ML20148E709
| ML20148E709 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/31/1997 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20148E704 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 9706030230 | |
| Download: ML20148E709 (815) | |
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!h NORTH ANNA POWER STATION ' UNITS 1 AND 2 REPORT ON VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT PREPARED IN RESPONSE TO USNRC GENERIC LETTER 87-02 UNRESOLVED SAFETY ISSUE (USI) A-46
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1 VIRGINIA ELECTRIC AND POWER COMPANY j MAY 1997 O-9706030230 970527 PDR ADOCK 05000332 PDR P
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PRINCIPAL CONTRIBUTORS Dr. A. Asfura (EQE International) l Mr. J. Betlack (MPR Associates) l Mr. D. Bhargava (Virginia Power)
Mr. R. D. Campbell (EQE International) l Mr. D. L. Harris (MPR Associates) l Mr. P. Hayes (MPR Associates) l Mr. T. W. Hsu (Virginia Power) l Ms. D. Jacobs (MPR Associates) l Dr. J. J. Johnson (EQE International) !
Mr. D. P. Madden (Virginia Power) i Mr. K. N. Mehrotra (Virginia Power)
Mr. C. G. Ranganath (Virginia Power)
Mr. M. Salmon (EQE International)
Mr. D. Werder (MPR Associates)
Mr. S. E. Zinkham (Virginia Power)
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INDEPENDENT REVIEW Mr. G. B. Crisman (Virginia Power)
Dr. K. K. Dwivedy (Virginia Power)
Dr. R. P. Kennedy (Structural Mechanics Consulting, Inc.)
Mr. D. B. Roth (Virginia Power)
Mr. C. E. Sorrell (Virginia Power) f rx>
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l g EXECUTIVE
SUMMARY
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As stated in NUREG 1211, " Regulatory Analysis for Resolution of Unresolved Safety Issue A-46.. ", published in 1987, seismic qualification of mechanical and electrical equipment in operating nuclear plants was designated as an Unresolved Safety Issue (USI) A-46 by the NRC in December 1980. The concern was that equipment in nuclear plants with construction permit applications docketed before about 1972 had not been reviewed in accordance with the then current criteria for seismic qualification of equipment (Regulatory Guide 1.100, Institute of Electrical and Electronics I Engineers (IEEE) Standard 344-1975, and Standard Review Plan Section 3.10 (NUREG-0800)). l A Seismic Qualification Utility Group (SQUG) was formed and in 1983, proposed the formation of a panel of consultants, the Senior Seismic Review and Advisory Panel (SSRAP), to independently assess the feasibility of using earthquake experience data which was being collected by industry consultants. In 1984, Electdc Power Research Institute (EPRI) began collecting and evaluating earthquake test data on nuclear plant equipment. Based on the collective effort of SSRAP, EPRI, industry consultanu, and othm, SQUG developed and submitted Generic Implementation Procedure l
(GIP), Revision 2 to the NRC in February 1992 to resolve USI A-46. The NRC issued Supplement 1 to the Generic Letter (GL) 87-02 which transmitted Supplemental Safety Evaluation Report No.2 ,
(SSER-2) on the GIP in May 1992. The GIP and SSER-2 endorse a methodology which is primarily based on earthquake experience and test data for determining the seismic adequacy of mechanical !
and electrical equipment in operating reactors for the resolution of the USI A-46 issue.
In response to NRC's GL 87-02 Supplement 1, Virginia Power submitted its 120-day response letter O in September 1992 and committed to use the SQUG methodology and commitments set forth in the O GIP, as clarified in SSER-2. In addition, this letter stated that elements of the effort to resolve USI A-46, notably plant walkdowns, will be integrated with the resolution of seismic issue identified in GL 88-20 Supplement 4," Individual Plant Examination for External Events - Seismic". The NRC issued a Safety Evaluation Report (SER) in November 1992 on Virginia Power's proposed implementation to resolve USI A-46. In June 1993, Virginia Power identified specific deviations from the GIP criteria to the NRC. A completion schedule was provided in October 1994. The implementation of the USI A-46 program at North Anna Power Station has followed the GIP /SSER- l 2 methodology and commitments made by Virginia Power in accordance with the completion schedule.
As part of the resolution of USI A-46, conservative, design in-st wre response spectra were developed. These spectra were based on the Design Basis Earthquake 1,BE) ground spectral shape as identified in the North Anna Power Station Updated Final Safety Analysis Report (UFSAR). A DBE for North Anna is identical to the term Safe Shutdown Earthquake (SSE) as defined in the GIP.
A Safe Shutdown Equipment List (SSEL) was developed which included 20 classes of equipment, and tanks and heat exchangers for the following four functions: Reactor Reactivity Control, Reactor Coolant Pressure Control, Reactor Coolant Inventory Control, and Decay Heat Removal. In addition, equipment from supporting systems was included in the SSEL. The SSEL was reviewed by Operations department personnel. A relay seismic functionality review was performed to determine if the plant safe shutdown systems could be adversely affected by relay malfunction in t% ; .
