppression capabilities in areas containing, or potentially containing, radioactive materials and is not dependent on the type of conduit material. The licensee further stated that the conduit material does not change the radiological release evaluation which concludes that potentially contaminated water is contained and smoke is monitored, and the conduits do not add additional radiological materials to the area or challenge system boundaries.
The licensee stated that EMT is noncombustible and that self-ignited cable fires contained within conduit are not postulated to spread beyond the conduit. The licensee further stated that precautions and limitations on use and installation ensure that these materials do not impact the analysis of the fire event, and, therefore, the inherent safety margin and conservatisms in these analysis methods remain unchanged.
The licensee stated that embedded nonmetallic conduit is protected from mechanical damage and from damage resulting from either an exposure fire or from a fire within the conduit impacting other targets. The licensee further stated that the areas with plastic conduit have been Page 39 of 315
 
American Electric Power                                  NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                      Rev. 4 NFPPM                                                                                        Page 40 analyzed in their current configuration and that precautions and limitations on use ensure that these materials do not impact the analysis of the fire event, and, therefore, the inherent safety margin and conservatisms in these analysis methods remain unchanged.
The licensee provided a discussion of the use of EMT on the three elements of DID. With regard to preventing fires from starting, the licensee stated that the use of EMT and embedded/buried plastic conduit does not create ignition sources and does not impact fire prevention. The licensee further stated that EMT and embedded plastic conduit have been in use since original plant construction, are allowed by the NEC, and do not increase the potential for a fire to start.
With regard to detecting, controlling, and extinguishing fires, the licensee stated that the EMT and embedded plastic conduit have no impact on the ability of the automatic suppression or detection systems to perform their functions. The licensee further stated that portable fire extinguishers and hose reel stations are available for manual firefighting activities by the site fire brigade and are unaffected by the presence of EMT and embedded/buried plastic conduit. The licensee further stated that EMT provides a similar level of cable protection during a fire as rigid conduit.
With regard to providing an adequate level of fire protection so that a fire will not prevent essential safety functions from being performed, the licensee stated that the use of EMT and embedded/buried plastic conduit does not result in compromising automatic fire suppression functions, manual fire suppression functions, or post-fire safe shutdown capability, and will not prevent essential safety functions from being performed.
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed PB method as described by the licensee in its request to use electric metallic tubing and embedded/buried polyvinyl chloride conduit, is an acceptable alternative to the NFPA 805, Section 3.3.5.2, requirement. The proposed PB method is acceptable because it satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains safety margins, and maintains fire protection DID (fire prevention, fire detection, fire suppression, mitigation, and post-fire safe shutdown capability).
Page 40 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                              Page 41 6.2.3.2    For one of the NFPA 805 Chapter 3 requirements, the licensee requested approval for the use of a performance-based method to demonstrate compliance with a fundamental FPP element.
Amendments were requested to approve deviation from the requirements of National Fire Protection Association Standard 805, Section 3.3.5.2, regarding the use of flexible metallic conduit in configurations other than to connect components, and in lengths greater than short lengths. The licensee submitted the proposed license amendment request in accordance with Title 10 of the Code of Federal Regulations, Section 50.48(c)(2)(vii), requesting to use a performance based method in a fire protection program element.
The NFPA 805 section identified in Attachment 1 as complying with this method is as follows:
3.3.5.2 Electrical Raceway Construction Limits Only metal tray and metal conduits shall be used for electrical raceways. Thin wall metallic tubing shall not be used for power, instrumentation, or control cables. Flexible metallic conduits shall only be used in short lengths to connect components.
Specifically, CNP has used flexible metallic conduit in other applications than to connect components that are original to plant construction, and flexible metallic conduit has been used at building transitions, building expansion joints, as raceway expansion joints, and in congested areas in place of complex rigid conduit or electrical metallic tubing (EMT) bends. CNP has used flexible metallic conduits in lengths greater than short lengths throughout the CNP power block and that prior to transition to NFPA 805, engineering specification for cables allowed the use of flexible metallic conduits up to 5 feet in length, and also allowed for longer lengths when approved in accordance with the configuration change process.
Based on its review of the information submitted by CNP, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed PB method as described by the licensee in its basis for the request, for the use of flexible metallic conduit in configurations other than to connect components, and for the use of flexible metallic conduit in lengths greater than short lengths, are acceptable alternatives to the corresponding NFPA 805, Section 3.3.5.2 requirements. The proposed PB methods satisfy the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains safety margins, and maintains fire protection DID (fire prevention, fire detection, fire suppression, mitigation, and post-fire safe shutdown capability).
Page 41 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                              Page 42 7.0    NATIONAL FIRE PROTECTION ASSOCIATION (NFPA) CODE COMPLIANCE REVIEWS Attachment 2, NFPA Codes of Record Summary, contains a table which includes NFPA codes of record, applicable code compliance review(s), and/or documentation which justifies compliance with each code of record.
8.0    RADIOACTIVE RELEASE REVIEW Compliance with the radioactive release performance criteria of NFPA 805 is documented in Attachment 3, Radioactive Release Review.
9.0    ENGINEERING EQIVALENCY EVALUATIONS 9.1    During the process of transition to NFPA 805 as the fire protection licensing basis, engineering equivalency evaluations (EEEs) were reviewed and documented in R1900-001-003, Existing Engineering Evaluation Review. In reviewing the EEEs, a determination was made as to whether the document reflects the present configuration of the plant; and whether it meets the criteria for an EEE as described in Nuclear Energy Institute (NEI) report 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program Under 10 CFR 50.48(c); NEI 02-03, Guidance for Performing a Regulatory Review of Proposed Changes to the Approved Fire Protection Program; and NRC Generic Letter 82- 21, Technical Specifications for Fire Protection Audits. Those EEEs which were determined to be required for compliance with the NFPA 805 fire protection program have EEE listed in the Credited As EEE column of Attachment 4, Engineering Equivalency Evaluations and Technical Evaluations.
The listing of EEEs required for the fire protection program will be maintained in Attachment 4 of this document, instead of R1900-001-003. In order to ensure that compliance with NFPA 805 is maintained, the credited bases of each EEE / Technical Evaluation listed in Attachment 4 as Credited as EEE must be maintained.
Attachment 4 also lists additional evaluations that support the fire protection program, but which do not fall within the category of suppression, detection, or boundary evaluations (i.e., not EEEs).
These Technical Evaluations do not have EEE listed in the Credited As EEE column of Attachment 4. Some of these evaluations do not have any specific relevance to NFPA 805, but are included for historical reference.
10.0  EXISTING LICENSING ACTION REVIEW 10.1  Overview of Evaluation Process The existing licensing actions (exemption requests and SEs) review was performed in accordance with NEI 04-02. The methodology for the licensing action review included the following:
Page 42 of 315
 
American Electric Power                                        NFPA 805 Fire Protection Program Manual D. C. Cook Nuclear Plant                                                                              Rev. 4 NFPPM                                                                                                Page 43 Determination of the bases for acceptability of the licensing action.
Determination that these bases for acceptability are still valid and required for NFPA 805.
10.2  Results Attachment 5 contains the detailed results of the Licensing Action Review for licensing actions which have been transitioned to NFPA 805.
The following licensing actions have been transitioned into the NFPA 805 fire protection program as previously approved (NFPA 805 Section 2.2.7). The bases for previous acceptance of these licensing actions have been verified and determined to remain valid. These licensing actions are considered acceptable under 10 CFR 50.48(c).
Exemption for the lack of automatic suppression for Fire Zone 29G, Circulating Water Pump MCC Room, Elevation 575 feet, both units (NRC SER Dated December 23, 1983)
Exemption from the requirements of 10 CFR 50 Appendix R Section III.O, Reactor Coolant Pump Oil Collection System (NRC SERs Dated December 23, 1983 and January 19, 2001) 11.0  NON-POWER OPERATIONAL MODES REVIEW NFPA 805 requires that, for a fire during operations at power, the ability to achieve and maintain safe and stable hot standby conditions is assured until the fire is extinguished and the plant is capable of transitioning to cold shutdown. Similarly, ensuring the post-fire ability to accomplish required key safety functions during non-power operational (NPO) modes is also necessary.
The goal of this NPO review is to identify fire areas where a fire affects the ability to maintain key safety functions (KSF) and to ensure that contingency plans and additional protective measures are established. During low risk periods, normal risk management controls and fire prevention / protection processes and procedures will be utilized. During NPO conditions when CNP is engaged in higher risk evolutions (HRE) the risk of losing KSFs is intrinsically high; therefore, additional protective controls/measures are established when considering potential fire impact.
The NPO review ensures that CNP can maintain or achieve its key safety functions post-fire during plant shutdown conditions from hot shutdown to refueling conditions (Modes 4 and below). The capability of CNP to achieve safe and stable (Hot Standby - Mode 3) from a fire occurring during power operation (Modes 1, 2) is covered separately under the Nuclear Safety Capability Assessment (NSCA).
The CNP NPO review is documented in Technical Evaluation R1900-005-001, Cook Nuclear Plant Non-Power Operation Modes Transition Review.
Page 43 of 315
 
American Electric Power                            Fundamental FP Program and Design Elements Review D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM - Attachment 1                                                                              Page 1-1 1.0    PURPOSE The Fundamental Fire Protection Program and Design Elements Review is intended to compare the minimum design requirements specified in each section and subsection of Chapter 3 of National Fire Protection Association (NFPA) Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 edition, to the fire protection program and design features at Cook Nuclear Plant (CNP).
2.0    METHODOLOGY The Fundamental Fire Protection Program and Design Elements Review was performed by comparing the minimum design requirements specified in each section and subsection of Chapter 3 of NFPA 805 to the fire protection program and design features at CNP in accordance with EPM Division Procedure EPM-DP-FP-008. A Fundamental Elements Review Table similar to NEI 04-02, Table B-1, has been prepared to perform the fundamental elements review. The table displays the NFPA 805 requirements, fundamental program and design elements, methods of compliance, and licensing basis references.
2.1    Determination of the Current Licensing Basis (CLB)
To determine the Current Licensing Basis (CLB), guidance documents, plant submittals to the NRC, and corresponding NRC SERs were reviewed. Through this document review, the appropriate plant licensing basis was identified as Appendix A to BTP 9.5-1.
Specific compliance statements in existing licensing documents (e.g., exemptions, SERs, etc.) are reviewed to determine prior approval of an alternative to compliance with the similar Chapter 3 attribute and documented in the Fundamental Elements Review Table. The compliance statements in previous licensing basis documents for which alternate compliance was approved by the NRC will continue to be acceptable by the NRC as long as the NFPA 805 requirement is identical to the original requirement. Although, in some cases, previously approved alternatives may contradict Section 3.1 of NFPA 805, which, in part, states, These fire protection program elements and minimum design requirements shall not be subject to the performance-based methods permitted elsewhere in this standard these will continue to acceptable to the NRC as approved alternate compliance, as long as the basis are still valid. The rationale and references used to demonstrate prior approval are documented in the Fundamental Elements Review Table (Appendix A of this attachment).
2.2    Mapping of NFPA 805 Chapter 3 Requirements to Appendix A to BTP 9.5-1 Requirements As CNP was required by the NRC to comply with Appendix A to BTP 9.5-1 prior to the adoption of NFPA 805, proof of compliance with these similar requirements is utilized in the justification of compliance with the particular section of NFPA 805. Based on the similarities between sections of NFPA 805 and those of current licensing basis documents, a review was performed to map the NFPA 805 Chapter 3 requirements to those requirements of the licensing basis Page 44 of 315
 
American Electric Power                            Fundamental FP Program and Design Elements Review D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM - Attachment 1                                                                            Page 1-2 document. For those sections and/or subsections of NFPA 805 Chapter 3 that have not been previously evaluated in the current licensing basis documentation, a review of the CNP Fire Protection Program (e.g., procedures, drawings) against each individual requirement is performed to justify compliance.
2.3    Evaluation of Compliance with NFPA 805 Chapter 3 Requirements The determination of compliance with the requirements of NFPA 805 is performed through research of plant documents including NRC SERs, correspondence between CNP and the NRC, Updated Fire Safety Analysis Report (UFSAR), plant procedures, system descriptions, and specifications. Each requirement (termed a fundamental element) in each specific section and subsection of Chapter 3 of NFPA 805 is reviewed through these plant documents for status of compliance.
The required fire protection systems and features reviewed for compliance with NFPA 805 Chapter 3 were those credited for NFPA 805 Chapter 4 deterministic separation, credited for an engineering equivalency evaluation, credited in an exemption, credited in the Fire PRA, or required for defense-in-depth, as determined by a Fire Risk Evaluation. The required fire protection systems and features are identified in the D. C. Cook Nuclear Plant Fire Safety Analysis (FSA).
3.0    OVERVIEW OF THE EVALUATION PROCESS 3.1    Each section and subsection of NFPA 805 Chapter 3 was reviewed to determine if the current CNP FPP complied with the section or subsection. The NFPA 805 Chapter 3 sections and subsections are listed in the NFPA 805 Elements column of Table B-1 provided in Appendix A of this attachment. The text of the NFPA 805 Chapter 3 section or subsection is presented in the NFPA 805 Requirement column of Table B-1. As shown in Table B-1, one or more of the following Compliance Statements was assigned to the NFPA 805 Chapter 3 section or subsection:
a) Complies was assigned to those NFPA 805 sections/subsections determined to be met by the existing CNP FPP.
b) Complies with Clarification was assigned to those NFPA 805 Chapter 3 sections/subsections determined to be met by the existing CNP FPP with the NFPA 805 Chapter 3 requirement clarified as stated in the Compliance Basis column of the table.
c) Complies by previous NRC approval was assigned to those NFPA 805 Chapter 3 sections/subsections that are not met by the existing CNP FPP, but previous NRC approval of the associated CNP configuration exists.
d) Complies with use of EEEEs was assigned to those NFPA 805 Chapter 3 sections/subsections determined to be met the by the existing CNP FPP through the use of EEEEs showing equivalency to the NFPA 805 requirement(s).
e) Submit for NRC Approval was assigned to those NFPA 805 Chapter 3 sections/subsections for which approval is requested to use performance based methods to establish compliance in Page 45 of 315
 
American Electric Power                            Fundamental FP Program and Design Elements Review D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM - Attachment 1                                                                            Page 1-3 accordance with 10 CFR 50.48(c)(2)(vii) as detailed in Attachment L to the D. C. Cook NFPA 805 Transition Report.
f) Complies with Required Action was assigned to those NFPA 805 Chapter 3 sections/subsections determined to be met by the CNP FPP after completion of an action, to be completed after submittal of the NFPA 805 License Amendment Request.
3.2    The Compliance Basis column in Table B-1 provides details regarding above defined Compliance Statements. In some cases multiple Compliance Statements were assigned to a specific NFPA 805 Chapter 3 section/subsection. Where this is the case, the Compliance Basis clearly delineates the aspects of the basis statement that correspond to the Compliance Statement.
The Reference Document column in Table B-1 identifies the CNP documents that establish compliance with the indicated NFPA 805 Chapter 3 section/subsection.
4.0    RESULTS OF THE EVALUATION PROCESS 4.1    NFPA 805 Chapter 3 Requirements Met or Previously Approved by the NRC Appendix A of this attachment contains NEI 04-02 Table B-1, Transition of Fundamental FP Program and Design Elements. This table provides the compliance basis for the requirements in NFPA 805 Chapter 3. Except as identified in Sections below, Appendix A of this attachment demonstrates that the fire protection program at CNP either:
Complies directly with the requirements of NFPA 805 Chapter 3, Compiles with clarification with the requirements of NFPA 805 Chapter 3, Complies through the use of existing engineering equivalency evaluations which are valid and of appropriate quality, or Complies with a previously NRC-approved alternative to NFPA 805 Chapter 3 and therefore the specific requirement of NFPA 805 Chapter 3 is supplanted.
Complies with a required action to be performed after submittal of the NFPA 805 License Amendment Request Page 46 of 315
 
American Electric Power                              Fundamental FP Program and Design Elements Review D. C. Cook Nuclear Plant                                                                            Rev. 4 NFPPM - Attachment 1                                                                              Page 1-4 4.2      NFPA 805 Chapter 3 Requirements Requiring Clarification of Prior NRC Approval NFPA 805 Section 3.1 states in part, Previously approved alternatives from the fundamental protection program attributes of this chapter by the AHJ take precedence over the requirements contained herein. In some cases prior NRC approval of an NFPA 805 Chapter 3 program attribute may be unclear. As a result of this review, there were no previous approvals credited that require clarification by the NRC.
4.3      NFPA 805 Chapter 3 Requirements not Previously Approved by the NRC There are no sections of NFPA 805 Chapter 3 that are not specifically met, or for which previous NRC approvals of alternatives do not exist. As such no 10 CFR 50.48(c)(2)(vii) performance-based methods will be provided in Attachment L of the D. C. Cook NFPA 805 Transition Report.
 
==5.0      REFERENCES==
 
NOTE: References utilized in demonstrating compliance with NFPA 805 Chapter 3 elements are identified in those specific subsections of Appendix A of this attachment in which they are referenced.
5.1      EPM Division Procedure EPM-DP-FP-002, Performance of Field Walkdowns, Rev. 0 5.2      EPM Division Procedure EPM-DP-FP-008, NFPA 805 Fundamental Fire Protection Program and Design Elements Review, Rev. 1 5.3      NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition 5.4      NEI 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program under 10 CFR 50.48(c), Rev. 2 5.5      NRC Regulatory Guide 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, Rev. 1 Page 47 of 315
 
American Electric Power                          Fundamental FP Program and Design Elements Review D. C. Cook Nuclear Plant                                                                        Rev. 4 NFPPM - Attachment 1                                                                          Page 1-5 NFPA 805 Chapter 3 Transition of Fundamental FP Program and Design Elements The remaining pages of Attachment 1 are Appendix A to Attachment 1, Table B-1.
Note: revision bars are not used to denote changes from Table B-1 as contained in Technical Evaluation 10.28, Technical Evaluation for NFPA Chapter 3 Fire Protection Program and Design Elements Review. This revision made changes to the B-1 table to reflect the completion of NFPA 805 implementation items and documents NRC approval of requests for approval made in the License Amendment Request.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                            Page 1A-1 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                Reference Document 3.1 General            This chapter contains the fundamental            N/A                                N/A - Section Heading, see sub- N/A elements of the fire protection program                                              sections for any specific and specifies the minimum design                                                      compliance statements.
requirements for fire protection systems and features. These fire protection program elements and minimum design requirements shall not be subject to the performance-based methods permitted elsewhere in this standard. Previously approved alternatives from the fundamental protection program attributes of this chapter by the AHJ take precedence over the requirements contained herein. N/A - Section Heading, see sub-sections for any specific compliance statements.
3.2 Fire Protection    N/A                                              N/A                                N/A - Section Heading, see sub- N/A Plan                                                                                                        sections for any specific compliance statements.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-2 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.2.1 Intent          A site-wide fire protection plan shall be          Complies                            A site-wide fire protection program  PMI-2270, Fire Protection established. This plan shall document                                                  (FPP) has been established. The      Program management policy and program                                                          purpose of the CNP FPP is to direction and shall define the                                                        incorporate, identify and discuss responsibilities of those individuals                                                  the applicable commitments, responsible for the plans                                                            documents, administrative controls, implementation. This section establishes                                              departmental responsibilities and the criteria for an integrated combination                                            activities which together form the of components, procedures, and                                                        CNP FPP.
personnel to implement all fire protection program activities.
3.2.2 Management      A policy document shall be prepared that          Complies                            The FPP procedure defines            PMI-2270, Fire Protection Policy Direction and  defines management authority and                                                      management authority and            Program Responsibility        responsibilities and establishes the                                                  responsibilities and establishes the general policy for the site fire protection                                            general policy for the site FPP.
program.
3.2.2.1 [Management    The policy document shall designate the            Complies                            The Senior Vice President/Chief      PMI-2270, Fire Protection Policy on Senior      senior management position with                                                        Nuclear Officer is responsible for  Program Management]            immediate authority and responsibility                                                development, implementation, and for the fire protection program.                                                      periodic assessment of the CNP FPP.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-3 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.2.2.2 [Management    The policy document shall designate a            Complies                            The Fire Protection Program          PMI-2270, Fire Protection Policy on Daily        position responsible for the daily                                                  Manager is responsible for assuring Program Administration]        administration and coordination of the                                              adequate implementation of the fire protection program and its                                                      overall FPP.
implementation.
3.2.2.3 [Management    The policy document shall define the fire        Complies                            PMI-2270 identifies the various      PMI-2270, Fire Protection Policy on Interfaces]  protection interfaces with other                                                    plant positions having the authority Program organizations and assign responsibilities                                            for implementing the various areas for the coordination of activities. In                                              of the FPP and identifies interfaces addition, this policy document shall                                                between the FPP and other identify the various plant positions                                                organizations.
having the authority for implementing the various areas of the fire protection program.
3.2.2.4 [Management    The policy document shall identify the          Complies                            The AHJ is identified in CNP        PMI-2270, Fire Protection Policy on AHJ]        appropriate AHJ for the various areas of                                            Procedure PMI-2270.                  Program the fire protection program.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-4 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.2.3 Procedures      Procedures shall be established for              Complies                            Procedures have been established    NFPPM, NFPA 805 Fire implementation of the fire protection                                                for implementation of the FPP.      Protection Program Manual program. In addition to procedures that                                              These procedures accomplish the      (NFPPM) could be required by other sections of the                                          requirements outlined in the sub-standard, the procedures to accomplish                                              sections of this element.            PMI-2270, Fire Protection the following shall be established:                                                                                      Program 3.2.3(1) Procedures    Inspection, testing, and maintenance for        Complies with                      Complies with clarification:        Electric Power Research Institute fire protection systems and features            Clarification                      Procedures have been established    (EPRI) Technical Report (TR) credited by the fire protection program.                                            for inspection, testing, and        1006756, Fire Protection maintenance for fire protection      Surveillance Optimization and systems and features credited by    Maintenance Guide for Fire the FPP. These procedures are        Protection Systems and Features listed in the NFPA 805 Monitoring Program Analysis (FPMP). Where      FPMP, NFPA 805 Monitoring practical, performance-based        Program Analysis surveillance frequencies may be established as described in Electric PMI-4030, Technical Power Research Institute (EPRI)      Specification Surveillance Test Technical Report (TR) 1006756,      Program Fire Protection Surveillance        PMP-2291-PLN-001, Work Optimization and Maintenance        Control Activity Planning Process Guide for Fire Protection Systems and Features.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-5 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document 3.2.3(2) Procedures    Compensatory actions implemented when            Complies                            Procedures have been established  12-FPP-2270-066-013, Control fire protection systems and other systems                                            to implement compensatory actions of Inoperable Fire Protection credited by the fire protection program                                              when fire protection systems and  Systems, Structures, or and this standard cannot perform their                                              other systems credited by the FPP Components intended function and limits on                                                      cannot perform their intended impairment duration                                                                  function.                        1-OHP-4030-066-4025, UNIT 1 NFPA 805 AND VENTILATION REQUIREMENTS FOR UNIT 2 2-OHP-4030-066-4025, UNIT 2 NFPA 805 REQUIREMENTS FOR UNIT 1 PMI-2270, Fire Protection Program PMP-2291-PLN-001, Work Control Activity Planning Process Transition Document Access Code - D.C. Cook Version 2.4.3 Page 53 of 315
 
American Electric Power                                                            NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-6 NFPA 805 Ch. 3 Ref    Requirements/Guidance                      Compliance Statement                Compliance Basis                Reference Document 3.2.3(3) Procedures    Reviews of fire protection program        Complies                            Procedures have been established PMI-4030, Technical related performance and trends                                                  for reviewing performance and    Specification Surveillance Test trends of the FPP.              Program PMP-2291-PLN-001, Work Control Activity Planning Process PMP-7034-SAP-001, Conduct of Self-Assessments Procedure 12-FPE-2270-FPMP-001, Fire Protection Required SSC Monitoring Program Transition Document Access Code - D.C. Cook Version 2.4.3 Page 54 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-7 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                Reference Document 3.2.3(4) Procedures    Reviews of physical plant modifications        Complies                            Procedures have been established PMP-5043-CCD-001, and procedure changes for impact on the                                            for reviews of physical plant    Configuration Change fire protection program                                                            modifications and procedure      Determinations changes for impact on the FPP.
Procedure 12-FPE-2270-EVL-001, Preparation and Approval of Fire Protection Technical Evaluations Procedure 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation Procedure 12-FPE-2270-RICE-001, NFPA 805 Fire Protection Program Risk Informed Change Evaluation Procedure IP-ENG-001, Standard Design Process Transition Document Access Code - D.C. Cook Version 2.4.3 Page 55 of 315
 