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the event of an SSE. A cable and conduit raceway system review was performed to determine the Q seismic adequacy of these systems.
i The USI A-46 review consisted of plant walkdowns, component screening, analytical reviews, and resolution ofoutliers via analyses or design change modifications. Approximately 1340 SSEL items of equipment, and cable and conduit raceway systems in various areas of the plant were walked down by Seismic Review Teams (SRT) consisting of trained and experienced engineers. The vast majority of these walkdowns were performed by in-house SRTs. Following the walkdowns, anchorage and functionality evaluations, as appropriate, were performed for each group or item of equipment and raceway system. Outliers for approximately 180 items of electrical and mechanical
, equipment, and tanks and heat exchangers were identified. Of these, outliers for about 85% of the l components have been satisfactorily resolved. The resolution consisted of design modifications I
! such as side-to-side bolting of cabinets, and analysis. Approximately 54 pieces of equipment I required modification, and the remaining outliers were resolved via analytical evaluations. In addition, about 35 minor issues related to cable and conduit raceway were identified during the walkdowns, and the majority of these issues have also been resolved. The remaining outliers, which I are primarily related to seismic spatial interaction issues, are planned to be resolved at a later date. l However, it is determined that these outliers do not impact operability for safe-shutdown of the plant during or following an SSE.
A two part evaluation of the seismic functionality of relays was performed. It consisted of identifying relays whose function is essential to safe shutdown of the plant, and then assessing their O seismic ruggedness. No low ruggedness relays were identified at North Anna Power Station. Spot U check of relay mountings, types and locations was performed during the plant walkdowns.
In Februay 1996, a third party or peer review was conducted to assess the implementation of USI A-46 program at North Anna as required by the GlP. This review included walkdown of about 20%
of the items in the SSEL. Although a few open issues were noted at the time of the review, the reviewer concluded that the SRTs involved did an excellent seismic walkdown review at North Anna.
Based on the results of the walkdowns, analyses, and design modification efforts conducted to resolve the USI A-46 issue, it is concluded that North Anna Power Station Units 1 and 2 can be safely . shutdown and maintained in a safe shutdown condition following an SSE.
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1 TABLE OF CONTENTS i SECTION/ DESCRIPTION RAGE i
3 Executive Summary i l Table of Contents iii
! Glossary of Acronyms and Symbols viii 4
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- l. Introduction 11 4
{ l.1 Background 1.2 Scope 1.3 Plant Description
- 1.4 Report Organization i
j 2. Criteria, Procedures, Guidelines, and Assumptions 2-1
] 3. Safe Shutdown Earthquake 3-1 3.1 Safe Shutdown Earthquake and Ground Response Spectrum j 3.2 In-Structure SSE Response Spectra )
i 3.3 Effective Grade of Structures
- 4. Safe Shutdown Equipment Identification 4-1
- 5. Relay Evaluation 5-1
- 6. Mechanical and Electrical Equipment Review 6-1 6.1 Summary of Review 6.2 Seismic Capacity vs. Demand 6.3 Equipment Class Descriptions 6.4 Equipment Anchorage 6.5 Seismic Interaction
- 7. Tank and Heat Exchanger Review 1 7.1 Introduction and Summary 7.2 Discussion of Review I l
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TABLE OF CONTENTS 1 CONTINUED)
V SECTION/ DESCRIPTION l PAGE i
- 8. Cable and Conduit Raceway Review 8-1 8.1 Introduction 8.2 Results of Walkdown 8.2.1 Inclusion Rules Check l 8.2.2 Seismic Performance Concerns Check j 8.2.3 Seismic Interaction I
8.3 Limited AnalyticalEvaluation 8.3.1 Selection Criteria of Non-ductile Supports 8.3.2 Selection Criteria of Ductile Supports 8.3.3 Examples of Limited Analytical Review 8.4 Conclusions
- 9. Third Party Audit 9-1 O
- 10. Significant and Programmatic Deviations from the GIP 10-1 l
- 11. Outliers 11-1 l
11.1 Resolved Outliers 11.1.1 Electrical and Mechanical Equipment i 11.1.2 Tanks and Heat Exchangers 11.1.3 Relays 11.1.4 Cable and Conduit Raceway Systems j 11.2 Unresolved Outliers and Plan for Resolution 11.2.1 Electrical and Mechanical Equipment ;
11.2.2 Cable and Conduit Raceway Systems 11.2.3 Safety Significance and Resolution Plan
- 12. Summary and Conclusion 12-1 l
l 13. References 13-1
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i APPENDICES ;
, - SECTION DESCRIPTION I i
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) APPENDIX A Safe Shutdown Equipment List (SSEL) Report ;
l e Composite SSEL i
- e Seismic Review SSEL
! APPENDIX B Relay Report j.
! e Relay SSEL 1
i i APPENDIX C Third Party Audit Report !
APPENDIX D SVDS and Notes APPENDIX E Resumes and Training Records of Key Personnel l V
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LIST OF TABLES d
e TABLE No. DESCRIPTION PAGE e
- Table 3-1 Structures for which ISRS were Developed and Effective Grade ' 3-3
- Table 5-1 Cabinets in Auxiliary Building Containing Essential Relays 5-2 i
- Table 5-2 Capacity / Demand Comparison of Essential Relays in MCCs 5-3 l Located in Auxiliary Building Table 6-1 Buildings Containing SSEL Equipment 6-5
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1 Table 11.1-1 ' List of Major Resolved Outliers - Electrical / Mechanical Equipment I l-1
. Table 11.1-2 Tank and IIeat Exchanger Equipment Outlier Description Il-5 and Resolution Summary l
1 j Table 11.2-1 List of Outstanding Outliers and Issues Il-9 j ..
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l l p LIST OF FIGURES i
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FIGURE No. DESCRIPTION IMiiE Figure 3.1-1 SSE Horizontal Ground Response Spectrum - Rock 3-4 l (3% and 5% spectral damping)
Figure 3.1-2 SSE Horizontal Ground Response Spectrum - Soil 3-5 (3% and 5% spectral damping)
Figure 5-1 In-Structure SSE Response Spectrum - Auxiliary Building 5-4 elevation 259' - Emergency 480V MCCs (5% spectral damping) l l
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l g Glossary of Acronyms and Symbols
! ABS Amplified (1.5 times) Bounding Spectrum l l
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ALARA As Low As Reasonably Achievable (Radiation)
ASME American Society of Mechanical Engineers BS Bounding Spectrum
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CRS Conservative, Design, in-Structure SSE Response Spectrum DCP Design Change Package i
DBE Design Basis Earthquake, as defined in the North Anna UFSAR (Same as Safe Shutdown Earthquake)
DOC Documentation EPRI Electric Power Research Institute GERS Generic Equipment Ruggedness Spectrum ;
GIP Generic Implementation Procedure, Revision 2 GL Generic Letter l GRS f'
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Ground Response Spectrum lix fleat Exchanger Hz. liertz (cycles per second)
IEEE Institute of Electrical and Electronics Engineers, Inc.
IPEEE Individual Plant Examination of External Events ISRS In-Structure Response Spectrum MOV Motor Operated Valve NAPS North Anna Power Station NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System OSVS Outlier Seismic Verification Sheet PE Professional Engineer pga Peak ground acceleration l
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PSAR Preliminary Safety Analysis Report ROB Rule-of-the-Box item of equipment
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SCE Seismic Capability Engineer j
i SEWS Screening Evaluation Work Sheet
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l SQUG Seismic Qualification Utility Group i
l SRT Seismic Review Team l l l SSE Safe Shutdown Earthquake (Same as Design Basis Earthquake) )
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i j SSEL Safe Shutdown Equipment List SSER-2 Supplemental Safety Evaluation Report No.2, issued by the NRC in May 1992 SSI Soil-Structure Interaction SSRAP Senior Seismic Review and Advisory Panel t
SVDS' Screening Verification Data Sheet SWEC Stone & Webster Engineering Corporation
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r TRS Test Response Spectrum k
UFSAR Updated Final Safety Analysis Report USI Unresolved Safety issue VP Virginia Power ZPA Zero Period Acceleration 1
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- 1. INTRODUCTION O
1.1 BACKGROUND
Seismic qualification of mechanical and electrical equipment in operating nuclear plants was designated as an Unresolved Safety Issue (USI) A-46 by the NRC in December 1980. The concern was that equipment in nuclear plants with construction permit applications docketed before about 1972 had not been reviewed in accordance with the then current criteria for seismic qualification of equipment. A Seismic Qualification Utility Group (SQUG) was formed and developed Generic Implementation Procedure (GIP) for resolving USl A-46. Revision 2 of the GIP was submitted to the NRC in February 1992. The NRC issued Supplement I to the Generic Letter (GL) 87-02 which transmitted Supplemental Safety Evaluation Report No.2 (SSER-2) on the GlP in May 1992. The GIP and SSER-2 endorse a methodology which is primarily based on earthquake experience and test data for the verification of seismic adequacy of mechanical and electrical equipment in operating reactors for the resolution of the USI A-46 issue.
Virginia Power in its September 1992 letter to the NRC committed to use the SQUG methodology and guidelines set forth in the GlP, as clarified in SSER-2. In addition, the letter to the NRC stated that elements of the elTort to resolve USI A-46, notably plant walkdowns, will be integrated with the resolution of seismic issue identified in GL 88-20 Supplement 4," Individual Plant Examination for External Events - Seismic". The NRC issued a Safety Evaluation Report (SER) in November 1992 on Virginia Power's proposed implementation to resolve USI A-46. In June 1993, Virginia Power identified a few specific deviations it took from the GIP to the NRC. A completion schedule was provided to the NRC in October 1994. This report provides the results of the implementation of the USI A-46 program at North Anna Power Station.
1.2 SCOPE The scope of the USI A-46 program at North Anna includes walkdown and evaluation of safe-shutdown equipment, primarily consisting of 20 classes of equipment and tanks and heat exchangers l for the following four functions: Reactor Reactivity Control, Reactor Coolant Pressure Control, I Reactor Coolant Inventory Control, and Decay Heat Removal. In addition, equipment from supporting systems was included. The USI A-46 requirement for the selection of equipment in the SSEL is tha' it can be used to bring the plant to, and maintain it in a hot shutdown condition during the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a Safe Shutdown Earthquake (SSE). Virginia Power chose to include additional components in the SSEL which will be capable of bringing the plant to cold shutdown.
Loss of off-site power is considered to occur simultaneously with SSE. In addition to the SSEL items of equipment, the USl A-46 scope includes identification of relays whose function is essential to safe shutdown, and then assessing their seismic ruggedness. Seismic adequacy of cable and conduit raceway systems is also evaluated via walkdowns and analyses.
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g 1.3 PLANT DESCRIPTION The North Anna Units 1 and 2 Preliminary Safety Analysis Report (PSAR) was filed with the U.S.
Atomic Energy Commission (AEC) on March 21,1969, and Docket Nos. 50-338 (Unit 1) and 50-339 (Unit 2) were assigned. On February 19,1971, Construction Permits CPPR-77 and CPPR-78 were issued for North Anna Units 1 and 2, respectively. )
North Anna Units I and 2 are located on a site on the southem shore of Lake Anna in Louisa County, approximately 40 miles north-west of Richmond. Lake Anna was created by impounding excess waters of the North Anna River and was developed by Virginia Power. Water from the reservoir is used as a cooling medium for surface condensers and other heat exchanger equipment at the North Anna Power Station.