American Electric Power                                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-8 NFPA 805 Ch. 3 Ref    Requirements/Guidance                      Compliance Statement                Compliance Basis                      Reference Document 3.2.3(5) Procedures    Long-term maintenance and                    Complies                            Procedures have been established      Quality Assurance Program configuration of the fire protection                                            for long-term maintenance and        Description program                                                                          configuration of the FPP.
PMP-5043-CCD-001, Configuration Change Determinations Procedure 12-FPE-2270-EVL-001, Preparation and Approval of Fire Protection Technical Evaluations Procedure 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation Procedure 12-FPE-2270-RICE-001, NFPA 805 Fire Protection Program Risk Informed Change Evaluation 3.2.3(6) Procedures    Emergency response procedures for the        Complies                            An emergency response procedure      CNP Fire Pre-Plans, Volumes I, plant industrial fire brigade                                                    for the plant industrial fire brigade II, and III, has been established (Fire Pre-Plan).                                PMP-2270-FRP-001, Fire Response Plan Transition Document Access Code - D.C. Cook Version 2.4.3 Page 56 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-9 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.3 Prevention        A fire prevention program with the goal            Complies                            The CNP FPP establishes,            PMI-2270, Fire Protection of preventing a fire from starting shall be                                            documents, and implements,          Program established, documented, and                                                          specific requirements for fire implemented as part of the fire protection                                            prevention. The two basic program. The two basic components of                                                  components of fire prevention are the fire prevention program shall consist                                              met as described in the sub-of both of the following:                                                              sections of this element.
3.3(1) Prevention      Prevention of fires and fire spread by            Complies                            CNP procedures establish controls  12-FPP-2270-066-011, Fire controls on operational activities                                                    on operation activities in order to Watch Activities prevent fires and fire spread.
PMI-2270, Fire Protection Program PMP-2270-CCM-001, Control of Combustible Materials PMP-2270-WBG-001, Welding, Burning and Grinding Activities 3.3(2) Prevention      Design controls that restrict the use of          Complies                            CNP procedures establish design    PMI-2270, Fire Protection combustible materials                                                                  controls that restrict the use of  Program combustible materials.
The design control requirements listed in                                                                                  Procedure 12-FPE-2270-FPCE-the remainder of this section shall be                                                                                    001, Fire Protection Program provided as described.                                                                                                    Change Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 57 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                            Page 1A-10 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.3.1 Fire Prevention  The fire prevention program activities            Complies                            CNP procedures establish              Quality Assurance Program for Operational        shall consist of the necessary elements to                                            requirements to address the control    Description Activities            address the control of ignition sources                                              of ignition sources and the use of and the use of transient combustible                                                  transient combustible materials        12-FPP-2270-066-012, Transient materials during all aspects of plant                                                during all aspects of plant            Combustible Monitoring operations. The fire prevention program                                              operations. These procedures focus PMI-2270, Fire Protection shall focus on the human and                                                          on the human and programmatic Program programmatic elements necessary to                                                    elements necessary to prevent fires prevent fires from starting or, should a                                              from starting or, should a fire start, PMP-2270-CCM-001, Control of fire start, to keep the fire as small as                                              to keep the fire as small as          Combustible Materials possible.                                                                            possible.
PMP-2270-WBG-001, Welding, Burning and Grinding Activities 3.3.1.1 General Fire  The fire prevention activities shall              Complies                            Plant procedures for fire              Refer to basis documentation in Prevention Activities  include but not be limited to the                                                    prevention activities have been        the sub-sections of this element.
following program elements:                                                          implemented. The procedures address, at a minimum, the FPP elements identified in this section, but are not limited to these elements. The NFPA 805 code requirements for this element are satisfied.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-11 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.3.1.1(1) General    Training on fire safety information for all      Complies                            I&M establishes training            DCC-CEST-200-QCS, Auxiliary Fire Prevention        employees and contractors including, as a                                            requirements for all plant          Building Reroofing Section Activities            minimum, familiarization with plant fire                                              personnel, including plant fire    07526 Modified Bitumous Sheet prevention procedures, fire reporting, and                                            prevention procedures, fire        Roofing Seismic Class III plant emergency alarms                                                                reporting, and familiarization with Application plant emergency alarms.
Nuclear Energy Institute (NEI) 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program under 10 CFR 50.48(c), Rev. 2 / Section K.3 (FAQ 06-0028)
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-12 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.3.1.1(2) General    Documented plant inspections including        Complies                            CNP procedures establish            12-FPP-2270-066-011, Fire Fire Prevention        provisions for corrective actions for                                              requirements for spot plant        Watch Activities Activities            conditions where unanalyzed fire hazards                                          inspections to ensure that are identified                                                                    combustibles are properly          12-FPP-2270-066-012, Transient controlled and are not allowed to  Combustible Monitoring accumulate in amounts that are in excess of that analyzed in the Fire Safety Analysis (FSA). Periodic tours by the fire brigade are established by station procedures (FPCE-2017-0021). If problems with conditions or combustible loading are identified, corrective actions are required to be taken.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-13 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.3.1.1(3) General    Administrative controls addressing the          Complies                            Procedures have been established    PMP-5043-CCD-001, Fire Prevention        review of plant modifications and                                                  for reviews of physical plant        Configuration Change Activities            maintenance to ensure that both fire                                                modifications and maintenance for    Determinations hazards and the impact on plant fire                                                impact on the FPP.
protection systems and features are                                                                                      Procedure 12-EHP-2270-FPCE-minimized                                                                                                                001, Fire Protection Program Change Evaluation Procedure 12-FPE-2270-EVL-001, Preparation and Approval of Fire Protection Technical Evaluations Procedure 12-FPE-2270-RICE-001, NFPA 805 Fire Protection Program Risk Informed Change Evaluation Procedure IP-ENG-001, Standard Design Process 3.3.1.2 Control of    Procedures for the control of general          Complies                            Plant procedures for the control of  12-FPP-2270-066-012, Transient Combustible            housekeeping practices and the control of                                          general housekeeping practices and  Combustible Monitoring Materials              transient combustibles shall be developed                                          the control of transient and implemented. These procedures shall                                            combustibles have been              PMP-2220-HSK-001, include but not be limited to the                                                  implemented. The procedures          Housekeeping and Material following program elements:                                                        address, at a minimum, the FPP      Condition elements identified in this section, PMP-2270-CCM-001, Control of but are not limited to these elements.                            Combustible Materials Transition Document Access Code - D.C. Cook Version 2.4.3 Page 61 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-14 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.3.1.2(1) Control of  Wood used within the power block shall          Complies                            Wood smaller than 6 inch by 6      PMP-2270-CCM-001, Control of Combustible            be listed pressure-impregnated or coated                                            inch used in the power block shall  Combustible Materials Materials              with a listed fire-retardant application.                                            be listed pressureimpregnated or coated with a listed fire-retardant Exception: Cribbing timbers 6 in. by 6 in.                                          paint. Wood materials not meeting (15.2 cm by 15.2 cm) or larger shall not                                            this requirement will be monitored be required to be fire-retardant treated.                                            by trained fire watch personnel (FPPR-2015-0002).
3.3.1.2(2) Control of  Plastic sheeting materials used in the          Complies                            All sheet plastic used in the power PMP-2270-CCM-001, Control of Combustible            power block shall be fire-retardant types                                            block is required to meet the      Combustible Materials Materials              that have passed NFPA 701, "Standard                                                requirements of NFPA 701.
Methods of Fire Tests for Flame Propagation of Textiles and Films" Transition Document Access Code - D.C. Cook Version 2.4.3 Page 62 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-15 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.3.1.2(3) Control of  Waste, debris, scrap, packing materials,        Complies                            Whenever possible, equipment or      12-FPP-2270-066-012, Transient Combustible            or other combustibles shall be removed                                              parts shipped or packed in          Combustible Monitoring Materials              from an area immediately following the                                              combustible materials are required completion of work or at the end of the                                            to be removed from their shipping    PMP-2220-HSK-001, shift, whichever comes first.                                                      crates or containers prior to those  Housekeeping and Material items being taken into a safety      Condition related area. Those items that PMP-2270-CCM-001, Control of cannot be removed from shipping/packing materials may be    Combustible Materials taken into safety related areas when needed, unpacked and the shipping/packing materials immediately removed.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-16 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with                      All waste, debris, scrap, or other  12-FPP-2270-066-012, Transient Clarification                      combustibles resulting from an      Combustible Monitoring activity is required to be cleaned up, and stored in proper containers PMP-2220-HSK-001, or removed from the area during    Housekeeping and Material the work activity, upon completing  Condition the activity and/or at the end of PMP-2270-CCM-001, Control of each work shift. All waste is required to be disposed of in      Combustible Materials proper containers.                  Procedure 12-FPE-2270-FPCE-001, Fire Protection Program Procedure PMP-2270-CCM-001,        Change Evaluation Control of Combustible Materials, provides guidance for limiting the quantity and duration of combustible materials (e.g.,
debris, packing materials etc.) for safety-related and critical buildings. These requirements include: (1) a review by the Fire Protection Supervisor/Designee for Compensatory actions (e.g., fire watch tour, storage in metal container etc.) if anticipated combustibles are to exceed the Fire Safety Analysis (FSA) allowable limits and (2) a review by Fire Protection Engineering to assure that all long term/permanent combustibles comply with licensing bases requirements.
Procedure 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation, provides guidance for review of combustible loading on fire protection/safe shutdown equipment/components and installation activities. These Transition Document Access Code - D.C. Cook Version 2.4.3 Page 64 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                          Page 1A-17 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                  Reference Document controls comply with NFPA 805, Section 3.3.1.2 (4), which allows combustible storage to be used if such storage is in a designated storage/staging area with limits placed on the types and quantities of stored materials. Additionally, CNP has a Clean As You Go Policy as described in Procedure PMP-2220-HSK-001, "Housekeeping and material Condition", to preclude in-situ storage of waste, debris, scrap packing materials, or other combustibles as required by NFPA 805.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-18 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.3.1.2(4) Control of  Combustible storage or staging areas              Complies                            Transient combustible storage is    FSA, D. C. Cook Fire Safety Combustible            shall be designated, and limits shall be                                              controlled on the basis of physical  Analysis Materials              established on the types and quantities of                                            location and restricted to the stored materials.                                                                    limitations set forth in the D. C. PMP-2270-CCM-001, Control of Cook Fire Safety Analysis (FSA). Combustible Materials CNP has chosen graded approach to combustible material control based on multiple factors including risk significance of the room, current in-situ combustible loading, as well as potential to exceed the combustible loading limits set forth in the Fire Safety Analysis.
(FPCE-2017-0021).
3.3.1.2(5) Control of  Controls on use and storage of flammable          Complies with                      Plant procedures are in place to    Nuclear Energy Institute (NEI)
Combustible            and combustible liquids shall be in              Clarification                      control the use and storage of      04-02, Guidance for Materials              accordance with NFPA 30, "Flammable                                                  flammable and combustible            Implementing a Risk-Informed, and Combustible Liquids Code, or other                                                liquids. These controls use NFPA    Performance-Based Fire applicable NFPA standards."                                                          30 as a developmental reference. Protection Program under 10 CFR 50.48(c), Rev. 2 / Section No other NFPA Standards were        K.1 (FAQ 06-0020) determined to be applicable based on guidance in NEI 04-02, section    PMP-2270-CCM-001, Control of K.1 (FAQ 06-0020).                  Combustible Materials Transition Document Access Code - D.C. Cook Version 2.4.3 Page 66 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-19 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                  Reference Document Complies with Use of                CNP complies with NFPA 30,        NFPA 30 Code Compliance EEEEs                              1987 edition, as evaluated in the Evaluation for Donald C. Cook CNP NFPA 30 Code Compliance      Nuclear Plant Unit 1 and 2, dated Evaluation.                      July 25, 1990 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications 3.3.1.2(6) Control of  Controls on use and storage of flammable      Complies with                      A plant procedure is in place to  Nuclear Energy Institute (NEI)
Combustible            gases shall be in accordance with              Clarification                      control use and storage of        04-02, Guidance for Materials              applicable NFPA standards.                                                        flammable gases. These controls  Implementing a Risk-Informed, use NFPA 50A "Standard for        Performance-Based Fire Gaseous Hydrogen Systems at      Protection Program under 10 Consumer Sites", as a            CFR 50.48(c), Rev. 2 / Section developmental reference.          K.1 (FAQ 06-0020)
No other NFPA Standards were      PMP-2270-CCM-001, Control of determined to be applicable based Combustible Materials on guidance in NEI 04-02, section K.1 (FAQ 06-0020)
Complies with Use of                CNP complies with NFPA 50A,      Engineering Equivalency EEEEs                              1999 edition, as evaluated in    Evaluation 14-1-1, CNP Fire Engineering Equivalency          Protection Code Conformance Evaluation 14.1.1.                Review Transition Document Access Code - D.C. Cook Version 2.4.3 Page 67 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-20 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document 3.3.1.3 Control of    Control of Ignition Sources.                    N/A                                N/A - Section Heading, see sub-    N/A Ignition Sources                                                                                          sections for any specific compliance statements.
3.3.1.3.1 [Control of  A hot work safety procedure shall be            Complies with                      A hot work safety procedure and a  12-FPP-2270-066-011, Fire Ignition Sources      developed, implemented, and                    Clarification                      fire watch procedure have been    Watch Activities Code Requirements]    periodically updated as necessary in                                                developed, implemented, and are accordance with NFPA 51B, "Standard                                                periodically updated as necessary. PMP-2270-WBG-001, Welding, for Fire Prevention During Welding,                                                Fire watch personnel may have      Burning and Grinding Activities Cutting, and Other Hot Work", and                                                  multiple duties.
NFPA 241, "Standard for Safeguarding Construction, Alteration, and Demolition Operations."
Complies with Use of                The hot work safety procedure and  Engineering Equivalency EEEEs                              fire watch procedure comply with  Evaluation 14-1-1, CNP Fire the requirements of NFPA 51B,      Protection Code Conformance 1971 Edition, and NFPA 241, 2000  Review Edition, as evaluated in Engineering Equivalency Evaluation 14.1.1.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-21 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.3.1.3.2 [Control of  Smoking and other possible sources of          Complies                            Smoking is not allowed in any          PMI-2270, Fire Protection Ignition Sources      ignition shall be restricted to properly                                            plant building or any other specific  Program Smoking Limitations]  designated and supervised safe areas of                                            area posted as "No Smoking", per the plant.                                                                          procedure PMI-2270. Restrictions for other possible ignition sources are addressed by sections 3.3.1.3.1, 3, and 4.
3.3.1.3.3 [Control of  Open flames or combustion-generated            Complies                            Precautions and limitations are        12-FPP-2270-066 Series Ignition Sources for  smoke shall not be permitted for leak or                                            listed for all fire protection testing Leak Testing]          air flow testing.                                                                  procedures. These precautions and      Procedure, 2-IHP-4030-266 limitations require that there be no  Series deviations from the listed test Procedure, 1-IHP-4030-166 sequence unless specific Series instructions to the contrary exist within the test procedure. Test procedures do not use open flames or combustion-generated smoke for leak or air flow testing.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 69 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                            Page 1A-22 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.3.1.3.4 [Control of  Plant administrative procedure shall              Complies                            CNP procedures control the use of Ignition sources on    control the use of portable electrical                                                portable electrical heaters in the    PMI-2270, Fire Protection Portable Heaters]      heaters in the plant. Portable fuel-fired                                              plant. CNP procedures also require    Program heaters shall not be permitted in plant                                                that portable fuel-fired heaters are areas containing equipment important to                                                not permitted in plant areas          PMP-2270-CCM-001, Control of nuclear safety or where there is a                                                    containing equipment important to      Combustible Materials potential for radiological releases                                                    nuclear safety or where there is a resulting from a fire.                                                                potential for radiological releases resulting from a fire.
3.3.2 Structural      Walls, floors, and components required            Complies                            Interior walls, floors, and structural Procedure 12-EHP-2270-FPCE-to maintain structural integrity shall be of                                          components are noncombustible.        001, Fire Protection Program noncombustible construction, as defined                                                Noncombustible is defined by          Change Evaluation in NFPA 220, "Standard on Types of                                                    NFPA 220-1999 edition, as a Building Construction."                                                                material that, in the form in which it is used and under the conditions anticipated, will not ignite, burn, support combustion, or release flammable vapors when subjected to fire or heat.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-23 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                By the response to Appendix A to      I&M response to Appendix A to NRC Approval                        Branch Technical Position APCSB      Branch Technical Position 9.5-1 for Units No. 1 and 2, dated    APCSB 9.5-1 for Units No. 1 and January 31, 1977, item D.1.(d)        2, dated January 31, 1977 / item I&M stated:                          D.1.(d)
                                                                                        "Interior wall and structural components, thermal insulation,      NRC Safety Evaluation radiation shielding, and sound        supporting Amendment Nos. 31 proofing are, to the extent possible, and 12 to License No. DPR-58 noncombustible or have the UL        and DPR-74, dated July 31, 1979 flame spread, smoke, and fuel        / Page 79 contribution rating of 25 or less.
Where this was not possible, these materials are protected by other means. In the two cases where this occurred (noted below) the following was done:
Building expansion or seismic gaps were filled in some cases with urethane or styrene foam plastic to act as a seal to prevent infiltration of air or sand, or to act as non-removable forms between concrete pours. In areas where this material violated fire rated walls or where the material, if ignited, could potentially damage adjacent equipment; a fire proofing method was devised by raking out the foam plastic to a four or six inch depth, filling the void with rolled refractory fiber insulation held in place with glass fiber screening and noncombustible silicone adhesive, all of which is covered with a glass fiber reinforced Transition Document Access Code - D.C. Cook Version 2.4.3 Page 71 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-24 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document silicone sheet material cemented to the concrete walls with noncombustible silicone adhesive.
Tests of this concept were conducted in March 1975. The test was an ASTM E-119 wall test where the refractory fiber/silicone sheet was used to seal a pipe sleeve. After five hours of exposure, the seal was still intact and functional."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "We conclude that the administrative controls [including controls on construction of walls, floors and components required to maintain structural integrity], fire brigade equipment and training conform to the recommendations of the National Fire Protection Association and Appendix A to Branch Technical Position 9.5-1 and are, therefore, acceptable."
The noncombustible features (i.e.
the expansion and seismic gap filling materials, the interior wall and structural components, thermal insulation, radiation shielding and sound proofing), as approved by the SE Report, are still installed at CNP. There have been no plant modifications or other changes that would invalidate the basis for Transition Document Access Code - D.C. Cook Version 2.4.3 Page 72 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                        Page 1A-25 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                  Reference Document approval. These features have not been changed.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                                                            Page 1A-26 NFPA 805 Ch. 3 Ref      Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.3.3 Interior Finishes Interior wall or ceiling finish                  Complies by Previous                By the response to Appendix A to      NRC Safety Evaluation classification shall be in accordance with        NRC Approval                        Branch Technical Position APCSB      supporting Amendment Nos. 31 NFPA 101, "Life Safety Code",                                                        9.5-1 for Units No. 1 and 2, dated    and 12 to License No. DPR-58 requirements for Class A materials.                                                  January 31, 1977, item D.1.(d)        and DPR-74, dated July 31, 1979 Interior floor finishes shall be in                                                  I&M stated:                          / page 17 accordance with NFPA 101 requirements for Class I interior floor finishes.                                                  "Interior wall and structural        I&M response to Appendix A to components, thermal insulation,      Branch Technical Position radiation shielding, and sound        APCSB 9.5-1 for Units No. 1 and proofing are, to the extent possible, 2, dated January 31, 1977 / item noncombustible or have the UL        D.1.(d) flame spread, smoke, and fuel contribution rating of 25 or less."  I&M Letter to NRC, Control Room Carpeting, dated May 30, The NRC Safety Evaluation, dated      1986 July 31, 1979 states:
NRC Safety Evaluation, Installation of Carpet in the "We conclude that the Control Rooms, dated June 16, administrative controls [including interior wall, ceiling and floor      1988 finishes], fire brigade equipment    PMI-2270, Fire Protection and training conform to the          Program recommendations of the National Fire Protection Association and      Procedure 12-EHP-2270-FPCE-Appendix A to Branch Technical        001, Fire Protection Program Position 9.5-1 and are, therefore,    Change Evaluation acceptable."
By {{letter dated|date=May 30, 1986|text=letter dated May 30, 1986}}, I&M informed the NRC that carpeting had been installed in both units' control rooms to close out human factors concerns as a result of the Detailed Control Room Design Review. The licensee stated that this carpeting had a flame spread rating of 30 which is higher than the 25 recommended by NRC staff guidance. The carpeting also has a Transition Document Access Code - D.C. Cook Version 2.4.3 Page 74 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-27 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document radiant flux rating of .98 watts/cm.
The NRC Safety Evaluation, "Installation of Carpet in the Control Rooms", dated June 16, 1988 states:
                                                                                        "The carpeting installed in the control room deviates from NRC staff guidance because the flame spread rating is higher than identified in Section D.1.d of Appendix A to BTP APCSB 9.5-1.
The concern is that a fire involving carpeting with a high flame spread could propagate rapidly, potentially damaging safe shutdown equipment and also making the control room uninhabitable. However, the flame spread of the carpeting installed in the D.C. Cook control rooms is only slightly higher than staff guidance, 30 versus 25.
Since the issuance of the staff guidelines, objections have been raised in the fire protection industry regarding the measure of flame spread to evaluate floor coverings. The test method used to evaluate flame spread, NFPA 255, "Surface Burning Characteristics of Building Materials," holds the test specimen upside down in a position that bears no resemblance to its position when it is installed.
In a effort to correctly assess the flame spread hazard of floor Transition Document Access Code - D.C. Cook Version 2.4.3 Page 75 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-28 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document coverings, the concept of radiant flux was used and NFPA 253, "Standard Method of Test for Critical Radiant Flux of Floor Covering Systems Using a Radiant Heat Energy Source" was developed. NFPA 253 involves subjecting a horizontal floor covering specimen to a radiant energy flux which decreases along the length of the specimen according to a standard energy flux vs. distance profile. The higher the critical heat flux rating a carpet has, the more resistive it is to flame spread.
The subject carpeting has a critical heat flux of .98 watts/cm(2). This rating is significantly higher than the minimum of 0.45 watts/cm(2) used to define a Class I interior finish in NFPA 101, "Life Safety Code." Since the control rooms are continuously manned, fires would be detected quickly and extinguished using portable fire extinguishers. Based on the above, there is reasonable assurance that the slightly higher flame spread rating of control room carpeting would not adversely affect plant safety.
Based on the above evaluation, the staff finds that the installation of carpeting in the control rooms which has a flame spread rating of 30 is an acceptable deviation from Transition Document Access Code - D.C. Cook Version 2.4.3 Page 76 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-29 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document the guidance provided in Appendix A to BTP APCSB 9.5-1, Section D.1.d."
The carpeting, as approved by the SE Report, is still installed in the control room at CNP. There have been no plant modifications or other changes that would invalidate the basis for approval. The carpeting features remain unchanged.
Complies with Use of                Epoxy floor coating is used in      Engineering Equivalency EEEEs                              some fire areas. This has been      Evaluation 11-55, Flammability evaluated as acceptable via an      of Floor Coating Systems Engineering Equivalency Evaluation and AR GT00120103.        AR GT00120103 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 77 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-30 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                Reference Document 3.3.4 Insulation      Thermal insulation materials, radiation        Complies                            Thermal insulation materials,    12-THP-6010-RPP-015, Materials              shielding materials, ventilation duct                                              shielding materials, ventilation Temporary Shielding materials, and soundproofing materials                                            duct materials and soundproofing shall be noncombustible or limited                                                materials at CNP are of limited  ES-HVAC-0804-QCN, Nuclear combustible.                                                                      combustibility.                  Grade Ductwork ES-HVAC-0806-QCS, Conventional HVAC Ductwork ES-PIPE-1007-QCS, Thermal Insulation Procedure 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 78 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-31 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                By the response to Appendix A to      NRC Safety Evaluation NRC Approval                        Branch Technical Position APCSB      supporting Amendment Nos. 31 9.5-1 for Units No. 1 and 2, dated    and 12 to License No. DPR-58 January 31, 1977, item D.1.(d)        and DPR-74, dated July 31, 1979 I&M stated:                          / page 17 and table 1, item 8.
                                                                                        "Interior wall and structural        I&M response to Appendix A to components, thermal insulation,      Branch Technical Position radiation shielding, and sound        APCSB 9.5-1 for Units No. 1 and proofing are, to the extent possible, 2, dated January 31, 1977 / item noncombustible or have the UL        D.1.(d) flame spread, smoke, and fuel contribution rating of 25 or less.
Where this was not possible, these materials are protected by other means. In the two cases where this occurred (noted below) the following was done:
Building expansion or seismic gaps were filled in some cases with urethane or styrene foam plastic to act as a seal to prevent infiltration of air or sand, or to act as non-removable forms between concrete pours. In areas where this material violated fire rated walls or where the material, if ignited, could potentially damage adjacent equipment; a fire proofing method was devised by raking out the foam plastic to a four or six inch depth, filling the void with rolled refractory fiber insulation held in place with glass fiber screening and noncombustible silicone adhesive, all of which is covered with a glass fiber reinforced silicone sheet material cemented to Transition Document Access Code - D.C. Cook Version 2.4.3 Page 79 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-32 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document the concrete walls with noncombustible silicone adhesive.
Tests of this concept were conducted in March 1975. The test was an ASTM E-119 wall test where the refractory fiber/silicone sheet was used to seal a pipe sleeve. After five hours of exposure, the seal was still intact and functional."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "We conclude that the administrative controls [including controls on thermal insulation, radiation shielding materials, ventilation duct materials and soundproofing materials], fire brigade equipment and training conform to the recommendations of the National Fire Protection Association and Appendix A to Branch Technical Position 9.5-1 and are, therefore, acceptable."
The noncombustible features (i.e.
the expansion and seismic gap filling materials, the interior wall and structural components, thermal insulation, radiation shielding and sound proofing), as approved by the SE Report, are still used at CNP. There have been no plant modifications or other changes that would invalidate the basis for approval. These features have not been changed.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                      Page 1A-33 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                Reference Document 3.3.5 Electrical.      Electrical                  N/A                                N/A - Section Heading, see sub- N/A sections for any specific compliance statements Transition Document Access Code - D.C. Cook Version 2.4.3 Page 81 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-34 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.3.5.1 [Electrical    Wiring above suspended ceiling shall be        Complies by Previous                By the response to Appendix A to    NRC Safety Evaluation Wiring Above          kept to a minimum. Where installed,            NRC Approval                        Branch Technical Position APCSB    supporting Amendment Nos. 31 Suspended Ceiling      electrical wiring shall be listed for                                              9.5-1 for Units No. 1 and 2, dated  and 12 to License No. DPR-58 Limitations]          plenum use, routed in armored cable,                                                January 31, 1977, item D.1.(f)      and DPR-74, dated July 31, 1979 routed in metallic conduit, or routed in                                            I&M stated:                        / page 17 and table 1, item 3.D.1.
cable trays with solid metal top and bottom covers.                                                                      "The only locations containing      I&M response to Appendix A to Class I equipment with suspended    Branch Technical Position ceilings are each of the control    APCSB 9.5-1 for Units No. 1 and rooms. The ceiling in this case    2, dated January 31, 1977 / item consists of acoustic metal tiles    D.1.(f) which are noncombustible, and plastic diffusers (egg crate) under EC-0000054707, UNIT 1 the recessed fluorescent lighting. CONTROL ROOM These diffusers meet the UL 25      FLUORESCENT LIGHTING flame spread requirements."        REPLACEMENT TO LED EC-0000054824, UNIT 2 The NRC Safety Evaluation, dated CONTROL ROOM July 31, 1979 states:
FLUORESCENT LIGHTING "We conclude that the              REPLACEMENT TO LED administrative controls [including  Procedure 12-FPE-2270-FPCE-controls on wiring above            001, Fire Protection Program suspended ceilings], fire brigade  Change Evaluation equipment and training conform to the recommendations of the National Fire Protection Association and Appendix A to Branch Technical Position 9.5-1 and are, therefore, acceptable."
EC-0000054707 and EC-0000054824 changed the fluorescent lighting to LED lighting and replaced the (egg crate) diffusers with polycarbonate prismatic diffusers that meet the flame spread and smoke generation requirements of NFPA 286 for a Transition Document Access Code - D.C. Cook Version 2.4.3 Page 82 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                        Page 1A-35 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                  Reference Document ceiling application in the Unit 1 and Unit 2 Main Control Rooms.
[FPCE-2016-0017]
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-36 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies by NRC                    Contrary to these requirements,      None Approval                            CNP has wiring installed above suspended ceilings not routed in raceways that could not be verified as rated for plenum use. These cables are considered unverified cables and it is assumed that some population of these unverified cables is not listed for plenum use.
These unverified cables above suspended ceilings are located in the following areas:
Fire Analysis Area AA2:
Fire Zone 87 (Makeup Water Plant Office)
Fire Zone 126 (Shift Manager's Office (SMO) and Technical Support Center (TSC))
Fire Zone 129 (Auxiliary Equipment Operator (AEO) Break Room, Online Laboratory, and Turbine office)
Fire Analysis Area AA36/42:
Fire Zone 43 (Turbine/Auxiliary Building Access (TRPAC))
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed PB method as described by the licensee in its request to use non-plenum listed cable above suspended ceilings, is an acceptable alternative to the corresponding NFPA 805, Section 3.3.5.1 requirement. The proposed PB method is acceptable because it Transition Document Access Code - D.C. Cook Version 2.4.3 Page 84 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-37 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains safety margins, and maintains fire protection DID (fire prevention, fire detection, fire suppression, mitigation, and post-fire safe shutdown capability).
This approval was provided in ML18131A253 dated July 6, 2018.
3.3.5.2 [Electrical    Only metal tray and metal conduits shall        Complies with                      All exposed electrical raceways are ES-CABLE-0221-QCN, Design Raceway                be used for electrical raceways. Thin wall      Clarification                      metal tray or metal conduit. In    and Installation Criteria for Construction Limits]  metallic tubing shall not be used for                                              general, all cable is run through  Cable, Trough, and Conduit power, instrumentation, or control cables.                                          conduits or trays, with the Flexible metallic conduits shall only be                                            exception of short cable air drops. Nuclear Energy Institute (NEI) used in short lengths to connect                                                    The approximately 3 foot air drops  04-02, Guidance for components.                                                                        align with the guidance of Section  Implementing a Risk-Informed, K.4 to NEI-04-02 (FAQ 06-0021)      Performance-Based Fire and are therefore acceptable.      Protection Program under 10 CFR 50.48(c), Rev. 2 / Section K.4 (FAQ 06-0021)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-38 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies by NRC                    Contrary to these requirements,      None Approval                            CNP has used electrical metallic tubing (EMT) extensively throughout the power block and that per CNP specification for cables, all exposed rigid metal conduit 2" or smaller inside the plant (excluding containment) is EMT, except as noted on drawings.
Additionally, other sizes of EMT are not prohibited and EMT is used for power, instrumentation, and control cables. Further, per CNP specification, some conduit used in structural slabs is polyvinyl chloride (PVC) which is a plastic and is nonmetallic.
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed PB method as described by the licensee in its request to use electric metallic tubing and embedded/buried polyvinyl chloride conduit, is an acceptable alternative to the NFPA 805, Section 3.3.5.2, requirement. The proposed PB method is acceptable because it satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains safety margins, and maintains fire protection DID (fire prevention, fire detection, fire suppression, Transition Document Access Code - D.C. Cook Version 2.4.3 Page 86 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-39 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document mitigation, and post-fire safe shutdown capability).
This approval was provided in ML18131A253 dated July 6, 2018.
Contrary to these requirements, CNP has used flexible metallic conduit in configurations other than to connect components, and in lengths greater than short lengths throughout the power block.
Based on its review of the information submitted by the licensee, and in accordance with 10 CFR 50.48(c)(2)(vii), the NRC staff concludes that the proposed PB method for the use of flexible metallic conduit in lengths greater than short lengths, and for the use of flexible metallic conduit in configurations other than to connect components, are acceptable alternatives to the NFPA 805, Section 3.3.5.2, requirement. In each case, the proposed PB method is acceptable because it satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release, maintains safety margins, and maintains fire protection DID (fire prevention, fire detection, fire suppression, mitigation, and post-fire safe Transition Document Access Code - D.C. Cook Version 2.4.3 Page 87 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-40 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis              Reference Document shutdown capability).
This approval was provided in ML18284A254 dated November 16, 2018.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                          Page 1A-41 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.3.5.3 [Electrical    Electric cable construction shall comply          Complies by Previous                By the response to Appendix A to      NRC Safety Evaluation Cable Flame            with a flame propagation test as                  NRC Approval                        Branch Technical Position APCSB      supporting Amendment Nos. 31 Propagation Limits]    acceptable to the AHJ.                                                                9.5-1 for Units No. 1 and 2, dated    and 12 to License No. DPR-58 January 31, 1977, item D.3.(f)        and DPR-74, dated July 31, 1979 Note: the exception to this section is not                                            I&M stated:                          / page 17.
endorsed by 10 CFR 50.48(c)(2)(v) and has been removed.                                                                    "Cables used in Unit 1 were not      I&M response to Appendix A to required to pass any fire test at    Branch Technical Position time of purchase. Samples of all      APCSB 9.5-1 for Units No. 1 and cables were subjected to the          2, dated January 31, 1977 / item IPCEA S-19-81 paragraph 6.19.6        D.3.(f) vertical flame resisting test. The vertical flame test IPCEA S-19 is    ES-CABLE-0221-QCN, Design adequate to show the flame            and Installation Criteria for resistance capability of these        Cable, Trough, and Conduit cables since they are already in FAQ 06-0022, Acceptable use. All cables passed this test with Electrical Cable Construction the exception of 600 volt, Tests, Rev. 3 / All Sections unjacketed, power cables using cross linked polyethylene            Procedure 12-FPE-2270-FPCE-insulation and one type of two        001, Fire Protection Program conductor control cable supplied      Change Evaluation by one of the two manufacturers who supplied the cable. This cable is currently installed in Unit 1 and there are no present plans to replace the cable. Cable insulation materials were selected for their electrical properties, radiation and containment environment resistance at the time of their purchase for Unit 1. Flame resistance properties were not the only factors to consider when Unit 1 cables were-purchased."
                                                                                                            "All cables installed in Unit 2 were documented to have passed the vertical flame test of IPCEA Transition Document Access Code - D.C. Cook Version 2.4.3 Page 89 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-42 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document S-19-81 Para. 6.19.6. Power cables used on safety systems within the containment were documented to pass the vertical flame test of IEEE 383."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "We conclude that the administrative controls [including cable construction], fire brigade equipment and training conform to the recommendations of the National Fire Protection Association and Appendix A to Branch Technical Position 9.5-1 and are, therefore, acceptable."
The electrical cables, as approved by the SE Report, are still installed at CNP. There have been no plant modifications or other changes that would invalidate the basis for approval.
Any new cable installed at CNP will be constructed similar or superior to the original cable and meeting the requirements of IEEE-383 or equivalent tests per FAQ 06-0022.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-43 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.3.6 Roofs            Metal roof deck construction shall be            Complies by Previous                By the response to Appendix A to      NRC Safety Evaluation designed and installed so the roofing            NRC Approval                        Branch Technical Position APCSB      supporting Amendment Nos. 31 system will not sustain a self-propagating                                          9.5-1 for Units No. 1 and 2, dated    and 12 to License No. DPR-58 fire on the underside of the deck when                                              January 31, 1977, item D.1.(d),      and DPR-74, dated July 31, 1979 the deck is heated by a fire inside the                                              I&M stated:                          / page 17 building. Roof coverings shall be Class A as determined by tests described in                                                  The auxiliary building roof at        I&M response to Appendix A to NFPA 256, "Standard Methods of Fire                                                  Cook Plant is reinforced concrete    Branch Technical Position Tests of Roof Coverings."                                                            over metal pan (Q deck) ceiling.      APCSB 9.5-1 for Units No. 1 and To prevent condensation it was        2, dated January 31, 1977 / item necessary to add urethane foam        D.1.(d) and (e) insulation between the concrete and the metal pan. The foam          DCC-CEST-200-QCS, Auxiliary selected met the UL25 flame          Building Reroofing Section spread requirement; however, for      07526 Modified Bitumous Sheet additional protection a layer of fire Roofing Seismic Class III rated gypsum board was installed      Application between the metal pan and the Procedure 12-FPE-2270-FPCE-urethane foam. This will protect the foam from an interior building    001, Fire Protection Program fire which could degrade the foam,    Change Evaluation liberating combustible gases which can contribute to the intensity and spread of the fire."
By response to Item D.1.(e), I&M stated:
                                                                                                            "All roofs at the Cook Plant are of UL Class A and FM Class I construction."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                                            "We conclude that the administrative controls [including roof construction], fire brigade equipment and training conform to Transition Document Access Code - D.C. Cook Version 2.4.3 Page 91 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-44 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document the recommendations of the National Fire Protection Association and Appendix A to Branch Technical Position 9.5-1 and are, therefore, acceptable."
The Auxiliary Building roof construction, as approved by the SE Report, is still installed at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. This feature remains unchanged.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-45 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.3.7 Bulk            Bulk compressed or cryogenic flammable          Complies with                      Bulk compressed flammable gas      Engineering Equivalency Flammable Gas          gas storage shall not be permitted inside        Clarification                      cylinder storage is located in the  Evaluation 11-11, Storage of Storage                structures housing systems, equipment, or                                            Gas Bottle Storage Facility, which  Flammable Gases in Fire Areas components important to nuclear safety.                                              is separated from structures        AA2 and YD housing systems, equipment, or components important to nuclear    FSA, D. C. Cook Fire Safety safety. The 3-hour rated concrete  Analysis wall that separates the full bottle storage area of the Gas Cylinder    PMP-2270-CCM-001, Control of Storage Building is a maximum      Combustible Materials fire loss (MFL) type firewall. The combination of the firewall and spatial separation from the south wall of Fire Zones 97 and 98 provides assurance that a gas cylinder fire would not damage safety related equipment.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-46 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.3.7.1 [Bulk          Storage of flammable gas shall be located          Complies with                      Bulk compressed flammable gas      FSA, D. C. Cook Fire Safety Flammable Gas          outdoors, or in separate detached                  Clarification                      cylinder storage is located in the  Analysis Location              buildings, so that a fire or explosion will                                            Gas Bottle Storage Facility. The 3-Requirements]          not adversely impact systems, equipment,                                              hour rated concrete wall that      PMP-2270-CCM-001, Control of or components important to nuclear                                                    separates the full bottle storage  Combustible Materials safety. NFPA 50A, "Standard for                                                        area of the Gas Cylinder Storage Gaseous Hydrogen Systems at Consumer                                                  Building is an MFL type firewall.
Sites," shall be followed for hydrogen                                                The combination of the firewall storage.                                                                              and spatial separation from the south wall of Fire Zones 97 and 98 provides assurance that a gas cylinder fire would not adversely impact systems, equipment, or components important to nuclear safety.
Complies with Use of                Hydrogen storage complies with      Engineering Equivalency EEEEs                              NFPA 50A-1999 Edition, as          Evaluation 14-1-1, CNP Fire evaluated in Engineering            Protection Code Conformance Equivalency Evaluation 14.1.1.      Review Transition Document Access Code - D.C. Cook Version 2.4.3 Page 94 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-47 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.3.7.2 [Bulk          Outdoor high-pressure flammable gas              Complies with Use of                Bulk hydrogen storage is              Engineering Equivalency Flammable Gas          storage containers shall be located so that      EEEEs                              configured so the that the long axis  Evaluation 11-11, Storage of Container              the long axis is not pointed at buildings.                                            is not pointed at buildings, as      Flammable Gases in Fire Areas Restrictions]                                                                                                evaluated in Engineering              AA2 and YD Equivalency Evaluation 11.11.
3.3.7.3 [Bulk          Flammable gas storage cylinders not              Complies                            Flammable gas storage cylinders      12-OHP Procedure Series Flammable Gas          required for normal operation shall be                                                not required for normal operation Cylinder Limitations]  isolated from the system.                                                            are either returned to the gas bottle PMP-2270-CCM-001, Control of storage facility upon the            Combustible Materials completion of a job or are isolated from the system.
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American Electric Power                                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-48 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.3.8 Bulk Storage of  Bulk storage of flammable and                Complies                            Per plant procedure PMP-2270-      FSA, D. C. Cook Fire Safety Flammable and          combustible liquids shall not be                                                  CCM-001, "Control of                Analysis Combustible Liquids    permitted inside structures containing                                            Combustible Materials", the systems, equipment, or components                                                following areas are designated      PMP-2270-CCM-001, Control of important to nuclear safety. As a                                                storage for flammable/combustible  Combustible Materials minimum, storage and use shall comply                                            liquids:
with NFPA 30, "Flammable and Combustible Liquids Code."                                                        Storage of flammable liquids (NFPA Diamond Rating of 3 or 4) in quantities greater than one gallon per container shall be restricted to the U-1 Flammable Liquids Storage Room located on the 595' level of the Service Building.
Bulk storage of combustible liquids (those having a flash point above 100°F, NFPA Diamond Rating of 2 or less) will be permitted in the U-2 Storage Room located on the 591' level at the south end of the Turbine Building.
These areas are separated from systems, equipment, and components important to nuclear safety, by 3-hour fire resistive barriers.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-49 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies by Previous                By the response to Appendix A to    NRC Safety Evaluation NRC Approval                        Branch Technical Position APCSB      supporting Amendment Nos. 31 9.5-1 for Units No. 1 and 2, dated  and 12 to License No. DPR-58 January 31, 1977, item D.2.(a)(1),  and DPR-74, dated July 31, 1979 I&M stated (in part):                / page 17 "The emergency diesel generator      I&M response to Appendix A to fuel oil day tanks are enclosed in a Branch Technical Position 3 hour rated enclosure within each  APCSB 9.5-1 for Units No. 1 and of the diesel generator rooms. The  2, dated January 31, 1977 / item enclosure has 3 hour rated walls,    D.2.(a) floor, ceiling, doors, and dampers, is equipped with thermally actuated fire detection which operates a fixed automatic CO2 fire suppression system, and also is drained to remove any oil spill."
                                                                                        "While not safety related or an exposure hazard to safety related equipment, the turbine generator, its lube oil system, and the area surrounding it are fully fire protected. This is considered to be the highest fire potential area in a power plant.
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "We conclude that the administrative controls [including storage of flammable and combustible liquids], fire brigade equipment and training conform to the recommendations of the National Fire Protection Association and Appendix A to Branch Technical Position 9.5-1 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 97 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                          Page 1A-50 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document and are, therefore, acceptable."
The storage configurations of combustible liquids, as approved by the SE Report, are still used at CNP. There have been no plant modifications or other changes that would invalidate the basis for approval.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                Page 1A-51 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                  Reference Document Complies with Use of                Storage of flammable and          Engineering Equivalency EEEEs                              combustible liquids complies with  Evaluation 11-16, NFPA 30-1987 Edition, as          ENGINEERING evaluated in the "NFPA 30 Code    EQUIVALENCY Compliance Evaluation for Donald  EVALUATION FOR LUBE OIL C. Cook Nuclear Plant Unit 1 and  STORAGE ROOMS FIRE 2".                                ZONES 83, 88, 95 AND 100 (AA2), BOUNDARY The fire barriers of the Lube Oil  EVALUATION Storage Rooms have been evaluated in accordance with      Engineering Equivalency NFPA 805, section 3.11.2, and by  Evaluation 11-17, Diesel Engineering Equivalency            Generator Fuel oil Day Tank Evaluation 11.16.                  Rooms Fire Zones 15 (AA14), 16 (AA15), 18 (AA23) and 19 The fire barriers of the Diesel    (AA24) Boundary Evaluation Generator Fuel Oil Day Tank Rooms have been evaluated in      NFPA 30 Code Compliance accordance with NFPA 805,          Evaluation for Donald C. Cook section 3.11.2, and by Engineering Nuclear Plant Unit 1 and 2, dated Equivalency Evaluation 11.17.      July 25, 1990 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications Transition Document Access Code - D.C. Cook Version 2.4.3 Page 99 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-52 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                  Reference Document 3.3.9 Transformers    Where provided, transformer oil                  Complies                            CNP environmental review          12-EA-6090-ENV-112, Auxiliary collection basins and drain paths shall be                                            documents include requirements    Building Wastewater Management periodically inspected to ensure that they                                            for inspecting transformer oil are free of debris and capable of                                                    collection basins and drain paths. ENVG-SUR-001, performing their design function.                                                                                        ENVIRONMENTAL SURVEILLANCE GUIDELINE PMP-6090-ADM-001, Environmental Reviews and Surveillance 3.3.10 Hot Pipes and  Combustible liquids, including high              Complies                            CNP procedures designate storage  PMP-2220-HSK-001, Surfaces              flashpoint lubricating oils, shall be kept                                            areas for combustible materials,  Housekeeping and Material from coming in contact with hot pipes                                                none of which are around hot pipes Condition and surfaces, including insulated pipes                                              and surfaces. Also, CNP and surfaces. Administrative controls                                                procedures require that piping be  PMP-2270-CCM-001, Control of shall require the prompt cleanup of oil on                                            clean, well maintained and free of Combustible Materials insulation.                                                                          all clutter. Procedure PMP-2220-HSK-001 states that plant personnel responsible for area housekeeping.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-53 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.3.11 Electrical      Adequate clearance, free of combustible        Complies                            CNP procedures designate storage    12-FPP-2270-066-012, Transient Equipment              material, shall be maintained around                                              areas for combustible materials,    Combustible Monitoring energized electrical equipment.                                                    none of which are around energized electrical equipment. Nuclear Energy Institute (NEI)
Energized electrical components    04-02, Guidance for are maintained free from adjacent  Implementing a Risk-Informed, combustible material per            Performance-Based Fire PMP-2270-CCM-001. Procedure        Protection Program under 10 PMP-2220-HSK-001 states that        CFR 50.48(c), Rev. 2 / Section plant personnel are responsible for K.5 (FAQ 06-0024) area housekeeping. Environmental procedures require the clean up of  PMP-2220-HSK-001, all oil spills.                    Housekeeping and Material Condition PMP-2270-CCM-001, Control of Combustible Materials PMP-6090-ADM-001, Environmental Reviews and Surveillance Transition Document Access Code - D.C. Cook Version 2.4.3 Page 101 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-54 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.3.12 Reactor        For facilities with non-inerted                Complies by Previous                NRC Safety Evaluation dated          I&M Letter to NRC, Fire Coolant Pumps          containments, reactor coolant pumps with        NRC Approval                        December 23, 1983, states:            Protection - Appendix R an external lubrication system shall be                                                                                  Compliance, dated July 19, 1982 provided with an oil collection system.                                            "Each unit has four reactor The oil collection system shall be                                                  coolant pumps with an oil            I&M Letter to NRC, Fire designed and installed such that leakage                                            collection system which drains to a  Protection - 10 CFR 50, from the oil system is safely contained                                            vented closed collection tank. The    Appendix R, Section III.O, dated for off normal conditions such as                                                  quantity of lubricating oil in each  December 30, 1982 accident conditions or earthquakes. All of                                          pump is 265 gallons; the capacity of the oil collection tank is 275    NRC Safety Evaluation, Donald the following shall apply.                                                                                                C. Cook Nuclear Power Plant, gallons.
Unit Nos. 1 and 2 Fire The collection tank is arranged      Protection - Request for such that if a failure of more than  Exemption from requirements of one RCP motor lube system            Appendix R to 10 CFR 50, occurred, the oil collection tank    Sections III.G and III.O, dated would over-flow onto the lower        December 23, 1983 / Pages 10 containment floor. There are no      and 11, and enclosure 2, pages 15 ignition sources at the floor level  and 16 of the lower containment.
The RCP motor lube oil system does not comply with Section III.O because the oil collection tank is not sized to contain the entire lube oil system inventory.
The RCP motor lube oil system is capable of withstanding the safe shutdown earthquake. The oil collection tank is provided with sufficient capacity to hold the total lube oil inventory of one reactor coolant pump with margin and is designed so that any overflow will be drained to a safe location.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-55 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document collection system provides a level of safety equivalent to the technical requirements of Section III.O and, therefore, the exemption should be granted."
The oil collection tank for the RCP motor lube system, as approved by the SE Report, is still used at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. This feature remains unchanged.
3.3.12(1) Reactor      The oil collection system for each reactor      Complies                            As stated in the FPPM, section        NFPPM, NFPA 805 Fire Coolant Pumps          coolant pump shall be capable of                                                    12.8, each RCP is provided with      Protection Program Manual collecting lubricating oil from all                                                  oil collection enclosures to capture  (NFPPM) potential pressurized and nonpressurized                                            oil from potential pressurized and leakage sites in each reactor coolant                                                unpressurized leakage sites in the pump oil system.                                                                    lube oil system.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-56 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.3.12(2) Reactor      Leakage shall be collected and drained to      Complies by Previous                NRC Safety Evaluation dated          I&M Letter to NRC, Fire Coolant Pumps          a vented closed container that can hold        NRC Approval                        December 23, 1983, states:            Protection - Appendix R the inventory of the reactor coolant pump                                                                                Compliance, dated July 19, 1982 lubricating oil system.                                                            "Each unit has four reactor coolant pumps with an oil            I&M Letter to NRC, Fire collection system which drains to a  Protection - 10 CFR 50, vented closed collection tank. The    Appendix R, Section III.O, dated quantity of lubricating oil in each  December 30, 1982 pump is 265 gallons; the capacity of the oil collection tank is 275    NRC Safety Evaluation, Donald gallons.                              C. Cook Nuclear Power Plant, Unit Nos. 1 and 2 Fire The collection tank is arranged      Protection - Request for such that if a failure of more than  Exemption from requirements of one RCP motor lube system            Appendix R to 10 CFR 50, occurred, the oil collection tank    Sections III.G and III.O, dated would over-flow onto the lower        December 23, 1983 / Pages 10 containment floor. There are no      and 11, and enclosure 2, pages 15 ignition sources at the floor level  and 16 of the lower containment.
The RCP motor lube oil system does not comply with Section III.O because the oil collection tank is not sized to contain the entire lube oil system inventory.
The RCP motor lube oil system is capable of withstanding the safe shutdown earthquake. The oil collection tank is provided with sufficient capacity to hold the total lube oil inventory of one reactor coolant pump with margin and is designed so that any overflow will be drained to a safe location.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-57 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document collection system provides a level of safety equivalent to the technical requirements of Section III.O and, therefore, the exemption should be granted."
The oil collection tank for the RCP motor lube system, as approved by the SE Report, is still used at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. This feature remains unchanged.
3.3.12(3) Reactor      A flame arrestor is required in the vent if        Complies                            A flame arrestor is provided in the  DB-12-APPR, American Electric Coolant Pumps          the flash point characteristics of the oil                                            vent.                                Power Nuclear Organization present the hazard of a fire flashback.                                                                                      Donald C. Cook Nuclear Plant Design Basis Document for 10 CFR 50 Appendix R / Section 4.4 NFPPM, NFPA 805 Fire Protection Program Manual (NFPPM)
RFC-DC-12-2225, INSTALL OIL SPILLAGE PROTECTION
                                                                                                                                                    & CONTROL SYSTEM AT EACH REACTOR COOLANT PUMP IN UNIT 1 & UNIT 2 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 105 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                          Page 1A-58 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                      Reference Document 3.3.12(4) Reactor      Leakage points on a reactor coolant                Complies                            All leakage points are protected on  DB-12-APPR, American Electric Coolant Pumps          pump motor to be protected shall include                                                reactor coolant pump motors.          Power Nuclear Organization but not be limited to the lift pump and                                                                                      Donald C. Cook Nuclear Plant piping, overflow lines, oil cooler, oil fill                                                                                  Design Basis Document for 10 and drain lines and plugs, flanged                                                                                            CFR 50 Appendix R connections on oil lines, and the oil reservoirs, where such features exist on                                                                                      NFPPM, NFPA 805 Fire the reactor coolant pumps.                                                                                                    Protection Program Manual (NFPPM) 3.3.12(5) Reactor      The collection basin drain line to the              Complies                            A calculation has been performed      Engineering and Control Coolant Pumps          collection tank shall be large enough to                                                to verify that the RCP oil collection Procedure 1-L3-01, Calculation accommodate the largest potential oil                                                  system is sufficient to permit flow  of Flow in RCP Oil Collection leak such that oil leakage does not                                                    from all of the drip pans where the  System for Unit overflow the basin.                                                                    flow is driven by gravity and resisted by pipe friction. The calculation also verified the adequacy of the drain piping in the event that the lube oil lift pump discharges directly into its housing.
3.4 Industrial Fire    Industrial Fire Brigade.                            N/A                                N/A - Section Heading, see sub-      N/A Brigade                                                                                                        sections for any specific compliance statements.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-59 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.4.1 On-Site Fire-    On-Site Fire-Fighting Capability. All of          N/A                                N/A - Section Heading, see sub-      Engineering Equivalency Fighting Capability    the following requirements shall apply.                                              sections for any specific            Evaluation 14-1-1, NFPA 600 compliance statements - See NFPA      Code Conformance Review 600 CCR.
3.4.1(a) On-Site Fire- A fully staffed, trained, and equipped fire-      Complies                            A fully staffed, trained, and        PMI-2270, Fire Protection Fighting Capability    fighting force shall be available at all                                              equipped fire-fighting force is      Program times to control and extinguish all fires                                            available at all times to control and on site. This force shall have a minimum                                              extinguish all fires on site. This    TRM-U1, UNIT 1 TECHNICAL complement of five persons on duty and                                                force is required to have a          REQUIREMENTS MANUAL /
shall conform with the following NFPA                                                minimum complement of five            10.1 standards as applicable:                                                              persons on duty and conforms with TRM-U2, UNIT 2 TECHNICAL the applicable NFPA standards of this element.                        REQUIREMENTS MANUAL /
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-60 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                Per the "Technical Requirements      NRC Safety Evaluation NRC Approval                        Manual and Bases", "The              supporting License Amendment composition of the fire brigade      Nos. 154 and 138, dated April 9, may be less than the minimum          1991 / Page 2, Section 2.0(3).
requirements for a period of time not to exceed 2 hours, in order to    Technical Requirements Manual accommodate unexpected absence        and Bases, Unit 1: Rev. 1, Unit 2:
provided immediate action is taken    Rev. 1, Section 10.1, to fill the required positions." This Administrative Controls, Site Fire provision is allowed by CNP TRM      Brigade, Unit 1 Rev. 1, Unit 2 Section 10.1. This provision was      Rev. 1.
approved by the NRC via Unit 1 and Unit 2 Licensee Amendments 154 and 138, respectively, dated April 9, 1991. Therefore, the provision is considered to be previously approved by the NRC.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-61 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.4.1(a)(1) On-Site    NFPA 600, "Standard on Industrial Fire            Complies with                      As required, and in accordance      Nuclear Energy Institute (NEI)
Fire-Fighting          Brigades" (interior structural fire fighting)      Clarification                      with the guidance of Section K to  04-02, Guidance for Capability                                                                                                    NEI-04-02 (FAQ 06-0007), the        Implementing a Risk-Informed, CNP Fire Brigade has the ability to Performance-Based Fire control and extinguish exterior    Protection Program under 10 fires similarly to interior fires,  CFR 50.48(c), Rev. 2 / Section through the development, review,    K.6 (FAQ 06-0007) and maintenance of associated fire emergency plans and fire attack    PMP-2270-FRP-001, Fire plans; regular training and        Response Plan education; the use of appropriate protective clothing and equipment; and brigade member medical and physical performance requirements; as addressed through compliance with NFPA 600-2000 Edition, Chapters 2 and 5.
Complies with Use of                For interior fire fighting, CNP    Engineering Equivalency EEEEs                              complies with NFPA 600-2000        Evaluation 14-1-1, NFPA 600 Edition, Chapter 5. The fire        Code Conformance Review brigade has been reviewed against the requirements of NFPA 600, 2000 Edition, Chapters 2 and 5, as detailed in the CNP "Fire Protection Code Conformance Review".
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American Electric Power                                                          NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-62 NFPA 805 Ch. 3 Ref    Requirements/Guidance                    Compliance Statement                Compliance Basis                    Reference Document 3.4.1(a)(2) On-Site    NFPA 1500, "Standard on Fire              N/A                                CNP complies with NFPA 600 and      Nuclear Energy Institute (NEI)
Fire-Fighting          Department Occupational Safety and                                            as such NFPA 1500 is not            04-02, Guidance for Capability            Health Program"                                                              applicable to CNP per Section K.6    Implementing a Risk-Informed, of NEI 04-02, which states, "The    Performance-Based Fire NFPA standards divide fire          Protection Program under 10 brigades into two types, based on    CFR 50.48(c), Rev. 2 / Section organization and duties: "Industrial K.6 (FAQ 06-0007) fire Brigades" and "Industrial Fire Departments." Practically this means that a fire fighting organization at a nuclear power plant must comply with either NFPA 600 (for an Industrial Fire Brigade) or both NFPA 1500 and NFPA 1582 (for an Industrial Fire Department)."
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-63 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.4.1(a)(3) On-Site    NFPA 1582, "Standard on Medical                N/A                                CNP complies with NFPA 600 and      Nuclear Energy Institute (NEI)
Fire-Fighting          Requirements for Fire Fighters and                                                  as such NFPA 1582 is not            04-02, Guidance for Capability            Information for Fire Department                                                    applicable to CNP per Section K.6    Implementing a Risk-Informed, Physicians"                                                                        of NEI 04-02, which states, "The    Performance-Based Fire NFPA standards divide fire          Protection Program under 10 brigades into two types, based on    CFR 50.48(c), Rev. 2 / Section organization and duties: "Industrial K.6 (FAQ 06-0007) fire Brigades" and "Industrial Fire Departments." Practically this means that a fire fighting organization at a nuclear power plant must comply with either NFPA 600 (for an Industrial Fire Brigade) or both NFPA 1500 and NFPA 1582 (for an Industrial Fire Department)."
3.4.1(b) On-Site Fire- Industrial fire brigade members shall          Complies                            CNP Fire Brigade members have        PMP-2270-FRP-001, Fire Fighting Capability    have no other assigned normal plant                                                no other assigned normal plant      Response Plan duties that would prevent immediate                                                duties that would prevent response to a fire or other emergency as                                            immediate response to a fire or required.                                                                          other emergency as required.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-64 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.4.1(c) On-Site Fire- During every shift, the brigade leader and      Complies                            CNP meets the exception to (c) Per  PMP-2270-FRP-001, Fire Fighting Capability    at least two brigade members shall have                                              PMP-2270-FRP-001, "One person        Response Plan sufficient training and knowledge of                                                from the Operations Department nuclear safety systems to understand the                                            with a reactor operators license or effects of fire and fire suppressants on                                            equivalent training will advise the nuclear safety performance criteria.                                                Fire Brigade Leader on safety related/safe shutdown and general Exception to (c): Sufficient training and                                            plant systems in the fire area".
knowledge shall be permitted to be provided by an operations advisor dedicated to industrial fire brigade support.
3.4.1(d) On-Site Fire- The industrial fire brigade shall be            Complies                            Per CNP procedures, the fire        PMP-2270-FRP-001, Fire Fighting Capability    notified immediately upon verification of                                            brigade is immediately notified in  Response Plan a fire.                                                                              the event of a fire alarm.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-65 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.4.1(e) On-Site Fire- Each industrial fire brigade member shall        Complies                            Per TPD-600-FP, when selected          PMP-2281-RES-001, Control and Fighting Capability    pass an annual physical examination to                                              for initial training, students must    Use of Respiratory Protection determine that he or she can perform the                                            complete physical examination strenuous activity required during manual                                            requirements as well as a physical    SPP-2281-HAZ-001, Hazardous firefighting operations. The physical                                                ability test. They are also subject to Material Response Organization examination shall determine the ability of                                          the requirements of PMP-2281-          and Training each member to use respiratory                                                      RES-001. Here, formal respiratory TPD-600-FP, Fire Protection protection equipment.                                                                training is required to be completed prior to the initial use of a          Training Program Description respiratory protection device and on an annual basis thereafter.
Further, the "Hazardous Material Response Organization and Training" states that all HAZMAT qualified individuals shall have had a medical assessment (baseline) and a follow-up assessment every 12 months unless the attending physician believes a longer interval (not greater than biennially) is appropriate. Procedure TPD-600-FP requires "Hazardous Materials -
Technician Level Evolutions" as part of the fire brigade member training, therefore, the members of the fire brigade is HAZMAT qualified and subject to the requirements of the "Hazardous Material Response Organization and Training".
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-66 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.4.2 Fire Pre-Plans  Current and detailed pre-fire plans shall          Complies                            Per Procedure PMI-2270, Fire Pre-    CNP Fire Pre-Plans, Volumes I, be available to the industrial fire brigade                                            Plans that detail all hazardous      II, and III, for all areas in which a fire could                                                    conditions in certain areas are jeopardize the ability to meet the                                                    available to the fire brigade. Refer PMI-2270, Fire Protection performance criteria described in Section                                              to Fire Pre-Plans Volumes I, II,    Program 1.5.                                                                                  and III. These Fire Pre-Plans "describe the facility layout, access, contents, construction, hazards, hazardous materials, types and locations of fire protection systems, and other information pertinent to the formulation, planning, and execution of emergency fire response." The Fire Pre-Plans meet Radioactive Release performance criteria.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-67 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.4.2.1 [Fire Pre-    The plans shall detail the fire area            Complies                            CNP Fire Pre-Plans contain the      CNP Fire Pre-Plans, Volumes I, Plan Contents]        configuration and fire hazards to be                                                following information for each Fire  II, and III, encountered in the fire area, along with                                            Zone:
any nuclear safety components and fire protection systems and features that are                                            A graphical representation of the present.                                                                            area depicting the fire area configuration Combustibles: A listing of the combustibles in the fire area.
Hazards: A listing of special hazards including: Radiological, Substance (e.g.,
combustible/flammable gases and liquids), and Physical Access/Egress: The primary access/egress path (and, where available, the alternate path) is described.
Ventilation System: Installed fixed supply and exhaust ventilation equipment is listed.
Routing for manual ventilation of the fire area is described to route smoke products out of the area.
General Notes: The recommended extinguishing agent is listed, based on the primary combustibles in the fire area. Fire brigade training includes choosing the proper extinguishing agent for each type of combustible. Based on the actual combustibles involved, the proper extinguishing agent would be utilized during the fire event; any special tactics appropriate for the fire area are identified (e.g., actuation of fixed suppression systems); Additional Transition Document Access Code - D.C. Cook Version 2.4.3 Page 115 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-68 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document equipment available for fighting fires in the area is identified, including fire hose stations, extinguishers and automatic extinguishing system manual release stations, floor drains, sump pumps.
Management of Plant Systems:
Potentially damaged safe shutdown equipment is listed.
3.4.2.2 [Fire Pre-    Pre-fire plans shall be reviewed and            Complies                            CNP procedures indicate that the    PMI-2270, Fire Protection Plan Updates]          updated as necessary.                                                              Fire Pre-Plans are maintained and    Program updated by the Fire Marshal.
3.4.2.3 [Fire Pre-    Pre-fire plans shall be available in the        Complies                            The Fire Response Plan,              PMI-2270, Fire Protection Plan Locations]        control room and made available to the                                              PMP-2270-FRP-001 states that the    Program plant industrial fire brigade.                                                      PFPs are located in the control room.                                PMP-2270-FRP-001, Fire Response Plan Transition Document Access Code - D.C. Cook Version 2.4.3 Page 116 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-69 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.4.2.4 [Fire Pre-    Pre-fire plans shall address coordination        Complies with                      Site procedure PMP-2270-            CNP Fire Pre-Plans, Volumes I, Plan Coordination      with other plant groups during fire              Clarification                      FRP-001 is not specifically a fire  II, and III, Needs]                emergencies.                                                                        pre-plan, however, it provides specific instructions for actions  PMP-2270-FRP-001, Fire required from key groups at CNP    Response Plan supporting fire brigade/fire emergency actions. Detailed response coordination actions are specified for control room personnel and the Security Group.
Any other coordination actions would be initiated by control room personnel as needed for any plant emergency.
3.4.3 Training and    Training and Drills. Industrial fire            Complies                            Compliance is demonstrated in the  TPD-600-FP, Fire Protection Drills                brigade members and other plant                                                      subsections to this element, below. Training Program Description personnel who would respond to a fire in conjunction with the brigade shall be provided with training commensurate with their emergency responsibilities.
3.4.3(a) Training and  Plant Industrial Fire Brigade Training.          Complies                            CNP procedures demonstrate          TPD-600-FP, Fire Protection Drills                All of the following requirements shall                                              compliance in the subsections to    Training Program Description apply.                                                                              this element, below.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-70 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.4.3(a)(1) Training  Plant industrial fire brigade members            Complies                            CNP program description              Engineering Equivalency and Drills            shall receive training consistent with the                                            TPD-600-FP has been developed        Evaluation 14-1-1, NFPA 600 requirements contained in NFPA 600,                                                  to assure appropriate CNP            Code Conformance Review "Standard on Industrial Fire Brigades,"                                              personnel are capable of fighting or NFPA 1500, "Standard on Fire                                                      fires. This procedure is also used to Nuclear Energy Institute (NEI)
Department Occupational Safety and                                                    plan and implement fire drills.      04-02, Guidance for Health Program," as appropriate.                                                                                            Implementing a Risk-Informed, NFPA 1500 is not applicable to        Performance-Based Fire CNP per Section K.6 of NEI            Protection Program under 10 04-02, which states, "The NFPA        CFR 50.48(c), Rev. 2 / Section standards divide fire brigades into  K.6 (FAQ 06-0007) two types, based on organization and duties: 'Industrial Fire          TPD-600-FP, Fire Protection Brigades' and 'Industrial Fire        Training Program Description Departments.' Practically, this means that a fire fighting organization at a nuclear power plant must comply with either NFPA 600 (for an Industrial Fire Brigade) or both NFPA 1500 and NFPA 1582 (for an Industrial Fire Department)."
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-71 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.4.3(a)(2) Training  Industrial fire brigade members shall be          Complies                            CNP program description              TPD-600-FP, Fire Protection and Drills            given quarterly training and practice in                                              TPD-600-FP establishes quarterly    Training Program Description fire fighting, including radioactivity and                                            classroom training and fire drills health physics considerations, to ensure                                              for fire brigade members. FP-        Training Document FP-C-1006, that each member is thoroughly familiar                                              C-9018, Site Specific Hazards, is    SITE SPECIFIC HAZARDS with the steps to be taken in the event of                                            included as a requirement in a fire.                                                                              TPD-600-FP to train the brigade on site specific hazards, including fire fighting in a radiologically controlled area.
3.4.3(a)(3) Training  A written program shall detail the                Complies                            The CNP training program            TPD-600-FP, Fire Protection and Drills            industrial fire brigade training program.                                            description details the fire brigade Training Program Description training program.
3.4.3(a)(4) Training  Written records that include but are not          Complies                            Records stored in accordance with    OHI-2270, Fire Drills and Drills            limited to initial industrial fire brigade                                            CNP's Records Management classroom and hands-on training,                                                      procedure include but are not        PMP-2030-REC-001, Records refresher training, special training                                                  limited to fire brigade training and Management schools attended, drill attendance                                                    qualification records.
TPD-600-FP, Fire Protection records, and leadership training for                                                                                      Training Program Description industrial fire brigades shall be maintained for each industrial fire brigade member.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-72 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.4.3(b) Training and  Training for Non-Industrial Fire Brigade          Complies                            CNP has a dedicated fire brigade    PMP-2270-FRP-001, Fire Drills                Personnel. Plant personnel who respond                                                and does not have personnel        Response Plan with the industrial fire brigade shall be                                              responding who are not active fire trained as to their responsibilities,                                                  brigade members. One SRO who potential hazards to be encountered, and                                              responds is trained with the fire interfacing with the industrial fire brigade.                                          brigade.
3.4.3(c) Training and  Drills. All of the following requirements          N/A                                N/A - Section Heading, see sub-    N/A Drills                shall apply.                                                                          sections for any specific compliance statements.
3.4.3(c)(1) Training  Drills shall be conducted quarterly for            Complies                            Per CNP program description        OHI-2270, Fire Drills and Drills            each shift to test the response capability                                            TPD-600-FP, at least one fire drill of the industrial fire brigade.                                                        per quarter shall be held for each  TPD-600-FP, Fire Protection shift of the fire brigade. Further, Training Program Description per OHI-2270, one drill is required for each fire brigade shift per quarter.
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American Electric Power                                                                      NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                            Page 1A-73 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                      Reference Document 3.4.3(c)(2) Training  Industrial fire brigade drills shall be              Complies                            TPD-600-FP establishes drill          OHI-2270, Fire Drills and Drills            developed to test and challenge industrial                                              instructions. These drills are fire brigade response, including brigade                                                designed to test and challenge        TPD-600-FP, Fire Protection performance as a team, proper use of                                                    industrial fire brigade response.      Training Program Description equipment, effective use of pre-fire plans,                                              Drill procedures are also and coordination with other groups.                                                      established in OHI-2270.
These drills shall evaluate the industrial fire brigades abilities to react, respond, and demonstrate proper fire-fighting techniques to control and extinguish the fire and smoke conditions being simulated by the drill scenario.
3.4.3(c)(3) Training  Industrial fire brigade drills shall be              Complies                            CNP procedures indicate that the      OHI-2270, Fire Drills and Drills            conducted in various plant areas,                                                        location of the drills is varied and especially in those areas identified to be                                              some of the drills are conducted in essential to plant operation and to contain                                              safety significant areas.
significant fire hazards.
3.4.3(c)(4) Training  Drill records shall be maintained                    Complies                            Per OHI-2270, drill records, which    OHI-2270, Fire Drills and Drills            detailing the drill scenario, industrial fire                                            includes all data sheets listed in the brigade member response, and ability of                                                  table of contents, are maintained in  PMP-2030-REC-001, Records the industrial fire brigade to perform as a                                              accordance with PMP-2030-              Management team.                                                                                    REC-001.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-74 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.4.3(c)(5) Training  A critique shall be held and documented          Complies                            A critique is held after each fire  OHI-2270, Fire Drills and Drills            after each drill.                                                                    drill per CNP procedures TPD-600-FP and TRP-2070-            PMP-2030-REC-001, Records TAP-400-FPP. This critique is part  Management of Data Sheet 10 in OHI-2270 and TPD-600-FP, Fire Protection is maintained and documented in Training Program Description accordance with PMP-2030-REC-001.
3.4.4 Fire-Fighting    Protective clothing, respiratory protective      Complies                            The clothing and fire fighting tools Engineering Equivalency Equipment              equipment, radiation monitoring                                                      supplied are discussed in 12-        Evaluation 14-1-1, NFPA 600 equipment, personal dosimeters, and fire                                              FPP-2270-066-023 and 12-            Code Conformance Review suppression equipment such as hoses,                                                  FPP-2270-066-005. These supplies nozzles, fire extinguishers, and other                                                conform to NFPA standards.          12-FPP-2270-066-005, Fire needed equipment shall be provided for                                                                                    Truck Inventory and Operability the industrial fire brigade. This                                                                                          Test equipment shall conform with the                                                                                          12-FPP-2270-066-023, Inventory applicable NFPA standards.                                                                                                of Fire Brigade Personal Protective Equipment 3.4.5 Off-Site Fire    Off-Site Fire Department Interface.              N/A                                N/A - Section Heading, see sub-      N/A Department Interface                                                                                        sections for any specific compliance statements.
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American Electric Power                                                                      NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                          Page 1A-75 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                    Reference Document 3.4.5.1 Mutual Aid    Off-site fire authorities shall be offered a        Complies                            Offsite resources are available      CNP Fire Pre-Plans, Volumes I, Agreement              plan for their interface during fires and                                                through local municipal paid on      II, and III, related emergencies on site.                                                            call and full time fire departments.
Resource planning is available in    TPD-600-FP, Fire Protection the Fire Pre-Plans, Volume III.      Training Program Description Drills are conducted at least once per year with offsite resources.
Mutual aid agreements have been established with the offsite fire departments.
3.4.5.2 Site-Specific  Fire fighters from the off-site fire                Complies                            CNP procedures state that the        TPD-600-FP, Fire Protection Training              authorities who are expected to respond                                                  offsite fire departments shall be    Training Program Description to a fire at the plant shall be offered site-                                            included in at least one fire drill specific training and shall be invited to                                                per calendar year. In addition, participate in a drill at least annually.                                                formalized yearly radiation protection training is provided for the local fire department.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-76 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.4.5.3 Security and  Plant security and radiation protection            Complies                            Per Plant Procedure PMP-2270-        CNP Fire Pre-Plans, Volume III Radiation Protection  plans shall address off-site fire authority                                            FRP-001, off-site fire authority response.                                                                              response is covered by security      TPD-600-FP, Fire Protection plans, and by Radiation Protection  Training Program Description plans (by reference to RMT-2080-Procedure PMP-2270-FRP-001, OSC-001). In addition, per plant FIRE RESPONSE PLAN procedure TPD-600-FP, firefighters from the off-site fire  Procedure RMT-2080-OSC-001, authorities who are expected to      ACTIVATION AND respond to a fire at the plant are  OPERATION OF THE OSC offered site-specific training and invited to participate in a drill at Procedure SPP-2060-SFI-203, least annually.                      SECURITY ACTIONS DURING EMERGENCY CONDITIONS.
Procedure SPP-2060-SFI-209, PROTECTED AREA ACCESS/EXIT REQUIREMENTS 3.4.6                  An effective emergency communications              Complies                            A fire and emergency radio system    Report R1900-0026-001, Communications        capability shall be provided for the                                                  is provided. Details of the system  Technical Evaluation for industrial fire brigade.                                                              design are provided in Technical    Recovery Action Transition in Evaluation R1900-0026-001,          Support of NFPA 805 Technical Evaluation for Recovery Action Transition in Support of NFPA 805, Attachment 5, Supplemental Communications System Overview.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-77 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.5 Water Supply      Water Supply.                                    N/A                                N/A - Section Heading, see sub-      N/A sections for any specific compliance statements.
3.5.1 [Water Supply    A fire protection water supply of                Complies                            Section Heading, see compliance      Refer to basis documentation in Flow Code              adequate reliability, quantity, and                                                  bases below for compliance          the sub-sections of this element.
Requirements]          duration shall be provided by one of the                                            statements for specific subsections.
two following methods.
3.5.1(a) [Water        Provide a fire protection water supply of        Complies                            The fire protection system includes  12-FPP-2270-066-031, Fire Supply Flow Code      not less than two separate 300,000-gal                                              two tanks nominally sized at        Protection Water Supply System Requirements]          (1,135,500-L) supplies.                                                              685,000 gallons. The normal tank    Fill and Vent water level for each tank is between 612,000 gallons and          OP-12-5152S, Fire Protection 621,000 gallons. The minimum        Water Piping at N & S Storage tank water level in each tank is set Tanks Units 1 & 2 at 565,000 gallons.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-78 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.5.1(b) [Water        Calculate the fire flow rate for 2 hours.        N/A                                This section is not applicable      N/A Supply Flow Code      This fire flow rate shall be based on 500                                            because CNP utilizes the method Requirements]          gpm (1892.5 L/min) for manual hose                                                    allowed in subsection (a) to comply streams plus the largest design demand of                                            with Section 3.5.1.
any sprinkler or fixed water spray system(s) in the power block as determined in accordance with NFPA 13, Standard for the Installation of Sprinkler Systems, or NFPA 15, "Standard for Water Spray Fixed Systems for Fire Protection." The fire water supply shall be capable of delivering this design demand with the hydraulically least demanding portion of fire main loop out of service.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                          Page 1A-79 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                    Reference Document 3.5.2 [Water Supply    The tanks shall be interconnected such              Complies                            The primary fire pumps can take      DCC-CE-185-QCF, Design, Tank Code              that fire pumps can take suction from                                                  suction from either of the tanks. Fabrication, and Erection of the Requirements]          either or both. A failure in one tank or its                                            The two tanks are isolated by        Dedicated Fire Protection Water piping shall not allow both tanks to drain.                                            valves so that the failure of one    Supply Storage Tanks The tanks shall be designed in                                                          tank will not affect the other tank.
accordance with NFPA 22, "Standard for                                                                                      OP-12-5152S, Fire Protection Water Tanks for Private Fire Protection."                                              The tanks have been designed in      Water Piping at N & S Storage accordance with NFPA 22, as          Tanks Units 1 & 2 Exception No. 1: Water storage tanks                                                    specified in DCC-CE-185-QCF.
shall not be required when fire pumps are able to take suction from a large body of water (such as a lake), provided each fire pump has its own suction and both suctions and pumps are adequately separated.
Exception No. 2: Cooling tower basins shall be an acceptable water source for fire pumps when the volume is sufficient for both purposes and water quality is consistent with the demands of the fire service.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-80 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document Complies with Use of                Non-listed valves are installed in    Engineering Equivalency EEEEs                              some portions of the fire protection  Evaluation 12-24, NFPA 24 -
system. These valves have been        Listed Valve Deviation 12-ZMO-evaluated to be equivalent to        400 & 401 NFPA requirements by Engineering Equivalency Evaluation 12.24.
3.5.3 [Water Supply    Fire pumps, designed and installed in          Complies                            CNP is provided with three fire      Calculation No. MD-12-FIRE-Pump Code              accordance with NFPA 20, "Standard for                                              pumps. Any two fire pumps can        008-S Requirements]          the Installation of Stationary Pumps for                                            supply enough water to extinguish Fire Protection," shall be provided to                                              a fire on the largest demand          CNP "NFPA Code Deviations ensure that 100 percent of the required                                            system.                              and Justifications" flow rate and pressure are available                                                                                      SD-DCC-FP106, Fire Protection assuming failure of the largest pump or                                            I&M has committed to NFPA 20 System - Water Supply System pump power source.                                                                  for the installation of fire pumps at CNP. The fire pumps have been        Report R2527-001-001, Fire reviewed against the requirements    Protection Water Main Loop and of NFPA 20, 1990 Edition, as          Fire Pump Set Point Adequacy evaluated in CNP "NFPA Code          Determination Deviations and Justifications".
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-81 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.5.4 [Water Supply    At least one diesel engine-driven fire          Complies                            Three fire pumps, two of which are  Calculation No. MD-12-FIRE-Pump Diversity and    pump or two more seismic Category I                                                  diesel engine-driven, each of 2,500  008-S Redundancy]            Class IE electric motor-driven fire pumps                                            gpm capacity are provided as the connected to redundant Class IE                                                      primary pumps for fire protection    CNP "NFPA Code Deviations emergency power buses capable of                                                    of both units. The water supply      and Justifications" providing 100 percent of the required                                                pumps are installed in accordance SD-DCC-FP106, Fire Protection flow rate and pressure shall be provided.                                            with NFPA 20, 1990 Edition, as System - Water Supply System evaluated in CNP "NFPA Code Deviations and Justifications".      Report R2527-001-001, Fire Protection Water Main Loop and Any two fire pumps can supply        Fire Pump Set Point Adequacy enough water to extinguish a fire    Determination on the largest demand system.
3.5.5 [Water Supply    Each pump and its driver and controls            Complies with Use of                Each fire pump and its driver and    Engineering Equivalency Pump Separation        shall be separated from the remaining fire      EEEEs                              controls is provided in its own      Evaluation 11-38, Fire Protection Requirements]          pumps and from the rest of the plant by                                              room with rated fire barriers. The  Pump House (Fire Area YD) rated fire barriers.                                                                fire barriers have been evaluated in accordance with NFPA 805,            RFC-12-3065, Installation of section 3.11.2, and by Engineering  Dedicated Water Supply Equivalency Evaluation 11.38.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-82 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.5.6 [Water Supply    Fire pumps shall be provided with              Complies                            All primary pumps are arranged for  12-OHP-4021-066-001, Fire Pump Start/Stop        automatic start and manual stop only.                                              (1) automatic starting by operation  Protection System (Water)
Requirements]                                                                                              of pressure sensing devices, (2)    Operation remote manual start of the fire pumps from switches in either        1-OHP-4024-101, Annunciator control room and (3) local starting  #101 Response: Plant Fire at each pump. They cannot be        System / Drop 34, 44, and 54 shutdown until extinguishment of a fire is verified by the control room 2-OHP-4024-201, Annunciator operators. Shutdown must be          #201 Response: Plant Fire performed at the local fire pump    System / Drop 34, 44, and 54 control panels.
3.5.7 [Water Supply    Individual fire pump connections to the        Complies                            Fire pump connections to the yard    Plant Drawing OP-12-5152T Pump Connection        yard fire main loop shall be provided and                                          main fire loop are provided with Requirements]          separated with sectionalizing valves                                                sectionalizing valves between between connections.                                                                connections. The three sectionalizing valves shown on the drawing are FP-636, FP-644, and FP-656.
Isolating valves with post indicators or curb boxes are installed in the outdoor loop header so that the entire loop is not disabled should maintenance be required on a small section.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-83 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.5.8 [Water Supply    A method of automatic pressure                    Complies                            One 50 gpm electric motor driven    OP-12-5152A, Fire Protection -
Pressure              maintenance of the fire protection water                                              pegging pump is provided and        Water Piping at Pumps Unit 1 & 2 Maintenance            system shall be provided independent of                                              located within the fire pump house.
Limitations]          the fire pumps.                                                                      Its sole purpose is to maintain      OP-12-98962, Dedicated Fire pressure in the fire protection      Protection Water Supply Electric piping system.                      & Pegging Pump Controlers Elementry Diagram 3.5.9 [Water Supply    Means shall be provided to immediately            Complies                            Control room signals will alarm      1-OHP-4024-101, Annunciator Pump Operation        notify the control room, or other suitable                                            when fire pumps are operated.        #101 Response: Plant Fire Notification]          constantly attended location, of operation                                                                                System / Drops 34, 44, and 54 of fire pumps.
2-OHP-4024-201, Annunciator
                                                                                                                                                  #201 Response: Plant Fire System / Drops 34, 44, and 54 Plant Procedure 12-PPP-4030-066-006, Three Year Fire Protection Water System Unobstructed Flow Test 3.5.10 [Water          An underground yard fire main loop,              Complies                            An underground yard fire main        Flow Diagram 12-5152 Series Supply Yard Main      designed and installed in accordance with                                            loop is installed in accordance with Code Requirements]    NFPA 24, "Standard for the Installation                                              NFPA 24.                            DCC-PV-108-QCS, Installation of Private Fire Service Mains and Their                                                                                    of Underground Piping Appurtenances," shall be installed to                                                                                      RFC-12-3065, Installation of furnish anticipated water requirements.                                                                                    Dedicated Water Supply Transition Document Access Code - D.C. Cook Version 2.4.3 Page 131 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-84 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document Complies with Use of                Non-listed valves are installed in    Engineering Equivalency EEEEs                              some portion of the fire protection  Evaluation 12-24, NFPA 24 -
system. These valves have been        Listed Valve Deviation 12-ZMO-evaluated to meet the NFPA            400 & 401 requirements by Engineering Equivalency Evaluation 12.24.
3.5.11 [Water          Means shall be provided to isolate                Complies                            Isolating valves with post            RFC-12-3003 Supply Yard Main      portions of the yard fire main loop for                                              indicators or curb boxes are Maintenance Issues]    maintenance or repair without                                                        installed in the fire protection      Flow Diagram 12-5152 Series simultaneously shutting off the supply to                                            header so that the entire loop is not both fixed fire suppression systems and                                              disabled should maintenance be fire hose stations provided for manual                                                required on a small section.
backup. Sprinkler systems and manual hose station standpipes shall be connected to the plant fire protection water main so that a single active failure or a crack to the water supply piping to these systems can be isolated so as not to impair both the primary and backup fire suppression systems.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                Page 1A-85 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with                      A single pipe break can cause loss  RFC-12-3003 Clarification                      of primary (sprinkler) and secondary (hose station)            Flow Diagram 12-5152 Series suppression in Fire Zones 28, 30, and 32. However, a yard hydrant and/or a more remote hose station can be used to place a hose stream in service.
A single pipe break can cause loss of primary (manual charcoal filter deluge system) and secondary (hose station) suppression in Fire Zones 49 and 50 at elevation 633'.
However, a sectionalizing valve in the 6" auxiliary building header allows FHC 64 at elevation 633' to be available for backup.
A single pipe break can cause loss of sprinkler protection as well as loss of one or more of the hose stations in Fire Zones 79, 80, 84, 85, 90, 91, and 97. However, one or more of the remaining hose stations in each zone will remain in service despite the worst case pipe break.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                Page 1A-86 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with Use of                Approved valves are not provided    CNP "NFPA Code Deviations EEEEs                              at the main riser to branches of    and Justifications" hose outlets or at each riser controlling more than two hose      0120-164-007, NFPA Code stations. Isolation valves are not  Evaluation Deviation Evaluation provided for the Turbine Building  D.C. Cook Units 1 and 2 hose systems risers and supplies. A review of the system design in "CNP NFPA Code Deviations and Justifications" verified that adequate isolation valves are provided for a majority of the hose risers without adversely impacting the operation of sprinklers protecting safety related equipment.
Sectionalizing valves have not been provided for isolating hose station risers from the fire main loop contained within the Turbine and Screen House Buildings. The areas affected include Fire Zones 80, 84, and 142. Justifications for these deviations are found in Calculation No. 0120-164-007, "NFPA Code Deviation Evaluation D.C. Cook Units 1 and 2".
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-87 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document 3.5.12 [Water          Threads compatible with those used by            Complies                            Threads which are compatible with  CNP Fire Pre-Plans, Volumes I, Supply Compatible      local fire departments shall be provided                                            those used by local fire          II, and III, Thread Connections]    on all hydrants, hose couplings, and                                                departments are provided on all standpipe risers.                                                                    hydrants, hose couplings and      OHI-2270, Fire Drills standpipe risers.
Exception: Fire departments shall be permitted to be provided with adapters that allow interconnection between plant equipment and the fire department equipment if adequate training and procedures are provided.
3.5.13 [Water          Headers fed from each end shall be              Complies                            Turbine and Auxiliary Building    12-5152 System Drawings Supply Header          permitted inside buildings to supply both                                            headers are double-end fed. These Options]              sprinkler and standpipe systems,                                                    headers are fed from both ends and ES-PIPE-1000-QCS, Pipe provided steel piping and fittings meeting                                          piping is CNP type A-31 or S-31. Material Specification the requirements of ANSI B31.1, Code                                                A-31 and S-31 piping is ASME for Power Piping, are used for the                                                  SA-106 Grade B seamless carbon headers (up to and including the first                                              steel or ASME SA-134 welded valve) supplying the sprinkler systems                                              plate. Each system is equipped where such headers are part of the                                                  with a shutoff valve.
seismically analyzed hose standpipe system. Where provided, such headers shall be considered an extension of the yard main system. Each sprinkler and standpipe system shall be equipped with an outside screw and yoke (OS&Y) gate valve or other approved shutoff valve.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-88 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                The hose stations and standpipes      RFCs 12-2229, 12-2621, 12-NRC Approval                        provided for CNP are in              2740, 12-2983 accordance with the requirements of BTP 9.5-1, Appendix A for          NRC Safety Evaluation plants which received a              supporting Amendment Nos. 31 construction permit before July 1,    and 12 to License No. DPR-58 1976. Section E.3.(d) of Appendix    and DPR-74, dated July 31, 1979 A to Branch Technical Position        / pages 6-7 APCSB 9.5-1 on interior manual hose stations does not contain any    I&M response to Appendix A to requirements for hose station        Branch Technical Position operability in the event of an SSE. APCSB 9.5-1 for Units No. 1 and 2, dated January 31, 1977 / item By the response to Appendix A to      E.3.(d)
Branch Technical Position APCSB 9.5-1 for Units No. 1 and 2, dated January 31, 1977, item E.3.(d)
I&M stated:
                                                                                        "All hose standpipes at Cook Plant are spaced at approximate 75 foot intervals in the turbine, office, and auxiliary buildings. Each hose station is provided with a 1-1/2-inch water spray nozzle, a minimum of 75 feet of 1-1/2-inch hose, a 1-1/2-inch angle hose valve, a spanner wrench, a backup 2-1/2-inch angle hose valve, 2-1/2 to 1-1/2-inch reducer and a 1-1/2-inch hose cap.
We are proposing to install additional hose station capability at access areas to the control room cable spreading room, the auxiliary cable vault, the switchgear room cable vault, and the containment penetration cable Transition Document Access Code - D.C. Cook Version 2.4.3 Page 136 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-89 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document tunnels."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "The standpipe system provides water to hose stations at various locations throughout the facility.
The licensees have committed to install additional hose stations and, where necessary, standpipes to satisfy the guidelines of Appendix A to BTP 9.5-1. We have reviewed the proposed additions and find them acceptable.
We have reviewed the design criteria and the basis for the water fire protection system. In certain areas we have required additional protection systems to be installed.
We find that the water fire protection system, as modified, meets the guidelines of Appendix A to Branch Technical Position APCSB 9.5-1 and applicable National Fire Protection Association standards and is, therefore, acceptable."
The additional protection systems have been installed per the RFCs.
The hose station and standpipe configuration, as approved by the SE Report, is still used at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. This feature remains Transition Document Access Code - D.C. Cook Version 2.4.3 Page 137 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-90 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document unchanged.
3.5.14 [Water          All fire protection water supply and fire        N/A                                N/A - Section Heading, see        N/A Supply Control        suppression system control valves shall                                              compliance bases below for Valve Supervision]    be under a periodic inspection program                                              compliance statements for specific and shall be supervised by one of the                                                subsections.
following methods.
3.5.14(a) [Water      Electrical supervision with audible and          Complies                            Per the Annunciator Plant          1-OHP-4024-101, Annunciator Supply Control        visual signals in the main control room or                                          Procedures, valve positions are    #101 Response: Plant Fire System Valve Supervision]    other suitable constantly attended                                                  inspected on a monthly basis.
location.                                                                            These procedures also confirm that 1-OHP-4024-102, Annunciator valves are properly supervised    #102 Response: Miscellaneous during inspection.                Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                              #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                              #202 Response: Miscellaneous Areas Fire System Transition Document Access Code - D.C. Cook Version 2.4.3 Page 138 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                                              Page 1A-91 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document 3.5.14(b) [Water      Locking valves in their normal position.        N/A                                N/A - The requirements of NFPA    N/A Supply Control        Keys shall be made available only to                                                805, Section 3.5.14 are met by the Valve Supervision]    authorized personnel.                                                                option discussed in Section 3.5.14(a).
3.5.14(c) [Water      Sealing valves in their normal positions.        N/A                                N/A - The requirements of NFPA    N/A Supply Control        This option shall be utilized only where                                            805, Section 3.5.14 are met by the Valve Supervision]    valves are located within fenced areas or                                            option discussed in Section under the direct control of the                                                      3.5.14(a).
owner/operator.
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American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-92 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.5.15 [Water          Hydrants shall be installed approximately          Complies with                      Fire hydrants have been provided    Plant Drawing 12-5260 Supply Hydrant        every 250 ft (76 m) apart on the yard              Clarification                      at the recommended 250-foot Code Requirements]    main system. A hose house equipped                                                    approximate spacing connected to    NFPA 24-1984 with hose and combination nozzle and                                                  the yard loop header with two        Flow Diagram 12-5152 Series other auxiliary equipment specified in                                                exceptions. Hydrants 1 and 14 are NFPA 24, "Standard for the Installation                                                located 350' apart in straight line  Plant Procedure 12-FPP-2270-of Private Fire Service Mains and Their                                                distance and 422' apart in actual    066-003, Monthly Inventory of Appurtenances," shall be provided at                                                  travel distance. Hydrants 4 and 7    Fire Response Vehicle intervals of not more than 1000 ft (305                                                are located 320' apart in straight m) along the yard main system.                                                        line distance and 406' apart in actual travel distance. This configuration is considered Exception: Mobile means of providing adequate given the strength of the hose and associated equipment, such as water supply and the availability of hose carts or trucks, shall be permitted in sufficient hose from a mobile lieu of hose houses. Where provided,                                                  vehicle in the yard.
such mobile equipment shall be equivalent to the equipment supplied by                                                A mobile means of providing hose three hose houses.                                                                    and associated equipment is provided for the fire brigade's use.
Equipment is equivalent to three hose houses and is based on NFPA 24-1987 Chapter 5 requirements and the NEIL Loss Constrol Standard 4.2.16.1.1 (FPCE-2017-0017).
Procedure 12-FPP-2270-066-003 specifies the mobile equipment inventory and confirms that all items required by NFPA 24-1984 are contained within.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-93 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.5.16 [Water          The fire protection water supply system          Complies by NRC                    Per OP-12-5152 series flow          Engineering Equivalency Supply Dedicated      shall be dedicated for fire protection use        Approval                            diagrams, the fire protection water Evaluation 11-61, Use of Fire Limits]                only.                                                                                supply system is normally          Water for Other Than Fire-dedicated for fire protection use  Related Purposes Exception No. 1: Fire protection water                                                only. Periodically, the fire water supply systems shall be permitted to be                                              supply system is used for non-fire  Letter from Thomas J. Wengert used to provide backup to nuclear safety                                              related purposes, and in these      (NRC) to Lawrence J. Weber systems, provided the fire protection                                                cases, the fire protection water    (AEP), Donald C. Cook Nuclear water supply systems are designed and                                                supply system is designed and      Plant, Units 1 and 2 - Request for maintained to deliver the combined fire                                              maintained to deliver the combined  Additional Information on the and nuclear safety flow demands for the                                              fire and non-fire flow demands. Application for Amendment to Justification is documented in      Transition the Fire Protection duration specified by the applicable Engineering Equivalency            Program to National Fire analysis.
Evaluation 11.61, and in            Protection Standard NFPA 805, accordance with 10CFR50.48(c)(2)    dated October 11, 2012 /
Exception No. 2: Fire protection water                                                (vii) is provided in Attachment L storage can be provided by plant systems                                                                                  Enclosure 1, RAI-11 Fire of the Transition Report submitted  Protection serving other functions, provided the                                                to the NRC as part of the license storage has a dedicated capacity capable                                              amendment request dated July 1,    Letter from Peter S. Tam (NRC) of providing the maximum fire protection                                              2011.                              to Lawrence J. Weber (AEP),
demand for the specified duration as                                                                                      Donald C. Cook Nuclear Plant, determined in this section.                                                          The NRC approved this license      Units 1 and 2 - Request for request in the Safety Evaluation    Additional Information on the (SE) dated October 24, 2013.        Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, dated January 27, 2012 /
Enclosure 1, RAI-11 (Fire Protection)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                      Page 1A-94 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Letter from Thomas J. Wengert (NRC) to Lawrence J. Weber (AEP), "Donald C. Cook Nuclear Plant, Units and 2 - Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in accordance with 10 CFR 50.48(c) (TAC NOS. ME6629 and ME6630),
dated October 24, 2013 /
Enclosure 3, Section 3.1.4.1 Letter AEP-NRC-2011-1 from Michael H. Carlson (AEP) to U.
S. Nuclear Regulatory Commission, Donald C. Cook Nuclear Plant Unit 1 and Unit 2 Docket Nos. 50-315 and 50-316 Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition), dated July 1, 2011 /
Enclosure 2, Attachment L Transition Document Access Code - D.C. Cook Version 2.4.3 Page 142 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                      Page 1A-95 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Letter AEP-NRC-2012-29 from Michael H. Carlson (AEP) to U.
S. Nuclear Regulatory Commission Donald C. Cook Nuclear Plant Units 1 and 2 Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, dated April 27, 2012 / Enclosure 2, RAI-11 (Fire Protection)
Letter AEP-NRC-2012-92 from Michael H. Carlson (AEP) to U.
S. Nuclear Regulatory Commission Donald C. Cook Nuclear Plant Units 1 and 2 Response to Second Round Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, dated October 15, 2012 /
Enclosure 3, RAI-11 (Fire Protection)
OP-12-5152 series Flow Diagrams Transition Document Access Code - D.C. Cook Version 2.4.3 Page 143 of 315
 