North Anna Units 1 and 2 each includes a three-coolant-loop pressurized light water reactor nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. The balance of the plant was designed and constructed by Virginia Power with the assistance ofits agent, Stone & Webster Engineering Corporation.
The nuclear steam supply system is similar in design concept to several such systems licensed by the NRC, including Virginia Power's Surry Power Station Units 1 and 2. The containments, which I house the major nuclear steam supply system components are steel-lined, reinforced-concrete structures that use dry, sub-atmospheric operation concepts. The containments are similar in design
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v concept to those employed in several projects reviewed by the NRC, including Virginia Power's Surry Power Station Units 1 and 2.
Each reactor unit is designed for an initial licensed core power output of 2775 MWt (this ,
corresponds to a nuclear steam supply system rating of 2785 MWt). This core power will result in a gross electrical output of approximately 907 MWe and a net electrical output of approximately 907 MWe with a circulating water temperature of 75 F, and a net electrical output of approximately 898 MWe with a circulating water temperature of 88" F. Each reactor is expected to be capable of achieving an ultimate core power level of 2900 MWt (this corresponds to a nuclear steam supply system rating of 2910 MWt). This core power would result in a gross electrical output of approximately 984 MWe and a net electrical output of approximately 944 MWe with a circulating water temperature of 75" F, and a net electrical output of approximately 934 MWe with a circulating water temperature of 88" F. Although the license application is for 2775 MWt (core power), all safety systems, including the containment and engineered safety features, were designed for .
operation at the expected ultimate power level. I Fuel was loaded in Unit 1 in December 1977, with commercial operation commencing in June 1978.
Fuel was loaded in Unit 2 in April 1980, with commercial operation commencing in December 1980.
In 1986, both units were uprated to a core power output of 2893 MWt (NSSS Rating of 2905 MWt) with an expected gross electrical output of 982 MWe.
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,m 1.4 REPORT ORGANIZATION t i G
The report organization of the remaining sections is described below:
Section 2 provides the criteria, procedures, guidelines and assumptions used for implementing the USl A-46 program.
Section 3 provides a description of the Safe Shutdown Earthquake for North Anna Power Station.
Ground Response Spectra (GRS) and In-Structure Response Spectra (ISRS) are described and identified.
Section 4 describes how the safe shutdown items of equipment are identified. The SSEL report, the j composite SSEL, the seismic SSEL, and documentation of Operations department review of the SSEL are provided in Appendix A.
4 Section 5 contains a brief summary of the selection and evaluation of essential relays. This section also provides a revised evaluation of the relays in Auxiliary Building from that contained in the relay report. The relay report and the relay SSEL are included in Appendix B.
Sections 6,7, and 8 provide the results of the review for the mechanical and electrical equipment, tanks and heat exchangers, and cable tray and conduit raceway systems respectively, based on plant walkdowns and evaluations.
p Section 9 summarizes the results of the third party audit and resolution of reviewer's comments. The audit report is provided in Appendix C.
Section 10 describes significant and programmatic deviation from the GIP criteria for USI A-46 implementation.
Section 11 describes the outliers that did not met the screening criteria of the GIP. Both the resolved and unresolved outliers are identified. For the unresolved outliers, a plan ofresolution is provided.
Section 12 contains a brief summary and conclusion of the effort to resolve USI A-46 for North Anna Power Station. The main references used in the program are provided in Section 13.
The Screening Verification Data Sheets (SVDS) that contain a summary of the results of seismic verification of equipment are provided in Appendix D.
The resumes and training records of the key personnel, i.e., Seismic Capability Engineers (SCEs) who participated in the walkdowns, and the relay lead reviewers are included in Appendix E. 1 l
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- 2. CRITERI
A. PROCEDURE
S. GUIDELINES. AND ASSUMPTIONS O The GIP, as supplemented by SSER-2, provides the primary criteria for resolving USI A-46 at North i
Anna Power Station. However, during the implementation of the USI A-46 program, the GIP /SSER-
- 2 criteria were enhanced by in-house developed procedures and guidelines, and supplemented by j industry criteria / guidelines.
A brief description of the procedures and guidelines developed in-house is provded below.
e Walkdown procedures and an outlier resolution matrix were developed in a Design Change
] Package (DCP) DC 93-001-3, which also identifies the process for modifications to resolve
] outliers or design deficiencies per Station procedures.
i e Guidance was developed for Seismic Review Teams (SRTs) regarding exceptions taken to l GIP /SSER-2 criteria. This included requiring walkdown of all items of equipment in the j
' seismic SSEL (with the exception of high radiation areas) even if equipment was qualified to IEEE Std. 344-1975.
e A guideline was developed for the use of appropriate Conservative, Design, In-Structure Response Spectra (CRS), which are described in section 3, for various structures at North Anna Units 1 and 2 for the screening and evaluation of equipment in the USI A-46 program.
- Effective grades of all structures housing SSEL equipment were determined per the GIP criteria.
This information was used for the capacity / demand comparisons of a few components which !
were within 40' of grade. A description of these components is provided in section 6.
- A guideline was prepared to evaluate power-operated valves when the valve parameters were j outside the earthquake experience database. It was supplemented by a technical report to j determine seismic motion amplification at valve-operator location for pipe mounted valves. It 4 is noted that the GIP contains Generic Equipment Ruggedness Spectrum (GERS) for Motor Operated Valves (MOVs), but does not provide criteria to estimate seismic demand for
, comparison with the GERS.