American Electric Power                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                              Page 1A-96 NFPA 805 Ch. 3 Ref    Requirements/Guidance              Compliance Statement                Compliance Basis                Reference Document 3.6 Standpipe and      Standpipe and Hose Stations.        N/A                                N/A - Section Heading, see sub- N/A Hose Stations                                                                                  sections for any specific compliance statements Transition Document Access Code - D.C. Cook Version 2.4.3 Page 144 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-97 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.6.1 [Standpipe and  For all power block buildings, Class III        Complies by Previous                Hose stations designed for Class II  RFCs 12-2229, 12-2621, 12-Hose Station Code      standpipe and hose systems shall be            NRC Approval                        service are not in direct compliance  2740, 12-2983 Requirements]          installed in accordance with NFPA 14,                                              with this section. However, the "Standard for the Installation of                                                  standpipe system was previously      NRC Safety Evaluation Standpipe, Private Hydrant, and Hose                                                found to be acceptable by the        supporting Amendment Nos. 31 Systems."                                                                          NRC.                                  and 12 to License No. DPR-58 and DPR-74, dated July 31, 1979 By the response to Appendix A to      / pages 6-7 Branch Technical Position APCSB 9.5-1 for Units No. 1 and 2, dated    I&M response to Appendix A to January 31, 1977, item E.3.(d)        Branch Technical Position I&M stated:                          APCSB 9.5-1 for Units No. 1 and 2, dated January 31, 1977 / item "All hose standpipes at Cook Plant    E.3.(d) are spaced at approximate 75 foot intervals in the turbine, office, and auxiliary buildings. Each hose station is provided with a 1-1/2-inch water spray nozzle, a minimum of 75 feet of 1-1/2-inch hose, a 1-1/2-inch angle hose valve, a spanner wrench, a backup 2-1/2-inch angle hose valve, 2-1/2 to 1-1/2-inch reducer and a 1-1/2-inch hose cap.
We are proposing to install additional hose station capability at access areas to the control room cable spreading room, the auxiliary cable vault, the switchgear room cable vault, and the containment penetration cable tunnels."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                                          "The standpipe system provides Transition Document Access Code - D.C. Cook Version 2.4.3 Page 145 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-98 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document water to hose stations at various locations throughout the facility.
The licensees have committed to install additional hose stations and, where necessary, standpipes to satisfy the guidelines of Appendix A to BTP 9.5-1. We have reviewed the proposed additions and find them acceptable.
We have reviewed the design criteria and the basis for the water fire protection system. In certain areas we have required additional protection systems to be installed.
We find that the water fire protection system, as modified, meets the guidelines of Appendix A to Branch Technical Position APCSB 9.5-1 and applicable National Fire Protection Association standards and is, therefore, acceptable."
The additional protection systems have been installed per the RFCs.
The hose station and standpipe configuration, as approved by the SE Report, is still used at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. This feature remains unchanged.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 146 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-99 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document Complies with Use of                Manual hose stations are located      CNP "NFPA Code Deviations EEEEs                              throughout the plant and are          and Justifications" designed for either NFPA 14 Class II or Class III service. The hose    0120-108-005, NFPA 14 - Code stations are capable of directing an  Compliance Verification effective stream to any safety-      Checklist D.C. Cook Units 1 and related area of the plant. The 0120-164-003, NFPA 14 - Code standpipe and hose systems comply with NFPA 14, 1971, 1978, and        Compliance Verification 1986 Editions, as evaluated in the    Checklist D.C. Cook Units 1 and CNP NFPA 14 Code Compliance          0120-164-007, NFPA Code Evaluations.                          Evaluation Deviation Evaluation D.C. Cook Units 1 and 2 09-0120-0123, NFPA Code Compliance Evaluation Donald C. Cook Nuclear Plant 09-0120-0381, Extended NFPA Code Compliance Evaluation for the Donald C. Cook Nuclear Plant 3.6.2 [Standpipe and  A capability shall be provided to ensure        Complies with Use of                Hydraulic calculations have been      Calculation No. MD-12-FIRE-Hose Station          an adequate water flow rate and nozzle          EEEEs                              performed to provide verification    008-S Capability            pressure for all hose stations. This                                                of the ability of the existing Limitations]          capability includes the provision of hose                                            standpipe system to deliver          CNP "NFPA Code Deviations station pressure reducers where necessary                                            adequate flow for all hose stations  and Justifications" for the safety of plant industrial fire                                              to supply water for fighting fires in brigade members and off-site fire                                                    accordance with the guidance of department personnel.                                                                NFPA 14.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-100 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.6.3 [Standpipe and  The proper type of hose nozzle to be            Complies with                      The appropriate type of hose        Donald C. Cook Nuclear Plant Hose Station Nozzle    supplied to each power block area shall          Clarification                      nozzle is provided to each power    NFPA Code Deviations and Restrictions]          be based on the area fire hazards. The                                              block area. All hose nozzles have    Justifications usual combination spray/straight stream                                              shutoff capability and are able to nozzle shall not be used in areas where                                              control water flow from full open    12-FPP-4030-066-023, Test and the straight stream can cause                                                        to full closed.                      Inspection of the Plant Fire Hose unacceptable damage or present an                                                                                        Standpipe Stations electrical hazard to fire-fighting                                                  CNP complies with NFPA 14 with exception to size, location and      CNP Fire Pre-Plans, Volumes I, personnel. Listed electrically safe fixed                                                                                II, and III, fog nozzles shall be provided at locations                                          spacing, including hose length, of where high-voltage shock hazards exist.                                              selected hose stations as documented in CNP report NFPA All hose nozzles shall have shutoff Code Deviations and capability and be able to control water Justifications, Revision 2.
flow from full open to full closed.
Fire Pre-Plans re-enforce the use of electrically safe fixed fog nozzles in high voltage settings and use of straight stream nozzles for hydrogen fires.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-101 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.6.4 [Standpipe and  Provisions shall be made to supply water        Complies by Previous                By the response to Appendix A to      RFCs 12-2229, 12-2621, 12-Hose Station          at least to standpipes and hose stations        NRC Approval                        Branch Technical Position APCSB      2740, 12-2983 Earthquake            for manual fire suppression in all areas                                            9.5-1 for Units No. 1 and 2, dated Provisions]            containing systems and components                                                  January 31, 1977, item E.3.(d)        NRC Safety Evaluation needed to perform the nuclear safety                                                I&M stated:                          supporting Amendment Nos. 31 functions in the event of a SSE.                                                                                          and 12 to License No. DPR-58 "All hose standpipes at Cook Plant    and DPR-74, dated July 31, 1979 are spaced at approximate 75 foot    / pages 6-7 intervals in the turbine, office, and auxiliary buildings. Each hose        I&M response to Appendix A to station is provided with a 1-1/2-    Branch Technical Position inch water spray nozzle, a            APCSB 9.5-1 for Units No. 1 and minimum of 75 feet of 1-1/2-inch      2, dated January 31, 1977 / item hose, a 1-1/2-inch angle hose        E.3.(d) valve, a spanner wrench, a backup 2-1/2-inch angle hose valve, 2-1/2 to 1-1/2-inch reducer and a 1-1/2-inch hose cap.
We are proposing to install additional hose station capability at access areas to the control room cable spreading room, the auxiliary cable vault, the switchgear room cable vault, and the containment penetration cable tunnels."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                                          "The standpipe system provides water to hose stations at various locations throughout the facility.
The licensees have committed to install additional hose stations and, where necessary, standpipes to satisfy the guidelines of Appendix A to BTP 9.5-1. We have Transition Document Access Code - D.C. Cook Version 2.4.3 Page 149 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-102 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document reviewed the proposed additions and find them acceptable.
We have reviewed the design criteria and the basis for the water fire protection system. In certain areas we have required additional protection systems to be installed.
We find that the water fire protection system, as modified, meets the guidelines of Appendix A to Branch Technical Position APCSB 9.5-1 and applicable National Fire Protection Association standards and is, therefore, acceptable."
The additional hose station capability has been installed per the RFCs. The hose station and standpipe configuration, as approved by the SE Report, is still used at CNP. There have been no plant modifications or other changes that would invalidate the basis for approval. This feature remains unchanged.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 150 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-103 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.6.5 [Standpipe and  Where the seismic required hose stations          N/A                                Hose stations are not cross-        OP-12-5152 series Flow Hose Station Seismic  are cross-connected to essential seismic                                              connected to non-fire protection    Diagrams Connection            non-fire protection water supply systems,                                            water supply systems.
Limitations]          the fire flow shall not degrade the essential water system requirement.
3.7 Fire Extinguishers Where provided, fire extinguishers of the        Complies with Use of                The fire extinguishers comply with  Donald C. Cook Nuclear Plant appropriate number, size, and type shall          EEEEs                              the requirements of NFPA 10,        NFPA Code Deviations and be provided in accordance with NFPA                                                  1984 Edition, as evaluated in CNP  Justifications 10, "Standard for Portable Fire                                                      NFPA 10 Code Compliance Extinguishers." Extinguishers shall be                                                Evaluations.                        0120-108-001, NFPA 10 Code permitted to be positioned outside of fire                                                                                Compliance Verification Checklist areas due to radiological conditions.                                                Fire extinguishers are not provided 0120-164-001, NFPA 10 Code inside containment due to radiological reasons, however,      Compliance Verification Checklist water mist fire extinguishers have  09-0120-0123, NFPA Code been made available outside of      Compliance Evaluation Donald containment for use inside          C. Cook Nuclear Plant containment.
09-0120-0381, Extended NFPA Code Compliance Evaluation for the Donald C. Cook Nuclear Plant 3.8 Fire Alarm and    Fire Alarm and Detection Systems.                N/A                                N/A - Section Heading, see sub-    N/A Detection systems                                                                                            sections for any specific compliance statements.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-104 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.8.1 Fire Alarm      Alarm initiating devices shall be installed      Complies with Use of                CNP complies with NFPA 72 as        Engineering Equivalency in accordance with NFPA 72, "National            EEEEs                              evaluated in the CNP NFPA 72D        Evaluation 11-41, Raised Floors Fire Alarm Code." Alarm annunciation                                                and NFPA 72E Code Compliance        in Control Rooms shall allow the proprietary alarm system                                              Evaluations. Refer to I&M "NFPA to transmit fire-related alarms,                                                      Deviations and Recommendations"      CNP "NFPA Code Deviations supervisory signals, and trouble signals to                                          for NFPA 72D-1967 and NFPA          and Justifications" the control room or other constantly                                                  72E-1974 deviations and 0120-164-005, NFPA 72D Code attended location from which required                                                justifications.
Compliance Verification Checklist notifications and response can be initiated. Personnel assigned to the                                                  Fire protection functions are        0120-164-005, NFPA 72D Code proprietary alarm station shall be                                                    displayed on a comprehensive        Compliance Verification annunciator panel in the control    Checklist - Extended permitted to have other duties. The rooms to alert the operator in case following fire-related signals shall be of fire, primary fire pump          0120-164-006, NFPA 72E Code transmitted:
operation, or fire system            Compliance Verification Checklist malfunction. Pressure gauges on the panel also tell the operator the 0120-164-006, NFPA 72E Code pressure conditions in the fire      Compliance Verification protection water piping headers. Checklist - Extended 09-0120-0123, NFPA Code Compliance Evaluation Donald C. Cook Nuclear Plant 09-0120-0381, Extended NFPA Code Compliance Evaluation for the Donald C. Cook Nuclear Plant 1-OHP-4024-101, Annunciator
                                                                                                                                                  #101 Response: Plant Fire System 1-OHP-4024-102, Annunciator
                                                                                                                                                  #102 Response: Miscellaneous Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                                  #201 Response: Plant Fire System Transition Document Access Code - D.C. Cook Version 2.4.3 Page 152 of 315
 
American Electric Power                                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-105 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 2-OHP-4024-202, Annunciator
                                                                                                                                            #202 Response: Miscellaneous Areas Fire System 3.8.1(1) Fire Alarm    Actuation of any fire detection device        Complies                            Automatic detection actuation      1-OHP-4024-101, Annunciator signals are transmitted to the      #101 Response: Plant Fire System control room. Automatic fire alarm systems are actuated by detectors  1-OHP-4024-102, Annunciator that sense fire conditions. Fire    #102 Response: Miscellaneous alarm detection devices generally  Areas Fire System transmit signals to the local fire 2-OHP-4024-201, Annunciator alarm panels and then to the control room annunciators, or, they #201 Response: Plant Fire System transmit signals directly to the    2-OHP-4024-202, Annunciator control room annunciators.          #202 Response: Miscellaneous Areas Fire System All CNP fire detection system alarms sound and are visually displayed on the emergency fire panel in the respective control room.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-106 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.8.1(2) Fire Alarm    Actuation of any fixed fire suppression        Complies                            The fire suppression system alarm  1-OHP-4024-101, Annunciator system                                                                              signaling capabilities that may be  #101 Response: Plant Fire System used involve automatic sprinkler waterflow, CO2 system monitoring    1-OHP-4024-102, Annunciator and Halon system monitoring.        #102 Response: Miscellaneous These systems alarm in the control  Areas Fire System room upon actuation.
2-OHP-4024-201, Annunciator All CNP water-using systems;        #201 Response: Plant Fire System sprinklers, deluge, and standpipes, 2-OHP-4024-202, Annunciator are instrumented to provide flow    #202 Response: Miscellaneous indication and to provide audible  Areas Fire System and visual annunciation in the respective control rooms.
3.8.1(3) Fire Alarm    Actuation of any manual fire alarm station      Complies                            Automatic fire alarm systems are    1-OHP-4024-101, Annunciator actuated through manual pull        #101 Response: Plant Fire System stations. The systems alarm in the control room upon actuation.        1-OHP-4024-102, Annunciator
                                                                                                                                              #102 Response: Miscellaneous Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                              #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                              #202 Response: Miscellaneous Areas Fire System Transition Document Access Code - D.C. Cook Version 2.4.3 Page 154 of 315
 