- A guideline was developed for SCEs to review essential relays during walkdowns and SEWS j completion, to comply with the GIP requirements.
4 i In addition to the above, other criteria and guidelines such as those developed by SQUG and Electric Power Research Institute (EPRI), and from North Anna Updated Final Safety Analysis Report l
(UFSAR),IEEE Standards 344-1975 and 1987, IEEE Standard C37.98-1987, ASME Section III, NRC Regulatory Guides 1.92,1.100 Rev.1, and 1.122, and Brookhaven National Laboratory Report, BNL 52361 October 1995, were utilized where appropriate, especially for the resolution of
- concerns which did not meet the GIP screening criteria or where the GIP did not provide sufficient guidelines.
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i l No significant assumptions were made, other than those listed in GIP /SSER-2, during the resolution j of the USI A-46 program.
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- 3. SAFE SHUTDOWN EARTHOUAKE 3.1 SAFE SHUTDOWN EARTHQUAKE AND GROUND RESPONSE SPECTRUM j
As identified in the North Anna UFSAR, the earthquake producing the maximum vibratory accelerations at the site is designated the Design-Basis Earthquake (DBE). The Preliminary Safety
- Analysis Report (PSAR) and design for this station were done before the issuance of Appendix A, 10 CFR 100. Accordingly, the term design-basis earthquake has the meaning it had before the i issuance of Appendix A. DBE for North Anna is identical to the term Safe Shutdown Earthquake j (SSE) as defined in the GIP.
, For the purpose of establishing a design-basis earthquake, it was assumed that an earthquake equal l to the largest shock associated with the Arconia Syncline might occur close to the site area. With the ;
, epicenter of a shock similar to the 1875 intensity-VH Arconia carthquake shifted to the vicinity of l i the site, it was estimated that the maximum horizontal ground acceleration at the rock surface would be less than 0.12 g. Accordingly, the design-basis earthquake for structures founded on rock was 1
taken at 0.12 g for horizontal ground motion and two-thirds that value (0.08g) for vertical ground '
motion. For structures founded on soil, the design-basis earthquake was taken at 0.18 g for horizontal j motion and 0.12 g for vertical motion.
i For Seismic Class I structures founded on rock, analyses for earthquake motion were made using response spectra developed by enveloping the response spectra, for various degrees of damping, of l the east-west and north-south components of the Helena (1935) earthquake and the south-east
\ component of the Golden Gate record of the San Francisco (1957) earthquake, all normalized to l
- 0.12g for the horizontal design-basis earthquake. For Seismic Class I structures founded on saprolite j more than 15 ft thick, these analyses for horizontal earthquake motions were normalized to 0.18 g for the design-basis earthquake to provide for calculated amplification through the overburden. The Rock and Soil site Ground Response Spectra (GRS) are shown in Figures 3.1-1 and 3.1-2 j respectively.
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, Based on the two-to-three pulses of strong ground motion for the San Francisco, California (1957),
- and Helena, Montana (1935), earthquakes, a conservative estimate of strong ground motion pulses i
to be experienced at the North Anna site is eight to ten pulses of strong ground motion for the design-basis earthquake.
J The results of the regional seismicity and structural geology update did not provide any basis fbr modifying the original seismic design basis for the site. Additionally, continued seismic monitoring in the region surrounding the site over the last 20 years has not provided any basis to associate the minor seismicity of the region with either Lake Anna or the fault at the North Anna Power Station.
The seismic design for the North Anna Power Station provides adequate conservatism for seismic Class I Structures at the North Anna Power Station.
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ii j 3.2 IN-STRUCTURE SSE RESPONSE SPECTRA
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The amplification of earthquake motion through the structures was con.puted from the SSE ground ,
spectral shape using lumped-rnass models consisting of beams and miffness matrix elements with six degrees of freedom at each node. Time history analyses were used. Structural damping values were consistent with the North Anna UFSAR. New In-Structure Response Spectrum (ISRS) were
- Synthetic time-histories which represent the soil and rock GRS shape were developed. They were of 20 seconds duration defined at a 0.01 second interval. The three time histories for each l orthogonal direction were statistically independent. Previously existing structural models and a
founding conditions were evaluated and refined or recreated as necessary for the USI A-46 program.
j For structures founded on soil, soil structure interaction (SSI) analyses were performed. In the SSI analyses, the building models were used together with the proper impedance and scattering '
! functions. Three SSI analyses were performed, one for each of the following conditions: lower l bound, best estimate, and upper bound soil properties. The resulting spectra from the SSI analyses i
at each nodal point were enveloped from these three cases. An exception was the Auxiliary
[ Building, where the soil foundation was represented by three translational and three rotational soil
, springs in accordance with the previously existing design basis calculations. It is noted that the ISRS (especially the peaks and zero period accelerations) using this method are conservative when compared to the ISRS for other soil founded structures which used SSI with impedance and scattering functions.
I ISRS were developed for 3% and 5% equipment damping at each elevation for each structure
- founded on soil or rock. These ISRS were peak broadened +15% and -15% to account for uncertainties and variabilities in the structural frequencies, in accordance with the UFSAR and NRC Regulatory Guide 1.122. Table 3-1 identifies the structures analyzed, their founding conditions and
- the organization that developed the ISRS.