American Electric Power                                                        NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                                          Page 1A-107 NFPA 805 Ch. 3 Ref    Requirements/Guidance                  Compliance Statement                Compliance Basis                    Reference Document 3.8.1(4) Fire Alarm    Starting of any fire pump              Complies                            Fire suppression system alarm      1-OHP-4024-101, Annunciator signaling capabilities include fire #101 Response: Plant Fire System pump monitoring. The signals are displayed on a comprehensive        1-OHP-4024-102, Annunciator annunciator panel in the control    #102 Response: Miscellaneous rooms to alert the operator in case Areas Fire System of fire, primary fire pump 2-OHP-4024-201, Annunciator operation or fire system malfunction.                        #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                      #202 Response: Miscellaneous Areas Fire System 3.8.1(5) Fire Alarm    Actuation of any fire protection        Complies                            The fire suppression system alarm  1-OHP-4024-101, Annunciator supervisory device                                                          signaling capabilities include      #101 Response: Plant Fire System supervisory alarms.
1-OHP-4024-102, Annunciator
                                                                                                                                      #102 Response: Miscellaneous Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                      #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                      #202 Response: Miscellaneous Areas Fire System Transition Document Access Code - D.C. Cook Version 2.4.3 Page 155 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-108 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies by Previous                Per letter by I&M to NRC dated      Letter from I&M (Fitzpatrick) to NRC Approval                        December 2, 1991:                    the NRC (Murley), dated December 2, 1991 / Body of "There actually are more than two    letter and Attachment 3 circuits that are not electronically supervised. These include some      NRC Safety Evaluation, Donald water flow, sprinkler alarms, fire  C. Cook Nuclear Plant, Unit Nos.
detection, and suppression          1 and 2 - NFPA Code Review actuation/initiating systems that    and Related Appendix R SER are not electronically supervised in Clarifications (TAC Nos.
accordance with NFPA 72D.            M82265 AND M82266), dated Justifications for each are outlined January 24, 1995 / Section 3.0 in Attachment 3 to this letter."
The NRC Safety Evaluation dated 1/24/95, Section 3.0 states:
                                                                                        "Based on the regular testing to confirm operability, the daily monitoring of the alarm panels, the fact the circuits have not experienced integrity problems, and the circuits only provide secondary annunciation of local fire alarms in the control room, the staff finds these additional unsupervised circuits acceptable."
The unsupervised circuits, as approved by the SE Report, are still used at CNP. There have been no plant modifications or other changes that would invalidate the basis for approval. This approved justification for the unsupervised circuits remains unchanged.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-109 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.8.1(6) Fire Alarm    Indication of alarm system trouble                Complies                            The emergency fire panel provides    1-OHP-4024-101, Annunciator condition                                                                            annunciation in the associated      #101 Response: Plant Fire System control room in the event of a trouble signal.                      1-OHP-4024-102, Annunciator
                                                                                                                                                  #102 Response: Miscellaneous Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                                  #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                                  #202 Response: Miscellaneous Areas Fire System 3.8.1.1 [Fire Alarm    Means shall be provided to allow a                Complies                            Per Plant Procedure PMP-2270-        PMP-2270-FRP-001, Fire Communications        person observing a fire at any location in                                            FRP-001, personnel observing a      Response Plan Requirements]          the plant to quickly and reliably                                                    fire or explosion at any location in communicate to the control room or other                                              the plant are able to communicate suitable constantly attended location.                                                quickly with the control room by telephone, PA system, or radio.
3.8.1.2 [Fire Alarm    Means shall be provided to promptly              N/A                                N/A - Section Heading, see sub-      N/A Prompt Notification    notify the following of any fire                                                      sections for any specific Limits]                emergency in such a way as to allow                                                  compliance statements.
them to determine an appropriate course of action:
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 157 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-110 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                      Reference Document 3.8.1.2(1) [Fire      General site population in all occupied        Complies                            Per procedure PMP-2270-              PMP-2270-FRP-001, Fire Alarm Prompt          areas                                                                              FRP-001, the general site            Response Plan Notification Limits]                                                                                      population can be notified of a fire by making PA announcements, sounding the fire siren, and initiating a "Fire Page Out" to site personnel.
3.8.1.2(2) [Fire      Members of the industrial fire brigade        Complies                            Per Plant Procedure PMP-2270-        PMP-2270-FRP-001, Fire Alarm Prompt          and other groups supporting fire                                                  FRP-001, the fire brigade is          Response Plan Notification Limits]  emergency response                                                                immediately notified during a fire or other emergency. Fire brigade notification of a fire is provided by a site announcement over the Plant Public Address System and through personal electronic pagers.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-111 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.8.1.2(3) [Fire      Off-site fire emergency response                Complies                            Per PMP-2270-FRP-001, when          CNP Fire Pre-Plans, Volume III Alarm Prompt          agencies. Two independent means shall                                              requested, the security department Notification Limits]  be available (e.g., telephone and radio)                                            will contact the Berrien County    PMP-2270-FRP-001, Fire for notification of off-site emergency                                              Dispatch Center.                    Response Plan services.
Per the Fire Pre-Plans, Volume III, Radio communications shall be established between Bridgman and Lake Township Fire Departments and the CNP Fire Brigade Leader immediately upon manning fire stations. Portable radios equipped with CNP Fire Brigade frequencies have been provided to the Lake Township and Bridgman Fire Departments. The CNP Fire Brigade has access to an 800 MHz radio to allow for communications with Berrien County Emergency Response Agencies.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-112 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                  Reference Document 3.8.2 Detection        If automatic fire detection is required to        Complies with Use of                Automatic fire detection systems  CNP NFPA Code Deviations and meet the performance or deterministic            EEEEs                              credited to meet the requirements Justifications requirements of Chapter 4, then these                                                of NFPA 805 Chapter 4 are devices shall be installed in accordance                                              identified in the D. C. Cook Fire 0120-164-005, NFPA 72D Code with NFPA 72, "National Fire Alarm                                                    Safety Analysis (FSA).            Compliance Verification Code," and its applicable appendixes.                                                                                  Checklist - Extended CNP complies with NFPA 72 as 0120-164-006, NFPA 72E Code evaluated in the CNP NFPA 72D and NFPA 72E Code Compliance      Compliance Verification Evaluations. Refer to I&M "NFPA  Checklist - Extended Deviations and Recommendations"  09-0120-0123, NFPA Code for NFPA 72D-1967 and NFPA        Compliance Evaluation Donald 72E-1974 deviations and          C. Cook Nuclear Plant justifications.
09-0120-0381, Extended NFPA Code Compliance Evaluation for the Donald C. Cook Nuclear Plant FSA, D. C. Cook Fire Safety Analysis 3.9 Automatic and      Automatic and Manual Water-Based Fire            N/A                                N/A - Section Heading, see sub-  N/A Manual Water-Based    Suppression Systems.                                                                  sections for any specific Fire Suppression                                                                                            compliance statements.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                                            Page 1A-113 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                  Reference Document 3.9.1 [Fire            If an automatic or manual water-based          N/A                                N/A - Section Heading, see        N/A Suppression System    fire suppression system is required to                                            compliance bases below for Code Requirements]    meet the performance or deterministic                                              compliance statements for specific requirements of Chapter 4, then the                                                subsections.
system shall be installed in accordance with the appropriate NFPA standards including the following:
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American Electric Power                                                          NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 1                                                                                                                                              Page 1A-114 NFPA 805 Ch. 3 Ref    Requirements/Guidance                    Compliance Statement                Compliance Basis                    Reference Document 3.9.1(1) [Fire        (1) NFPA 13, "Standard for the            Complies with Use of                Suppression systems credited to    Engineering Equivalency Suppression System    Installation of Sprinkler Systems"        EEEEs                              meet the requirements of NFPA      Evaluation 11-41, Unit 1 Fire Code Requirements]                                                                                  805 Chapter 4 are identified in the Zone 53 (AA46) and Unit 2 Fire D. C. Cook Fire Safety Analysis    Zone 54 (AA47) Boundary (FSA).                              Evaluation The sprinkler systems comply with  Engineering Equivalency the requirements of NFPA 13,        Evaluation 12-20, Unit 1 Turbine 1971 and 1983 editions, as          Oil Tank Room Fire Zone 95 evaluated in the CNP NFPA 13        (AA2A)
Code Compliance Evaluations.
Engineering Equivalency Evaluation 12-22, Units 1 & 2 Auxiliary Building North and South Elevations 609 Fire Zones 44N (AA36) and 44S (AA42)
Analysis of Sprinkler System CNP "NFPA Code Deviations and Justifications" 0120-108-004, NFPA 13 - Code Compliance Verification Checklist D.C. Cook Units 1 & 2 0120-164-002, NFPA 13 - Code Compliance Verification Checklist D.C. Cook Units 1 & 2 0120-164-007, NFPA Code Evaluation Deviation Evaluation D.C. Cook Units 1 and 2 09-0120-0123, NFPA Code Compliance Evaluation Donald C. Cook Nuclear Plant 09-0120-0381, Extended NFPA Code Compliance Evaluation for the Donald C. Cook Nuclear Plant Transition Document Access Code - D.C. Cook Version 2.4.3 Page 162 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                  Page 1A-115 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document FSA, D. C. Cook Fire Safety Analysis Transition Document Access Code - D.C. Cook Version 2.4.3 Page 163 of 315
 
American Electric Power                                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-116 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.9.1(2) [Fire        (2) NFPA 15, "Standard for Water Spray        Complies with Use of                Suppression systems credited to    Engineering Equivalency Suppression System    Fixed Systems for Fire Protection"            EEEEs                              meet the requirements of NFPA      Evaluation 11-41, Unit 1 Fire Code Requirements]                                                                                      805 Chapter 4 are identified in the Zone 53 (AA46) and Unit 2 Fire D. C. Cook Fire Safety Analysis    Zone 54 (AA47) Boundary (FSA).                              Evaluation CNP complies with NFPA 15,          Engineering Equivalency 1973 edition, as evaluated in the  Evaluation 12-20, Unit 1 Turbine CNP NFPA 15 Code Compliance        Oil Tank Room Fire Zone 95 Evaluations.                        (AA2A)
Engineering Equivalency Evaluation 12-22, Units 1 & 2 Auxiliary Building North and South Elevations 609 Fire Zones 44N (AA36) and 44S (AA42)
Analysis of Sprinkler System CNP "NFPA Code Deviations and Justifications" 0120-108-1375, NFPA 15 - Code Compliance Verification Checklist D.C. Cook Units 1 & 2 0120-164-004, NFPA 15 - Code Compliance Verification Checklist D.C. Cook Units 1 & 2 0120-164-007, NFPA Code Evaluation Deviation Evaluation D.C. Cook Units 1 and 2 09-0120-0123, NFPA Code Compliance Evaluation Donald C. Cook Nuclear Plant 09-0120-0381, Extended NFPA Code Compliance Evaluation for the Donald C. Cook Nuclear Plant Transition Document Access Code - D.C. Cook Version 2.4.3 Page 164 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-117 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                  Reference Document FSA, D. C. Cook Fire Safety Analysis 3.9.1(3) [Fire        (3) NFPA 750, "Standard on Water Mist          N/A                                Water mist systems are not        FSA, D. C. Cook Fire Safety Suppression System    Fire Protection Systems"                                                          installed at Cook Nuclear Plant. Analysis Code Requirements]
3.9.1(4) [Fire        (4) NFPA 16, "Standard for the                N/A                                Foam-water and foam-water spray  FSA, D. C. Cook Fire Safety Suppression System    Installation of Foam-Water Sprinkler and                                          systems are not installed at Cook Analysis Code Requirements]    Foam-Water Spray Systems"                                                          Nuclear Plant.
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American Electric Power                                                            NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-118 NFPA 805 Ch. 3 Ref    Requirements/Guidance                      Compliance Statement                Compliance Basis                    Reference Document 3.9.2 [Fire            Each system shall be equipped with a        Complies                            Fire protection functions are        12-5152 System Drawings Suppression System    water flow alarm.                                                              displayed on a comprehensive Flow Alarm]                                                                                            annunciator panel in the control      2-OHP-4024-201, Annunciator rooms to alert the operator in case  #201 Response: Plant Fire System of fire, primary fire pump 1-OHP-4024-101, Annunciator operation, sprinkler waterflow
                                                                                                                                            #101 Response: Plant Fire System supervisory alarms, or fire system malfunction. Pressure gauges on      1-OHP-4024-102, Annunciator the panel also tell the operator the #102 Response: Miscellaneous pressure conditions in the fire      Areas Fire System protection water piping headers.
2-OHP-4024-202, Annunciator
                                                                                                                                            #202 Response: Miscellaneous Areas Fire System Complies with Use of                Refer to CNP "NFPA Code              CNP "NFPA Code Deviations EEEEs                              Deviations and Justifications" for  and Justifications" NFPA 72D-1967 and NFPA 14-1971 for justifications to deviations related to this requirement.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-119 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.9.3 [Fire            All alarms from fire suppression systems        Complies                            Fire protection functions are        UFSAR / Section 9.8.1, Suppression system    shall annunciate in the control room or                                            displayed on a comprehensive        "Miscellaneous Protective Alarm Locations]      other suitable constantly attended                                                  annunciator panel in the control    Features", Item g) location.                                                                          rooms to alert the operator in case of fire, primary fire pump          1-OHP-4024-101, Annunciator operation, sprinkler waterflow      #101 Response: Plant Fire System supervisory alarms, or fire system 1-OHP-4024-102, Annunciator malfunction. Pressure gauges on the panel also tell the operator the #102 Response: Miscellaneous pressure conditions in the fire      Areas Fire System protection water piping headers. 2-OHP-4024-201, Annunciator
                                                                                                                                                #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                                #202 Response: Miscellaneous Areas Fire System Complies with Use of                Refer to CNP "NFPA Code              CNP "NFPA Code Deviations EEEEs                              Deviations and Justifications" for  and Justifications" NFPA 72D-1967 and NFPA 14-1971 for justifications to deviations related to this requirement.
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American Electric Power                                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-120 NFPA 805 Ch. 3 Ref    Requirements/Guidance                      Compliance Statement                Compliance Basis                    Reference Document 3.9.4 [Fire            Diesel-driven fire pumps shall be            Complies                            The fire pump house structure is    FSA, D. C. Cook Fire Safety Suppression System    protected by automatic sprinklers.                                              protected by a dry pilot preaction  Analysis Diesel Pump                                                                                            sprinkler system. Sprinklers are Sprinkler Protection]                                                                                  provided in each primary fire pump room.
3.9.5 [Fire            Each system shall be equipped with an        Complies                            All sprinkler systems are equipped  Flow Diagrams 5152 Series Suppression System    OS&Y gate valve or other approved                                                with isolation valves.
Shutoff Controls]      shutoff valve.
Complies with Use of                Non-listed valves are installed in  Engineering Equivalency EEEEs                              some portion of the fire protection Evaluation 12-24, NFPA 24 -
system. These valves have been      Listed Valve Deviation 12-ZMO-evaluated to meet the intent of the 400 & 401 NFPA requirements by Engineering Equivalency            Engineering Equivalency Evaluation 12.26.                  Evaluation 12-26, NFPA 13 -
                                                                                                                                            "NON-LISTED" & "NON-RISING STEM" VALVE DEVIATION 12-FP-389, 12-FP-493 AND 12-FP-494 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 168 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-121 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document 3.9.6 [Fire            All valves controlling water-based fire        Complies with                      Valves are supervised as required. 1-OHP-4024-101, Annunciator Suppression System    suppression systems required to meet the        Clarification                      Valve positions are inspected on a #101 Response: Plant Fire System Valve Supervision]    performance or deterministic                                                        monthly basis.
requirements of Chapter 4 shall be                                                                                    1-OHP-4024-102, Annunciator supervised as described in 3.5.14.                                                                                    #102 Response: Miscellaneous Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                              #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                              #202 Response: Miscellaneous Areas Fire System Procedure 12-FPP-4030-066-011, FIRE PROTECTION VALVE LINEUP VERIFICATION 3.10 Gaseous Fire      Gaseous Fire Suppression Systems.              N/A                                N/A - Section Heading, see sub-    N/A Suppression Systems                                                                                        sections for any specific compliance statements.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-122 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                  Reference Document 3.10.1 [Gaseous        If an automatic total flooding and local        Complies                            Gaseous fire suppression systems  FSA, D. C. Cook Fire Safety Suppression System    application gaseous fire suppression                                                credited to meet the requirements  Analysis Code Requirements]    system is required to meet the                                                      of NFPA 805 Chapter 4 are performance or deterministic                                                        identified in the D. C. Cook Fire requirements of Chapter 4, then the                                                  Safety Analysis (FSA). These system shall be designed and installed in                                            systems are designed and installed accordance with the following applicable                                            in accordance with the applicable NFPA codes:                                                                          NFPA codes, as reviewed in the sub-sections of this element.
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American Electric Power                                                            NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 1                                                                                                                                              Page 1A-123 NFPA 805 Ch. 3 Ref    Requirements/Guidance                      Compliance Statement                Compliance Basis                  Reference Document 3.10.1(1) [Gaseous    NFPA 12, "Standard on Carbon Dioxide        Complies with Use of                CO2 extinguishing systems        Engineering Equivalency Suppression System    Extinguishing Systems"                      EEEEs                              credited to meet the requirements Evaluation 12-19, CO2 Fire Code Requirements]                                                                                    of NFPA 805 Chapter 4 comply      Suppression Systems in Fire with NFPA 12-1968, as evaluated  Zones Containing Concentrations in CNP NFPA Code Compliance      of Cable Insulation (Fire Areas Evaluations, and Engineering      AA7, AA8, AA9, AA10, AA29, Equivalency Evaluations.          AA30, AA31, AA37, AA38, AA39, AA40 AA41, AA43, AA44, AA45, AA48, AA49, AA50, AA51, AA52 and AA53)
Engineering Equivalency Evaluation 12-21, Analysis of Fire Zones 13, 21, 57, 58, and 59 Lack of CO2 Suppression System Calculations Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications 0120-108-002, NFPA 12 Code Compliance Verification Checklist 09-0120-0123, NFPA Code Compliance Evaluation Donald C. Cook Nuclear Plant Transition Document Access Code - D.C. Cook Version 2.4.3 Page 171 of 315
 
American Electric Power                                                            NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                                            Page 1A-124 NFPA 805 Ch. 3 Ref    Requirements/Guidance                    Compliance Statement                Compliance Basis                  Reference Document 3.10.1(2) [Gaseous    NFPA 12A, "Standard on Halon 1301          Complies with Use of                Halon 1301 Fire Extinguishing    Engineering Equivalency Suppression System    Fire Extinguishing Systems"                EEEEs                              Systems credited to meet the      Evaluation 12-23, Analysis of Code Requirements]                                                                                    requirements of NFPA 805 Chapter Fire Zones 57 and 58 Lack of 4 comply with NFPA 12A-1977, as Halon Suppression System evaluated in CNP NFPA Code        Calculations Compliance Evaluations and Engineering Equivalency          Donald C. Cook Nuclear Plant Evaluations.                      NFPA Code Deviations and Justifications 0120-108-003, FPA 12A Code Compliance Verification Checklist 09-0120-0123, NFPA Code Compliance Evaluation Donald C. Cook Nuclear Plant 3.10.1(3) [Gaseous    NFPA 2001, "Standard on Clean Agent        N/A                                There are no clean agent fire    N/A Suppression System    Fire Extinguishing Systems"                                                    extinguishing systems required to Code Requirements]                                                                                    meet the performance or deterministic requirements of Chapter 4.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-125 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis              Reference Document 3.10.2 [Gaseous        Operation of gaseous fire suppression          Complies                            Operation of all gaseous fire  1-OHP-4024-101, Annunciator Suppression System    systems shall annunciate and alarm in the                                          suppression systems annunciate #101 Response: Plant Fire System Alarm Location]        control room or other constantly attended                                          and alarm in the control room.
location identified.                                                                                              1-OHP-4024-102, Annunciator
                                                                                                                                          #102 Response: Miscellaneous Areas Fire System 2-OHP-4024-201, Annunciator
                                                                                                                                          #201 Response: Plant Fire System 2-OHP-4024-202, Annunciator
                                                                                                                                          #202 Response: Miscellaneous Areas Fire System SD-12-COAUX-100, System Description for Low Pressure Carbon Dioxide Fire Fighting System SD-12-HALON-100, System Description Fire Protection -
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-126 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.10.3 [Gaseous        Ventilation system design shall take into        Complies with                      Per Section E.5.(d) of FPPM        Fire Protection Program Manual Suppression System    account prevention from over-                    Clarification                      Design Basis Table 5.1, the Cardox  (FPPM) / Table 5.1, Section Ventilation            pressurization during agent injection,                                                (Cheme-tron) design calculations    E.5(d)
Limitations]          adequate sealing to prevent loss of agent,                                            and pre-op tests have confirmed and confinement of radioactive                                                        that offsetting requirements to    FL-15771, Cardox Design contaminants.                                                                        prevent over-pressurization are    Calculations "Low Pressure satisfied.                          Carbon Dioxide Flow Calculations" Fire areas and fire zones that are protected by CO2 systems have      FSA, D. C. Cook Fire Safety boundary penetrations (i.e.,        Analysis dampers, seismic gaps and          NFPPM, NFPA 805 Fire openings around cables, conduits    Protection Program Manual and pipes) sealed to ensure        (NFPPM) / 4.1.3, 4.1.4 retention of the CO2 concentrations. In some fire areas, PO-050-506, LOW PRESSURE however, dampers have not been      CARBON DIOXIDE FIRE provided for duct work that        SYSTEMS, PROCEDURE, communicates directly with the      STATUS REPORTS, TEMP plant exterior or that pass through SHEETS, LOG, other areas within rated            REVIEW/APPROVAL SHEET, construction boundaries to the      DATA SHEETS, plant exterior. For the CO2        INSTRUCTIONS, REVISIONS systems in these fire areas, concentration tests have been      SD-12-COAUX-100, System performed that demonstrate that the Description for Low Pressure required concentration levels can  Carbon Dioxide Fire Fighting be maintained without dampers.      System The affected fire zones in which this situation exists are 40A, 40B, SD-12-HALON-100, System 42A, 45, 46A, 47A and 47B.          Description Fire Protection -
Halon Systems Technical Evaluation-12-21, ANALYSIS OF FIRE ZONES 13, 21, 57, 58, AND 59 LACK OF CO2 SUPPRESSION SYSTEM CALCULATIONS Transition Document Access Code - D.C. Cook Version 2.4.3 Page 174 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-127 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                    Reference Document 3.10.4 [Gaseous        In any area required to be protected by          N/A                                Not Applicable. CNP does not        N/A Suppression System    both primary and backup gaseous fire                                                  have any areas required to be Single Failure Limits] suppression systems, a single active                                                  protected by both primary and failure or a crack in any pipe in the fire                                            backup gaseous fire suppression suppression system shall not impair both                                              systems.
the primary and backup fire suppression capability.
3.10.5 [Gaseous        Provisions for locally disarming                  Complies                            Plant documents ensure that        12-OHP-4021-030-003, Suppression System    automatic gaseous suppression systems                                                disarming automatic gaseous        Operation of the CO2 System Disarming Controls]    shall be secured and under strict                                                    systems is secured and under strict administrative control.                                                              administrative control.            1-OHP-4021-066-004, Isolation and Restoration of the Control Room Cable Vault Halon System 2-OHP-4021-066-004, Isolation and Restoration of the Control Room Cable Vault Halon System SD-12-COAUX-100, System Description for Low Pressure Carbon Dioxide Fire Fighting System SD-12-HALON-100, System Description Fire Protection -
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-128 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.10.6 [Gaseous        Total flooding carbon dioxide systems          Complies with                      The normally occupied areas of the  FSA, D. C. Cook Fire Safety Suppression System    shall not be used in normally occupied        Clarification                      plant are considered to be the      Analysis CO2 Limitations]      areas.                                                                            general floor areas of the auxiliary and turbine buildings, as well as the control rooms. Total flooding CO2 systems are not used in these areas.
3.10.7 [Gaseous        Automatic total flooding carbon dioxide        Complies                            A discharge delay time with          SD-12-COAUX-100, System Suppression system    systems shall be equipped with an                                                  audible alarm is incorporated into  Description for Low Pressure CO2 Warnings]          audible pre-discharge alarm and                                                    each automatic system design to      Carbon Dioxide Fire Fighting discharge delay sufficient to permit                                              allow personnel time to leave the    System egress of personnel. The carbon dioxide                                            area. CO2 systems are provided system shall be provided with an odorizer.                                        with an odorizer.
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American Electric Power                                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-129 NFPA 805 Ch. 3 Ref    Requirements/Guidance                      Compliance Statement                Compliance Basis                    Reference Document 3.10.8 [Gaseous        Positive mechanical means shall be          Complies                            CO2 systems can be isolated by      SD-12-COAUX-100, System Suppression System    provided to lock out total flooding                                              five different methods. These are:  Description for Low Pressure CO2 Required          carbon dioxide systems during work in                                                                                Carbon Dioxide Fire Fighting Disarming]            the protected space.                                                              Individual hazard "Detection      System Isolating Key-Lock Switches.
Grouped hazard "Main Detection Isolating Key-Lock Switches (Master Isolation Switches).
Automatic Isolation (Control Room Cable Vault only).
Header Shutoff Valves.
Tank Shutoff Valves.
When entering a CO2 protected area, to assure safety, one of the above methods must be employed to isolate and block an operation of the CO2 system. The method selected is dependent on the length of time the work in the area is expected to take and the nature of the work.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-130 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                  Reference Document 3.10.9 [Gaseous        The possibility of secondary thermal              Complies                            I&M performed a study that took    Technical Evaluation 12.1, Fire Suppression System    shock (cooling) damage shall be                                                      into account suppression effects  Suppression Effects Study Cooling                considered during the design of any                                                  concerns related to CO2 systems at Considerations]        gaseous fire suppression system, but                                                  CNP including the consideration of particularly with carbon dioxide.                                                    "electrical shorting due to condensation formation and the failure of sensitive electronic equipment due to electrostatic buildup."
3.10.10 [Gaseous      Particular attention shall be given to            Complies                            Corrosive characteristics of agent SD-12-HALON-100, System Suppression System    corrosive characteristics of agent                                                    decomposition products has been    Description Fire Protection -
Decomposition          decomposition products on safety                                                      considered.                        Halon Systems Issues]                systems.
3.11 Passive fire      This section shall be used to determine          N/A                                N/A - General Statement; No        N/A Protection Features    the design and installation requirements                                              Technical Requirements.
for passive protection features. Passive fire protection features include wall, ceiling, and floor assemblies, fire doors, fire dampers, and through fire barrier penetration seals. Passive fire protection features also include electrical raceway fire barrier systems (ERFBS) that are provided to protect cables and electrical components and equipment from the effects of fire.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-131 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                    Reference Document 3.11.1 Building        Each major building within the power            Complies                            The Auxiliary Building,            FSA, D. C. Cook Fire Safety Separation            block shall be separated from the others                                            Containment Buildings, Service      Analysis by barriers having a designated fire                                                Building, and Turbine Building are resistance rating of 3 hours or by open                                              separated from other buildings by space of at least 50 ft (15.2 m) or space                                            3-hour barriers or by greater than that meets the requirements of NFPA                                                  50ft of open space.
80A, "Recommended Practice for Protection of Buildings from Exterior                                                The Auxiliary Building is adjacent Fire Exposures."                                                                    to the Containment Buildings and Turbine Building. The Auxiliary Exception: Where a performance-based                                                Building is separated from the Containment Buildings and analysis determines the adequacy of Turbine Building by a reinforced building separation, the requirements of concrete wall with a 3 hour rated 3.11.1 shall not apply.
design. Openings are rated or have been evaluated as equivalent or adequate for the hazard.
The Containment Buildings are adjacent to the Auxiliary Building.
The Containment Buildings are separated from the Auxiliary Building by a reinforced concrete wall with a 3 hour rated design.
Openings are rated or discussed within the D. C. Cook Fire Safety Analysis (FSA).
The Service Building is adjacent to the Turbine Building. The Service Building is separated from the Turbine Building by a reinforced concrete wall with a 3 hour rated design. Openings are rated or discussed with individual Fire Safety Analyses Reports.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                        Page 1A-132 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                  Reference Document Service Building. The Turbine Building is separated from the Auxiliary Building and Service Building by a reinforced concrete wall with a 3 hour rated design.
Openings are rated or discussed with individual Fire Safety Analyses Reports.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                Page 1A-133 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with Use of                A seismic gap exists around the    Engineering Equivalency EEEEs                              Containment Buildings that          Evaluation 11-46, Seismic Gaps provides an opening of              Between the Containment and approximately 6 in. between the    Auxiliary Buildings Boundary Containment Buildings and the      Evaluation (Fire Areas AA2A, walls, ceilings and floors of the  AA2B, AA3, AA7, AA8, AA9, structures immediately adjacent to  AA10, AA11, AA27, AA29, containment. This opening has      AA30, AA31, AA34, AA35, been determined adequate by an      AA37 and AA38) engineering evaluation. CNP currently utilizes the exception to Engineering Equivalency Section 3.11.1, which is endorsed. Evaluation 11-54, Unit 1 Main Control Room Cable Vault Penetration Seal W5111 Fire Zone 57 and 91 (Fire Areas AA50 and AA2A)
Engineering Equivalency Evaluation 11-65, Fire Door Closure Evaluation (Fire Areas AA2, AA7, AA8, AA14, AA15, AA23, AA24, AA30, AA31, AA34, AA35, AA36/42, AA37, AA38, AA39, AA41, AA43, AA44, AA45, AA48, and AA53)
Engineering Equivalency Evaluation 9-39, Fire Zone 70 (AA57A) to Fire Zone 129 (AA2A) Boundary Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 181 of 315
 
American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                          Page 1A-134 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                        Reference Document 3.11.2 Fire Barriers  Fire barriers required by Chapter 4 shall        Complies                            Fire barriers required by Chapter 4    Engineering Equivalency include a specific fire-resistance rating.                                            are identified in the D. C. Cook        Evaluation 11-67, Technical Fire barriers shall be designed and                                                  Fire Safety Analysis (FSA). A          Evaluation for Embedded installed to meet the specific fire                                                  specific fire-resistance rating for all Conduit Evaluation resistance rating using assemblies                                                    fire barriers is included qualified by fire tests. The qualification                                                                                    12-FPP-4030-066-025, fire tests shall be in accordance with                                                All walls, floors, and ceilings        Inspection of Fire Rated NFPA 251, "Standard Methods of Tests                                                  separating fire areas are either        Assemblies of Fire Endurance of Building                                                        reinforced concrete construction which exceed a 3 hour fire rating,      FSA, D. C. Cook Fire Safety Construction and Materials," or ASTM E                                                                                        Analysis 119, "Standard Test Methods for Fire                                                  or are of concrete block construction with a 3 hour fire Tests of Building Construction and resistance rating or have been Materials."
evaluated as equivalent or adequate for the hazard. The design and installation of fire barriers meets the requirements of ASTM E 119.
All openings for cable, pipe, and ductwork in walls, floor, and ceilings separating fire areas have been sealed with foamed in place silicone which was tested for up to five hours fire exposure in an ASTM E 119 wall fire test. Cable tray openings have been sealed and verified by ASTM E 119 tests.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 182 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-135 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies with Use of                Each barrier which contained a        Engineering Equivalency EEEEs                              feature with an unrated component    Evaluation 11-11, Storage of was analyzed with respect to its fire Flammable Gases in Fire Areas suppression and detection systems,    AA2 and YD proximity to safe-shutdown equipment, and the impact that the    Engineering Equivalency unrated portion of the fire barrier  Evaluation 11-12, Stairwells and could have on safe-shutdown          Elevator Construction Boundary capability. These barriers which      Evaluations (Fire Areas AA1, contained unrated components          AA2A, AA2B, AA3, AA5/6, have been evaluated as equivalent    AA36 and AA42 or adequate for the hazard.
Engineering Equivalency Evaluation 11-18, Fire Zones 3, 31, 32 and 35 (AA3) Boundary Evaluation Engineering Equivalency Evaluation 11-36, Unit 1 and 2 Hot Shutdown Panel
 