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~ 3.3 EFFECTIVE GRADE OF STRUCTURES i The effective grade of each structure waich contains SSEL equipment was determined by reviewing i the drawings and performing evaluations as necessary. The effective grade information was used for screening of relays (screening level 1 of the GIP), and for the comparison of capacity and demand l for a few items of equipment which are within 40' of grade as identified in section 6 of this report.
The effective grade of each structure is provided in Table 3-1.
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TABLE 3-1 i
Structures for which ISRS were Developed and Effective Grade Structure Founding Effective Grade pga Organization Condition (horiz.) developing ISRS Reactor Containment Internal Rock 214'-5" 0.12g Virginia Power l Structure Reactor Containment Rock 214'-5" 0.12g Virginia Power
- External Structure Reactor Safeguards Structure Rock 263.6' O.12g Virginia Power i
Main Steam Valve House, Rock 261.5' O.12g Virginia Power j Unit 1 (includes Quench Spray Pump House) 4 a Main Steam Valve House, Soil 261.5' O.18g EQE International l j Unit 2 (includes Quench !
Spray Pump House)
Auxiliary Building' Soil 241.5' O.12g Virginia Power (Q.
l L/ Service Water Pump House Soil 314.8' O.18g EQE International Service Water Valve House Soil 313.7' O.18g EQE International
- Service /rurbine Building 2 Rock / Soil 247.75' (Service 0.12g EQE International j (Including Emergency Diesel building)
Generator Rooms and Control 262.5' (Turbine j Room) building) l Auxiliary Feedwater Rock 269.3' O.12g Virginia Power
) Pumphouse '
] Intake Structure Soil -
0.18g EQE International 1
i Consistent with the Design Basis Analysis, spectra from synthetic time-histories which were used to develop the ISRS matched the rock GRS as defined in the North Anna UFSAR. Three translational and three rotational springs were used to represent soil.
2 The building is mostly on rock, with a small portion on soil. Spectra from synthetic time-histories used to develop the ISRS matched the Soil GRS at 0.12g pga for this building. The soil GRS peak spectral acceleration is higher than the rock GRS, as defined in the North Anna UFSAR. Deconvolution effects were found to be negligible and the building was modeled as a fixed base, surface founded structure, f%
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Notes: . !
pga = 0.12 g :
3.0 % and 5 % Spec. Damping i Accelerations in g's i
Figure 3.1-1
?
NAPS DBE 5% Damped Horizontal Spectrum for Rock Supported Structures !
s.
l 3 '- 4 l t
.____...__________._...__-_._____...______....__._.._._..-._...___.___..._-__m _ ... . .
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-Pga = 0.18 g !
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i Accelerations in g's' '
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Figure 3.1-2 , ,
NAPS DBE St Damped Horizontal Spectrum for Soil Supported Structures !
5 ^ -
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l I
l
- 4. SAFI; SHUTDOWN EOUIPMENT IDENTIFICATION
( )
I The identification of safe shutdown equipment was performed in accordance with the requirements !
of the GIP, as supplemented by SSER-2. A safe shutdown equipment list report, MPR-1201, !
Revision 1, prepared by MPR Associates, Inc., contains the methodology, description and results I of the selection of the SSEL for North Anna Power Station. Since the USI A-46 effort was )
integrated with the IPEEE-Seismic effort, the SSEL report is a combined report for both efforts. l llowever, the report clearly identifies the criteria, methodology and components for the USl A-46 I scope, and those for the additional IPEEE-Seismic scope. The SSEL report, MPR-1201, Revision 1, is provided in Appendix A. The USI A-46 SSEL was reviewed and approved by the Operations Department personnel. The documentation of this review is provided in Appendix A. Appendix A 1 also provides the composite SSEL, i.e., a list containing all USI A-46 equipment (but excluding equipment selected only for IPEEE-Seismic) which was identified from drawings and system review for the four functions / supporting systems discussed below. In addition.the USl A-46 seismic review SSEL, which is a subset of the composite SSEL, is provided in Appendix A. The seismic review SSEL identifies equipment selected for plant walkdown for which Screening Evaluation Work l Sheets (SEWS) were prepared.
The SSEL includes 20 classes of equipment as identified in the GIP, and other items of equipment which are not discussed in the GIP, classified as class 0. It also includes tanks and heat exchangers.
SSEL equipment is selected for the following four functions: Reactor Reactivity Control, Reactor Coolant Pressure Control, Reactor Coolant Inventory Control, and Decay Heat Removal. In (9 addition, equipment from supporting systems was included. Some of the more significant criteria V in selecting the safe-shutdown systems were as follows:
- Safe shutdown is defined as bringing the plant to, and maintaining it in, a hot shutdown condition during the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following an SSE. However, Virginia Power has chosen to include additional components capable of bringing the plant to cold shutdown.
- The safe shutdown should not rely upon off-site power. No accidents or extraordinary I
events are postulated to occur concurrently or following an SSE.
e Single active failure of any item of equipment does not preclude the fulfilment of the safe-shutdown function and the safe-shutdown systems chosen are consistent with the normal and emergency operating procedures which are used to bring the plant to a safe-shutdown condition.
It is noted that subsequent to the preparation of the SSEL by MPR Associates, the list underwent minor revisions primarily as a result of the walkdowns by SRTs, but also because of additional review of systems. These revisions consisted of changes in the equipment class, locations, elevations etc. and also addition or deletion of a few components to/from the list. The significant revisions are identified as follows.
O V 4-1
P 250 Computers (1/2-El-CB-18A,B,C)
V These cabinets were deleted from the seismic review SSEL based on a functionality review, and it was determined that the P250 is not required for safe shutdown following an SSE.
Main Steam Isolation Test Valves and Service Water to Sump Isolation Valves (1-MS-SOV-101 A3/B3/C3,2-MS-201 A3/B3/C3,1-SW-SOV-110 A and 2-SW-SOV-210B)
These valves have been removed from service and are deleted from the seismic review SSEL. As identified during the relay review, no equipment was added as a result of their removal from service.
First Point Feedwater IIeaters (1-FW-E-1A/IB)
These components were deleted from the seismic review SSEL since isolation of the main feedwater i flow path is not required to extend that far back into the main feedwater system. Instead, the Unit '
1 feedwater regulator valves and the main regulator by-pass valves (1-FW-1478,1488,1498; l-FW- l 1479,1489,1499, and associated SOVs), and the corresponding unit 2 valves were added to the ,
SSEL.
j l
Condensate Storage Tanks (1-CN-TK-2 and 2-CN-TK-2) '
These tanks were deleted from the seismic review SSEL since they are not required for safe r shutdown following an SSE. Emergency Condensate Storage Tanks (1/2-CN-TK-1), which are on the SSEL, provide the required safe shutdown ftmetion.
l V 4-2
- 5. RELAY EVALUATION
[m\
V An evaluation of relay seismic functionality was performed in accordance with the requirements of the GIP, as supplemented by SSER-2. The purpose of the review was to verify that safe shutdown systems will not be prevented from performing their safe shutdown functions due to relay (contact) chatter during the vibratory motion associated with an SSE. A relay evaluation report, MPR-1392, Revision 2, prepared by MPR Associates, Inc., contains the description and results of the relay functionality review for North Anna Power Station. This report is provided in Appendix B.
Appendix B also provides the Relay SSEL, which contains cabinets that house e.ssential relays.
In accordance with the relay evaluation guidelines of the GIP, the walkdowns by the SCEs included spot checking of relays for appropriate mounting within the cabinets. Nothing was discovered by the SCEs which would indicate inappropriate relay mounting. Cabinets containing essential relays were walked down by SRTs and evaluated per the GIP guidelines. The relay evaluation concluded that all essential relays have peak and ZP.A capacities higher than their corresponding seismic demand, and no low ruggedness relays were identified at North Anna. However, several cabinets containing essential relays were found to be not connected to adjacent cabinets. As discussed in section 11 and Appendix D (SVDS), most of these cabinets have now been connected together. A few remaining cabinets are planned to be connected in the future as identified in section 11.2.
Subsequent to the completion of the relay report by MPR Associates, Inc., the ISRS for the Auxiliary building were revised. This revision was necessitated because of an inappropriate founding condition previously modeled fbr the Auxiliary building. The revised Auxiliary building ISRS were
(}
' different than those used in report MPR-1392. Therefore, an evaluation was made to determine the i impact of the revised ISRS for essential relays located in the Auxiliary Building. From report MPR-1392, cabinets located in the Auxiliary building which contain essential relays are listed in Table 5- I 1.
For the five relay panels listed in Table 5-1, Level 1 screening criterion of the GIP was used in relay report MPR-1392. Therefore, the Auxiliary building spectra revision has no impact for these panels.
It is noted that cabinets 1-EP-CB-121 A/B are located in the Service Building and not in the Auxiliary building, as was indicated in Appendix H of report MPR-1392. Level I criteria was used for these cabinets also. Since these cabinets are within 40' of grade, there is no change in the conclusions reached in report MPR-1392 for relays in these cabinets. Therefore, only the relays in ,
the four MCCs identified in Table 5-1 are required to be reevaluated for capacity / demand {
comparisons. This evaluation is shown below. !
i The floor spectra for elevation 259' of Auxiliary building are shown in Figure 5-1. The in-cabinet ,
spectra for MCCs are determined per the criteria of GIP, as documented on p. 5-4 of report MPR- !
1392. These in-cabinet spectra are based on multiplying the Auxiliary Building floor spectra by an i in-cabinet amplification factor of 3. The amplified spectral ordinates can be compared to the celay l capacities for both - the peak acceleration value and the ZPA value. The revised seismic densand accelerations for relays in the MCCs are:
t1 V 5-1
~
Floor Demand:
Peak = 1.2 g ZPA = 0.25g In-Cabinet Demand:
Peak = 3.6g ZPA = 0.75g The relay capacities of all the relays in the MCCs are obtained from the G.4 forms in report MPR-
, 1392, and tabulated in Table 5-2. Also shown in this table are the demand acceleration values for comparison purposes. Per Table 5-2, all relays in the four MCCs listed above are acceptable for the revised Auxiliary building ISRS.