==Enclosure:==
 
Unit 1 Fire Zone 144 (AA50) and Unit Fire Zone 145 (AA51)
Engineering Equivalency Evaluation 11-38, Fire Protection Pump House (Fire Area YD)
Engineering Equivalency Evaluation 11-39, Fireproofing for the West Motor Driven Auxiliary Feedwater Pump Enclosures Fire Zones 17A (AA16), 17B (AA17), 80 (AA2A) and 84 (AA2B)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-136 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-41, Unit 1 Fire Zone 53 (AA46) and Unit 2 Fire Zone 54 (AA47) Boundary Evaluation Engineering Equivalency Evaluation 11-44, Unrated Fire Doors (361 and 362) and Unrated Personnel Walkways (AA3, AA34, AA35, and AAYD)
Engineering Equivalency Evaluation 11-51, Screenhouse and Water Intake System Boundary Evaluation Fire Zone 142 (AA2A) to Fire Zone 143 (YD)
Engineering Equivalency Evaluation 11-66, Yard (YD) to Fire Zone 19 (AA24) Boundary Evaluation Engineering Equivalency Evaluation 11-67, Technical Evaluation for Embedded Conduit Evaluation Engineering Equivalency Evaluation 11-7, Fire Zone 5 (AA5/6) to Unit 1 Fire Zones 62A, 62B and 62C (AA54) and Unit 2 Fire Zones 63A, 63B and 63C (AA5) Removable Block Walls Transition Document Access Code - D.C. Cook Version 2.4.3 Page 184 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-137 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-9, Turbine, Auxiliary and Containment Buildings Boundary Evaluation Engineering Equivalency Evaluation 12-11, Structural Steel Evaluations in Fire Areas AA2A, AA2B, AA3, AA34, AA35, AA56 and AA58 Engineering Equivalency Evaluation 12-16, Radiant Heat Shields for Fire Area AA58 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 185 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-138 NFPA 805 Ch. 3 Ref    Requirements/Guidance                            Compliance Statement                Compliance Basis                      Reference Document 3.11.3 Fire Barrier    Penetrations in fire barriers shall be            Complies                            In general, fire-rated door          FSA, D. C. Cook Fire Safety Penetrations          provided with listed fire-rated door                                                  assemblies or listed rated fire      Analysis assemblies or listed rated fire dampers                                                dampers having the fire resistance having a fire resistance rating consistent                                            rating consistent with the fire with the designated fire resistance rating                                            resistance rating of the fire barrier of the barrier as determined by the                                                    are provided. Fire-rated assemblies performance requirements established by                                                which include fire-rated doors and Chapter 4. (See [3.11.4] for penetration                                              fire dampers required by Chapter 4 seals for through penetration fire stops.)                                            are outlined in the D. C. Cook Fire Safety Analysis (FSA).
Exception: Where fire area boundaries are not wall-to-wall, floor-to-ceiling boundaries with all penetrations sealed to the fire rating required of the boundaries, a performance-based analysis shall be required to assess the adequacy of fire barrier forming the fire boundary to determine if the barrier will withstand the fire effects of the hazards in the area.
Openings in fire barriers shall be permitted to be protected by other means as acceptable to the AHJ.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-139 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies with Use of                Where fire-rated door assemblies      Equivalency Evaluations is listed EEEEs                              or listed rated fire dampers are not  in 3.11.3(1) through 3.11.3(3),
provided with the fire resistance    Rev. 0 rating consistent with the fire resistance rating of the fire barrier (e.g. hatches, water curtains, manways, etc.), the assemblies have been evaluated to be equivalent or adequate for the hazard.
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American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-140 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.11.3(1) [NFPA        Passive fire protection devices such as        Complies with                      All doors are UL Class A (3 hour)    Engineering Equivalency 80 - Fire Door and    doors and dampers shall conform with          Clarification                      fire rating or a UL Class B (1-1/2  Evaluation 11-71, Emergency Window                the following NFPA standards, as                                                  hour) rating to be commensurate      Power Systems Area & EPS Requirements]          applicable:                                                                        with the severity of the hazard as  Control Rod Drive Room Fire determined by the performance        Door Closure Evaluation, dated (1) NFPA 80, "Standard for Fire Doors                                              requirements established by          April 6, 2017 and Fire Windows"                                                                  Chapter 4 of NFPA 805. I&M has committed CNP to comply with        Engineering Equivalency NFPA 80. Modifications to rated      Evaluation 11-72, Fire Door fire doors are made in accordance    Automatic Release Device with NFPA 80 in order to ensure      Evaluation (12-DR-TUR224, 12-that the fire protection features of DR-TUR242, 1-DR-AUX313, the door are not degraded.          and 2-DR-AUX314), dated March 13, 2017 Fire rated doors that are designed to be left in the open position, if  Procedure 12-FPE-2270-FPCE-desired, are provided with self-    001, Fire Protection Program closing hardware which, when        Change Evaluation activated by exposure to the heat of a fire, allows the door to close.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 188 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-141 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies by Previous                During the review for compliance    NRC Safety Evaluation NRC Approval                        with Appendix A to BTP 9.5-1, the  supporting Amendment Nos. 31 NRC identified concerns relating to and 12 to License No. DPR-58 the installation placement and      and DPR-74, dated July 31, 1979 rating of fire doors at CNP. I&M    / Page 13, Other Items relating to committed to upgrading affected    the Station Fire Protection fire doors and per the NRC Safety  Program, item B Evaluation, dated July 31, 1979, which states:                      I&M Letter, Request for Approval and Exemptions, dated "We conclude that fire doors and    March 31, 1983 / Section 7.2.6 dampers are provided or committed where necessary in        NRC Safety Evaluation, Donald accordance with the provisions of  C. Cook Nuclear Power Plant, Appendix A to Branch Technical      Unit Nos. 1 and 2 Fire Position APCSB 9.5-1 and are,      Protection - Request for therefore, acceptable.            Exemption from requirements of Appendix R to 10 CFR 50, These commitments to remedy any    Sections III.G and III.O, dated deficiencies listed in the          December 23, 1983 / page 5, aforementioned Safety Evaluation    Section 4.0, Conclusion Report have been fulfilled per the FPPM, which states:
                                                                                        "The noted deficiencies were corrected or appropriate justifications have been prepared."
The fire doors where deficiencies were corrected or justifications prepared, as approved by the SE Report, are still used at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. The corrected doors remain unchanged. The justification for the any deficiencies remains valid and Transition Document Access Code - D.C. Cook Version 2.4.3 Page 189 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                Page 1A-142 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document unchanged.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 190 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                Page 1A-143 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with Use of                Where any unrated doors are        Engineering Equivalency EEEEs                              located in fire area boundaries, an Evaluation 11-1, Auxiliary evaluation has been performed to    Building El. 587 to Spent Fuel determine the doors are equivalent  Heat Exchanger Pit Pump Room or adequate for the hazard.        Hatch Boundary Evaluation Fire Zone 5 (AA5/6) and Fire Zone 36 Where non-UL/FM approved            (AA3) Hatch Evaluation electromagnetic door latches are used in doors located in fire area  Engineering Equivalency boundaries, an evaluation has been  Evaluation 11-15, Switchgear performed to determine that the    Room Construction Boundary fire rating of the door is not      Room Evaluation Unit 1 Fire Zones 14, 40A, 40B, 41 and 42A (AA13, AA39A, AA39B, AA40 and AA41) & Unit 2 Fire Zones 20, 45, 46A, 47A and 47B (AA25, AA43, AA44, AA45A and AA45B)
Engineering Equivalency Evaluation 11-37, Fire Zones 52 and Fire Zone 44N Hatch Evaluation Engineering Equivalency Evaluation 11-39, Fireproofing for the West Motor Driven Auxiliary Feedwater Pump Enclosures Fire Zones 17A (AA16), 17B (AA17), 80 (AA2A) and 84 (AA2B)
Engineering Equivalency Evaluation 11-44, Unrated Fire Doors (361 and 362) and Unrated Personnel Walkways (AA3, AA34, AA35, and AAYD)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                        Page 1A-144 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis            Reference Document Engineering Equivalency Evaluation 11-56, Turbine Building Main Steam Access Way Fire Zones 110 to 114, Fire Zones 111 to 115, Fire Zones 112 to 2N, Fire Zones 113 to 2S (Fire Areas AA2A, AA2B, AA2C)
Engineering Equivalency Evaluation 11-65, Fire Door Closure Evaluation (Fire Areas AA2, AA7, AA8, AA14, AA15, AA23, AA24, AA30, AA31, AA34, AA35, AA36/42, AA37, AA38, AA39, AA41, AA43, AA44, AA45, AA48, and AA53)
Engineering Equivalency Evaluation 11-69, Technical Evaluation for NFPA 80 1970 ED Code Deviation Electromagnetic Fire/Security Door Locks Fire Door Automatic Release Engineering Equivalency Device Evaluation (12-DR-  Evaluation 11-9, Turbine, TUR224, 12-DR-TUR242, 1-    Auxiliary and Containment DR-AUX313, and 2-DR-        Buildings Boundary Evaluation AUX314)
Engineering Equivalency Evaluation 9-13, Fire Zone 53 (AA46) and Fire Zone 57 (AA50)
Hatch Evaluation Engineering Equivalency Evaluation 9-14, Fire Zone 43 (AA36) and Fire Zone 56 (AA48)
Hatch Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 192 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-145 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 9-15, Fire Zone 40B (AA39B) and Fire Zone 55 (AA48) Hatch Evaluation Engineering Equivalency Evaluation 9-16, Fire Zone 41 (AA40) and Fire Zone 55 (AA48)
Hatch Evaluation Engineering Equivalency Evaluation 9-17, Fire Zone 54 (AA47) and Fire Zone 58 (AA51)
Hatch Evaluation Engineering Equivalency Evaluation 9-18, Fire Zone 52 (AA3) and Fire Zone 59 (AA52)
Hatch Evaluation Engineering Equivalency Evaluation 9-19, Fire Zone 45 (AA43) and Fire Zone 60 (AA52)
Hatch Evaluation Engineering Equivalency Evaluation 9-21, Fire Zone 110 (AA2A) and Fire Zone 43 (AA36) Door Evaluation Engineering Equivalency Evaluation 9-22, Fire Zone 111 (AA2B) and Fire Zone 44S (AA42) Door Evaluation Engineering Equivalency Evaluation 9-23, Fire Zone 116 (AA9) Boundary Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 193 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-146 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 9-24, Fire Zone 117 (AA29) Boundary Evaluation Engineering Equivalency Evaluation 9-25, Essential Service Water Pump House Hatch and Fire Damper Evaluation (Fire Areas AA2, AA32 and AA33)
Engineering Equivalency Evaluation 9-31, Fire Zones 62A, 62B and 62C (AA54) Boundary Evaluation Engineering Equivalency Evaluation 9-32, Fire Zones 63A, 63B and 63C (AA56) Boundary Evaluations Engineering Equivalency Evaluation 9-37, Fire Zones 5 (AA5/6) and 32 (AA3) Boundary Evaluations Engineering Equivalency Evaluation 9-39, Fire Zone 70 (AA57A) to Fire Zone 129 (AA2A) Boundary Evaluation Engineering Equivalency Evaluation 9-5, Fire Zones 70 (AA57A) and 73 (AA57B) Hatch Evaluations Procedure 12-FPE-2270-FPCE-001, Fire Protection Program Change Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 194 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                                    Page 1A-147 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                    Reference Document 3.11.3(2) [NFPA        Passive fire protection devices such as        Complies                            All ventilation dampers carry UL    Procedure 12-FPE-2270-FPCE-90A - Fire Damper      doors and dampers shall conform with                                              Class A (3 hour) fire rating or a UL 001, Fire Protection Program Requirements]          the following NFPA standards, as                                                  Class B (1-1/2 hour) rating to be    Change Evaluation applicable:                                                                        commensurate with the severity of the hazard as determined by the (2) NFPA 90A, "Standard for the                                                    performance requirements Installation of Air-Conditioning and                                              established by Chapter 4 of NFPA Ventilating Systems"                                                              805. I&M has committed CNP to comply with NFPA 90A.
Modifications to rated fire dampers are made in accordance with NFPA 90A in order to ensure that the fire protection features of the damper are not degraded.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-148 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies by Previous                Technical specification-related fire NRC Safety Evaluation of Fire NRC Approval                        dampers and HVAC system              Protection Requests, dated designs have been reviewed by the    August 27, 1985 / Section 3.4 NRC for damper placement and ratings. These dampers have also    I&M Letter 0692R, Request for been reviewed by I&M for rating      Additional Technical Exemptions and installation.                    to Certain Fire dampers and "Seismic Gaps", dated June 15, Per letter from I&M to the NRC      1984 dated June 15, 1984:
I&M Letter 0692U, Appendix R "In the area of HVAC ductwork,      Technical Exemption for Seismic we have recently discovered that    Gaps and HVAC Duct technical exemptions are required    Penetrations, dated August 13, for 17 ducts which penetrate fire    1994 barriers. These areas are typified by low combustible loading, and duct outlets being located in an area sufficiently removed from equipment important to the safe shutdown of the facility. Sound engineering evaluations can be used to justify our request for technical exemption of the requirements for fire dampers.
Per letter from I&M to the NRC dated August 13, 1984:
The evaluation concludes that, because of a low combustible loading of less than 15 minutes in all applicable fire areas/zones, the location of safe shutdown components/circuits and the detection and suppression systems available in the subject fire area/zones, adequate protection from duct related fire damage is Transition Document Access Code - D.C. Cook Version 2.4.3 Page 196 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-149 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document provided and safe shutdown capability is ensured. As discussed with your staff, the evaluation includes five additional ventilation duct penetrations without fire dampers, that also require technical exemptions. These duct penetrations listed below were not identified in the {{letter dated|date=June 15, 1984|text=June 15, 1984 letter}}.
The NRC Safety Evaluation, dated August 27, 1985 states:
Based on our evaluation, we conclude that we have reasonable assurance that the 22 Auxiliary Building undampered ventilation duct penetrations will not affect safe-shutdown in the event of a fire in Fire Area A, B, C, D or E. The lack of fire dampers in these 22 ventilation duct penetrations is, therefore, an acceptable deviation from the guidelines of Section D.l.(j) of Appendix A to BTP APCSB 9.5-1.
The 22 undampered ventilation duct penetrations, as approved by the SE Report, still exist at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. The justification for the ventilation ducts remains valid and unchanged.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                Page 1A-150 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Transition Document Access Code - D.C. Cook Version 2.4.3 Page 198 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                              Page 1A-151 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                  Reference Document Complies with Use of                Engineering equivalency            Engineering Equivalency EEEEs                              evaluations have been performed    Evaluation 11-14, Cable for any unrated dampers located in Spreading Room Construction fire area boundaries. These        Boundary Evaluation (Fire Areas engineering equivalency            AA3,AA7, AA8, AA9, AA10, evaluations determined the        AA29, AA30, AA31, AA34, dampers are equivalent or adequate AA35, AA36, AA37, AA38, for the hazard.                    AA42, AA48, AA50, AA51 and AA52)
Engineering Equivalency Evaluation 11-15, Switchgear Room Construction Boundary Room Evaluation Unit 1 Fire Zones 14, 40A, 40B, 41 and 42A (AA13, AA39A, AA39B, AA40 and AA41) & Unit 2 Fire Zones 20, 45, 46A, 47A and 47B (AA25, AA43, AA44, AA45A and AA45B)
Engineering Equivalency Evaluation 11-16, ENGINEERING EQUIVALENCY EVALUATION FOR LUBE OIL STORAGE ROOMS FIRE ZONES 83, 88, 95 AND 100 (AA2), BOUNDARY EVALUATION Engineering Equivalency Evaluation 11-45, Auxiliary Building HVAC Duct Penetrations Boundary Evaluation Fire Areas AA1, AA3, AA5/6, AA36 and AA42 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 199 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-152 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-56, Turbine Building Main Steam Access Way Fire Zones 110 to 114, Fire Zones 111 to 115, Fire Zones 112 to 2N, Fire Zones 113 to 2S (Fire Areas AA2A, AA2B, AA2C)
Engineering Equivalency Evaluation 12-13, Fire Damper Closure Review Engineering Equivalency Evaluation 9-1, Fire Zone 43 (AA36) and 91 (AA2A) Duct Evaluation Engineering Equivalency Evaluation 9-2, Fire Zone 54 (AA47) and Fire Zone 73 (AA57B) Duct Evaluation Engineering Equivalency Evaluation 9-3, CCW Pump Air Supply Duct Evaluation: Fire Zone 44S (AA42)
Engineering Equivalency Evaluation 9-33, Fire Zone 6A (AA5/6) to 138B (AA1)
Boundary Evaluations Engineering Equivalency Evaluation 9-34, Fire Zone 36 (AA3) to Fire Zone 5 (AA5/6)
Boundary Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 200 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-153 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 9-35, Fire Zone 108 (AA2A) to Fire Zone 33A (AA34) Boundary Evaluation Engineering Equivalency Evaluation 9-36, Fire Zone 109 (AA2B) to 34A (AA35)
Boundary Evaluation Engineering Equivalency Evaluation 9-37, Fire Zones 5 (AA5/6) and 32 (AA3) Boundary Evaluations Engineering Equivalency Evaluation 9-38, Fire Zone 69 (AA3) to Fire Zones 108 (AA2A) and 109 (AA2B) Boundary Evaluations Engineering Equivalency Evaluation 9-4, Auxiliary Building Vertical Air Shafts Evaluation: Fire Zones 12 (AA11) and 22 (AA27)
Engineering Equivalency Evaluation 9-40, Fire Zone 7 (AA7) to Fire Zone 61 (AA5/6)
Boundary Elevation Engineering Equivalency Evaluation 9-41, Fire Zones 37 (AA36) and 51(AA3) HVAC Duct Penetrations Transition Document Access Code - D.C. Cook Version 2.4.3 Page 201 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                                  Page 1A-154 NFPA 805 Ch. 3 Ref    Requirements/Guidance                        Compliance Statement                Compliance Basis                  Reference Document Engineering Equivalency Evaluation 9-7, Fire Zone 13 (AA12) and Fire Zone 14 (AA13)
Boundary Evaluation Engineering Equivalency Evaluation 9-8, Fire Zone 20 (AA25) and Fire Zone 21 (AA26)
Boundary Evaluatio 3.11.3(3) [NFPA        Passive fire protection devices such as        Complies with                      CNP complies with clarification    NFPA 101, Life Safety Code, 101 - Life Safety      doors and dampers shall conform with          Clarification                      with regards to NFPA 101, 2000    2000 Edition / Sections Code Requirements]    the following NFPA standards, as                                                  Edition. NFPA 101 compliance is    8.2.3.2.1(a) and 9.2.1 applicable:                                                                        achieved through NFPA 80 and NFPA 90A. NFPA 101, 2000 (3) NFPA 101, "Life Safety Code"                                                  Edition, Section 8.2.3.2.1(a) with regards to rated fire door assemblies refers to NFPA 80.
NFPA 101, 2000 Edition, Section 9.2.1 with regards to rated fire dampers refers to NFPA 90A.
Table B-1, Section 3.11.3(1) and 3.11.3(2) discuss compliance of NFPA 80 and NFPA 90A.
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American Electric Power                                                                  NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-155 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                      Reference Document 3.11.4 Through        Through penetration fire stops for              Complies                            CNP specification ES-FIRE-0601-      Plant Specification ES-FIRE-Penetration Fire      penetrations such as pipes, conduits, bus                                            QCF details the requirements for      0601-QCF, Fire Rated Seals Stops                  ducts, cables, wires, pneumatic tubes and                                            the installation and maintenance of ducts, and similar building service                                                  fire rated seals and fire stops at equipment that pass through fire barriers                                            CNP. The scope of this shall be protected as follows.                                                      specification is for penetration seals that are installed or are being installed at CNP that will function to prevent the spread of fire.
Additionally, per specification ES-FIRE-0601-QCF, CNP allows the use of additional test standards ASTM E-814, MEEB 634 and NFPA 251 for development of standard fire test, and qualification of fire rated penetration seals.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-156 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                By the response to Appendix A to      NRC Safety Evaluation, dated NRC Approval                        Branch Technical Position APCSB      July 31, 1979 / Page 13, Other 9.5-1, dated January 31, 1977, item  Items Relating to the Station Fire D.1.(j) I&M stated:                  Prtotection Program, Section A "all openings for cable, pipe, and    I&M response to Appendix A to ductwork in these walls, floors,      Branch Technical Position and ceilings have been sealed with    APCSB 9.5-1 for Units No. 1 and foamed in place silicone which was    2, dated January 31, 1977 /
tested in march 1975 for up to five  Section D.1.(j) hours fire exposure in an ASTM E 119 wall fire test."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "The test report shows that the penetration seal passed a 3-hour E-119 type fire exposure test.
However, the test included only the Unit 2 penetration design. The licensees have provided a comparison between Unit 1 and Unit 2 penetration seal designs to justify that the Unit 2 design is the "worst case" for fire testing. We agree with this evaluation and conclude that the Unit 2 seal tests are acceptable for the Unit 1 seals.
We conclude that the penetration fire stops which are in place provide sufficient protection from the unbounded spread of fire along electrical cables. We base this conclusion on our knowledge of ASTM E-119 fire tests including those cited by the licensees which substantiate the fire resistive ability of penetration fire stops Transition Document Access Code - D.C. Cook Version 2.4.3 Page 204 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-157 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document constructed with silicone foam."
The foamed in place silicone design, as approved by the SE Report, is still in use at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. The foamed in place silicone design and the justification of the worst case configuration has not changed.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                            Revision 4 NFPPM - Attachment 1                                                                                                                              Page 1A-158 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                Reference Document Complies with Use of                Where through penetration fire  Engineering Equivalency EEEEs                              stops are not protected in      Evaluation 11-15, Switchgear accordance with Section 3.11.4, Room Construction Boundary these assemblies have been      Room Evaluation Unit 1 Fire evaluated to be equivalent or  Zones 14, 40A, 40B, 41 and 42A adequate for the hazard.        (AA13, AA39A, AA39B, AA40 and AA41) & Unit 2 Fire Zones 20, 45, 46A, 47A and 47B (AA25, AA43, AA44, AA45A and AA45B)
Engineering Equivalency Evaluation 11-16, ENGINEERING EQUIVALENCY EVALUATION FOR LUBE OIL STORAGE ROOMS FIRE ZONES 83, 88, 95 AND 100 (AA2), BOUNDARY EVALUATION Engineering Equivalency Evaluation 11-17, Diesel Generator Fuel oil Day Tank Rooms Fire Zones 15 (AA14), 16 (AA15), 18 (AA23) and 19 (AA24) Boundary Evaluation Engineering Equivalency Evaluation 11-2, Fire Zone 7 (AA7) to Fire Zone 38 (AA37)
Boundary Evaluation Engineering Equivalency Evaluation 11-24, Fire Retention Capability of Nonconforming Fire Seals in Fire Zones having a Low Fire Severity Transition Document Access Code - D.C. Cook Version 2.4.3 Page 206 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-159 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-26, Fire Retention Capability of a HELB 3 Pressure Boundary Seal (Fire Areas AA19, AA20, AA21 and AA22)
Engineering Equivalency Evaluation 11-27, Generic Fire Seal Design 1 Engineering Equivalency Evaluation 11-28, Generic Fire Seal Design 2 (Fire Areas AA7, AA8, AA39A, AA40, AA43, AA45A, AA45B, AA48 and AA52)
Engineering Equivalency Evaluation 11-29, Generic Fire Seal Design 3 in Fire Areas AA2A, AA2B, and AA15 Engineering Equivalency Evaluation 11-3, Fire Zone 27 (AA31) to Fire Zone 39 (AA38)
Engineering Equivalency Evaluation 11-30, Generic Fire Seal Design 4 (AA2)
Engineering Equivalency Evaluation 11-31, Generic Fire Seal Design 5 (Fire Areas AA31 and AA38)
Engineering Equivalency Evaluation 11-32, Generic Fire Seal Design 6 (AA2)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-160 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-33, Generic Fire Seal Design 7 (Fire Areas AA7 and AA37)
Engineering Equivalency Evaluation 11-34, Generic Fire Seal Design 8 Engineering Equivalency Evaluation 11-35, Generic Fire Seal Design 9 Engineering Equivalency Evaluation 11-4, Unit 1 Auxiliary Building Elevation 620 ft.-6 in. to Auxiliary Cable Vault Fire Zone 44n to Fire Zone 56 Engineering Equivalency Evaluation 11-47, Fire Zones 44N (AA36), 44S (AA42) and 52 (AA3) Penetration Seals Engineering Equivalency Evaluation 11-48, Fire Zones 15 (AA14), 16 (AA15) 18 (AA23) and 19 (AA24) Penetration Seals Engineering Equivalency Evaluation 11-5, Unit 1 EPS/4 KV Switchgear Complex Ventilation Shaft Boundary Evaluation (Fire Areas AA39A, AA39B, AA40, AA41 and AA48)
Engineering Equivalency Evaluation 11-50, Embedded Conduit Fire Wrap Protection (Fire Areas AA14 and AA24)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-161 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-51, Screenhouse and Water Intake System Boundary Evaluation Fire Zone 142 (AA2A) to Fire Zone 143 (YD)
Engineering Equivalency Evaluation 11-54, Unit 1 Main Control Room Cable Vault Penetration Seal W5111 Fire Zone 57 and 91 (Fire Areas AA50 and AA2A)
Engineering Equivalency Evaluation 11-56, Turbine Building Main Steam Access Way Fire Zones 110 to 114, Fire Zones 111 to 115, Fire Zones 112 to 2N, Fire Zones 113 to 2S (Fire Areas AA2A, AA2B, AA2C)
Engineering Equivalency Evaluation 11-6, Fire Zones 45 (AA43), 46A through 46D (AA44), 47A (AA45A), 47B (AA45B) to Fire Zone 60 (AA52)
Shaft Boundary Evaluation Engineering Equivalency Evaluation 11-7, Fire Zone 5 (AA5/6) to Unit 1 Fire Zones 62A, 62B and 62C (AA54) and Unit 2 Fire Zones 63A, 63B and 63C (AA5) Removable Block Walls Transition Document Access Code - D.C. Cook Version 2.4.3 Page 209 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-162 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-79, Fire Zone 53 (AA46) And Fire Zone 57 (AA50) Fire Barrier Penetration Seals Engineering Equivalency Evaluation 11-80, Fire Zone 54 (AA47) And Fire Zone 58 (AA51) Fire Barrier Penetration Seals Engineering Equivalency Evaluation 9-35, Fire Zone 108 (AA2A) to Fire Zone 33A (AA34) Boundary Evaluation Engineering Equivalency Evaluation 9-36, Fire Zone 109 (AA2B) to 34A (AA35)
Boundary Evaluation Engineering Equivalency Evaluation 9-37, Fire Zones 5 (AA5/6) and 32 (AA3) Boundary Evaluations Technical Evaluation-11-20, Narrow Space Openings between Penetrating Items and the Barrier or Between Penetrating Items Boundary Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 210 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                        Revision 4 NFPPM - Attachment 1                                                                                                                                                          Page 1A-163 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                      Reference Document 3.11.4(a) [Annular    The annular space between the                      Complies                            CNP specification ES-FIRE-0601-        Plant Specification ES-FIRE-Space Requirements]    penetrating item and the through opening                                                QCF details the requirements for      0601-QCF, Fire Rated Seals /
in the fire barrier shall be filled with a                                              the installation and maintenance of    Attachment 1, Typical Details qualified fire-resistive penetration seal                                              fire rated seals and fire stops at assembly capable of maintaining the fire                                                CNP. The scope of this resistance of the fire barrier. The                                                    specification is for penetration assembly shall be qualified by tests in                                                seals that are installed or will be accordance with a fire test protocol                                                    installed at CNP that will function acceptable to the AHJ or be protected by                                                to prevent the spread of fire. Per a listed fire-rated device for the specified                                            this specification, the contractor fire-resistive period.                                                                  installing the fire seals must furnish documentation that the configurations have passed ASTM E-119 fire and hose stream tests that have been performed and documented by an independent laboratory.
Additionally, per specification ES-FIRE-0601-QCF, the standards which can be used for development of standard fire test and qualification of fire rated penetration seals are ASTM E-814, MEEB 634 and NFPA 251.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-164 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                By the response to Appendix A to      NRC Safety Evaluation, dated NRC Approval                        Branch Technical Position APCSB      July 31, 1979 / Other Items 9.5-1, dated January 31, 1977, item  Related to the Station Fire D.1.(j) I&M stated:                  Protection Program, Section A "all openings for cable, pipe, and    I&M response to Appendix A to ductwork in these walls, floors,      Branch Technical Position and ceilings have been sealed with    APCSB 9.5-1 for Units No. 1 and foamed in place silicone which was    2, dated January 31, 1977 /
tested in march 1975 for up to five  Section D.1.(j) hours fire exposure in an ASTM E 119 wall fire test."
The NRC Safety Evaluation, dated July 31, 1979 states:
                                                                                        "The test report shows that the penetration seal passed a 3-hour E-119 type fire exposure test.
However, the test included only the Unit 2 penetration design. The licensees have provided a comparison between Unit 1 and Unit 2 penetration seal designs to justify that the Unit 2 design is the "worst case" for fire testing. We agree with this evaluation and conclude that the Unit 2 seal tests are acceptable for the Unit 1 seals.
We conclude that the penetration fire stops which are in place provide sufficient protection from the unbounded spread of fire along electrical cables. We base this conclusion on our knowledge of ASTM E-119 fire tests including those cited by the licensees which substantiate the fire resistive ability of penetration fire stops Transition Document Access Code - D.C. Cook Version 2.4.3 Page 212 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-165 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document constructed with silicone foam."
The foamed in place silicone design, as approved by the SE Report, is still in use at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. The foamed in place silicone design and the justification of the worst case configuration has not changed.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-166 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with Use of                Engineering equivalency              Engineering Equivalency EEEEs                              evaluations have been performed      Evaluation 11-15, Switchgear for any penetrations that do not    Room Construction Boundary provide a fire resistance rating at  Room Evaluation Unit 1 Fire least equal to that of the fire area Zones 14, 40A, 40B, 41 and 42A barrier itself. These engineering    (AA13, AA39A, AA39B, AA40 equivalency evaluations              and AA41) & Unit 2 Fire Zones determined the penetrations are      20, 45, 46A, 47A and 47B equivalent or adequate for the      (AA25, AA43, AA44, AA45A hazard.                              and AA45B)
Engineering Equivalency Evaluation 11-16, ENGINEERING EQUIVALENCY EVALUATION FOR LUBE OIL STORAGE ROOMS FIRE ZONES 83, 88, 95 AND 100 (AA2), BOUNDARY EVALUATION Engineering Equivalency Evaluation 11-17, Diesel Generator Fuel oil Day Tank Rooms Fire Zones 15 (AA14), 16 (AA15), 18 (AA23) and 19 (AA24) Boundary Evaluation Engineering Equivalency Evaluation 11-2, Fire Zone 7 (AA7) to Fire Zone 38 (AA37)
Boundary Evaluation Engineering Equivalency Evaluation 11-24, Fire Retention Capability of Nonconforming Fire Seals in Fire Zones having a Low Fire Severity Transition Document Access Code - D.C. Cook Version 2.4.3 Page 214 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-167 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-26, Fire Retention Capability of a HELB 3 Pressure Boundary Seal (Fire Areas AA19, AA20, AA21 and AA22)
Engineering Equivalency Evaluation 11-27, Generic Fire Seal Design 1 Engineering Equivalency Evaluation 11-28, Generic Fire Seal Design 2 (Fire Areas AA7, AA8, AA39A, AA40, AA43, AA45A, AA45B, AA48 and AA52)
Engineering Equivalency Evaluation 11-29, Generic Fire Seal Design 3 in Fire Areas AA2A, AA2B, and AA15 Engineering Equivalency Evaluation 11-3, Fire Zone 27 (AA31) to Fire Zone 39 (AA38)
Engineering Equivalency Evaluation 11-30, Generic Fire Seal Design 4 (AA2)
Engineering Equivalency Evaluation 11-31, Generic Fire Seal Design 5 (Fire Areas AA31 and AA38)
Engineering Equivalency Evaluation 11-32, Generic Fire Seal Design 6 (AA2)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-168 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-33, Generic Fire Seal Design 7 (Fire Areas AA7 and AA37)
Engineering Equivalency Evaluation 11-34, Generic Fire Seal Design 8 Engineering Equivalency Evaluation 11-35, Generic Fire Seal Design 9 Engineering Equivalency Evaluation 11-4, Unit 1 Auxiliary Building Elevation 620 ft.-6 in. to Auxiliary Cable Vault Fire Zone 44n to Fire Zone 56 Engineering Equivalency Evaluation 11-47, Fire Zones 44N (AA36), 44S (AA42) and 52 (AA3) Penetration Seals Engineering Equivalency Evaluation 11-48, Fire Zones 15 (AA14), 16 (AA15) 18 (AA23) and 19 (AA24) Penetration Seals Engineering Equivalency Evaluation 11-5, Unit 1 EPS/4 KV Switchgear Complex Ventilation Shaft Boundary Evaluation (Fire Areas AA39A, AA39B, AA40, AA41 and AA48)
Engineering Equivalency Evaluation 11-50, Embedded Conduit Fire Wrap Protection (Fire Areas AA14 and AA24)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-169 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-51, Screenhouse and Water Intake System Boundary Evaluation Fire Zone 142 (AA2A) to Fire Zone 143 (YD)
Engineering Equivalency Evaluation 11-54, Unit 1 Main Control Room Cable Vault Penetration Seal W5111 Fire Zone 57 and 91 (Fire Areas AA50 and AA2A)
Engineering Equivalency Evaluation 11-56, Turbine Building Main Steam Access Way Fire Zones 110 to 114, Fire Zones 111 to 115, Fire Zones 112 to 2N, Fire Zones 113 to 2S (Fire Areas AA2A, AA2B, AA2C)
Engineering Equivalency Evaluation 11-6, Fire Zones 45 (AA43), 46A through 46D (AA44), 47A (AA45A), 47B (AA45B) to Fire Zone 60 (AA52)
Shaft Boundary Evaluation Engineering Equivalency Evaluation 11-7, Fire Zone 5 (AA5/6) to Unit 1 Fire Zones 62A, 62B and 62C (AA54) and Unit 2 Fire Zones 63A, 63B and 63C (AA5) Removable Block Walls Transition Document Access Code - D.C. Cook Version 2.4.3 Page 217 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-170 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 9-35, Fire Zone 108 (AA2A) to Fire Zone 33A (AA34) Boundary Evaluation Engineering Equivalency Evaluation 9-36, Fire Zone 109 (AA2B) to 34A (AA35)
Boundary Evaluation Engineering Equivalency Evaluation 9-37, Fire Zones 5 (AA5/6) and 32 (AA3) Boundary Evaluations Technical Evaluation-11-20, Narrow Space Openings between Penetrating Items and the Barrier or Between Penetrating Items Boundary Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 218 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                      Revision 4 NFPPM - Attachment 1                                                                                                                                                        Page 1A-171 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                    Reference Document 3.11.4(b) [Conduit    Conduits shall be provided with an                  Complies                            CNP specification ES-FIRE-0601-    Plant Specification ES-FIRE-Internal Fire Seals]  internal fire seal that has an equivalent                                              QCF details the requirements for    0601-QCF, Fire Rated Seals /
fire-resistive rating to that of the fire                                              the installation and maintenance of Attachment 1, Typical Details.
barrier through opening fire stop and                                                  fire rated seals and fire stops at shall be permitted to be installed on                                                  CNP.
either side of the barrier in a location that is as close to the barrier as possible.
Exception: Openings inside conduit 4 in.
(10.2 cm) or less in diameter shall be sealed at the fire barrier with a fire-rated internal seal unless the conduit extends greater than 5 ft (1.5 m) on each side of the fire barrier. In this case the conduit opening shall be provided with noncombustible material to prevent the passage of smoke and hot gases. The fill depth of the material packed to a depth of 2 in. (5.1 cm) shall constitute an acceptable smoke and hot gas seal in this application.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                                    Page 1A-172 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                      Reference Document Complies by Previous                By I&M submittal, dated October      NRC Safety Evaluation Report, NRC Approval                        20, 1988, Pg. 2 stated:              dated April 26, 1990 / Evaluation of I&M response to Unresolved "In consonance with our policy to    Issue Related to Post-Fire Safe maintain a safe as possible plant,    Shutdown Methodology, Page 10, we plan to seal conduits that meet    Section 2.18.2 the following criteria:
: 1) An open-ended conduit is one in    I&M Letter, Status of Internal which the contained cables exit the  Conduit Fire Seal Program and conduit into a non-enclosed air      NRC Inspection Report 85013, space and do not directly enter      Item 2.R, dated October 20, 1988 into a metal enclosure such as a      / Pg. 2 junction box or other similar noncombustible closure.
: 2) When both ends of a double open-ended conduit terminate at the wall, it will be treated as a sleeve and sealed.
: 3) For double open-ended conduits smaller than 2 inches in diameter:
: a. When both ends of the conduit terminate less than one foot from the barrier, at least one end will be sealed.
: b. When only one end of the conduit terminates less than one foot from the barrier, only that end of the conduit will be sealed.
: 4) For double open-ended conduits 2 inches in diameter:
: a. When both ends of the conduit terminate less than 3 feet from the barrier, at least one end will be sealed.
: b. When only one end of the conduit terminates less than 3 feet from the barrier, only that end of the conduit will be sealed.
: 5) Double open-ended conduits Transition Document Access Code - D.C. Cook Version 2.4.3 Page 220 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                          Revision 4 NFPPM - Attachment 1                                                                                                                            Page 1A-173 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document greater than 2 inches in diameter will be sealed on at least one end."
The NRC Safety Evaluation, dated April 26, 1990 states:
                                                                                        "Internal conduit seals are provided as delineated in a letter to the staff dated October 20, 1988. The internal seal program is consistent with the guidance provided in Appendix A to BTP APCSB 9.5-1 and is, therefore, acceptable."
The internal conduit sealing criteria, as approved by the SE Report, is still in use at CNP.
There have been no plant modifications or other changes that would invalidate the basis for approval. The criteria for internally sealing conduit has not changed.
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 1                                                                                                                                  Page 1A-174 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis                    Reference Document Complies with Use of                Engineering equivalency              Engineering Equivalency EEEEs                              evaluations have been performed      Evaluation 11-15, Switchgear for any penetrations that do not    Room Construction Boundary provide a fire resistance rating at  Room Evaluation Unit 1 Fire least equal to that of the fire area Zones 14, 40A, 40B, 41 and 42A barrier itself. These engineering    (AA13, AA39A, AA39B, AA40 equivalency evaluations              and AA41) & Unit 2 Fire Zones determined the penetrations are      20, 45, 46A, 47A and 47B equivalent or adequate for the      (AA25, AA43, AA44, AA45A hazard.                              and AA45B)
Engineering Equivalency Evaluation 11-16, ENGINEERING EQUIVALENCY EVALUATION FOR LUBE OIL STORAGE ROOMS FIRE ZONES 83, 88, 95 AND 100 (AA2), BOUNDARY EVALUATION Engineering Equivalency Evaluation 11-17, Diesel Generator Fuel oil Day Tank Rooms Fire Zones 15 (AA14), 16 (AA15), 18 (AA23) and 19 (AA24) Boundary Evaluation Engineering Equivalency Evaluation 11-2, Fire Zone 7 (AA7) to Fire Zone 38 (AA37)
Boundary Evaluation Engineering Equivalency Evaluation 11-24, Fire Retention Capability of Nonconforming Fire Seals in Fire Zones having a Low Fire Severity Transition Document Access Code - D.C. Cook Version 2.4.3 Page 222 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-175 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-26, Fire Retention Capability of a HELB 3 Pressure Boundary Seal (Fire Areas AA19, AA20, AA21 and AA22)
Engineering Equivalency Evaluation 11-27, Generic Fire Seal Design 1 Engineering Equivalency Evaluation 11-28, Generic Fire Seal Design 2 (Fire Areas AA7, AA8, AA39A, AA40, AA43, AA45A, AA45B, AA48 and AA52)
Engineering Equivalency Evaluation 11-29, Generic Fire Seal Design 3 in Fire Areas AA2A, AA2B, and AA15 Engineering Equivalency Evaluation 11-3, Fire Zone 27 (AA31) to Fire Zone 39 (AA38)
Engineering Equivalency Evaluation 11-30, Generic Fire Seal Design 4 (AA2)
Engineering Equivalency Evaluation 11-31, Generic Fire Seal Design 5 (Fire Areas AA31 and AA38)
Engineering Equivalency Evaluation 11-32, Generic Fire Seal Design 6 (AA2)
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 223 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-176 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-33, Generic Fire Seal Design 7 (Fire Areas AA7 and AA37)
Engineering Equivalency Evaluation 11-34, Generic Fire Seal Design 8 Engineering Equivalency Evaluation 11-35, Generic Fire Seal Design 9 Engineering Equivalency Evaluation 11-4, Unit 1 Auxiliary Building Elevation 620 ft.-6 in. to Auxiliary Cable Vault Fire Zone 44n to Fire Zone 56 Engineering Equivalency Evaluation 11-47, Fire Zones 44N (AA36), 44S (AA42) and 52 (AA3) Penetration Seals Engineering Equivalency Evaluation 11-48, Fire Zones 15 (AA14), 16 (AA15) 18 (AA23) and 19 (AA24) Penetration Seals Engineering Equivalency Evaluation 11-5, Unit 1 EPS/4 KV Switchgear Complex Ventilation Shaft Boundary Evaluation (Fire Areas AA39A, AA39B, AA40, AA41 and AA48)
Engineering Equivalency Evaluation 11-50, Embedded Conduit Fire Wrap Protection (Fire Areas AA14 and AA24)
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American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-177 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 11-51, Screenhouse and Water Intake System Boundary Evaluation Fire Zone 142 (AA2A) to Fire Zone 143 (YD)
Engineering Equivalency Evaluation 11-54, Unit 1 Main Control Room Cable Vault Penetration Seal W5111 Fire Zone 57 and 91 (Fire Areas AA50 and AA2A)
Engineering Equivalency Evaluation 11-56, Turbine Building Main Steam Access Way Fire Zones 110 to 114, Fire Zones 111 to 115, Fire Zones 112 to 2N, Fire Zones 113 to 2S (Fire Areas AA2A, AA2B, AA2C)
Engineering Equivalency Evaluation 11-6, Fire Zones 45 (AA43), 46A through 46D (AA44), 47A (AA45A), 47B (AA45B) to Fire Zone 60 (AA52)
Shaft Boundary Evaluation Engineering Equivalency Evaluation 11-7, Fire Zone 5 (AA5/6) to Unit 1 Fire Zones 62A, 62B and 62C (AA54) and Unit 2 Fire Zones 63A, 63B and 63C (AA5) Removable Block Walls Transition Document Access Code - D.C. Cook Version 2.4.3 Page 225 of 315
 
American Electric Power                                              NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                  Revision 4 NFPPM - Attachment 1                                                                                                                    Page 1A-178 NFPA 805 Ch. 3 Ref    Requirements/Guidance      Compliance Statement                Compliance Basis      Reference Document Engineering Equivalency Evaluation 9-35, Fire Zone 108 (AA2A) to Fire Zone 33A (AA34) Boundary Evaluation Engineering Equivalency Evaluation 9-36, Fire Zone 109 (AA2B) to 34A (AA35)
Boundary Evaluation Engineering Equivalency Evaluation 9-37, Fire Zones 5 (AA5/6) and 32 (AA3) Boundary Evaluations Technical Evaluation-11-20, Narrow Space Openings between Penetrating Items and the Barrier or Between Penetrating Items Boundary Evaluation Transition Document Access Code - D.C. Cook Version 2.4.3 Page 226 of 315
 
American Electric Power                                                                    NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                    Revision 4 NFPPM - Attachment 1                                                                                                                                                      Page 1A-179 NFPA 805 Ch. 3 Ref    Requirements/Guidance                              Compliance Statement                Compliance Basis                  Reference Document 3.11.5 Electrical      ERFBS required by Chapter 4 shall be                Complies                            ERFBS that are credited to meet    12-FPP-4030-066-016, Raceway Fire Barrier  capable of resisting the fire effects of the                                            the requirements of NFPA 805      Inspection of Thermo-Lag, Systems (ERFBS)        hazards in the area. ERFBS shall be                                                    Chapter 4 are identified in the D. Darmatt and Mecatiss wrapped tested in accordance with and shall meet                                                C. Cook Fire Safety Analysis      enclosures the acceptance criteria of NRC Generic                                                  (FSA). ERFBS are installed to Letter 86-10, Supplement 1, Fire                                                      meet the requirements of GL        FSA, D. C. Cook Fire Safety Endurance Test Acceptance Criteria for                                                  86-10, Supplement 1.              Analysis Fire Barrier Systems Used to Separate                                                                                      NFPPM, NFPA 805 Fire Safe Shutdown Trains Within the Same                                                                                      Protection Program Manual Fire Area. The ERFBS needs to                                                                                            (NFPPM) / Attachment 6 adequately address the design requirements and limitations of supports and intervening items and their impact on the fire barrier system rating. The fire barrier systems ability to maintain the required nuclear safety circuits free of fire damage for a specific thermal exposure, barrier design, raceway size and type, cable size, fill, and type shall be demonstrated.
Exception No. 1: When the temperatures inside the fire barrier system exceed the maximum temperature allowed by the acceptance criteria of Generic Letter 86-10, Fire Endurance Acceptance Test Criteria for Fire Barrier Systems Used to Separate Redundant Safe Shutdown Training Within the Same Fire Area, Supplement 1, functionality of the cable at these elevated temperatures shall be demonstrated. Qualification demonstration of these cables shall be performed in accordance with the electrical testing requirements of Generic Letter 86-10, Supplement 1, Attachment 1, Attachment Methods for Transition Document Access Code - D.C. Cook Version 2.4.3 Page 227 of 315
 
American Electric Power                                                                NFPA 805 Chapter 3 Fundamental FP Program and Design Elements - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 1                                                                                                                                                Page 1A-180 NFPA 805 Ch. 3 Ref    Requirements/Guidance                          Compliance Statement                Compliance Basis                Reference Document Demonstrating Functionality of Cables Protected by Raceway Fire Barrier Systems During and After Fire Endurance Test Exposure.
Exception No. 2: ERFBS systems employed prior to the issuance of Generic Letter 86-10, Supplement 1, are acceptable providing that the system successfully met the limiting end point temperature requirements as specified by the AHJ at the time of acceptance.
Complies with Use of                Engineering Equivalency          Engineering Equivalency EEEEs                              Evaluation 11.57 evaluates      Evaluation 11-50, Embedded unprotected supports as adequate Conduit Fire Wrap Protection for the hazard.                  (Fire Areas AA14 and AA24)
Engineering Equivalency Evaluation 11-57, Fire-Wrapped Cable Trays and Conduit Evaluations (Fire Areas AA14, AA24, AA32, AA39A, AA45A, AA2A and AA2B)
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American Electric Power                                                                                      NFPA Codes of Record Summary D. C. Cook Nuclear Plant                                                                                                                    Rev. 4 NFPPM - Attachment 2                                                                                                                      Page 2-1 Code        Year      Title                                      Applicable Evaluation(s)/Documents NFPA 10      1984      Standard for Portable Fire                  Report 09-0120-0123 Extinguishers                              Report 09-0120-0381 Report 0120-108-001 Report 0120-164-001 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 12      1968      Standard on Carbon Dioxide                  Report 09-0120-0123 Extinguishing Systems                      Report 0120-108-002 EEE-12-19 Technical Evaluation 12.21 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 12A    1977      Standard on Halon 1301 Fire                Report 09-0120-0123 Extinguishing Systems                      Report 0120-108-003 EEE-12-23 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 13      1971,    Standard for the Installation of Sprinkler  Report 09-0120-0123 1983      Systems                                    Report 09-0120-0381 Report 0120-108-004 Report 0120-164-002 Report 0120-164-007 EEE-11-41 EEE-12-20 EEE-12-22Donald C Cook Nuclear Plant NFPA Code Deviations and Justifications Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 14      1971,    Standard for the Installation of            Report 09-0120-0123 1978,    Standpipe, Private Hydrant and Hose        Report 09-0120-0381 1986      Systems                                    Report 0120-108-005 Report 0120-164-003 Report 0120-164-007 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NRC Safety Evaluation supporting Amendment Nos. 31 and 12 to License No.
DPR-58 and DPR-74, dated July 31, 1979 I&M response to Appendix A to Branch Technical Position APCSB 9.5-1 for Units No. 1 and 2, dated January 31, 1977 Page 229 of 315
 
American Electric Power                                                                                      NFPA Codes of Record Summary D. C. Cook Nuclear Plant                                                                                                                    Rev. 4 NFPPM - Attachment 2                                                                                                                      Page 2-2 Code        Year      Title                                    Applicable Evaluation(s)/Documents NFPA 15      1973      Standard for Water Spray Fixed Systems    Report 09-0120-0123 for Fire Protection                      Report 09-0120-0381 Report 0120-108-1375 Report 0120-164-004 Report 0120-164-007 EEE-11-41 EEE-12-20 EEE-12-22 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 16      N/A      Standard for the Installation of Foam-  N/A - No such systems at CNP Water Sprinkler and Foam-Water Spray Systems NFPA 20      1990      Standard for the Installation of            EEE-11-62Donald C Cook Nuclear Plant NFPA Code Deviations and Justifications Stationary Pumps for Fire Protection NFPA 22      1987      Standard for Water Tanks for Private        EEE-11-77DCC-CE-185-QCF Fire Protection NFPA 24      1987      Standard for the Installation of Private  EEE-11-78 Fire Service Mains and their              EEE-12-24 Appurtenances                            DCC-PM-108-QCS RFC-12-3065 NFPA 27      1986      Private Fire Brigades                    N/A - NFPA 600 reviewed NFPA 30      1987      Flammable and Combustible Liquids        NFPA 30 Code Compliance Evaluation for Donald C. Cook Nuclear Plant Unit 1 Code                                        and 2 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 50A    1999      Standard for Gaseous Hydrogen Systems    EEE-14-1-1 at Consumer Sites NFPA 51B    1999      Standard for Fire Prevention During        EEE-14-1-1 Welding, Cutting, and Other Hot Work NFPA 72D    1967,    Installation, Maintenance, and Use of      Report 09-0120-0123 1979      Proprietary Protective Signaling            Report 09-0120-0381 Systems                                    Report 0120-164-005 EEE-11-41 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications Page 230 of 315
 
American Electric Power                                                                                  NFPA Codes of Record Summary D. C. Cook Nuclear Plant                                                                                                              Rev. 4 NFPPM - Attachment 2                                                                                                              Page 2-3 Code        Year      Title                            Applicable Evaluation(s)/Documents NFPA 72E    1974,    Automatic Fire Detectors          Report 09-0120-0123 1978,                                      Report 09-0120-0381 1982,                                      Report 0120-164-006 1984                                        EEE-11-41 Donald C. Cook Nuclear Plant NFPA Code Deviations and Justifications NFPA 80      1970      Standard for Fire Doors and Fire  NRC Safety Evaluation supporting Amendment Nos. 31 and 12 to License No.
Windows                              DPR-58 and DPR-74, dated July 31, 1979 I&M Letter, Request for Approval and Exemptions, dated March 31, 1983 NRC Safety Evaluation, Donald C. Cook Nuclear Power Plant, Unit Nos. 1 and 2 Fire Protection - Request for Exemption from requirements of Appendix R to 10 CFR 50, Sections III.G and III.O, dated December 23, 1983 EEE-9-5 EEE-9-13 EEE-9-14 EEE-9-15 EEE-9-16 EEE-9-17 EEE-9-18 EEE-9-19 EEE-9-21 EEE-9-22 EEE-9-23 EEE-9-24 EEE-9-25 EEE-9-31 EEE-9-32 EEE-9-37 EEE-9-39 EEE-11-1 EEE-11-9 EEE-11-15 EEE-11-37 EEE-11-39 EEE-11-44 EEE-11-56 Page 231 of 315
 
American Electric Power                                                                                            NFPA Codes of Record Summary D. C. Cook Nuclear Plant                                                                                                                    Rev. 4 NFPPM - Attachment 2                                                                                                                      Page 2-4 Code        Year      Title                                  Applicable Evaluation(s)/Documents EEE-11-65 EEE-11-69 EEE-11-71 EEE-11-72 NFPA 80A    1996      Recommended Practice for Protection of  Refer to Chapter 3 Section 3.11.1, Building Separation in NFPPM, Appendix A.
Buildings from Exterior Fire Exposures NFPA 90A    1978      Standard for the Installation of air-      NRC Safety Evaluation of Fire Protection Requests, dated August 27, 1985 Conditioning and Ventilating Systems      I&M Letter 0692R, Request for Additional Technical Exemptions to Certain Fire dampers and "Seismic Gaps", dated June 15, 1984 I&M Letter 0692U, Appendix R Technical Exemption for Seismic Gaps and HVAC Duct Penetrations, dated August 13, 1994 EEE-9-1 EEE-9-2 EEE-9-3 EEE-9-4 EEE-9-7 EEE-9-8 EEE-9-33 EEE-9-34 EEE-9-35 EEE-9-36 EEE-9-37 EEE-9-38 EEE-9-40 EEE-9-41 EEE-11-14 EEE-11-15 EEE-11-16 EEE-11-45 EEE-11-56 EEE-12-13 NFPA 101    Current  Life Safety Code                        Current edition will apply at the time of material purchase NFPA 220    1999      Standard on Types of Building          Refer to Chapter 3 Section 3.3.2, Structural in NFPPM, Appendix A.
Construction NFPA 241    2000      Standard for Safeguarding Construction,    EEE-14-1-1 Alteration, and Demolition Operations Page 232 of 315
 
American Electric Power                                                                                          NFPA Codes of Record Summary D. C. Cook Nuclear Plant                                                                                                                      Rev. 4 NFPPM - Attachment 2                                                                                                                        Page 2-5 Code        Year      Title                                  Applicable Evaluation(s)/Documents NFPA 251    1999      Methods of Tests of Fire Endurance of  Refer to Chapter 3 Section 3.11.2, Fire Barriers in NFPPM, Appendix A.
Building Construction and Materials NFPA 256    1998      Standard Methods of Fire Tests of Roof Refer to Chapter 3 Section 3.3.6, Roofs in NFPPM, Appendix A.
Coverings NFPA 600    2000      Standard on Industrial Fire Brigades    EEE-14-1-1 NFPA 701    1999      Standard Methods of Fire Tests for    Refer to Chapter 3 Section 3.3.1.2(2), Control of Combustible Materials in NFPPM, Flame Propagation of Textiles and      Appendix A.
Films NFPA 750    N/A      Standard on Water Mist Fire Protection N/A - No such systems at CNP Systems NFPA 2001    N/A      Standard on Clean Agent Fire          N/A - Systems at CNP are not required for NFPA Chapter 4 compliance Extinguishing Systems Page 233 of 315
 
American Electric Power                                                                                        Radioactive Release Review D. C Cook Nuclear Plant                                                                                                                            Rev. 4 NFPPM - Attachment 3                                                                                                                          Page 3-1 Attachment 3 Radioactive Release Review Table of Contents
 
==1.0    INTRODUCTION==
........................................................................................................................ 3-2 1.1  Objective................................................................................................................................... 3-2 1.2  Overview .................................................................................................................................. 3-2 1.3  Scope ........................................................................................................................................ 3-2 1.4  Summary of Revisions.............................................................................................................. 3-2 2.0    ASSUMPTIONS ........................................................................................................................... 3-3 3.0    METHODOLOGY ....................................................................................................................... 3-3 3.1  Determine Radioactive Release Compartmentation ................................................................. 3-3 3.2  Review and Update Fire Pre-Plans for Screened In Fire Areas ............................................ 3-3 3.3  Review Fire Brigade Training Materials .................................................................................. 3-4 3.4  Review Engineering Controls for Gaseous and Liquid Effluents............................................. 3-4 4.0    ANALYSIS ................................................................................................................................... 3-5 4.1  Review of Fire Pre-Plans .......................................................................................................... 3-5 4.2  Review of Fire Brigade Training Materials .............................................................................. 3-6 4.3  Review of Engineering Controls for Gaseous and Liquid Effluents ........................................ 3-6
 
==5.0    REFERENCES==
............................................................................................................................. 3-7 APPENDIX A: RADIOACTIVE RELEASE REVIEW (NEI 04-02 Table E-1) ................................... 3A-1 APPENDIX B: FIRE ZONES WITH POTENTIAL FOR RADIOACTIVE RELEASE ....................... 3B-1 Page 234 of 315
 
American Electric Power                                                          Radioactive Release Review D. C Cook Nuclear Plant                                                                                Rev. 4 NFPPM - Attachment 3                                                                                Page 3-2
 
==1.0    INTRODUCTION==
 
1.1    Objective The radioactive release review is intended to demonstrate that the fire protection goals, objectives, and criteria for addressing the possibility of radioactive release due to potential fuel damage and firefighting activities are met for Cook Nuclear Plant (CNP).
1.2    Overview As discussed in Nuclear Energy Institute (NEI) 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program Under 10 CFR 50.48(c), Appendix G, Considerations for Radioactive Release, the treatment of radiological release to any unrestricted area due to fire is focused on potential radioactive release due to potential fuel damage and firefighting activities. The nuclear safety goal, nuclear safety objectives, and nuclear safety performance criteria specified in NFPA 805 require the prevention of fuel cladding damage. As such, radiological release due to fuel damage should not require a separate examination since no such damage is assumed to occur without violating the basic requirements of NFPA 805. This effectively limits the source of radiation (release source term). Therefore, containment integrity should not require specific examination. This means the scope of the fire protection analyses does not need to be expanded to include all containment isolation valves. No additional analyses are needed for radioactive release due to potential fuel damage.
Therefore, the focus of this report is to address the potential for radiological release due to firefighting activities. The objective is to address the potential for the loss of boundary control for contaminated spaces and to identify whether radiation release during transient conditions exceeds the limits designated in the plants Technical Specifications. The analysis focuses on the review of the fire emergency plans, fire brigade training materials, engineering controls, Technical Specification radiation limits, plant radiological procedures and calculations that are necessary to ensure that potential radioactive release is addressed.
1.3    Scope The following buildings contain zones that have the potential for radioactive release due to fire suppression activities, and are included in this review:
Auxiliary Building (Units 1 and 2)
Containment Building (Units 1 and 2)
Radioactive Materials Storage Building Outdoor Containers Vehicles Transporting Radioactive Materials 1.4    Summary of Revisions Technical Evaluation 12.31, Revision 0 - Represents the initial issue of the document; includes incorporation of guidance provided by NFPA 805 FAQ 09-0056 NFPPM, Revision 1, Attachment 3 - Represents updates made due to completion of NFPA 805 implementation items. Appendices C and D are no longer required since the suggested document Page 235 of 315
 
American Electric Power                                                      Radioactive Release Review D. C Cook Nuclear Plant                                                                              Rev. 4 NFPPM - Attachment 3                                                                              Page 3-3 markups have been incorporated into current plant documentation. While this entire attachment is new to the NFPPM, changes from Technical Evaluation 12.31, Revision 0 are marked with revision bars. Fire Zones 131 and 147 have been removed from this report to match the updated Power Block definition, as contained in the UFSAR. These fire zones do not contain any radioactive release potential.
2.0    ASSUMPTIONS The following assumptions are provided for this Radioactive Release Review:
Sea van containers are of sealed, non-combustible construction. Normal practices do not allow multiple containers to be open and unsecured. Therefore, when considering the potential for radioactive release from locations containing sea van containers, combustion of only one container is assumed. Other metal containers may be used to store combustible contaminated materials provided that the volume is not greater than that of a 40 sea van container as discussed in Technical Evaluation 11.76 (Ref. 5.24).
Technical Evaluation 11.76, NFPA 805 Airborne and Liquid Effluents Offsite Dose Analysis, Revision 0 (Ref. 5.24) considers the worst-case (i.e., most conservative) locations with regard to complete combustion of one sea van container and its corresponding potential for radioactive exposure to the public.
Drainage retention volume and/or drainage flow rate calculations are not provided or reviewed as part of this analysis. However, discussion regarding waste collection tank overflow implications is provided in the analysis below.
3.0    METHODOLOGY 3.1    Determine Radioactive Release Compartmentation All fire zones and outbuildings have been mapped to the corresponding Fire Pre-Plan that covers them. The results of the mapping are identified in Table B-1 (Appendix B).
Those areas that do not have fire zone numbers (e.g., the Radioactive Material Storage Building) are also identified in NEI 04-02 Table E-1 (Appendix A) as they are considered to be screened in in some cases.
Based on input from Plant Radiation Protection (RP) personnel, each fire zone is determined to be screened in or screened out of the radioactive release review. Those areas in which there is no potential for radioactive release exists are considered screened out. The results of the screening process are documented in NEI 04-02 Table E-1 (Appendix A) and Appendix B.
3.2    Review and Update Fire Pre-Plans for Screened In Fire Areas Fire Pre-Plans have been reviewed to ensure that, for locations with a potential for radioactive release due to fire suppression activities, specific steps are included for the containment and monitoring of potential gaseous and liquid effluents involving:
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American Electric Power                                                          Radioactive Release Review D. C Cook Nuclear Plant                                                                                  Rev. 4 NFPPM - Attachment 3                                                                                    Page 3-4 fire suppression agents (e.g., water, foam, dry chemical, halon, CO2), with particular attention given to drainage paths and contaminated liquid drainage systems; smoke and combustion products; post-fire salvage, overhaul, cleanup and recovery activities; and tools and gear used by the fire brigade and offsite fire responders The review has been completed in accordance with EPM Division Procedure EPM-DP-FP-010, Radioactive Release Review, (Ref. 5.23) and with NRC FAQ 09-0056 which is intended to provide further guidance to Appendix G of NEI 04-02, Rev. 1. FAQ 09-0056, states, in part, Ensure for locations that have the potential for contamination that specific steps are included for containment and monitoring of potentially contaminated gaseous and liquid effluents (typically smoke and fire suppression water). Update fire pre-plans as necessary. This review included the following steps:
Identification of applicable documentation, including the plant FSAR, fire pre-plans, procedures, and support drawings; Identification of contaminated plant areas, or areas that have the potential for contamination due to the effects of fire; Review of applicable documentation to identify whether the containment and monitoring of potential contamination involving fire suppression activities is discussed; Revision of documents to require the monitoring and containment of fire suppression agents, products of combustion, and fire brigade tools and gear where the potential for contamination exists Refer to Section 4.1 for results of the fire pre-plan review.
3.3    Review Fire Brigade Training Materials In accordance with NRC FAQ 09-0056, fire brigade training materials have been reviewed to verify whether they specifically address the containment and monitoring of potential contamination due to fire suppression activities. As necessary, the fire brigade training materials have been revised to address such containment and monitoring in potentially contaminated areas.
Refer to Section 3.2 for results of the Fire Brigade Training Materials review.
3.4    Review Engineering Controls for Gaseous and Liquid Effluents In accordance with NRC FAQ 09-0056, engineering controls have been reviewed to ensure that, for locations with a potential for radioactive release due to fire suppression activities (i.e. screened in locations), gaseous and liquid effluents are contained and monitored within the plant boundaries. All plant operating modes, including full power and non-power conditions, were reviewed to confirm that radioactive dose limits found in PMP-6010-OSD-001, Off-Site Dose Calculation Manual are not exceeded.
Examples of engineering controls reviewed include:
Automatic ventilation systems which monitor, filter, and control release of gaseous effluents; Drainage systems which monitor, filter, and control release of liquid effluents; Page 237 of 315
 
American Electric Power                                                        Radioactive Release Review D. C Cook Nuclear Plant                                                                                  Rev. 4 NFPPM - Attachment 3                                                                                  Page 3-5 Review of plant procedures/safeguards and documentation which address available engineering controls for non-power operations (NPO). Examples of NPO conditions include presence of openings such as doors and equipment hatches which could, if not addressed, provide a path for unmonitored and uncontrolled gaseous and liquid effluents This review included the following steps:
Identification of applicable documentation, including the plant UFSAR, fire pre-plans, design basis documents, procedures, and support drawings; Identification of contaminated plant areas, or areas that have the potential for contamination due to the effects of fire; Review of applicable documentation to identify whether the containment and monitoring of potential contamination involving fire suppression activities is discussed Refer to Section 3.3 for results of the Plant Engineering Controls review.
4.0    ANALYSIS 4.1    Review of Fire Pre-Plans Based on review of the CNP fire pre-plans and an assessment by CNP Radiation Protection, the plant areas containing the potential for radioactive release due to fire suppression activities and where the fire itself could cause a radioactive release (e.g., locations where fire could melt a non-metallic vessel containing a radioactive material) have been determined. The plant areas that do contain the potential for radioactive release due to fire suppression activities are listed in Appendix B of this report.
Per plant Procedure ENVI-8914, Coordination of the Operational Aspects of the Radioactive Effluents Program at Cook Nuclear Plant, a system is in place to monitor and contain radioactive effluents. Dose from gaseous effluents is maintained as low as reasonably achievable (ALARA) through operational processes and procedures. The Operations Department maintains a standard decay time for waste gas decay tanks as defined in the Updated Final Safety Analysis Report (UFSAR) (Chapter 11) and plant procedures. Waste gas in the tanks is released only if the required decay time has been met, if operational focus requires it, or if any explosive mixture of gases exists in a tank. In the event of a discharge, radioactive gaseous releases are potentially discharged and monitored from five discharge points: the unit vent, the condenser evacuation system, the gland seal exhaust, the plant heating boiler, and the steam generator blow-down start-up flask tank vent.
Procedure ENVI-8914 states that all options shall be exhausted before determining that the release of a gas volume to the environment is required, and Attachment 1 to the procedure details the monitoring and release points of gaseous effluents.
Per Procedure ENVI-8914, liquid waste effluents are maintained ALARA by generation monitoring, work control/procedure input, and use of enhanced technologies. The Operations Department maintains a standard decay time for liquid waste containments as defined in the UFSAR (Chapter 11) and plant procedures. In the event of a discharge, radioactive liquid effluents are potentially discharged and monitored from four discharge points: the Liquid Radwaste Line, Steam Generator Blowdown and Blowdown Treatment, Turbine Building Sump, and the Service Water System, as further discussed in Attachment 1 of Procedure ENVI-8914, Effluent Release Points and Monitoring.
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American Electric Power                                                          Radioactive Release Review D. C Cook Nuclear Plant                                                                                  Rev. 4 NFPPM - Attachment 3                                                                                    Page 3-6 Actions to contain potentially contaminated fire suppression water should follow guidance similar to that found in ENVI-8914 and Chapter 11 of the UFSAR to the extent that potentially contaminated water be isolated and monitored prior to discharge.
Based on this analysis, the fire pre-plans have been revised to reflect that, in locations where the potential for radioactive release due to fire suppression activities exists, communication with Radiation Protection must be established; the contaminated liquid or gaseous substance(s) must be contained within the radiologically controlled area or drained / exhausted to monitored locations; and that contained substances, including tools and gear, must be monitored and then discharged only when the limits specified in PMP-6010-OSD-001 are not exceeded. Fire Pre-Plans have also been revised to include required precautions to be undertaken for manual ventilation and smoke monitoring when normal ventilation is not available. The results of the fire pre-plan review are included in NEI 04-02 Table E-1 (Appendix A).
4.2    Review of Fire Brigade Training Materials Appendix G of NEI 04-02 states, in part, Ensure that training materials deal specifically with the containment and monitoring of potentially contaminated fire suppression water. Update training materials as necessary. Fire brigade training materials have been revised to address the containment of potentially contaminated smoke, fire suppression agents, and fire brigade tools and gear. The revised training materials reinforce the use of fire pre-plans which, as discussed above, detail the steps and precautions necessary to contain radioactive release in potentially contaminated areas. The results of the Fire Brigade training materials review are included in NEI 04-02 Table E-1 (Appendix A).
4.3    Review of Engineering Controls for Gaseous and Liquid Effluents In accordance with NRC FAQ 09-0056, engineering controls have been reviewed to ensure that, for locations with a potential for radioactive release due to fire suppression activities (i.e. screened in), gaseous and liquid effluents (i.e. contaminated smoke and fire-fighting water) are contained and monitored within the plant boundaries. All plant operating modes, including full power and non-power conditions, were reviewed. Per review of plant documentation described in Section 2.4 (Methodology) and discussion with Plant Engineers, engineering controls are capable of containing and monitoring radioactive gaseous and liquid effluents prior to safe discharge to atmosphere. The plants approach is deemed acceptable to meet NFPA 805 radioactive release performance criteria.
Refer to NEI 04-02 Table E-1 (Appendix A) for system specifics regarding engineering controls present in specific screened in fire zones. NEI 04-02 Table E-1 is provided in the format recommended in NRC FAQ 09-0056.
Except as noted below, the Fire Areas where liquid effluents are collected in sumps or floor drains and routed to holdup tanks) are located in the Auxiliary building. All drainage in the Auxiliary Building above the elevation of 587 ft is routed to one of two Waste Holdup Tanks. Each of these tanks has a capacity of approximately 25,000 gallons. Drainage below the elevation of 587 ft is routed to either the Dirty Station Drain Sump Tank or the Clean Sump Tank, which have capacities of 600 gallons and 525 gallons, respectively. Liquid entering either of these sump tanks is then pumped to the Waste Holdup Tanks. The capacity of these tanks provides reasonable assurance that they will hold firefighting hose stream runoff or fixed suppression system discharge for fires within all of the permanent RCA Fire Areas. However, if these tanks were to overflow, additional Page 239 of 315
 
American Electric Power                                                      Radioactive Release Review D. C Cook Nuclear Plant                                                                              Rev. 4 NFPPM - Attachment 3                                                                                Page 3-7 water would travel to the Chemical and Volume Control System (CVCS) Hold Up Tank Room, which has no overflow or outlet and is capable of holding a large amount of water (two 21,000 gallon tanks per unit).
Drainage in containment Fire Areas AA56 and AA58 is collected in the Reactor Coolant Drain Tank, which has a capacity of 350 gallons. Water can then be pumped to the eves Holdup Tanks for reuse, or transferred to the Waste Holdup Tanks for processing. Fire Area AA22, U2 East MDAFWP Room was screened out.
Liquid wastes in the Waste Holdup Tanks are processed using the Radioactive Waste Demineralization System (RWDS). The RWDS decontaminates the waste using filtration and ion exchange. The processed waste is routed to the waste evaporator condensate tanks and then pumped to one of two CVCS Monitor Tanks. The discharge from these tanks is monitored by the Radiation Monitoring System.
In addition, Fire Pre-Plans and training materials describe the presence and potential use of monitored drainage systems to drain firefighting liquid effluents if the systems are deemed operational and capable of supporting manual removal efforts.
There are screened-in fire zones which do not have fixed engineering controls, and therefore have the potential for unmitigated release beyond the plant boundaries. Potential releases of contaminated gaseous effluents and liquid effluents resulting from a fire in these areas are bounded by the results documented in Technical Evaluation 11.76 (Ref. 5.24). This calculation demonstrates that releases are within Technical Specifications limits.
 
==5.0    REFERENCES==
 
5.1    National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition 5.2    NFPA 805 FAQ 09-0056, Radioactive Release Transition 5.3    Nuclear Energy Institute (NEI) 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program Under 10 CFR 50.48(c), Rev. 2 5.4    Nuclear Regulatory Commission (NRC) Regulatory Guide 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, Rev. 1, 12/2009 5.5    10 CFR 20, Standards for Protection against Radiation 5.6    Donald C. Cook Nuclear Plant Updated Final Safety Analysis Report (UFSAR), Chapter 5, Rev.
20.2 5.7    Donald C. Cook Nuclear Plant Updated Final Safety Analysis Report (UFSAR), Chapter 9, Rev.
20 5.8    Donald C. Cook Nuclear Plant Updated Final Safety Analysis Report (UFSAR), Chapter 11, Rev.
20.2 Page 240 of 315
 
American Electric Power                                                  Radioactive Release Review D. C Cook Nuclear Plant                                                                        Rev. 4 NFPPM - Attachment 3                                                                        Page 3-8 5.9    Donald C. Cook Nuclear Plant Fire Pre-Plans Units 1 & 2, Volume 1, Rev. 17 5.10  Donald C. Cook Nuclear Plant Fire Pre-Plans Units 1 & 2, Volume 2, Rev. 14 5.11  Flow Diagram OP-12-5148K-4, Auxiliary Building West Ventilation, Rev. 4 5.12  Lesson Plan FW-C-9004, Operation of Fire Extinguishers, Rev. 6 5.13  Lesson Plan FW-C-9027, Ventilation 5.14  Lesson Plan FW-C-9033, Fire Control 5.15  Lesson Plan RP-L-0509, Respond to a fire in the Restricted Area, Rev. 1 5.16  Lesson Plan FW-L-9044, Fire Brigade Annual Training, Rev. 4 5.17  Procedure ENVI-8914, Coordination of the Operational Aspects of the Radioactive Effluents Program at Cook Nuclear Plant, Rev. 4 5.18  Procedure PMP-2270-FRP-001, Fire Response Plan, Rev. 23 5.19  Procedure PMP-6010-OSD-001, Off-Site Dose Calculation Manual, Rev. 25 5.20  Program Description TPD-600-FP, Fire Protection Training Program Description, Rev. 10 5.21  E-mail from R. Gray (AEP) to P. Ouellette (EPM) dated 8/13/2008 Re: Potential for Radioactive Release (EPM File Access Number 20080819-10) 5.22  E-mail from R. Gray (AEP) to J. LeMaire (EPM) dated 8/14/2008 Re: Potential for radioactive Release (EPM File Access Number 20080819-10) 5.23  EPM Division Procedure EPM-DP-FP-010, Radioactive Release Review, Rev. 0 5.24  Technical Evaluation 11.76, NFPA 805 Airborne Effluents Offsite Does Analysis, Rev. 0 5.25  Enclosure 2 to Letter AEP-NRC-2012-47, dated 06/29/2012 5.26  Lesson Plan RP-L-EP01, RP Section Emergency Plan Response, Rev. 2 Page 241 of 315
 
American Electric Power                                                  Radioactive Release Review D. C Cook Nuclear Plant                                                                        Rev. 4 NFPPM Attachment 3 - Radioactive Release Review                                            Page 3A-1 APPENDIX A: RADIOACTIVE RELEASE REVIEW Note: Attachment 3, Appendix A was updated to incorporate the closure of NFPA 805 implementation items. Revision bars are not used on this Appendix.
(38 pages attached)
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American Electric Power                                                                                                        Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 3                                                                                                                                              Page 3A-2 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA1    1, 1A,  U1 & U2    Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 1B, 1C, RHR & CTS Fire Area AA1            collected in sumps which              Auxiliary Building is        reinforce use of fire pre-  engineered controls for 1D, 1E, Pump Area                          are routed to monitored              directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 1F, 1G, (El. 573)                        waste holdup tanks                    Each vent has radiation      identify potentially        suppression water runoff 1H,                                        [UFSAR Section                        detectors for continuous      contaminated areas,        and use of fire pre-plans 136,                                      11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, 137,                                                                            air during release to        communication with          CNP's approach meets 138A,                                                                            atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive 138B,                                                                            filtered in high efficiency  describe precautions to be  release performance 138C                                                                            particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-3 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                    Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions AA2    2N, 28, U1 & U2      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 77, 78, Turbine      Fire Area AA2 79, 80, Bldg.,
81, 82, Screenhouse, 83, 90, U1 & U2 91, 92, West Main 93, 94, Steam 95,    Enclosures 108,    & Pipe 110,    Tunnels 127, 129, 139, 140, 141,142
        , 2S, 100, 109, 111, 126, 130, 30, 84, 85, 86, 87, 88, 89, 96, 97, 98, 99 AA2C    112,    U1 & U2      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 113,    Sub-        Fire Area 114,    basement & AA2C 115    ESW Pipe Tunnels Transition DocumentPage Access 244 Code -ofD.C.
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American Electric Power                                                                                                            Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                                  Page 3A-4 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                          Engineering Controls                            Training and Fire Pre-Area Zone Description Plan              Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA3    3, 31,  Drumming/D Volume I:          9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 32, 35, rum          Fire Area AA3            collected in floor drains            Auxiliary Building is        reinforce use of fire pre-  engineered controls for 36, 48, Storage - El.                          and sumps which are                  directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 49, 50, 587', 609'                            routed to monitored waste            Each vent has radiation      identify potentially        suppression water runoff 51, 52, U1 & U2                                holdup tanks [UFSAR                  detectors for continuous      contaminated areas,        and use of fire pre-plans 69,    Aux. Bldg.                            Section 11.1.2.1.1].                  monitoring of the exhaust    provide instruction for    and training materials, 106,    & Fuel                                                                      air during release to        communication with          CNP's approach meets 107    Handling                                                                    atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive Areas El.                                                                    filtered in high efficiency  describe precautions to be  release performance 633                                                                        particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-5 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA5/6  4, 5,  Aux. Bldg. Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 6A,    (El. 587) Fire Area              collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for 6M,                AA5/6                  which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 6N, 6S,                                    monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff 61,                                        tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 64A,                                      11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, 65A,                                                                              air during release to        communication with          CNP's approach meets 64B,                                                                              atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive 65B                                                                              filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-6 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                    Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions AA7    7      U1 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 1 Cable    Fire Area AA7 Tunnel (El.
596)
AA8    8      U1 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 4 Cable    Fire Area AA8 Tunnel (El.
596)
AA9    9, 10,  U1 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 116    1 Cable    Fire Area AA9 Tunnel (El.
596)
AA10    11      U1 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 3S Cable    Fire Area Tunnel (El. AA10 596)
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-7 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA11    12      U1 Quadrant Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 2 Cable    Fire Area              collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for Tunnel (El. AA11                    which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 596)                              monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, air during release to        communication with          CNP's approach meets atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
AA12    13      U1 DG Oil Volume I:        9    Yes N/A                                    N/A                          N/A                        Not Required Pump Room Fire Area (el. 587)  AA12 Transition DocumentPage Access 248 Code -ofD.C.
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American Electric Power                                                                                                Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-8 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                    Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions AA13    14      U1            Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Transformer Fire Area Rm. (El.      AA13 591)
AA14    15      U1 CD DG      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 587)        AA14 AA15    16      U1 AB DG      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 587)        AA15 AA16    17A    U1 West      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required MDAFP        Fire Area Room (El      AA16 591)
AA17    17B    U2 West      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required MDAFP        Fire Area Room (El. AA17 591)
AA18    17C    AFP          Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Corridor (El. Fire Area 591)        AA18 AA19    17D    U1 East      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required MDAFP        Fire Area Room (El. AA19 591)
AA20    17E    U1 TDAFP      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 591)        AA20 Transition DocumentPage Access 249 Code -ofD.C.
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American Electric Power                                                                                              Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                Page 3A-9 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                    Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions AA21    17F    U2 TDAFP    Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 591)      AA21 AA22    17G    U2 East    Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required MDAFP      Fire Area Room (El    AA22 591)
AA23    18      U2 CD DG    Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El    Fire Area 587)      AA23 AA24    19      U2 AB DG    Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El    Fire Area 587)      AA24 AA25    20      U2          Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Transformer Fire Area Room Elec. AA25 (El. 591)
AA26    21      U2 DG Oil Volume I:        9    Yes N/A                                  N/A                  N/A                    Not Required Pump Room Fire Area (El. 587)  AA26 Transition DocumentPage Access 250 Code -ofD.C.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-10 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA27    22      U2 Quadrant Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 2 Piping    Fire Area              collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for Tunnel (El. AA27                    which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 596)                              monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, air during release to        communication with          CNP's approach meets atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                              Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                Page 3A-11 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                    Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions AA29    23, 24, U2 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 25, 117 3M & 3S    Fire Area Cable      AA29 Tunnel (El.
596)
AA30    26      U2 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 4 Cable    Fire Area Tunnel (El. AA30 596)
AA31    27      U2 Quadrant Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 1 Cable    Fire Area Tunnel (El. AA31 596)
AA32    29A,    U1 ESW      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 29B,    Pump Area Fire Area 29E    & U1 & U2 AA32 Basement MCC Room El. 591 AA32    29G    U1 ESW      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Pump Area Fire Area
                & U1 & U2 AA32 Basement MCC Room El. 575 AA33    29C,    U2 ESW      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 29D,    Pump Area  Fire Area 29F    (El. 591)  AA33 Transition DocumentPage Access 252 Code -ofD.C.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-12 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke            Plan Review Results              Conclusions AA34    33,    U1 East MS Volume I:        9    No  Liquid effluents are                  This fire zone does not      Training materials          Based on the results 33A,    Valve Encl., Fire Area              collected in floor drains              have a monitored            reinforce use of fire pre-  documented in Techinical 33B,    MS Line      AA34                    which are routed to                    ventilation system,          plans. Fire Pre-Plans        Evaluation 11.76; the 105    NESW                                monitored waste holdup                however, the CNP            identify potentially        availability of engineered Valve Areas                          tanks [UFSAR Section                  Emergency Plan includes    contaminated areas,          controls for fire
                & Contractor                        11.1.2.1.1].                          provisions for evaluating    provide instruction for      suppression water runoff; Acc Control                                                                radiological emergencies,    communication with          and the use of radiation Area (EL.                                                                  including exterior fire      Radiation Protection, and    protection procedures, fire 612)                                                                      events that could lead to    describe precautions to be  pre-plans, and training the release of gaseous      undertaken for safe          materials, CNP's approach radioactivity (e.g., fire    removal of contaminated      meets NFPA 805 damage affecting a loaded    smoke and water runoff in    radioactive release cask confinement            these potentially            performance criteria.
boundary). A fire event      contaminated areas.
will be classified in        Training material and fire accordance with PMP-        pre-plans describe the 2080-EPP-101                presence and potential use Emergency                  of monitored HVAC Classification as either an systems. The level of detail Alert or Unusual Event      provided in the training (UE), and appropriate        materials and fire pre-plans actions are taken. These    meets NFPA 805 actions include Activation  radioactive release and Operation of the        performance criteria.
Emergency Operations Facility (EOF), as specified in RMT-2080-EOF-001, which will initiate coordination between CNP departments to designate and dispatch plant-knowledgeable individual(s) in affected discipline(s) as the emergency warrants.
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American Electric Power                                                                                                    Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                    Page 3A-13 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                    Engineering Controls                            Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                  Water                                Smoke            Plan Review Results        Conclusions monitored and calculated using the methods specified in the offsite dose calculation manual (ODCM) [PMP-2080-EPP-101, Attachment 3]. The Off-Site Dose Calculation Manual (ODCM) is the top tier document for the Radiological Environmental Monitoring Program (REMP), the Radioactive Effluent Controls Program (RECP),
contains criteria pertaining to the previous Radiological Effluent Technical Specifications (RETS) as defined in NUREG-0472, and fully implements the requirements of Technical Specification 5.5.3, Radioactive Effluent Controls Program. The ODCM contains the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous monitoring instrumentation alarm/trip setpoints.
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American Electric Power                                                                                                  Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-14 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                    Engineering Controls                          Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                  Water                                Smoke            Plan Review Results        Conclusions The potential release of contaminated gaseous effluents is bound by a fire involving a single worst-case sea van as described in Technical Evaluation 11.76, Revision 0. This Technical Evaluation demonstrates that a release will not exceed Technical Specification limits.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-15 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke            Plan Review Results              Conclusions AA35    34,    U2 East MS Volume I:        9    No  Liquid effluents are                  This fire zone does not      Training materials          Based on the results 34A,    Valve Encl., Fire Area              collected in floor drains              have a monitored            reinforce use of fire pre-  documented in Techinical 34B    MS Line      AA35                    which are routed to                    ventilation system,          plans. Fire Pre-Plans        Evaluation 11.76; the NESW                                monitored waste holdup                however, the CNP            identify potentially        availability of engineered Valve Areas                          tanks [UFSAR Section                  Emergency Plan includes    contaminated areas,          controls for fire (EL. 612)                          11.1.2.1.1].                          provisions for evaluating    provide instruction for      suppression water runoff; radiological emergencies,    communication with          and the use of radiation including exterior fire      Radiation Protection, and    protection procedures, fire events that could lead to    describe precautions to be  pre-plans, and training the release of gaseous      undertaken for safe          materials, CNP's approach radioactivity (e.g., fire    removal of contaminated      meets NFPA 805 damage affecting a loaded    smoke and water runoff in    radioactive release cask confinement            these potentially            performance criteria.
boundary). A fire event      contaminated areas.
will be classified in        Training material and fire accordance with PMP-        pre-plans describe the 2080-EPP-101                presence and potential use Emergency                  of monitored HVAC Classification as either an systems. The level of detail Alert or Unusual Event      provided in the training (UE), and appropriate        materials and fire pre-plans actions are taken. These    meets NFPA 805 actions include Activation  radioactive release and Operation of the        performance criteria.
Emergency Operations Facility (EOF), as specified in RMT-2080-EOF-001, which will initiate coordination between CNP departments to designate and dispatch plant-knowledgeable individual(s) in affected discipline(s) as the emergency warrants.
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American Electric Power                                                                                                    Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                    Page 3A-16 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                    Engineering Controls                            Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                  Water                                Smoke            Plan Review Results        Conclusions monitored and calculated using the methods specified in the offsite dose calculation manual (ODCM) [PMP-2080-EPP-101, Attachment 3]. The Off-Site Dose Calculation Manual (ODCM) is the top tier document for the Radiological Environmental Monitoring Program (REMP), the Radioactive Effluent Controls Program (RECP),
contains criteria pertaining to the previous Radiological Effluent Technical Specifications (RETS) as defined in NUREG-0472, and fully implements the requirements of Technical Specification 5.5.3, Radioactive Effluent Controls Program. The ODCM contains the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous monitoring instrumentation alarm/trip setpoints.
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American Electric Power                                                                                                  Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-17 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                    Engineering Controls                          Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                  Water                                Smoke            Plan Review Results        Conclusions The potential release of contaminated gaseous effluents is bound by a fire involving a single worst-case sea van as described in Technical Evaluation 11.76, Revision 0. This Technical Evaluation demonstrates that a release will not exceed Technical Specification limits.
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American Electric Power                                                                                                        Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 3                                                                                                                                              Page 3A-18 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA36/42 37, 43, Aux. Bldg. Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 44A,    (El. 609) Fire Area              collected in sumps which              Auxiliary Building is        reinforce use of fire pre-  engineered controls for 44B,              AA36/42                are routed to monitored              directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 44C,                                      waste holdup tanks                    Each vent has radiation      identify potentially        suppression water runoff 44D,                                      [UFSAR Section                        detectors for continuous      contaminated areas,        and use of fire pre-plans 44E,                                      11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, 44F,                                                                            air during release to        communication with          CNP's approach meets 44G,                                                                            atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive 44H,                                                                            filtered in high efficiency  describe precautions to be  release performance 44N,                                                                            particulate air filter cells  undertaken for safe        criteria.
44S                                                                              [UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-19 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA37    38      U1 Quadrant Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 2 Cable    Fire Area              collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for Tunnel (El. AA37                    which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 612)                              monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, air during release to        communication with          CNP's approach meets atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                            Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                                  Page 3A-20 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                          Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA38    39      U2 Quadrant Volume I:        9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 2 Cable      Fire Area              collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for Tunnel (El. AA38                      which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire 612)                                monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, air during release to        communication with          CNP's approach meets atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
AA39A 40A      U1 AB        Volume I:      9    Yes N/A                                    N/A                          N/A                        Not Required Swgr. Room Fire Area (El. 609-6") AA39A AA39B 40B      U1 CD        Volume I:      9    Yes N/A                                    N/A                          N/A                        Not Required Swgr. Room Fire Area (El. 609-6") AA39B Transition DocumentPage Access 261 Code -ofD.C.
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American Electric Power                                                                                                Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-21 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                    Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions AA40    41      U1 ESS and Volume I:        9    Yes N/A                                  N/A                  N/A                    Not Required MCC Room Fire Area (El. 609-6") AA40 AA41    42A,    U1 Emerg. Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 42B,    Power        Fire Area 42C,    Systems      AA41 42D    Area (El.
609-6")
AA43    45      U2 ESS and Volume I:        9    Yes N/A                                  N/A                  N/A                    Not Required MCC Room Fire Area (El. 609-6") AA43 AA44    46A,    U2 Emerg. Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required 46B,    Power        Fire Area 46C,    Systems      AA44 46D    Area (El.
609-6")
AA45A 47A      U2 Swgr.      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 609-6")      AA45A AA45B 47B      U2 Swgr.      Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 609-6")      AA45B AA46    53      U1 Control    Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 633')        AA46 AA47    54      U2 Control    Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room (El. Fire Area 633')        AA47 Transition DocumentPage Access 262 Code -ofD.C.
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American Electric Power                                                                                                            Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                                  Page 3A-22 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke              Plan Review Results                Conclusions AA48    55, 56  U1 Swgr. Volume I:      9    No  This Fire Area does not                Fire Zone 56 is located      Training materials          Based on the results Rooms        Fire Area              contain a monitored                    within the radiologically-    reinforce use of fire pre-  documented in Techinical Cable Vault AA48                    drainage system. Plant fire            controlled area (RCA).        plans. Fire Pre-Plans        Evaluation 11.76; the
                & Aux.                              pre-plans provide                      Ventilation in this zone is  identify potentially        availability of engineered Cable Vault                          instructions to establish              part of the Auxiliary        contaminated areas,          controls for smoke; and the (El. 625-                          communications with                    Building system, in which    provide instruction for      use of radiation protection
: 10) & 620-                        Radiation Protection                  all exhaust air is directed  communication with          procedures, fire pre-plans,
: 6)                                  personnel and also provide            to the unit vents. Each vent  Radiation Protection, and    and training materials, precautions for containing,            has radiation detectors for  describe precautions to be  CNP's approach meets monitoring, and releasing              continuous monitoring of      undertaken for safe          NFPA 805 radioactive contaminated liquid                    the exhaust air during        removal of contaminated      release performance effluents.                            release to atmosphere.        smoke and water runoff in    criteria.
Exhaust air is filtered in    these potentially The potential release of              high efficiency particulate  contaminated areas.
contaminated liquid                    air filter cells [UFSAR      Training material and fire effluents is bound by a fire          Section 9.9.2, 11.3.2.1]. pre-plans describe the involving a single worst-                                            presence and potential use case sea van as described              If normal ventilation is not of monitored drainage in Technical Evaluation                available, smoke will be      systems. The level of detail 11.76, Revision 0. This                removed using manual          provided in the training Technical Evaluation                  ventilation to the outside or materials and fire pre-plans demonstrates that a release            to an area where normal      meets NFPA 805 will not exceed Technical              ventilation will remove the radioactive release Specification limits.                  smoke. Prior to any          performance criteria.
release, plant fire pre-plans provide instructions to establish communications with Radiation Protection personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                              Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                Page 3A-23 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                    Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke    Plan Review Results          Conclusions out of this analysis.
AA50    57, 144 U1 Control Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room Cable Fire Area Vault &      AA50 HSD Panel Area (El.
624 & 633)
AA51    58, 145 U2 Control Volume I:      9    Yes N/A                                  N/A                  N/A                    Not Required Room Cable Fire Area Vault &      AA51 HSD Panel Area (El.
624& 633)
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American Electric Power                                                                                                            Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                                  Page 3A-24 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke              Plan Review Results                Conclusions AA52    59, 60  U2 Swgr. Volume I:      9    No  This Fire Area does not                Fire Zone 59 is located      Training materials          Based on the results Room Cable Fire Area                contain a monitored                    within the radiologically-    reinforce use of fire pre-  documented in Techinical Vault &      AA52                    drainage system. Plant fire            controlled area (RCA).        plans. Fire Pre-Plans        Evaluation 11.76; the Aux. Cable                          pre-plans provide                      Ventilation in this zone is  identify potentially        availability of engineered Vault (El. .                        instructions to establish              part of the Auxiliary        contaminated areas,          controls for smoke; and the 625-10" &                          communications with                    Building system, in which    provide instruction for      use of radiation protection 620-6")                            Radiation Protection                  all exhaust air is directed  communication with          procedures, fire pre-plans, personnel and also provide            to the unit vents. Each vent  Radiation Protection, and    and training materials, precautions for containing,            has radiation detectors for  describe precautions to be  CNP's approach meets monitoring, and releasing              continuous monitoring of      undertaken for safe          NFPA 805 radioactive contaminated liquid                    the exhaust air during        removal of contaminated      release performance effluents.                            release to atmosphere.        smoke and water runoff in    criteria.
Exhaust air is filtered in    these potentially The potential release of              high efficiency particulate  contaminated areas.
contaminated liquid                    air filter cells [UFSAR      Training material and fire effluents is bound by a fire          Section 9.9.2, 11.3.2.1]. pre-plans describe the involving a single worst-                                            presence and potential use case sea van as described              If normal ventilation is not of monitored drainage in Technical Evaluation                available, smoke will be      systems. The level of detail 11.76, Revision 0. This                removed using manual          provided in the training Technical Evaluation                  ventilation to the outside or materials and fire pre-plans demonstrates that a release            to an area where normal      meets NFPA 805 will not exceed Technical              ventilation will remove the radioactive release Specification limits.                  smoke. Prior to any          performance criteria.
release, plant fire pre-plans provide instructions to establish communications with Radiation Protection personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
Fire Zone 60 is not located in the RCA and is screened Transition DocumentPage Access 265 Code -ofD.C.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-25 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions out of this analysis.
AA54    62A,    U1 Charging Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 62B,    Pumps Area Fire Area                collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for 62C    (El. 587)  AA54                    which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, air during release to        communication with          CNP's approach meets atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-26 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions AA55    63A,    U2 Charging Volume I:      9    No  Liquid effluents are                  All exhaust air from the      Training materials          Based on the availability of 63B,    Pumps Area Fire Area                collected in floor drains              Auxiliary Building is        reinforce use of fire pre-  engineered controls for 63C    (El. 587)  AA55                    which are routed to                    directed to the unit vents. plans. Fire Pre-Plans      both smoke and fire monitored waste holdup                Each vent has radiation      identify potentially        suppression water runoff tanks [UFSAR Section                  detectors for continuous      contaminated areas,        and use of fire pre-plans 11.1.2.1.1].                          monitoring of the exhaust    provide instruction for    and training materials, air during release to        communication with          CNP's approach meets atmosphere. Exhaust air is    Radiation Protection, and  NFPA 805 radioactive filtered in high efficiency  describe precautions to be  release performance particulate air filter cells  undertaken for safe        criteria.
[UFSAR Section 9.9.2,        removal of contaminated 11.3.2.1].                    smoke and water runoff in these potentially If normal ventilation is not contaminated areas.
available, smoke will be      Training material and fire removed using manual          pre-plans describe the ventilation to the outside or presence and potential use to an area where normal      of monitored HVAC and ventilation will remove the drainage systems. The smoke. Prior to any          level of detail provided in release, plant fire pre-plans the training materials and provide instructions to      fire pre-plans meets NFPA establish communications 805 radioactive release with Radiation Protection performance criteria.
personnel and also provide precautions for containing, monitoring, and releasing contaminated gaseous effluents.
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American Electric Power                                                                                                        Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 3                                                                                                                                            Page 3A-27 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results            Conclusions AA56    66, 67, U1          Volume I:      9    No  Liquid effluents are                  During Plant Operation:      Training materials        Based on the availability of 68,    Containment Fire Area              collected in floor drains            All containment ventilation  reinforce use of fire pre- engineered controls for 101,                AA56                    and sumps which are                  systems except for the      plans. Fire Pre-Plans      both smoke and fire 103,                                        routed to monitored waste            purge and pressure relief    identify potentially      suppression water runoff 118,                                        holdup tanks [UFSAR                  systems are of the          contaminated areas,        and use of fire pre-plans 120,                                        Section 11.1.2.1.1].                  recirculating type. The      provide instruction for    and training materials, 122,                                                                              containment purge exhaust    communication with        CNP's approach meets 132,                                                                              and the containment          Radiation Protection, and  NFPA 805 radioactive 134                                                                              pressure relief systems      describe precautions to be release performance discharge to the unit vent  undertaken for safe        criteria.
where they are monitored    removal of contaminated before release to the        smoke and water runoff in environment [UFSAR          these potentially Section 5.5.1].              contaminated areas.
Training material and fire During NPO: The              pre-plans describe the containment ventilation      presence and potential use system is designed to        of monitored HVAC and operate during outages      drainage systems. The
[UFSAR Section 5.5.2]. In level of detail provided in addition, the release of    the training materials and radioactive materials due    fire pre-plans meets NFPA to smoke migration is not    805 radioactive release expected to be significant performance criteria.
as plant personnel monitor the containment structure during non-power operations, thereby reducing the potential for a fire large enough to have radiological consequences.
In addition, the volume of containment is expected to be sufficiently large enough to ensure that smoke from any credible Transition DocumentPage Access 268 Code -ofD.C.
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American Electric Power                                                                                                Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                  Page 3A-28 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                      Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke      Plan Review Results          Conclusions ignition source will be contained within the structure.
AA57A 70, 71    U1 Control Volume I:      9    Yes N/A                                  N/A                    N/A                    Not Required Room      Fire Area HVAC      AA57A Equip. &
Computer Areas (El.
650)
AA57B 72, 73, U2 Control  Volume I:      9    Yes N/A                                  N/A                    N/A                    Not Required 74      Room      Fire Area HVAC      AA57B Equip. &
Computer Areas (El.
650)
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American Electric Power                                                                                                        Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 3                                                                                                                                            Page 3A-29 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results            Conclusions AA58    75, 76, U2          Volume I:      9    No  Liquid effluents are                  During Plant Operation:      Training materials        Based on the availability of 102,    Containment Fire Area              collected in floor drains            All containment ventilation  reinforce use of fire pre- engineered controls for 104,                AA58                    and sumps which are                  systems except for the      plans. Fire Pre-Plans      both smoke and fire 119,                                        routed to monitored waste            purge and pressure relief    identify potentially      suppression water runoff 121,                                        holdup tanks [UFSAR                  systems are of the          contaminated areas,        and use of fire pre-plans 123,                                        Section 11.1.2.1.1].                  recirculating type. The      provide instruction for    and training materials, 133,                                                                              containment purge exhaust    communication with        CNP's approach meets 135                                                                              and the containment          Radiation Protection, and  NFPA 805 radioactive pressure relief systems      describe precautions to be release performance discharge to the unit vent  undertaken for safe        criteria.
where they are monitored    removal of contaminated before release to the        smoke and water runoff in environment [UFSAR          these potentially Section 5.5.1].              contaminated areas.
Training material and fire During NPO: The              pre-plans describe the containment ventilation      presence and potential use system is designed to        of monitored HVAC and operate during outages      drainage systems. The
[UFSAR Section 5.5.2]. In level of detail provided in addition, the release of    the training materials and radioactive materials due    fire pre-plans meets NFPA to smoke migration is not    805 radioactive release expected to be significant performance criteria.
as plant personnel monitor the containment structure during non-power operations, thereby reducing the potential for a fire large enough to have radiological consequences.
In addition, the volume of containment is expected to be sufficiently large enough to ensure that smoke from any credible Transition DocumentPage Access 270 Code -ofD.C.
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American Electric Power                                                                                                  Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                Revision 4 NFPPM - Attachment 3                                                                                                                                    Page 3A-30 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                      Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke      Plan Review Results          Conclusions ignition source will be contained within the structure.
YD      143    Yard - Water Volume I:      9    Yes N/A                                  N/A                    N/A                    Not Required Intake and  Fire Area Discharge    AAYD System Transition DocumentPage Access 271 Code -ofD.C.
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American Electric Power                                                                                                          Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                            Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-31 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                        Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions YD      146    Yard - Trash Volume I:      9    No  This fire zone does not                This fire zone does not      Training materials          Based on the results Loading Area Fire Area              have a monitored drainage              have a monitored            reinforce use of fire pre-  documented in Techinical AAYD                    system, however, the CNP              ventilation system,          plans. Fire Pre-Plans      Evaluation 11.76 and the Emergency Plan includes              however, the CNP            identify potentially        use of radiation protection provisions for evaluating              Emergency Plan includes    contaminated areas,        procedures, fire pre-plans, radiological emergencies,              provisions for evaluating    provide instruction for    and training materials, including exterior fire                radiological emergencies,    communication with          CNP's approach meets events that could lead to              including exterior fire      Radiation Protection, and  NFPA 805 radioactive the release of liquid                  events that could lead to    describe precautions to be  release performance radioactivity (e.g., fire              the release of gaseous      undertaken for safe        criteria.
damage affecting a loaded              radioactivity (e.g., fire    removal of contaminated cask confinement                      damage affecting a loaded    smoke and water runoff in boundary). A fire event                cask confinement            these potentially will be classified in                  boundary). A fire event      contaminated areas. The accordance with PMP-                  will be classified in        level of detail provided in 2080-EPP-101                          accordance with PMP-        the training materials and Emergency                            2080-EPP-101                fire pre-plans meets NFPA Classification as either an          Emergency                  805 radioactive release Alert or Unusual Event                Classification as either an performance criteria.
(UE), and appropriate                  Alert or Unusual Event actions are taken. These              (UE), and appropriate actions include Activation            actions are taken. These and Operation of the                  actions include Activation Emergency Operations                  and Operation of the Facility (EOF), as                    Emergency Operations specified in RMT-2080-                Facility (EOF), as EOF-001, which will                    specified in RMT-2080-initiate coordination                  EOF-001, which will between CNP departments                initiate coordination to designate and dispatch              between CNP departments plant-knowledgeable                    to designate and dispatch individual(s) in affected              plant-knowledgeable discipline(s) as the                  individual(s) in affected emergency warrants.                    discipline(s) as the Radiation release is                  emergency warrants.
monitored and calculated              Radiation release is Transition DocumentPage Access 272 Code -ofD.C.
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American Electric Power                                                                                                      Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 3                                                                                                                                      Page 3A-32 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                    Water                                Smoke            Plan Review Results        Conclusions using the methods                      monitored and calculated specified in the offsite dose          using the methods calculation manual                    specified in the offsite dose (ODCM) [PMP-2080-EPP-                  calculation manual 101, Attachment 3]. The                (ODCM) [PMP-2080-EPP-Off-Site Dose Calculation              101, Attachment 3]. The Manual (ODCM) is the top              Off-Site Dose Calculation tier document for the                  Manual (ODCM) is the top Radiological                          tier document for the Environmental Monitoring              Radiological Program (REMP), the                    Environmental Monitoring Radioactive Effluent                  Program (REMP), the Controls Program (RECP),              Radioactive Effluent contains criteria pertaining          Controls Program (RECP),
to the previous                        contains criteria pertaining Radiological Effluent                  to the previous Technical Specifications              Radiological Effluent (RETS) as defined in                  Technical Specifications NUREG-0472, and fully                  (RETS) as defined in implements the                        NUREG-0472, and fully requirements of Technical              implements the Specification 5.5.3,                  requirements of Technical Radioactive Effluent                  Specification 5.5.3, Controls Program. The                  Radioactive Effluent ODCM contains the                      Controls Program. The methodology and                        ODCM contains the parameters to be used in              methodology and the calculation of off-site            parameters to be used in doses due to radioactive              the calculation of off-site liquid and gaseous                    doses due to radioactive effluents and in the                  liquid and gaseous calculation of liquid and              effluents and in the gaseous monitoring                    calculation of liquid and instrumentation alarm/trip            gaseous monitoring setpoints.                            instrumentation alarm/trip setpoints.
The potential release of Transition DocumentPage Access 273 Code -ofD.C.
315Cook Version 2.4.3
 
American Electric Power                                                                                                    Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 3                                                                                                                                    Page 3A-33 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                          Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                    Water                                Smoke            Plan Review Results        Conclusions contaminated liquid                    The potential release of effluents is bound by a fire          contaminated gaseous involving a single worst-              effluents is bound by a fire case sea van as described              involving a single worst-in Technical Evaluation                case sea van as described 11.76, Revision 0. This                in Technical Evaluation Technical Evaluation                  11.76, Revision 0. This demonstrates that a release            Technical Evaluation will not exceed Technical              demonstrates that a release Specification limits.                  will not exceed Technical Specification limits.
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315Cook Version 2.4.3
 
American Electric Power                                                                                                        Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                          Revision 4 NFPPM - Attachment 3                                                                                                                                              Page 3A-34 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan          Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions YD      Yard    Yard    Volume II:      7    No  This fire zone does not                This fire zone does not      Training materials          Based on the results Support                  have a monitored drainage              have a monitored            reinforce use of fire pre-  documented in Techinical Buildings and            system, however, the CNP              ventilation system,          plans. Fire Pre-Plans      Evaluation 11.76 and the Yard Areas                Emergency Plan includes              however, the CNP            identify potentially        use of radiation protection provisions for evaluating              Emergency Plan includes    contaminated areas,        procedures, fire pre-plans, radiological emergencies,              provisions for evaluating    provide instruction for    and training materials, including exterior fire                radiological emergencies,    communication with          CNP's approach meets events that could lead to              including exterior fire      Radiation Protection, and  NFPA 805 radioactive the release of liquid                  events that could lead to    describe precautions to be  release performance radioactivity (e.g., fire              the release of gaseous      undertaken for safe        criteria.
damage affecting a loaded              radioactivity (e.g., fire    removal of contaminated cask confinement                      damage affecting a loaded    smoke and water runoff in boundary). A fire event                cask confinement            these potentially will be classified in                  boundary). A fire event      contaminated areas. The accordance with PMP-                  will be classified in        level of detail provided in 2080-EPP-101                          accordance with PMP-        the training materials and Emergency                            2080-EPP-101                fire pre-plans meets NFPA Classification as either an          Emergency                  805 radioactive release Alert or Unusual Event                Classification as either an performance criteria.
(UE), and appropriate                  Alert or Unusual Event actions are taken. These              (UE), and appropriate actions include Activation            actions are taken. These and Operation of the                  actions include Activation Emergency Operations                  and Operation of the Facility (EOF), as                    Emergency Operations specified in RMT-2080-                Facility (EOF), as EOF-001, which will                    specified in RMT-2080-initiate coordination                  EOF-001, which will between CNP departments                initiate coordination to designate and dispatch              between CNP departments plant-knowledgeable                    to designate and dispatch individual(s) in affected              plant-knowledgeable discipline(s) as the                  individual(s) in affected emergency warrants.                    discipline(s) as the Radiation release is                  emergency warrants.
monitored and calculated              Radiation release is Transition DocumentPage Access 275 Code -ofD.C.
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American Electric Power                                                                                                      Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 3                                                                                                                                      Page 3A-35 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                    Water                                Smoke            Plan Review Results        Conclusions using the methods                      monitored and calculated specified in the offsite dose          using the methods calculation manual                    specified in the offsite dose (ODCM) [PMP-2080-EPP-                  calculation manual 101, Attachment 3]. The                (ODCM) [PMP-2080-EPP-Off-Site Dose Calculation              101, Attachment 3]. The Manual (ODCM) is the top              Off-Site Dose Calculation tier document for the                  Manual (ODCM) is the top Radiological                          tier document for the Environmental Monitoring              Radiological Program (REMP), the                    Environmental Monitoring Radioactive Effluent                  Program (REMP), the Controls Program (RECP),              Radioactive Effluent contains criteria pertaining          Controls Program (RECP),
to the previous                        contains criteria pertaining Radiological Effluent                  to the previous Technical Specifications              Radiological Effluent (RETS) as defined in                  Technical Specifications NUREG-0472, and fully                  (RETS) as defined in implements the                        NUREG-0472, and fully requirements of Technical              implements the Specification 5.5.3,                  requirements of Technical Radioactive Effluent                  Specification 5.5.3, Controls Program. The                  Radioactive Effluent ODCM contains the                      Controls Program. The methodology and                        ODCM contains the parameters to be used in              methodology and the calculation of off-site            parameters to be used in doses due to radioactive              the calculation of off-site liquid and gaseous                    doses due to radioactive effluents and in the                  liquid and gaseous calculation of liquid and              effluents and in the gaseous monitoring                    calculation of liquid and instrumentation alarm/trip            gaseous monitoring setpoints.                            instrumentation alarm/trip setpoints.
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315Cook Version 2.4.3
 
American Electric Power                                                                                                    Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 3                                                                                                                                    Page 3A-36 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                          Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                    Water                                Smoke            Plan Review Results        Conclusions contaminated liquid                    The potential release of effluents is bound by a fire          contaminated gaseous involving a single worst-              effluents is bound by a fire case sea van as described              involving a single worst-in Technical Evaluation                case sea van as described 11.76, Revision 0.This                in Technical Evaluation Technical Evaluation                  11.76, Revision 0. This demonstrates that a release            Technical Evaluation will not exceed Technical              demonstrates that a release Specification limits.                  will not exceed Technical Specification limits.
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315Cook Version 2.4.3
 
American Electric Power                                                                                                            Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                              Revision 4 NFPPM - Attachment 3                                                                                                                                                Page 3A-37 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                          Engineering Controls                            Training and Fire Pre-Area Zone Description Plan            Plan Rev Out?              Water                                Smoke              Plan Review Results              Conclusions YD      Yard    Radioactive Volume II:      7    No  This building does not                This building does not      Training materials          Based on the results Material    Support                  contain a monitored                    contain an automatic        reinforce use of fire pre-  documented in Techinical Building    Buildings and            drainage system. CNP                  ventilation system. CNP      plans. Fire Pre-Plans      Evaluation 11.76 and the (RMB)      Yard Areas                Emergency Plan includes              Emergency Plan includes    identify potentially        use of radiation protection provisions for evaluating              provisions for evaluating    contaminated areas,        procedures, fire pre-plans, radiological emergencies,              radiological emergencies,    provide instruction for    and training materials, including fire events                  including fire events        communication with          CNP's approach meets outside the protected area            outside the protected area  Radiation Protection, and  NFPA 805 radioactive that could lead to the                that could lead to the      describe precautions to be  release performance release of liquid                      release of gaseous          undertaken for safe        criteria.
radioactivity. A fire event            radioactivity. A fire event  removal of contaminated in the RMB that could                  in the RMB that could        smoke and water runoff in result in an offsite                  result in an offsite        these potentially radioactive release is                radioactive release is      contaminated areas. The classified in accordance              classified in accordance    level of detail provided in with PMP-2080-EPP-101                  with PMP-2080-EPP-101        the training materials and Emergency                            Emergency                  fire pre-plans meets NFPA Classification as either an          Classification as either an 805 radioactive release Alert or Unusual Event                Alert or Unusual Event      performance criteria.
(UE), and appropriate                  (UE), and appropriate actions are taken. These              actions are taken. These actions include Activation            actions include Activation and Operation of the                  and Operation of the Emergency Operations                  Emergency Operations Facility (EOF), as                    Facility (EOF), as specified in RMT-2080-                specified in RMT-2080-EOF-001, which will                    EOF-001, which will initiate coordination                  initiate coordination between CNP departments                between CNP departments to designate and dispatch              to designate and dispatch plant-knowledgeable                    plant-knowledgeable individual(s) in affected              individual(s) in affected discipline(s) as the                  discipline(s) as the emergency warrants.                    emergency warrants.
Radiation release is                  Radiation release is monitored and calculated              monitored and calculated Transition DocumentPage Access 278 Code -ofD.C.
315Cook Version 2.4.3
 
American Electric Power                                                                                                      Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 3                                                                                                                                      Page 3A-38 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                            Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                    Water                                Smoke            Plan Review Results        Conclusions using the methods                      using the methods specified in the offsite dose          specified in the offsite dose calculation manual                    calculation manual (ODCM) [PMP-2080-EPP-                  (ODCM) [PMP-2080-EPP-101, Attachment 3]. The                101, Attachment 3]. The Off-Site Dose Calculation              Off-Site Dose Calculation Manual (ODCM) is the top              Manual (ODCM) is the top tier document for the                  tier document for the Radiological                          Radiological Environmental Monitoring              Environmental Monitoring Program (REMP), the                    Program (REMP), the Radioactive Effluent                  Radioactive Effluent Controls Program (RECP),              Controls Program (RECP),
contains criteria pertaining          contains criteria pertaining to the previous                        to the previous Radiological Effluent                  Radiological Effluent Technical Specifications              Technical Specifications (RETS) as defined in                  (RETS) as defined in NUREG-0472, and fully                  NUREG-0472, and fully implements the                        implements the requirements of Technical              requirements of Technical Specification 5.5.3,                  Specification 5.5.3, Radioactive Effluent                  Radioactive Effluent Controls Program. The                  Controls Program. The ODCM contains the                      ODCM contains the methodology and                        methodology and parameters to be used in              parameters to be used in the calculation of off-site            the calculation of off-site doses due to radioactive              doses due to radioactive liquid and gaseous                    liquid and gaseous effluents and in the                  effluents and in the calculation of liquid and              calculation of liquid and gaseous monitoring                    gaseous monitoring instrumentation alarm/trip            instrumentation alarm/trip setpoints.                            setpoints.
The potential release of              The potential release of Transition DocumentPage Access 279 Code -ofD.C.
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American Electric Power                                                                                                    Radioactive Release Review - Appendix A D. C. Cook Nuclear Plant                                                                                                                                  Revision 4 NFPPM - Attachment 3                                                                                                                                    Page 3A-39 Fire Fire Fire Zone Fire Pre- Fire Pre- Screened                      Engineering Controls                          Training and Fire Pre-Area Zone Description Plan    Plan Rev Out?                    Water                                Smoke            Plan Review Results        Conclusions contaminated liquid                    contaminated gaseous effluents is bound by a fire          effluents is bound by a fire involving a single worst-              involving a single worst-case sea van as described              case sea van as described in Technical Evaluation                in Technical Evaluation 11.76, Revision 0. This                11.76, Revision 0. This Technical Evaluation                  Technical Evaluation demonstrates that a release            demonstrates that a release will not exceed Technical              will not exceed Technical Specification limits.                  Specification limits.
Transition DocumentPage Access 280 Code -ofD.C.
315Cook Version 2.4.3
 
American Electric Power                                                        Radioactive Release Review D. C Cook Nuclear Plant                                                                                Rev. 4 NFPPM Attachment 3 - Radioactive Release Review                                                    Page 3B-1 APPENDIX B: FIRE ZONES WITH POTENTIAL FOR RADIOACTIVE RELEASE (Due to fire suppression activities at CNP)
The following is a list of fire zones at CNP in which fire suppression activities have the potential to contribute to a radioactive release. For fire zones that have been screened out, it has been determined that there is no potential for radioactive release from fire suppression activities.
NOTE: Applicable fire zones are sorted in the order in which their pre-plans appear in the pre-plan document.
Fire Area      Fire Zone                                        Fire Pre-Plan                  Screened Out?
1, 1A, 1B, 1C, 1D, 1E, 1F, 1G, 1H, 136, AA1                                                              Volume I: Fire Area AA1        No 137, 138A, 138B, 138C 2N, 28, 77, 78, 79, 80, 81, 82, 83, 90, 91, 92, 93, 94, 95, 108, 110, 127, 129, 139, 140, AA2                                                              Volume I: Fire Area AA2        Yes 141,142, 2S, 100, 109, 111, 126, 130, 30, 84, 85, 86, 87, 88, 89, 96, 97, 98, 99 AA2C            112, 113, 114, 115                              Volume I: Fire Area AA2C        Yes 3, 31, 32, 35, 36, 48, 49, 50, 51, 52, 69, 106, AA3                                                              Volume I: Fire Area AA3        No 107 4, 5, 6A, 6M, 6N, 6S, 61, 64A, 65A, 64B, AA5/6                                                            Volume I: Fire Area AA5/6      No 65B AA7            7                                                Volume I: Fire Area AA7        Yes AA8            8                                                Volume I: Fire Area AA8        Yes AA9            9, 10, 116                                      Volume I: Fire Area AA9        Yes AA10            11                                              Volume I: Fire Area AA10        Yes AA11            12                                              Volume I: Fire Area AA11        No AA12            13                                              Volume I: Fire Area AA12        Yes AA13            14                                              Volume I: Fire Area AA13        Yes AA14            15                                              Volume I: Fire Area AA14        Yes AA15            16                                              Volume I: Fire Area AA15        Yes AA16            17A                                              Volume I: Fire Area AA16        Yes AA17            17B                                              Volume I: Fire Area AA17        Yes AA18            17C                                              Volume I: Fire Area AA18        Yes AA19            17D                                              Volume I: Fire Area AA19        Yes AA20            17E                                              Volume I: Fire Area AA20        Yes AA21            17F                                              Volume I: Fire Area AA21        Yes AA22            17G                                              Volume I: Fire Area AA22        Yes AA23            18                                              Volume I: Fire Area AA23        Yes AA24            19                                              Volume I: Fire Area AA24        Yes AA25            20                                              Volume I: Fire Area AA25        Yes AA26            21                                              Volume I: Fire Area AA26        Yes AA27            22                                              Volume I: Fire Area AA27        No AA29            23, 24, 25, 117                                  Volume I: Fire Area AA29        Yes AA30            26                                              Volume I: Fire Area AA30        Yes AA31            27                                              Volume I: Fire Area AA31        Yes AA32            29A, 29B, 29E, 29G                              Volume I: Fire Area AA32        Yes AA33            29C, 29D, 29F                                    Volume I: Fire Area AA33        Yes Page 281 of 315
 
American Electric Power                                                  Radioactive Release Review D. C Cook Nuclear Plant                                                                      Rev. 4 NFPPM Attachment 3 - Radioactive Release Review                                          Page 3B-2 Fire Area    Fire Zone                                    Fire Pre-Plan                Screened Out?
AA34        33, 33A, 33B, 105                            Volume I: Fire Area AA34    No AA35        34, 34A, 34B                                Volume I: Fire Area AA35    No 37, 43, 44A, 44B, 44C, 44D, 44E, 44F, 44G,  Volume I: Fire Area AA36/42                                                                                No 44H, 44N, 44S                                AA36/42 AA37        38                                          Volume I: Fire Area AA37    No AA38        39                                          Volume I: Fire Area AA38    No Volume I: Fire Area AA39A        40A                                                                      Yes AA39A Volume I: Fire Area AA39B        40B                                                                      Yes AA39B AA40        41                                          Volume I: Fire Area AA40    Yes AA41        42A, 42B, 42C, 42D                          Volume I: Fire Area AA41    Yes AA43        45                                          Volume I: Fire Area AA43    Yes AA44        46A, 46B, 46C, 46D                          Volume I: Fire Area AA44    Yes Volume I: Fire Area AA45A        47A                                                                      Yes AA45A Volume I: Fire Area AA45B        47B                                                                      Yes AA45B AA46        53                                          Volume I: Fire Area AA46    Yes AA47        54                                          Volume I: Fire Area AA47    Yes AA48        55, 56                                      Volume I: Fire Area AA48    No AA50        57, 144                                      Volume I: Fire Area AA50    Yes AA51        58, 145                                      Volume I: Fire Area AA51    Yes AA52        59, 60                                      Volume I: Fire Area AA52    No AA54        62A, 62B, 62C                                Volume I: Fire Area AA54    No AA55        63A, 63B, 63C                                Volume I: Fire Area AA55    No 66, 67, 68, 101, 103, 118, 120, 122, 132, AA56                                                      Volume I: Fire Area AA56    No 134 Volume I: Fire Area AA57A        70, 71                                                                    Yes AA57A Volume I: Fire Area AA57B        72, 73, 74                                                                Yes AA57B AA58        75, 76, 102, 104, 119, 121, 123, 133, 135    Volume I: Fire Area AA58 No YD          131                                          Volume I: Fire Area AAYD Yes YD          143                                          Volume I: Fire Area AAYD Yes YD          146                                          Volume I: Fire Area AAYD No YD          147                                          Volume I: Fire Area AAYD Yes Volume II: Support YD          Yard                                                                      No Buildings and Yard Areas Volume II: Support YD          Radioactive Material Storage Building                                    No Buildings and Yard Areas Page 282 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-1 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER EEE-9-1                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 43 (AA36/42) AND 91 (AA2) DUCT EVALUATION EEE-9-2                  EEE    FIRE ZONE 54 (AA47) AND FIRE ZONE 73 (AA57B) DUCT EVALUATION EEE-9-3                  EEE    CCW PUMP AIR SUPPLY DUCT EVALUATION: FIRE ZONE 44S (AA42)
EEE-9-4                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR AUXILIARY BUILDING VERTICAL AIR SHAFTS EVALUATION: FIRE ZONES 12 (AA11) AND 22 (AA27)
EEE-9-5                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONES 70 (AA57A) AND 73 (AA57B) HATCH EVALUATIONS TECHNICAL                        601 FT. PIPE TUNNEL EVALUATION (FIRE ZONE 6A)                        Cancelled EVALUATION 9-6 EEE-9-7                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 13 (AA12) AND FIRE ZONE 14 (AA13) BOUNDARY EVALUATION EEE-9-8                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 20 (AA25) AND FIRE ZONE 21 (AA26) BOUNDARY EVALUATION TECHNICAL                        FIRE AREA CONTAINING FIRE ZONES 3, 32, 36, 48 AND 69 AND              Cancelled EVALUATION 9-9                  FIRE AREA CONTAINING FIRE ZONES 49, 50, 51 AND 52 BOUNDARY EVALUATION TECHNICAL                        FIRE ZONE 43 AND FIRE ZONE 44N BOUNDARY EVALUATION                    Cancelled EVALUATION 9-10 TECHNICAL                        UNITS 1 AND 2 TURBINE BUILDING, MAIN STEAM PIPE                      Cancelled EVALUATION 9-11                  TUNNELS AND SERVICE/OFFICE BUILDING EVALUATION TECHNICAL                        TURBINE BUILDING AND SCREEN HOUSE BOUNDARY                            Cancelled EVALUATION 9-12                  EVALUATION EEE-9-13                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 53 (AA46) AND FIRE ZONE 57 (AA50) HATCH EVALUATION Page 283 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-2 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER EEE-9-14                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 43 (AA36/42) AND FIRE ZONE 56 (AA48) HATCH EVALUATION EEE-9-15                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 40B (AA39B) AND FIRE ZONE 55 (AA48) HATCH EVALUATION EEE-9-16                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 41 (AA40) AND FIRE ZONE 55 (AA48) HATCH EVALUATION EEE-9-17                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 54 (AA47) AND FIRE ZONE 58 (AA51) HATCH EVALUATION EEE-9-18                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 52 (AA3) AND FIRE ZONE 59 (AA52) HATCH EVALUATION EEE-9-19                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 45 (AA43) AND FIRE ZONE 60 (AA52) HATCH EVALUATION EEE-9-20                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 47B (AA45B) AND FIRE ZONE 60 (AA52) HATCH EVALUATION EEE-9-21                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 110 (AA2) AND FIRE ZONE 43 (AA36/42) DOOR EVALUATION EEE-9-22                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 111 (AA2) AND FIRE ZONE 44S (AA36/42) DOOR EVALUATION EEE-9-23                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 116 (AA9) BOUNDARY EVALUATION EEE-9-24                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 117 (AA29) BOUNDARY EVALUATION EEE-9-25                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR ESSENTIAL SERVICE WATER PUMP HOUSE HATCH AND FIRE DAMPER EVALUATION (FIRE AREAS AA2, AA32 AND AA33)
TECHNICAL                        FIRE ZONE 9 AND FIRE ZONE 10 BOUNDARY EVALUATION                      Cancelled EVALUATION 9-26 Page 284 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-3 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        FIRE ZONE 24 AND FIRE ZONE 25 BOUNDARY EVALUATION                    Cancelled EVALUATION 9-27 TECHNICAL                        FIRE ZONE 61 AND FIRE ZONE 5 BOUNDARY EVALUATION                      Cancelled EVALUATION 9-28 TECHNICAL                        FIRE ZONE 105 AND FIRE ZONES 33, 33A, 33B BOUNDARY                    Cancelled EVALUATION 9-29                  EVALUATION TECHNICAL                        FIRE AREA CONTAINING FIRE ZONES 3, 32, 36, 48, 49, 50, 51, 52,        Cancelled EVALUATION 9-30                  69 AND THE FIRE AREA CONTAINING FIRE ZONES 106, 107, 31 AND 35 BOUNDARY EVALUATIONS 9-151 EEE-9-31                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONES 62A, 62B AND 62C (AA54) BOUNDARY EVALUATION EEE-9-32                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONES 63A, 63B AND 63C (AA56) BOUNDARY EVALUATIONS EEE-9-33                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 6A (AA5/6) TO 138B (AA1) BOUNDARY EVALUATIONS EEE-9-34                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 36 (AA3) TO FIRE ZONE 5 (AA5/6) BOUNDARY EVALUATION EEE-9-35                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 108 (AA2A) TO FIRE ZONE 33A (AA34) BOUNDARY EVALUATION EEE-9-36                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 109 (AA2) TO 34A (AA35) BOUNDARY EVALUATION EEE-9-37                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONES 5 (AA5/6) AND 32 (AA3) BOUNDARY EVALUATION EEE-9-38                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 69 (AA3) TO FIRE ZONES 108 (AA2) AND 109 (AA2) BOUNDARY EVALUATIONS EEE-9-39                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 70 (AA57A) TO FIRE ZONE 129 (AA2) BOUNDARY EVALUATION Page 285 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-4 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER EEE-9-40                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 7 (AA7) TO FIRE ZONE 61 (AA5/6) BOUNDARY ELEVATION EEE-9-41                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONES 37 (AA36/42) AND 51 (AA3) HVAC DUCT PENETRATIONS EEE-11-1                  EEE    AUXILIARY BUILDING EL. 587 FT. TO SPENT FUEL HEAT EXCHANGER PIT PUMP ROOM HATCH BOUNDARY EVALUATION FIRE ZONE 5 TO FIRE ZONE 36 EEE-11-2                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 7 (AA7) AND FIRE ZONE 38 (AA37) BOUNDARY EVALUATION EEE-11-3                  EEE    UNIT 2 REACTOR CABLE TUNNELS QUADRANT 1 TO QUADRANT 2 BOUNDARY EVALUATION FIRE ZONE 27 TO ZONE 39 EEE-11-4                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR UNIT 1 AUXILIARY BUILDING EVALUATION 620 FT - 6 IN TO AUXILIARY CABLE VAULT FIRE ZONE 44N TO FIRE ZONE 56 EEE-11-5                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR UNIT 1 EPS/4 KV SWITCHGEAR COMPLEX VENTILATION SHAFT BOUNDARY EVALUATION (FIRE AREAS AA39A, AA39B, AA40, AA41 AND AA48)
EEE-11-6                  EEE    UNIT 2 EPS/4KV SWITCHGEAR COMPLEX VENTILATION SHAFT BOUNDARY EVALUATION FIRE ZONES 45, 46A THROUGH 46D, 47A AND 47B TO FIRE ZONE 60 EEE-11-7                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONE 5 (AA5/6) TO UNIT 1 FIRE ZONES 62A, 62B AND 62C (AA54) AND UNIT 2 FIRE ZONES 63A, 63B AND 63C (AA5) REMOVABLE BLOCK WALLS EEE-11-8                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR YARD TO FIRE ZONES 34 (AA35), 34A (AA35), 90 (AA2), 97 (AA2), 129 (AA2)
AND 130 (AA2) BOUNDARY EVALUATIONS Page 286 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-5 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER EEE-11-9                  EEE    ENGINEERING EQUIVALENCY EVALUATION FOR TURBINE, AUXILIARY AND CONTAINMENT BUILDINGS BOUNDARY EVALUATION TECHNICAL                        APPENDIX A TO BTP APCSB 9.5-1, SECTION D.2(A)
EVALUATION-11-10                ISOLATION/SEPARATION OF COMBUSTIBLE MATERIALS FROM SAFETY RELATED SYSTEMS EEE-11-11                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR STORAGE OF FLAMMABLE GASES IN FIRE AREAS AA2, AA3, AA34 AND YD EEE-11-12                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR STAIRWELLS AND ELEVATOR CONSTRUCTION BOUNDARY EVALUATION (FIRE ANALYSIS AREAS AA1, AA2, AA3, AA5/6, AA36 AND AA42)
TECHNICAL                        APPENDIX A TO BTP APCSB 9.5-1, SECTION E.2(C) FIRE PUMP              Cancelled EVALUATION 11-13                ROOMS (FIRE ZONES 2, 28 AND 30)
EEE-11-14                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR CABLE SPREADING ROOM CONSTRUCTION BOUNDARY EVALUATION (FIRE AREAS AA7, AA8, AA9, AA10, AA29, AA30, AA31, AA34, AA35, AA36/42, AA37, AA38, AA48, AA50, AA51 AND AA52)
EEE-11-15                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR SWITCHGEAR ROOM CONSTRUCTION BOUNDARY ROOM EVALUATION UNIT 1 FIRE ZONES 40A, 40B, 41 AND 42A (AA39A, AA39B, AA40 AND AA41) & UNIT 2 FIRE ZONES 45, 46A, 47A AND 47B (AA43, AA44, AA45A AND AA45B)
EEE-11-16                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR LUBE OIL STORAGE ROOMS FIRE ZONES 83, 88, 95 AND 100 (AA2),
BOUNDARY EVALUATION EEE-11-17                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR DIESEL GENERATOR FUEL OIL DAY TANK ROOMS FIRE ZONES 15 (AA14),16 (AA15), 18 (AA23) AND 19 (AA24) BOUNDARY EVALUATION Page 287 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-6 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER EEE-11-18                EEE    FIRE ZONES 3, 31, 32 AND 35 (AA3) BOUNDARY EVALUATION EEE-11-19                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR MISCELLANEOUS AREAS - FIRE BARRIER EVALUATION BETWEEN THE UNIT 1 TURBINE BUILDING AND BOTH THE SERVICE/OFFICE BUILDING AND THE HEATER BOILER ROOM (AA2) AND THE EVALUATION OF CONTAINMENT COOLING CHILLER EQUIPMENT ROOM TECHNICAL                EEE    NARROW SPACE OPENINGS BETWEEN PENETRATING ITEMS EVALUATION-11-20                AND THE BARRIER OR BETWEEN PENETRATING ITEMS BOUNDARY EVALUATION TECHNICAL                        USE OF SILICONE CAULKING IN SEISMIC/EXPANSION GAP EVALUATION-11-21                FIRE SEALS INSTALLED IN THE FLOORS OF HIGH TRAFFIC AREAS TECHNICAL                        UNIT 1 AUXILIARY FEEDWATER (N-TRAIN) BATTERY ROOM EVALUATION-11-22                BOUNDARY EVALUATION - FIRE ZONE 106 TO FIRE ZONE 52 TECHNICAL                        STORAGE OF DRY ACTIVE WASTE IN THE AUXILIARY                          Cancelled EVALUATION 11-23                BUILDING 609 FT. CRANE BAY FIRE ZONE 32 OR UNIT 2 TURBINE BUILDING 609 FT. CRANE BAY FIRE ZONES 97 AND 98 EEE-11-24                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE RETENTION CAPABILITY OF NONCONFORMING FIRE SEALS IN FIRE ZONES HAVING A LOW FIRE SEVERITY TECHNICAL                        PRSSURE RETENTION CAPABILITY OF CONTROL ROOM EVALUATION-11-25                PRESSURE BOUNDARY FIRE SEALS EEE-11-26                EEE    FIRE RETENTION CAPABILITY OF A HELB PRESSURE BOUNDARY SEAL EEE-11-27                EEE    GENERIC FIRE SEAL DESIGN 1 Page 288 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                                Page 4-7 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER EEE-11-28                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR GENERIC FIRE SEAL DESIGN 2 (FIRE AREAS AA7, AA8, AA39A, AA40, AA43, AA45A, AA45B, AA48 AND AA52)
EEE-11-29                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR GENERIC FIRE SEAL DESIGN 3 IN FIRE AREAS AA2 AND AA15 EEE-11-30                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR GENERIC FIRE SEAL DESIGN 4 (AA2)
TECHNICAL                EEE    GENERIC FIRE SEAL DESIGN 5 EVALUATION-11-31 EEE-11-32                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR GENERIC FIRE SEAL DESIGN 6 (AA2)
EEE-11-33                EEE    GENERIC FIRE SEAL DESIGN 7 EEE-11-34                EEE    GENERIC FIRE SEAL DESIGN 8 EEE-11-35                EEE    GENERIC FIRE SEAL DESIGN 9 EEE-11-36                EEE    UNITS 1 AND 2 HOT SHUTDOWN PANEL ENCLOSURE UNIT 1 FIRE ZONE 144 AND UNIT 2 FIRE ZONE 145 EEE-11-37                EEE    UNRATED FLOOR MATCH AT ELEVATION 633 FT. IN THE AUXILIARY BUILDING FIRE ZONES 52 AND 44N EEE-11-38                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE PROTECTION FOR THE PUMP HOUSE (FIRE AREA YD)
EEE-11-39                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIREPROOFING FOR THE WEST MOTOR DRIVEN AUXILIARY FEEDWATER PUMP ENCLOSURES FIRE ZONES 17A (AA16), 17B (AA17), 80 (AA2), AND 84 (AA2)
Page 289 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                                Page 4-8 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        APPENDIX A TO ETP APCSB 9.5-1 SECTION D.1(J)
EVALUATION-11-40                FIRE DOOR CLOSURES WITH HOLD OPEN DEVICES FIRE ZONES 17C, 17E AND 17F EEE-11-41                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR UNIT 1 FIRE ZONE 53 (AA46) AND UNIT 2 FIRE ZONE 54 (AA47) BOUNDARY EVALUATION TECHNICAL                        APPENDIX R SECTION III.G.2(b)                                          Archived, Info Only EVALUATION 11-42                TWENTY FT. SEPARATION BETWEEN REDUNDANT COMPONENTS WITH NO INTERVENING COMBUSTIBLES FIRE ZONES 6M AND 65 TECHNICAL                        SPATIAL FIRE SEPARATION BETWEEN ALTERNATE EVALUATION-11-43                SHUTDOWN COMPONENTS WITH NO INTERVENING COMBUSTIBLES FIRE ZONE 44N AND 44S EEE-11-44                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR UNRATED FIRE DOORS (361 AND 362) AND UNRATED PERSONNEL WALKWAYS (AA3, AA34, AA35 AND AAYD)
EEE-11-45                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR AUXILIARY BUILDING HVAC DUET PENETRATIONS BOUNDARY EVALUATION FIRE ANALYSIS AREAS AA1, AA3, AA5/6 AND AA36/42 EEE-11-46                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR SEISMIC GAPS BETWEEN THE CONTAINMENT AND AUXILIARY BUILDINGS BOUNDARY EVALUATION (FIRE AREAS AA2, AA3, AA7, AA8, AA9, AA10, AA11, AA27, AA29, AA30, AA31, AA34, AA35, AA37 AND AA38)
EEE-11-47                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE ZONES 44N (AA36), 44S (AA42) AND 52 (AA3) PENETRATION SEALS EEE-11-48                EEE    UNIT 1 & 2 EMERGENCY DIESEL GENERATOR ROOM AB/CD LARGE BORE PIPE PENETRATION SEALS FIRE ZONES 15, 16, 18
                                  & 19 Page 290 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                                Page 4-9 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER EEE-11-49                        PENETRATION SEAL F6124 UNIT 1 CONTROL ROOM                            Superseded ELEVATION 633' -O" FIRE ZONES 53 & 57 EEE-11-50                EEE    CONCRETE EMBEDDED CONDUITS PROTECTED BY EXTERNAL FIRE WRAP MATERIAL UNIT 1 CD DIESEL GENERATOR ROOM AND UNIT 2 AB DIESEL GENERATOR ROOM EEE-11-51                EEE    COOK NUCLEAR PLANT TECHNICAL EVALUATION 11.51 SCREENHOUSE AND WATER INTAKE SYSTEM BOUNDARY EVALUATION FIRE ZONE 142 TO FIRE ZONE 143 EEE-11-52                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR ACCEPTABILITY OF SELECTED PANEL REMOVAL FOR UNIT 1 MAIN TRANSFORMER RADIANT FIRE WALL TECHNICAL                        TECHNICAL EVALUATION FOR PARTIAL AREA FIRE EVALUATION-11-53                SUPPRESSION APPENDIX R SAFE SHUTDOWN ANALYSIS AREAS 57A AND 57B EEE-11-54                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR UNIT 1 MAIN CONTROL ROOM CABLE VAULT PENETRATION SEAL W5111 FIRE ZONE 57 AND 91 (FIRE AREAS AA50 AND AA2)
EEE-11-55                EEE    FLAMMABILITY OF FLOOR COATING SYSTEMS EEE-11-56                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR TURBINE BUILDING MAIN STEAM ACCESS WAY FIRE ZONES 110 TO 114, FIRE ZONES 111 TO 115, FIRE ZONES 112 TO 2N, FIRE ZONES 113 TO 2S (FIRE AREA AA2, AA2C)
EEE-11-57                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE-WRAPPED CABLE TRAYS AND CONDUIT EVALUATIONS (FIRE AREAS AA2, AA32, AA39A, AND AA45A)
EEE-11-58                EEE    UNIT 2 CONTROL ROOM FIRE RATED FLOOR PENETRATION SEALS FIRE ZONES 54 & 58 Page 291 of 315
 
American Electric Power                                      Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                            Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-10 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER EEE-11-59                EEE    UNIT 1 TURBINE BUILDING BELOW ELEVATION 633' -0" WATER FIRE SUPPRESSION SYSTEM SPRINKLER HEAD DEVIATIONS FIRE ZONES 90, 91, 92 & 93 EEE-11-60                EEE    FIRE ZONE 80/114 AND 84/115 BOUNDARY EVALUATION EEE-11-61                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR USE OF FIRE PROTECTION WATER SUPPLY SYSTEM FOR OTHER THAN FIRE PROTECTION RELATED PURPOSES EEE-11-62                        FIRE WATER SUPPLY NFPA 20 CODE CONFORMANCE REVIEW TECHNICAL                        Not Used EVALUATION 11-63 TECHNICAL                        CABLE MATERIAL IMPACT REVIEW EVALUATION-11-64 TECHNICAL                        TECHNICAL EVALUATION FOR SELF IGNITED CABLE FIRES                    Active, Info Only EVALUATION-11-64-1              WITHIN THE UNIT 1 AND UNIT 2 CONTROL ROOM CABLE VAULTS EEE-11-65                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR FIRE DOOR CLOSURE EVALUATION (FIRE AREAS AA2, AA7, AA8, AA14, AA15, AA23, AA24, AA30, AA31, AA34, AA35, AA36/42, AA37, AA38, AA39, AA41, AA43, AA44, AA45, AA48, AND AA53)
EEE-11-66                EEE    YARD (YD) TO FIRE ZONE 19 (AA24) BOUNDARY EVALUATION TECHNICAL                        TECHNICAL EVALUATION FOR EMBEDDED CONDUIT EVALUATION-11-67                EVALUATION TECHNICAL                        TECHNICAL EVALUATION FOR CLOSED HEAD SPRINKLER EVALUATION-11-68                SAMPLING / TESTING / REPLACEMENT PROGRAM PLAN BASIS DOCUMENT AND PROPOSED CLOSED SPRAY HEAD SAMPLING PLAN EEE-11-69                EEE    TECHNICAL EVALUATION FOR NFPA 80 1970 ED CODE DEVIATION ELECTROMAGNETIC FIRE/SECURITY DOOR LOCKS Page 292 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-11 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        TECHNICAL EVALUATION FOR NUCLEAR ELECTRIC EVALUATION-11-70                INSURANCE LIMITED (NEIL) TEMPORARY STRUCTURE VARIANCE UNIT 1 TURBINE ELEV 633 FT - 0 IN CRAFT STAGING AREA EEE 11-71                        Emergency Power Systems Area & EPS Control Rod Drive Room Fire Door Closure Evaluation TECHNICAL                        BASIS DOCUMENT FIRE WATER SYSTEM PIPING INTERNAL EVALUATION-11-72                INSPECTION PROGRAM TECHNICAL                        Not Used EVALUATION 11-73 TECHNICAL                        Not Used EVALUATION 11-74 TECHNICAL                        EVALUATION OF FIRE PROTECTION SYSTEM EVALUATION 11-75                UNAVAILABILITY TECHNICAL                        NFPA 805 AIRBORNE AND LIQUID EFFLUENTS OFFSITE DOSE EVALUATION-11-76                ANALYSIS EEE 11-79                EEE    FIRE ZONE 53 (AA46) AND FIRE ZONE 57 (AA50) FIRE BARRIER PENETRATION SEALS EEE 11-80                EEE    FIRE ZONE 54 (AA47) AND FIRE ZONE 58 (AA51) FIRE BARRIER PENETRATION SEALS TECHNICAL                        FIRE SUPPRESSION EFFECTS STUDY EVALUATION-12-1 TECHNICAL                        SUPPLEMENTAL INFORMATION TO FIRE SUPPRESSION EVALUATION-12-1                  EFFECTS STUDY - SUPPLEMENT 1 TECHNICAL                        PENETRATION SEALING PROGRAM
 
==SUMMARY==
;                                  Cancelled EVALUATION 12-2                  INFORMATION NOTICE 88-04 TECHNICAL                        TIME AND MANPOWER STUDY FOR THE ALTERNATE                              Cancelled EVALUATION 12-3                  SHUTDOWN METHOD TECHNICAL                        COMMUNICATIONS AVAILABILITY EVALUATION                                Cancelled EVALUATION 12-4 Page 293 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-12 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        ASSOICATED CIRCUITS BY COMMON POWER SUPPLY AND EVALUATION-12-5                  COMMON ENCLOSURE TECHNICAL                        SECONDARY FIRE EVALUATION EVALUATION-12-5-1 TECHNICAL                        TECHNICAL EVALUATION FOR CURRENT TRANSFORMER EVALUATION-12-6                  OPEN CIRCUITING CONCERN TECHNICAL                        SAFE SHUTDOWN MANUAL ACTION FEASIBILITY STUDY                          Superseded EVALUATION-12-7                  (Superseded by R1900-0026-001per FPPR-2014-0009)
TECHNICAL                        RCP LUBE OIL COLLECTION SYSTEM                                        Cancelled EVALUATION 12-8 TECHNICAL                        RCP TYGON TUBING SEISMIC QUALIFICATION EVALUATION                      Cancelled EVALUATION 12-9 TECHNICAL                        EVALUATION OF CO2 SYSTEM ACTUATION IMPACT ON THE                      Cancelled EVALUATION 12-10                EPS EEE-12-11                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR STRUCTURAL STEEL EVALUATIONS IN FIRE AREAS AA2, AA3, AA34, AA35, AA56 AND AA58 TECHNICAL                        HIGH IMPEDANCE ARC FAULTS ON ASSOCIATED CIRCUITS                      Cancelled EVALUATION 12-12 EEE-12-13                EEE    FIRE DAMPER CLOSURE REVIEW TECHNICAL                        BUILDING EXPANSION/SEISMIC GAP PENETRATION SEALING                    Cancelled EVALUATION 12-14               
 
==SUMMARY==
 
TECHNICAL                        EMERGENCY LIGHTING                                                    Cancelled EVALUATION 12-15 EEE-12-16-1              EEE    RADIANT HEAT SHIELDS FOR FIRE AREA 58 (SUPPLEMENT 1)
TECHNICAL                EEE    TECHNICAL EVALUATION 12.16 APPENDIX R REVALIDATION EVALUATION-12-16                PROJECT SUPPLEMENTAL ANALYSES AND POSITION PAPERS TECHNICAL                        TECHNICAL EVALUATION FOR FIRE AREA 56 AND 58 - UNIT 1 EVALUATION-12-16-8              AND UNIT 2 CONTAINMENTS Page 294 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                                Page 4-13 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        Not Used EVALUATION 12-17 TECHNICAL                        Not Used EVALUATION 12-18 EEE-12-19                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR CO2 FIRE SUPPRESSION SYSTEMS IN FIRE ZONES CONTAINING CONCENTRATIONS OF CABLE INSULATION (FIRE AREAS AA7, AA8, AA9, AA10, AA29, AA30, AA31, AA37, AA38, AA39, AA40, AA41, AA43, AA44, AA45, AA48, AA50, AA51, AND AA52)
EEE-12-20                EEE    ENGINEERING EQUIVALENCY EVALUATION FOR UNIT 1 TURBINE OIL TANK ROOM FIRE ZONE 95 (AA2)
TECHNICAL                        ANALYSIS OF FIRE ZONES 13, 21, 57, 58, AND 59 LACK OF CO2 EVALUATION-12-21                SUPPRESSION SYSTEM CALCULATIONS EEE-12-22                EEE    UNITS 1 & 2 AUXILIARY BUILDING NORTH AND SOUTH ELEVATION 609' FIRE ZONES 44N AND 44S EEE-12-23                EEE    ANALYSIS OF FIRE ZONES 57 AND 58 LACK OF HALON SUPPRESSION SYSTEM CALCULATIONS EEE-12-24                EEE    NFPA 24 - 'LISTED' VALVE DEVIATION 12-ZMO-400 & 401 TECHNICAL                        TECHNICAL EVALUATIN 12.25 FIRE RATED PENETRATION EVALUATION-12-25                SEALS EEE-12-26                EEE    NFPA 13 - "NON-LISTED" & "NON-RISING STEM" VALVE DEVIATION 12-FP-389, 12-FP-493 & 12-FP-494 TECHNICAL                        INSTRUMENT SENSING LINE EVALUATION EVALUATION-12-27 TECHNICAL                        TECHNICAL EVALUATION FOR NFPA 805 CHAPTER 3                            Superseded by EVALUATION-12-28                FUNDAMENTAL FIRE PROTECTION PROGRAM AND DESIGN                        NFPPM Attachment ELEMENTS REVIEW                                                        1 TECHNICAL                        TECHNICAL EVALUATION FOR NUCLEAR SAFETY                                Active, Info Only EVALUATION-12-29                CAPABILITY ANALYSIS METHODOLOGY REVIEW Page 295 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-14 EEE / TECHNICAL CREDITED EVALUATION                                                TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        TECHNICAL EVALUATION FOR FIRE AREA TRANSITION                          Superseded by FSA EVALUATION-12-30                REVIEW TECHNICAL                        TECHNICAL EVALUATION FOR RADIOACTIVE RELEASE                          Superseded by EVALUATION-12-31                REVIEW                                                                NFPPM Attachment 3
TECHNICAL                        TECHNICAL EVALUATION FOR PROCUREMENT AND EVALUATION-12-32                INSTALLATION OF NON-UL/FM APPROVED FIRE PROTECTION FEATURES EEE-14-1-1                      ENGINEERING EQUIVALENCY EVALUATION FOR NFPA CODE CONFORMANCE REVIEW REPORT TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-A                    FOR COMPLIANCE WITH 10CFR50 APPENDIX R SECTION III.G.3 FIRE AREA E CONTAINING FIRE ZONES 4,5,6A,6N,6M,6S,61,64A,64B,65A AND 65B APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 5/6 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-B                    FOR COMPLIANCE WITH 10CFR50 APPENDIX R SECTION III.G.3 SAFE SHUTDOWN ANALYSIS AREAS 36 AND 42 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-C                    FOR COMPLIANCE WITH III.G.3 FIRE AREA C CONTAINING FIRE ZONES 3,31,32,35,36,48-52,69,106 AND 107 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 3 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-D                    FOR COMPLIANCE WITH III.G.2 FIRE AREA A CONTAINING FIRE ZONES 1,1A-1H, 136, 137 AND 138A-138C APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 1 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-E                    FOR COMPLIANCE WITH III.G.3 FIRE AREA MM CONTAINING FIRE ZONES 42A-42D APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 41 Page 296 of 315
 
American Electric Power                                      Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                            Rev. 4 NFPPM - Attachment 4                                                                                            Page 4-15 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-F                    FOR COMPLIANCE WITH III.G.3 FIRE AREA OO CONTAINING FIRE ZONES 46A, 46B, 46C AND 46D APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 44 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-G                    FOR COMPLIANCE WITH 10CFR50 APPENDIX R SECTION III.G.3 SAFE SHUTDOWN ANALYSIS AREA 48 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEM EVALUATION-H                    FOR COMPLIANCE WITH 10CFR50 APPENDIX R SECTION III.G.3 SAFE SHUTDOWN ANALYSIS AREA 52 CONTAINING FIRE ZONE 59 & 60 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-I                    FOR COMPLIANCE WITH III.G.3 FIRE AREA UU CONTAINING FIRE ZONES 57 AND 144 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 50 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-J                    FOR COMPLIANCE WITH III.G.3 FIRE AREA VV CONTAINING FIRE ZONES 58 AND 145 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 51 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-K                    FOR COMPLIANCE WITH III.G.3 FIRE AREA QQ CONTAINING FIRE ZONE 53 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 46 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-L                    FOR COMPLIANCE WITH III.G.3 FIRE AREA RR CONTAINING FIRE ZONE 54 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 47 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-M                    FOR COMPLIANCE WITH III.G.2 FIRE AREA G CONTAINING FIRE ZONE 8 Page 297 of 315
 
American Electric Power                                        Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                              Rev. 4 NFPPM - Attachment 4                                                                                              Page 4-16 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-N                    FOR COMPLIANCE WITH III.G.1 FIRE AREA CC CONTAINING FIRE ZONE 26 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 30 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-O                    FOR COMPLIANCE WITH III.G.1 FIRE AREA I CONTAINING FIRE ZONE 11 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 10 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-P                    FOR COMPLIANCE WITH III.G.1 FIRE AREA AA CONTAINING FIRE ZONE 23 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 28 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-Q                    FOR COMPLIANCE WITH III.G.3 FIRE AREA II CONTAINING FIRE ZONE 38 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 37 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-R                    FOR COMPLIANCE WITH III.G.3 FIRE AREA JJ CONTAINING FIRE ZONE 39 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 38 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-S                    AND BOUNDARY EVALUATION APPENDIX R SAFE SHUTDOWN ANALYSIS AREAS 2A AND 2B TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-T                    FOR COMPLIANCE WITH III.G.3 FIRE AREA FF CONTAINING FIRE ZONES 33, 33A, 33B AND 105 APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 34 TECHNICAL                        PARTIAL AREA FIRE DETECTION AND SUPPRESSION SYSTEMS EVALUATION-U                    FOR COMPLIANCE WITH III.G.3 FIRE AREA GG CONTAINING FIRE ZONES 34, 34A AND 34B APPENDIX R SAFE SHUTDOWN ANALYSIS AREA 35 TECHNICAL                        WATER-BASED FIRE SUPPRESSION SYSTEM DRAWINGS AND EVALUATION-V                    CALCULATIONS EVALUATION Page 298 of 315
 
American Electric Power                                      Engineering Equivalency Evaluations and Technical Evaluations D. C. Cook Nuclear Plant                                                                                            Rev. 4 NFPPM - Attachment 4                                                                                            Page 4-17 EEE / TECHNICAL CREDITED EVALUATION                                              TITLE                                        NOTES AS EEE NUMBER AEPDCC- 11-001                  UNIT 1 & 2 COORDINATION STUDY TECHNICAL                        RECOVERY ACTION TRANSITION IN SUPPORT OF NFPA 805                    SUPERSEDED EVALUATION R1900-                                                                                    TECHNICAL 0026-001                                                                                              EVALUATION                                                                                                        7 Page 299 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-1 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 Basis Date:                December 23, 1983 To Be Transitioned?:        Yes Basis:                      Exemption approval per the NRC SER dated December 23, 1983 provides the following justification for the lack of automatic suppression as required by Section III.G.2.c of Appendix R, which was submitted by I&M Letter No. AEP:NRC:0692E dated March 31, 1983.
Ceilings and walls are 3 hour fire rated.
Arrangement of stairway and exhaust ventilation provide adequate ventilation to preclude the buildup of a hot gas layer where the ESW cables penetrate the fire zone.
ESW cables have 1 hour fire barriers.
Combustible loading is low.
3 hour fire rated dampers installed in the Unit 2 ESW pump cubicle HVAC supply ducts.
The bases for previous acceptance have been verified and are still valid.
The compliance strategy for Fire Zone 29G is in accordance with III.G.2.c. This area has a lack of automatic suppression therefore an exemption was required. Fire Zones 29A, 29B, 29E have been regrouped with Fire Zone 29G and they now form Fire Area AA32. The NFPA 805 transition compliance strategy for AA32 is in accordance with 4.2.3.3.c, a deterministic approach that credits the use of 1-hour rated ERFBS with automatic detection and automatic suppression. This exemption is required for transition to the NFPA 805 licensing basis because of the lack of automatic suppression within Fire Area AA32.
Applicable Fire Areas:
AA32      - Unit 1 Essential Service Water Pump Area and Unit 1 and Unit 2 Basement Motor Control Center Room (El. 591 ft. and 575 ft.)
Licensing Action Documentation:
Initial Exemption Request - I&M Letter No. AEP:NRC:0692E dated March 31, 1983 Fire Zone 29G Circulating Water Pump Motor Control Room below Unit 1 and Unit 2 ESW Pump Rooms EXEMPTION REQUEST Area Description Fire Zone 29G is the basement level below the essential service water pumps of both Units 1 and 2 and contains two non-safe shutdown motor control centers. The fire zone has a hatch with a ladder up to the Unit 2 ESW southeast pump cubicle and a stairway to the northwest Unit 1 pump cubicle.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 300 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-2 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 The ceiling and walls are all three-hour rated. Conduit for all four ESW pumps, their valves and strainers, enters the east wall via embedded conduit from the Turbine Room. With the exception of the four ESW pump power cable and a conduit for WMO-701 (the Unit 1 east pump discharge valve), all the conduit comes through the wall in pull boxes at near ceiling height and immediately exits up into the ceiling slab. The cabling into the ceiling runs in embedded conduit to its respective pump cubicle. All ceiling and wall penetrations are sealed with three-hour rated fire seals.
Pertinent room dimensional data is contained in Fire Zone 29G Summary Evaluation Table 7.7-1, and Figure 7.7.1.
Safe Shutdown Equipment Fire Zone 29G contains no safe shutdown equipment except cables in conduit for the components of both Units 1 and 2 Essential Service Water Systems The cables for the four pump strainers and discharge valves are located in conduit and in pull boxes at ceiling height. The conduits enter the zone from the Turbine Room floor slab and immediately exit through the ceiling slab to respective pump cubicles. Except for one conduit, the zone exit points are all within the pull boxes. One ESW discharge valve (WMO-701) conduit is run from the pull box near the ceiling to the cubicle area for the Unit 1 east pump and exits through the ceiling. The four pump power cables enter the zone through the east wall at about ceiling height (being run into the zone in the floor slab of the "u.ine Building) and area routed near the ceiling to the respective jump cubicle area where they exit Fire Zone 29G through the ceiling.
Fire Protection Systems Fire Zone 29G has no automatic suppression or detection systems installed and is provided with the manual suppression systems available to 29(A, B, E) and 29(C, D, F).
Fire Hazards Analysis Fire Zone 29G is a common zone for both Unit 1 and. Unit 2. The only safe shutdown equipment in the area is conduit containing cables for the ESW systems of both units. The combustible loading, due entirely to cable insulation, is approximately 4,750,000 Btu which, when distributed over the fire zone surface area, results in approximately 3560 Btu/ft2. The calculated fire severity is approximately three minutes.
The pump power cables are in four inch conduit entering the fire zone through the east wall. The valves and strainers for all four pumps likewise enter the fire zone through the east wall and immediately exit up through the ceiling. No protection presently exists for the conduits of all four pumps. The fire zone provides no path for transient combustibles; however, protection to all cabling associated with both units' ESW systems will be provided. There are no specific sections of the fire zone which contain high densities of combustible materials.
A stairway entering from the Unit 1 west pump cubicle and a ladder in a hatch from Unit 2 east pump cubicle, approximately 40 ft apart, provide a common connection between Units 1 and 2. Hot combustible gases from a fire in Fire Zone 29G could affect the ESW pumps in both units. To protect the unlikely occurrence of all four pumps being affected, a fire-rated hatch cover will be provided in the ladder way to the Unit 2 west cubicle.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 301 of 315
 
American Electric Power                                                                              Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                      Revision 4 NFPPM - Attachment 5                                                                                                            Page 5-3 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 Proposed Modifications The fire hazards analysis performed revealed that Fire Zone 29G is not in compliance with Appendix R and as a result the zone will be upgraded with fire protection modifications.
Fire Detection The fire zone will be provided with an automatic fire detection system.
Hatch The hatch exiting the fire zone to the east pump cubicle of Unit 2 will be provided with at least a one-hour-rated fire hatch door to isolate the Unit 2 pump rooms from the Unit 1 pump rooms (via 29G).
Conduits The following conduits will be provided with one-hour fire protection (grouped in four pull boxes) from the entry to exit point in the fire zone:
Pull Box: 8626G-1, 8627G-1, 8628G-1, 8629G-1 Pull Box: 8624R-1, 8624R-2, 8618R-1, 8619R-1, 8620R-1 Pull Box: 8618R-2, 8619R-2, 8620R-2, 8996R-2 Pull Box: 8977G-1, 9987G-2,8929G-2, 8626G-2 Pump Power and Discharge Valve Conduits The following pump power and discharge valve conduits will be provided with one-hour protection from the entry to the exit point of the fire zone:
8004R-1 (PP-1W Unit-2) 8004G-2 (PP-2E Unit-2) 8004G-1 (PP-1E Unit-1) 8004R-2 (PP-2W Unit-2) 9232G-1 (WMO-701 Unit-1 East)
Conclusion Transition Document Access Code - D.C. Cook Version 2.4.3 Page 302 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-4 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 Based on the previous analysis, exemption is requested from an automatic suppression system as prescribed in Section III.G.2 of Appendix R. The bases which justify the exemption are summarized as follows:
: 1. An automatic fire detection system is to be provided for the fire zone.
: 2. The conduits of both divisions (all four pumps and associated components) are to be provided with one-hour fire protection.
: 3. The hatch connecting the Unit 2 pump room to the Unit 1 pump room, via Fire Zone 29G, is to be provided with a one-hour-rated hatch cover.
: 4. The combustible loading of Fire Zone 29G is extremely low with a fire severity of less than five minutes.
: 5. The fire zone is not in a normal path for transporting transient combustibles.
: 6. Modifications required to meet Section III.G.2 would not significantly enhance fire protection safety above that provided by present commitments.
Exemption Correspondence - I&M Letter No. AEP:NRC:0692H dated August 22, 1983 "SUPPLEMENTAL INFORMATION TO SUPPORT EXEMPTION REQUEST 7.7 FOR FIRE ZONE 29G This section provides supplemental information concerning the proposed hatch construction and other fire hazards analysis considerations which support the III.G.2 suppression exemption request in the D. C. Cook Appendix R. Report, Section 7.7 An open stairway entering from the Unit 1 West ESW pump cubicle, Fire Zone 29B, and a ladder and a hatch opening from the Unit 2 East ESW pump cubicle, Fire Zone 29C, provide a common connection between the Unit 1 and 2 ESW pumps via Fire Zone 29G. As stated in the D. C. Cook Appendix R. Report, Section 8.11.3, the hatch opening from the Unit 2 East Pump cubicle will be provided with a hinged hatch for emergency egress from Fire Zone 29G which will prevent propagation of fire effects into the pump area. The hatch will be coated with materials to provide an equivalent three-hour fire rating. The hatch will ensure that hot combustible gases resulting from a fire in Fire Zone 29G will not affect the Unit 2 ESW pumps.
The Unit 1 West pump cubicle is provided with 10,000 cfm of ducted supply air. All cabling for the supply fans is embedded in concrete from the MCC in Fire Zone 29E to the fan motors, with none of the cabling existing in Fire Zone 29G. Two supply fans are provided, with only one required as each provides 100% of the required air flow for the cubicle. Air is exhausted from this cubicle through the screen mesh security gate in the north wall.
Due to the low combustible loading in Fire Zone 29G and these natural exhaust air flow paths out of the Unit 1 West pump cubicle, hot gases or other products of combustion from a fire in Fire Zone 29G which would flow up the stairway will flow directly out of the cubicle and prevent the formation of a stratified layer of hot gases with sufficient depth to damage the Unit 1 ESW pumps.
At the NRC Staff's request, we have reviewed the Fire Hazard Analysis to determine if three-hour raceway Transition Document Access Code - D.C. Cook Version 2.4.3 Page 303 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-5 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 barriers for two of the four ESW pump trains would be preferable to one-hour barriers for all four ESW trains.
Based on the low in-situ combustible loadings and a lack of major activity in the zone, Indiana and Michigan Electric Company believes that the previously proposed one-hour barriers for all four trains achieves an equivalent or superior level of fire protection for the zone configuration. In addition, the design and installation issues associated with the three-hour raceway barriers suggest that implementation of that alternative is not preferred.
Based on these considerations, both the east and west trains of ESW for both Units 1 and 2 will be protected from the effects of fires in Fire Zone 29G. In the highly unlikely event that a fire in Fire Zone 29G should cause failure of both Unit 1 ESW pumps, alternate shutdown capability for Unit 1 is available through the use of the Unit 2 ESW pumps.
The alternative shutdown capability is described in the D. C. Cook Appendix R. Report, Section 5.2.3.
Manual hose stations are provided in the Screen House for fighting fires in Fire Zone 29G. The hose stations are located such that all portions of Fire Zone 29G can be covered with 75 feet of hose and 30 feet of water stream.
Figures 6.1 and 6.2 indicate the locations of manual hose stations and portable extinguishers for fighting fires in Fire Zone 29G.
Based on this supplemental information and the analysis contained within the March 1983 Appendix R submittal for D. C. Cook, the exemption from providing an automatic suppression system in Fire Zone 29F should be granted.
Exemption SER - NRC SER dated December 23, 1983 12/23/1983 "Circulating Water Pump Motor Control Room (Fire Zone 29G)
Exemption Requested An exemption is requested from Section III.G to the extent it requires 3-hour barriers for the boundaries of fire areas, and the installation of automatic suppression in areas where redundant trains of safe shutdown cables are routed.
Discussion Fire zone 29G is the basement level below the essential service water pump rooms of both units and contains two non-safe shutdown motor control centers. The fire zone has an open hatch with a ladder up to the Unit 2 ESW southeast pump cubicle and a stairway which opens to the northwest Unit 1 pump cubicle.
The ceiling and walls are all three-hour rated. With the exception of the four ESW pump power cables and conduit for the Unit 1 east pump discharge valve, all the conduit comes through the wall in pull boxes near the ceiling and immediately exits up into the ceiling slab. The cabling into the ceiling runs in embedded conduit to its respective pump cubicle. All ceiling and wall penetrations are sealed with three-hour rated fire seals.
The licensee now proposes a different modification involving the open hatchway. Previously, a one-hour rated Transition Document Access Code - D.C. Cook Version 2.4.3 Page 304 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-6 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 hatch was proposed. Now a 3-hour rated hatch is proposed. The Unit 1 and Unit 2 ESW pumps will therefore be separated by a complete 3-hour barrier in compliance with Section III.G. In addition, the arrangement of the stairway and exhaust ventilation system provides a means for high-level venting of smoke, heat, and combustion products emanating from the fire zone 29G. This will preclude a buildup of a hot gas layer at the ceiling level in the fire zone 29G where ESW pump cables are located. Additional protection is provided by one-hour rated fire barriers on all four trains of ESW pump cables. We agree that the proposed modifications in conjunction with the low fuel load-in the area provides reasonable assurance that one train of ESW pumps will be maintained free of fire damage.
Conclusion Based on the above evaluation, the level of protection provided for the ESW pumps (Fire Zone 29G) provide a level of fire protection equivalent to the technical requirements of Section III.G. The exemption should be granted."
Additional SER: NRC SER dated June 17, 1988 "ESSENTIAL SERVICE WATER PUMP HOUSE DEVIATION REQUESTED A deviation was requested from Section D.1.j of Appendix A to BTP APCSB 9.5-1 to the extent that floors, walls and ceilings enclosing separate fire areas should have minimum fire ratings of three hours. Specifically, the licensee has identified an unrated steel hatch, an undampered ventilation duct and screen mesh access gates in fire area boundaries surrounding Essential Service Water Pumps and Circulating Water Pump Motor Control Room.
DISCUSSION Fire Zones 29A and 29B are the Unit 1 Essential Service Water (ESW) Pump Cubicles while Zones 29C and 29D house the Unit 2 ESW Pumps. The Circulating Water Pump Motor Control Room, Zone 29G, is located directly below all four pump cubicles. Zones 29A and 29B are separated from Zones 29C and 29D by a 3-hour rated barrier. Undampered HVAC supply air openings exist in the ceiling of each of the ESW Pump Cubicles, although, by {{letter dated|date=May 30, 1987|text=letter dated May 30, 1987}}, the licensee committed to install 3-hour rated dampers in the Unit 2 cubicle air openings. Unsealed piping penetrations are present in the Unit 1 cubicles while the piping penetrations in the Unit 2 ceiling area sealed. Access to Zone 29G is provided from an open curbed stairway from Zone 29B. Access to Zone 29C is provided by an unrated steel hatch in the ceiling of Zone 29G. Access to the screen house area from the pump rooms is provided through steel mesh gates.
The Unit 1 ESW Pumps provide alternate shutdown capabilities for Unit 2 and the Unit 2 pumps provide alternate shutdown capability to Unit 1. Zone 29G contains ESW Pump power cables for both Units, however, the cables are in conduits which are protected with 1-hour rated material.
Early warning fire detection has been installed in the Unit 1 and Unit 2 pump cubicles and Zone 29G. The early warning detection alarms in the control room. Fire suppression consists of extinguishers and manual hose Transition Document Access Code - D.C. Cook Version 2.4.3 Page 305 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-7 Licensing Action Appendix R Exemption, Screenhouse Auxiliary MCC Room Lack of Automatic Suppression (Criteria III.G.2.c) -
Exemption 7.7 stations provided throughout the zones. By {{letter dated|date=June 14, 1983|text=letter dated June 14, 1983}}, an exemption from Section III.G of Appendix R to 10 CFR 50 was granted for Zones 28A, B, C and D to the extent that a fixed suppression system is not provided in an area where alternate shutdown is provided.
The combustible loading for the ESW Pump Cubicles, Fire Zones 29A, B, C and D is approximately 7,000 Btu/ft(2) each. The loading for Zone 29G is less than 13,000 Btu/ft(2). These loadings correspond to an equivalent fire severity per ASTM E119 of less than 10 minutes.
EVALUATION The fire boundaries of the ESW Pump Cubicles and Circulating Water Pump Motor Control Room deviate from the requirements of Section D.1.j of Appendix A to BTP APCSB 9.5-1 to the extent that they contain openings and an unrated hatch thereby making the fire area boundaries not 3-hour rated. The concern is that a fire could propagate from one of the pump cubicles in one unit to the pump cubicles of the other unit and affect the ability of the plant to safely shut down.
However, the combustible loading in all of the areas of concern is low with an equivalent fire severity of under 10 minutes for each zone. The one zone which would have been a concern was the roof area which is used for the storage of wood and other combustibles. This would have allowed for the possibility for a fire to spread up through one of the air openings and then across and down through other openings in the other unit's pump cubicles. However, the licensee has committed to provide 3-hour rated dampers in the Unit 2 openings which would prevent this scenario from occurring. Another concern would be the possibility that a fire in either Zone 29B, 29G or 29C could propagate to the other two zones via the stairway and the unrated steel hatch. Since the combustible loading in each of the three areas is low, it is not probable that a single fire could travel the stairway in either direction and also cause the steel hatch to fail and spread to the zone on the opposite side. Flammable liquids would be prevented from traveling down the stairway due to a six inch curb at the top. For a fire to affect pumps from both units through the mesh access gates, it would have to travel 175 feet through an area with a combustible loading of under 10 minutes. The lack of combustibles provides reasonable assurance that this scenario is not probable. If a fire were to occur in any of the zones of concern, it would be expected that the early warning detection would alert Control Room personnel who in turn would notify the fire brigade. Due to the low combustible loading, it would also be expected that the brigade could control the fire prior to it spreading out of the zone of origin. Therefore, there is reasonable assurance that the lack of complete 3-hour boundaries of the Essential Service Water Pump Cubicles and the Circulating Water Pump Motor Control Room does not adversely affect plant fire safety or the ability of the plant to safely shutdown.
CONCLUSION Based on the above evaluation, it is concluded that the existing fire protection features of the ESW Pump Cubicles and the Motor Control Room, combined with the licensee's commitment to install 3-hour dampers, provide an acceptable level of protection in accordance with the guidelines of Sectio D.1.j of Appendix A to BTP APCSB 9.5-1. Therefore, the deviation for the unrated hatch, undampered air openings and screen mesh access gates is acceptable."
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 306 of 315
 
American Electric Power                                                                              Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                      Revision 4 NFPPM - Attachment 5                                                                                                            Page 5-8 Licensing Action Appendix R Exemption, RCP Lube Oil Collection System (Criteria III.O) - Exemption 7.15 Basis Date:                  December 23, 1983 To Be Transitioned?:          Yes Basis:                        Exemption approval per the NRC SER dated December 23, 1983 provides the following justification for RCP lube oil collection system as required by Section III.O of Appendix R, which was submitted by I&M Letter No. AEP:NRC:0692D dated December 30, 1982.
No ignition sources at the floor level of the lower containment.
Oil system is capable of withstanding a safe shutdown earthquake.
Tank has the capacity to hold the total lube oil inventory for one pump.
Section III.O of Appendix R requires that the oil collection system be large enough to handle the largest potential oil leak without overflowing. The oil collection tanks have a capacity to collect the oil from 1 RCP therefore an exemption was required. This requirement is applicable to section 3.3.12.2 of NFPA 805. This exemption will be transitioned to the NFPA licensing basis.
Applicable Fire Areas:
AA56        - Unit 1 Containment AA58        - Unit 2 Containment Licensing Action Documentation:
Initial Exemption Request - I&M Letter No. AEP:NRC:0692D dated December 30, 1982 I&M Letter No. AEP:NRC:0692D dated December 30, 1982 stated:
In our {{letter dated|date=July 19, 1982|text=July 19, 1982 letter}} (AEP:NRC:0692C), we committed to re-evaluate the seismic characteristics of the existing oil drainage piping and collection tank installed in Units 1 and 2 of the Cook Plant and also to undertake an evaluation of the seismic capability of the RCP motor lube oil system. In the former evaluation, we committed to inspect the oil drainage piping during the next refueling outages of each unit and to undertake modifications to the oil drainage system as necessary. Both-the-re-evaluation of the seismic characteristics of the oil drainage piping and collection tank and the evaluation of the seismic capability of the motor lube oil system have been completed. Based on the results of these evaluations and with the exception of the exemptions we are requesting, we have concluded that the oil collection system installed at the Cook Plant meets the requirements of Section III.O of Appendix R. A general summary of the results of our evaluations, the subsequent modifications we have taken on Unit 1 and are currently taking on Unit 2, and the areas where we are requesting exemptions from the specific requirements of Section III.O of Appendix R is presented below.
Based on our evaluation of the oil drainage piping and collection tank, utilizing inputs from EDS Nuclear with respect to the seismic capability of the oil collection tank and inputs from Stevenson & Associates with respect to the oil drainage piping, it was decided that certain modifications were desirable to insure the adequacy of the system. The modifications included the addition of pipe supports (generally in the area of the RCPs),
reinforcement of the lube oil collection tank, removal of the sight glass on the tank, sealing of the oil lift enclosures, and seal welding or socket welding of threaded piping connections.
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 307 of 315
 
American Electric Power                                                                              Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                      Revision 4 NFPPM - Attachment 5                                                                                                            Page 5-9 Licensing Action Appendix R Exemption, RCP Lube Oil Collection System (Criteria III.O) - Exemption 7.15 The above modifications were incorporated into Unit 1 during the recent refueling outage (JulySeptember, 1982). These same modifications, excluding seal welding, are being incorporated into Unit 2 during its current refueling outage. Consultation with Stevenson & Associates since the Unit 1 outage indicated that threaded connections which are not subject to vibration are seismically acceptable provided that the joint efficiency is reduced by a predetermined factor. The analysis was performed incorporating this criterion and the threaded joints were determined to be adequate. In addition, the threaded joints subject to vibration from the RCPs are being seal welded or replaced with socket welds.
To insure continued integrity of these systems, they will be inspected during each refueling outage in accordance with Plant Procedure 12 MHP 5030.001.003 (Maintenance Procedure for Inspection of Reactor Coolant Pump Motor Oil Levels and Oil Spill Protection Integrity).
The oil collection system installed at the Cook Plant preceded the issuance of the Appendix R requirements. As such, there are aspects of our design which do not meet the specific requirements of Appendix R but which we believe will not prevent the system from fulfilling its intended safety function. Specifically:
A. The presently installed system incorporates an oil collection tank sized to hold the inventory of only one RCP motor. It is our contention that such a system is adequate based on the following:
: 1. A credible event which could cause simultaneous failure of two- or more RCP motor lube oil systems is a seismic event. The results of our analysis indicate that the components of the RCP motor lube oil system are capable of withstanding a safe shutdown earthquake (SSE). In addition, Westinghouses analysis of the RCP lube oil system has confirmed that the RCP motor was conservatively designed and the stresses under design basis earthquake (DBE) conditions are well within the allowable stresses giving reasonable assurance that the RCP motor oil system (lift pump, oil coolers, etc.) can withstand a DBE and maintain its integrity.
: 2. Should a failure of more than one RCP motor lube oil system occur, the oil collection tank would overflow to the lower containment floor. The system uses a synthetic oil (Mobil SHC 824) which has a flash point of 480 F and an ignition temperature of about 700 F. There is no source of heat at the floor of the lower containment capable of igniting the oil.
B. Portions of the lube oil collection system are not designed to withstand a design basis accident (LOCA and Steamline Break) however, it is our contention that the system is adequate based on the following:
: 1. During normal operation, the lube oil collection system will function to collect drips and drains and route these to the oil collection tank. In addition, the RCP motor areas are protected by a fire sprinkler system.
: 2. As described previously, the lube oil collection system is adequate to perform its function during and after a SSE.
: 3. In the unlikely event of a design basis accident, some portions of the lube oil collection piping may be susceptible to failure. However, such failure would not result in a fire hazard because of the characteristics of the synthetic oil and the operation of the containment spray system, a safety grade system, acting as an effective fire suppression system.
Although the lube oil collection system, as described above, does not meet all the requirements of 10 CFR 50 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 308 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                        Page 5-10 Licensing Action Appendix R Exemption, RCP Lube Oil Collection System (Criteria III.O) - Exemption 7.15 Appendix R, Section III.O, we believe that the containment area is adequately protected from a fire which may initiate from a RCP lube oil collection system failure. We therefore request that, pursuant to the provisions of 10 CFR 50.48(c)(6), an exemption from the requirements of Section III.O of Appendix R to 10 CFR 50 be granted to us, such that it be acknowledged that the oil collection system for the RCPs installed at the Cook Plant and modified as described in this Attachment is adequate and sufficient to meet its intended safety function."
Exemption SER - NRC SER dated December 23, 1983 NRC SER dated December 23 1983 stated:
      "Oil Collection System for Reactor Coolant Pumps Exemption Requested An exemption is requested from Section III.0 to the extent it requires an oil collection tank sized to hold the lube oil inventory of all four-RCP motors.
Discussion Each unit has four reactor coolant pumps with an oil collection system which drains to a vented closed collection tank. The quantity of lubricating oil in each pump is 265 gallons. The capacity of the oil collection tank is 275 gallons. The components have been designed so that they are capable of withstanding a safe shutdown earthquake (SSE).
The collection tank is arranged such that if a failure of more than one RCP motor lube system occurred, the oil collection tank would overflow onto the lower containment floor. The lubricating oil used in the RCP motors has a flash point of approximately 480 degrees F. There are no ignition sources at the floor level of the lower containment.
Evaluation The RCP motor lube oil system does not comply with Section III.D because the oil collection tank is not sized to contain the entire lube oil system inventory.
The RCP motor lube oil system is capable of withstanding the safe shutdown earthquake. The oil collection tank is provided with sufficient capacity to hold the total lube oil inventory of one reactor coolant pump with margin and is designed so that any overflow will be drained to a safe location. We agree with the licensee that the combination of features is acceptable.
Conclusion Based on the above evaluation, the existing RCP motor lube oil collection system provides a level of safety equivalent to the technical requirements of Section III.O and, therefore, the exemption should be granted.
Additional Exemption SER - NRC SER dated January 19, 2001 Transition Document Access Code - D.C. Cook Version 2.4.3 Page 309 of 315
 
American Electric Power                                                                            Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                    Revision 4 NFPPM - Attachment 5                                                                                                          Page 5-11 Licensing Action Appendix R Exemption, RCP Lube Oil Collection System (Criteria III.O) - Exemption 7.15 NRC SER dated January 19, 2001 states "INTRODUCTION By {{letter dated|date=February 29, 2000|text=letter dated February 29, 2000}}, Indiana Michigan Power Company (I&M) provided corrected information related to a previous exemption from a 10 CFR Part 50, Appendix R, Section III.0 requirement dealing with the reactor coolant pumps (RCPs) motor lube oil collection system. Incorrect data regarding flash point for the RCPs oil was provided by the licensee in the exemption request dated May 4, 1982, as supplemented December 30, 1982. The RCP oil flash point was used in the exemption request to help justify the smaller tank size by showing that oil spill on the piping insulation or overflow on the containment floor would not present a fire hazard. In addition, no ignition sources were reported in proximity to the RCP lube oil tanks and no potential oil leakage sites were detected in the RCP oil collection system. The staff approved the requested exemption with the incorrect flash point (480 F) for the RCP oil by {{letter dated|date=December 23, 1983|text=letter dated December 23, 1983}}.
A telephone conversation was held on July 26, 2000, between members of I&M and the Nuclear Regulatory Commission (NRC) staff related to February 29, 2000, submittal to discuss the information provided by the licensee. At the close of the phone call, the NRC staff indicated that additional information would be required to complete the evaluation of the I&M February 29, 2000, submittal. Additional information was requested by the staff regarding the description of electrical ignition sources present, and where the oil collection tank overflows in the containment. I&M responded to the NRC request for additional information (RAI) by {{letter dated|date=October 6, 2000|text=letter dated October 6, 2000}}, which provided the information requested by the staff.
DISCUSSION Cook Nuclear Plant (CNP), Units 1 and 2, are each 4-loop Westinghouse Nuclear Steam Supply Systems (NSSS). Each reactor is equipped with four RCPs with an oil collection system which drains to a vented closed collection tank. The quantity of lubricating oil in each pump is approximately 265 gallons and the capacity of the oil collection tank is approximately 257 gallons. The collection tank is arranged such that if a failure of more than one RCP motor lubricating oil system occurred, the oil collection tank would overflow onto the lower containment floor in the containment building. The normal operating temperature of RCP lube oil is 140 F, and a bearing temperature alarm is set at 185 F to indicate when the oil exceeds the normal operating temperature.
I&M has determined that the flash point for the RCP lube oil is approximately 425 F. This value is 55 F lower than the previously stated value (480 F). The licensee stated that should the lube oil come in contact with the surface of the hottest insulation in the proximity of the RCP motors it will not result in the ignition of the lube oil. The maximum design outside surface temperature for the mirror insulation is approximately 140 F. Only noncombustible, non-oil absorbent, metal-jacketed mirror insulation is used in the potential oil spill area.
Additionally, potential electrical ignition sources were identified by the licensee in the area of the oil collection tank system which were not described in the original exemption. Potential electrical ignition sources include:
energized 480 volts ac (vac) welding transformer and associated welding outlets, open power take-off box, energized temporary extension cords, and improperly sealed junction boxes at the RCP lube oil collection tank level. The licensee has implemented plant administrative procedures and inspections under corrective maintenance program to control these ignition sources. The operating and surveillance procedures that administratively control these electrical circuits have been revised to ensure that these potential electrical ignition sources are de-energized whenever an RCP is running.
EVALUATION Transition Document Access Code - D.C. Cook Version 2.4.3 Page 310 of 315
 
American Electric Power                                                                              Existing Licensing Action Transition D. C. Cook Nuclear Plant                                                                                                      Revision 4 NFPPM - Attachment 5                                                                                                            Page 5-12 Licensing Action Appendix R Exemption, RCP Lube Oil Collection System (Criteria III.O) - Exemption 7.15 The RCP oil collection system is required to prevent a major lube oil fire from occurring inside of the reactor containment building, as a result of a lube oil leak from the RCPs. CNP Unit 1 and 2 collects lube oil leakage from each of the four RCP motors into a single collection tank for each unit. The oil collection tank is sized to collect approximately 265 gallons of lube oil the amount contained in one RCP motor, without overflowing. In the event of a single RCP lube oil leak occurring under normal operating conditions, the oil collection system will function to contain the oil and drain it to the oil retention tank. The oil collection system will prevent the lube oil from making contact with hot RCP piping and other external ignition sources. The combined loss of lube oil from all four RCPs motors failing simultaneously would be an overflow of approximately 785 gallons.
Any overflow oil would be discharged out of the RCP lube oil collecting tank vent piping tee, located approximately 6.5 feet above the lower containment floor. This oil would flow onto the tank exterior, then onto the lower containment flooring around the tank. There are no floor drains in the RCP lube oil collecting tank area. The lower containment floor does not have a significant slope in any direction, and there is no berm surrounding the RCP lube oil collection tank. There are no physical barriers to prevent overflowing oil from migrating toward the lower containment sump and containment recirculation sump. These two sumps are located in the lower containment, approximately 180 from the RCP oil collection tank. Oil reaching the sump area would flow directly from the lower containment floor evaluation into the lower containment sump.
The identified combustible materials in the area around RCP lube oil collection tank include cable insulation and lube oil. Both the migrating and pooling of oil from an overflow of the RCP lube oil collecting tank should not represent a fire hazard in the area. Also, the oil collecting sumps in the lower containment present no fire hazard to safe shutdown equipment. The temperature in the area is expected to remain below the auto ignition temperature of the lube oil. In addition, the licensee has implemented operating and surveillance procedures in order to control potential electrical ignition sources such that these ignition sources are de-energized whenever a RCP is running. The CNP has administrative controls to ensure that there are no ignition sources in the lower containment when RCPs are required to be operable. An automatic fire detection system and manual fire suppression system are available in the vicinity of the lube oil collecting system to control a postulated fire. In the event of a fire, it is expected that the detector will alarm in the main control room (MCR). The alarm will alert the MCR operators of a fire condition, allowing fire brigade personnel to be dispatched to the fire zone to extinguish the fire. This provides further assurance that a worst-case postulated fire would not damage safe shutdown equipment.
CONCLUSION Based on the above evaluation, the staff finds that the change in the flash point of the RCP lubrication oil flash point does not alter the conclusions reached by the staff in granting the original exemption from Section III.O of Appendix R to 10 CFR Part 50. Therefore, the exemption granted by the NRC remains valid."
Transition Document Access Code - D.C. Cook Version 2.4.3 Page 311 of 315
 
American Electric Power                                                                          Wrapped Raceway D. C. Cook Nuclear Plant                                                                                    Rev. 4 NFPPM - Attachment 6                                                                                      Page 6-1 Fire      Analysis                          Cable(s) of Unit Raceway  System                    Component Fire Rating          Comments Zone      Area                                Concern 6M        5/6          2  2-8154G EPS    2-8154G        2-QT-106-CD1  1 hour
                              & pull box 15        14            1  1-8002R ECCS    1-8002R        T11A, T11A3,  1 hour      1-8002R is wrapped in the (PP-9W)                  same pilaster as protected cable 1-8003R (reference drawing 1-1411).
15        14            1  1-8003R RHR    1-8003R        PP-35W        1 hour 15        14            1  1-8004R ESW    1-8004R        PP-7W        1 hour 15        14            1  1-8007R CVCS    1-8007R        PP-50W        1 hour 15        14            1  1-8048R EPS    1-8048R        AB-A          1 hour 15        14            1  1-8503R EPS    1-8503R        ABD-A        1 hour 15        14            1  1-8504R EPS    1-8504R        ABD-B        1 hour 19        24            2  2-8001G AFW    2-8001G        2PP3E        1 hour 19        24            2  2-8002G ECCS    2-8002G        T21D, T21D4,  1 hour      2-8002G is wrapped in the (PP-9E)                  same pilaster as protected cable 2-8003G (reference drawing 2-1411).
19        24            2  2-8003G RHR    2-8003G        2PP35E        1 hour 19        24            2  2-8004G ESW    2-8004G        2PP7E        1 hour 19        24            2  2-8007G CVCS    2-8007G        2PP50E        1 hour 19        24            2  2-8048G EPS    2-8048G        AB-D          1 hour 19        24            2  2-8544G EPS    2-8544G        ABD-C        1 hour 19        24            2  2-8545G EPS    2-8545G        ABD-D        1 hour 29G        32            2  2-8618R ESW    2-8618R        2-OME-34W    1 hour      Pullbox PB-3 also protected.
29G        32            2  2-8979R ESW    2-8979R        2-WMO-704    1 hour      Pullbox PB-3 also protected.
29G        32            2  2-8996R ESW    2-8996R        2-WMO-704    1 hour      Pullbox PB-3 also protected.
29G        32            2  2-8627G ESW    2-8627G        2-OME-34E    1 hour      Pullbox PB-4 also protected.
29G        32            2  2-8644G ESW    2-8644G        2-WMO-703    1 hour      Pullbox PB-4 also protected.
29G        32            2  2-8977G ESW    2-8977G        2-WMO-703    1 hour      Pullbox PB-4 also protected.
29G        32            2  2-8004R ESW    2-8004R        2-PP-7W      1 hour 29G        32            2  2-8004G ESW    2-8004G        2-PP-7E      1 hour 29G        32            2  2-8036R EPS    2-8036R        2-PS-A        1 hour      Pullbox also protected.
Page 312 of 315
 
American Electric Power                                                                          Wrapped Raceway D. C. Cook Nuclear Plant                                                                                      Rev. 4 NFPPM - Attachment 6                                                                                      Page 6-2 Fire      Analysis                          Cable(s) of Unit Raceway  System                    Component  Fire Rating        Comments Zone      Area                                Concern 29G        32            2  2-9993G EPS    2-9993G        2-PS-D        1 hour      Pullbox also protected.
40A        39A          1  conduit 1-250D  1-8353G        TDCD          1 hour 44S        42            2  2-8344G EPS    2-8344G        2-OME-150-CD  1 hour 44S        42            2  2-8333G EPS    2-8333G        2-OME-150-CD  1 hour 47A        45A              conduit 2-250D  2-8353G        TDCD          1 hour 79        2            1  1AZ-C34 EPS    1-8095G        1-QT-106-CD1  1 hour EPS    1-8098G        1-QT-106-CD2 EPS    1-8333G        1-OME-150-CD EPS    1-8338G        1-OME-150-CD EPS    1-8339G        1-OME-150-CD EPS    1-8340G        1-OME-150-CD              Component ID corrected to 1-OME-150-CD EPS    1-8343G        1-OME-150-CD EPS    1-8344G        1-OME-150-CD EPS    1-8345G        1-OME-150-CD EPS    1-8346G        1-OME-150-CD EPS    1-8347G        1-OME-150-CD EPS    1-8348G        1-OME-150-CD EPS    1-8349G        1-OME-150-CD, 1-T11C, 1-T11D EPS    1-8400G        1-OME-150-CD EPS    1-8409G        1-OME-150-CD EPS    1-8410G        1-OME-150-CD ESW    1-8466G        1-WMO-726 EPS    1-8592G        1-OME-150-CD EPS    1-8639G        1-OME-150-CD EPS    1-8526G        1-QT-106-CD1 EPS    1-8527G        1-QT-106-CD2 CVCS    1-8874G        1-PP-50E RHR    1-8889G        1-PP-35E ESW    1-8789G        1-PP-7E CCW    1-8862G        1-PP-10E AFW    1-9290G        1-PP-3E Page 313 of 315
 
American Electric Power                                                                          Wrapped Raceway D. C. Cook Nuclear Plant                                                                                    Rev. 4 NFPPM - Attachment 6                                                                                      Page 6-3 Fire      Analysis                            Cable(s) of Unit Raceway  System                    Component  Fire Rating        Comments Zone      Area                                Concern 79        2            1  1-      DIS    1-80009PR-1    1-COMBO-UDISB  1 hour      FPRA Only 80009PR-1 1-      DIS    1-80046PR-1    1-COMBO-LDISB  1 hour      FPRA Only 80046PR-1 85        2B            2  2AZ-C55  RHR    2-8889G        2-PP-35E      1 hour      85 ESW    2-8789G        2-PP-7E CCW    2-8862G        2-PP-10E AFW    2-9290G        2-PP-3E EPS    2-8095G        2-QT-106-CD1 EPS    2-8098G        2-QT-106-CD2 EPS    2-9231G        2-OME-150-CD 85        2B            2  2AZ-C99  CVCS    2-8874G        2-PP-50E EPS    2-8338G        2-OME-150-CD EPS    2-8339G        2-OME-150-CD EPS    2-8340G        2-OME-150-CD EPS    2-8343G        2-OME-150-CD EPS    2-8345G        2-OME-150-CD              AR 2016-14631 EPS    2-8347G        2-OME-150-CD EPS    2-8348G        2-OME-150-CD EPS    2-8349G        2-OME-150-CD, 2-T21C, 2-T21D EPS    2-8400G        2-OME-150-CD EPS    2-8409G        2-OME-150-CD EPS    2-8410G        2-OME-150-CD ESW    2-8466G        2-WMO-726                  AR 2016-14631 EPS    2-8346G        2-OME-150-CD              AR 2016-14631 EPS    2-8874G        2-OME-150-CD              AR 2016-14631 EPS    2-8339G        2-OME-150-CD              AR 2016-14631 ESW    2-8946G        2-WMO-708                  AR 2016-14631 EPS    2-8592G        2-OME-150-CD EPS    2-8639G        2-OME-150-CD Page 314 of 315
 
American Electric Power                                                                  Wrapped Raceway D. C. Cook Nuclear Plant                                                                          Rev. 4 NFPPM - Attachment 6                                                                            Page 6-4 Fire      Analysis                          Cable(s) of Unit Raceway  System                    Component  Fire Rating Comments Zone      Area                                Concern EPS    2-9921G        2-OME-150-CD EPS    2-8526G        2-QT-106-CD1 EPS    2-8527G        2-QT-106-CD2 85        2B            2  2E-C9  RHR    2-8889G        2-PP-35E ESW    2-8789G        2-PP-7E CCW    2-8862G        2-PP-10E AFW    2-9290G        2-PP-3E EPS    2-8095G        2-QT-106-CD1 EPS    2-8098G        2-QT-106-CD2 EPS    2-9231G        2-OME-150-CD 85        2B            2  2E-C10  CVCS    2-8874G        2-PP-50E EPS    2-8340G        2-OME-150-CD EPS    2-8343G        2-OME-150-CD EPS    2-8345G        2-OME-150-CD EPS    2-8346G        2-OME-150-CD EPS    2-8347G        2-OME-150-CD EPS    2-8348G        2-OME-150-CD EPS    2-8349G        2-OME-150-CD, 2-T21C, 2-T21D EPS    2-8400G        2-OME-150-CD EPS    2-8409G        2-OME-150-CD EPS    2-8410G        2-OME-150-CD EPS    2-8592G        2-OME-150-CD EPS    2-8639G        2-OME-150-CD EPS    2-9921G        2-OME-150-CD EPS    2-8526G        2-QT-106-CD1 EPS    2-8527G        2-QT-106-CD2 Page 315 of 315}}

Latest revision as of 09:11, 29 November 2024

Rev. 4 to NFPA 805 Fire Protection Program Manual
ML21125A540
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/19/2021
From:
American Electric Power, Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21126A238 List: ... further results
References
AEP-NRC-2021-19
Download: ML21125A540 (315)
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