4 Table 5-1 Cabinets in Auxiliary Building Containing Essential Relays CABINET MARK DESCRIPTION BUILDING ELEVATION NUMBER
,m) 1' ( *
'N s 1(2)-EP-MC-19 Emergency 480V MCC Auxiliary Building 260' 1(2)-EP-MC-20 Emergency 480V MCC Auxiliary Building 260' 1(2)-EP-MC-21 Emergency 480V MCC Auxiliary Building 260' 1(2)-EP-MC-22 Emergency 480V MCC Auxiliary Building 260' l-EP-CB-115B Relay Panel Auxiliary Building 274' l-EP-CB-115C Relay Panel Auxiliary Building 260' l-EP-CB-116C Relay Panel Auxiliary Building 274' 2-El-CB-115A Relay Panel Auxiliary Building 261' g-CB-116A Relay Panel Auxiliary Building 259' 1
~'
/
V) 5-2 l
Table 5-2 O Capacity / Demand Comparison of Essential Relays in MCCs Located in Auxiliary Building G.4 page Essential Relay Capacity from Demand - Comments Report Type /Model MPR-1392 peak /ZPA MPR-1392 peak / ZPA (g) (g) 7 Main / Aux /OL 4.5/1.8 3.6/0.75 8 Main / Aux /OL 4.5/1.8 3.6/0.75 13 Main / Aux /OL 4.5/1.8 3.6/0.75 15 Main / Aux /OL 4.5/1.8 3.6/0.75 17 Main / Aux /OL 4.5/1.8 3.6/0.75 22 W WL-2 10.0 (peak). 3.6/0.75 Level 1 screening was ZPA >0.75g used. Refer to Appendix B and the note below.
22 Main / Aux /OL 4.5/1.8 3.6/0.75 24 Main / Aux /OL 4.5/1.8 3.6/0.75 25 Main / Aux /OL 4.5/1.8 3.6/0.75 29 Main / Overload 4.5/1.8 3.6/0.75 29 DILOCLb -
3.6/0.75 Operator Action for reset capability is acceptable - refer to Appendix B 40 Main /OL 4.5/1.8 3.6/0.75 43 Main / Aux /OL 4.5/1.8 3.6/0.75 49 Main / Aux /OL 4.5/1.8 3.6/0.75 NOTE: For relay W WL-2 on G.4 p. 22 of MPR report MPR-1392, the ZPA capacity is not explicitly s' *-d in EPRI NP-7147-SL but isjudged to have been >0.75g (demand), based on the high - . spectral value. The Floor and in-cabinet seismic demand for emergency 480V MCCs in Table 5-2 of report MPR-1392 (Appendix B) should be replaced with the peak spectral accelerations and ZPA values given in this section.
5-3
- . . - - - . . . . . - - - - . - - . . . . ~
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8.80 iv iisi i e e i e s i ii i e i i i sei 8.so s.ee so.ee see.ee Frequenow, Hz In-Structure Response Spectrum - Auxiliary Building, Elevation 259' Emergency 480V MCCs 5% SpectralDamping E-W direction (UABN*X259D050B1259)
N-S direction (UABN*Z259D050B1259)
North Anna Power Station
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= 5-4
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.. __ _-. .-. - ~ . = _ - . - .. . . - . _
p 6. MECHANICAL AND ELECTRICAL EOUIPMENT REVIEW 6.1
SUMMARY
OF REVIEW A review of the seismic adequacy of mechanical and electrical equipment in the North Anna Power Station (NAPS) SSEL was performed in accordance with Section 11.4 of the GIP. The equipment j which was reviewed for seismic adequacy is listed on the Seismic Review SSEL and can be found in Appendix A. The list includes equipment mounted in or on other SSEL components and is considered seismically adequate through the Rule-of-the-box (ROB) criteria. The ROB components were inspected for mounting, seismic spatial interaction, and any special vulnerability. Separate SEWS were generally not generated for these items, but deficiencies were noted on SEWS and/or l OSVS containing the host item of equipment, as applicable.
Except for a few components that were in very high radiation areas, each component was walked down and inspected. The few components that were not walked down due to ALARA concerns were
' reviewed by using available plant drawings, equipment installation records, and previously taken photos of the area or equipment.
Each SSEL component was evaluated by an SRT consisting of at least two SCEs; at least one of whom was a registered Professional Engineer (PE). The equipment SEWS (not submitted with this report) provide the details of the screening evaluations. The results of the SEWS were tabulated on SVDSs, which have been reviewed and signed by the appropriate SRT personnel. The SVDSs are O presented in Appendix D. As discussed above, since SEWS were not prepared for ROB components, the SVDS do not include these components.
6.2 SEISMIC CAPACITY VS DEMAND Listed below are the methods used to verify that the seismic capacity of the equipment is greater than or equal to the seismic demand. As required by the GIP, the SVDSs will identify which of these methods were used for each component.
(a) Compare ABS vs. CRS (method used most often)
Plots were prepared comparing the CRS with the ABS. Table 6-1 lists the buildings which contain SSEL equipment along with the elevations at which the ABS envelopes the CRS.
(b) Compare BS vs. SSE Ground Response Spectrum (GRS)
The SQUG GIP Bounding Spectrum envelops the NAPS SSE ground response spectrum at 5%
damping. Therefore, per the GIP criteria, equipment located within 40 feet of effective grade and having natural frequencies greater than 8 Hz. (not applicable to in-line equipment) satisfies the seismic capacity to demand comparison. This criterion was used only for the capacity to demand comparisons of a few components which are listed below (also refer to the SVDS, 6-1
Appendix D).
North Anna Unit 1: l Class 18 level transmitter 1-RC-LT-1470 located in Reactor Containment (RC) - Internal l Structure; and Class 7 valves 1-MS-PCV-101 A,101B,101C, and 1-MS-TV-101 A,101B,101C, 111 A and 11IB, located in Main Steam Valve House (MSVH) were evaluated via the BS vs. I GRS comparison. The RC-Internal structure and the Unit 1 MSVH are both rock founded.
North Anna Unit 2:
1 Class 19 temperature elements 2-RC-TE-2410,2413,2420,2423,2430 and 2433 located in RC-Internal Structure; Class 7 valves 2-FW-FCV-2478,2479,2488,2489,2498 and 2499 located in Service building, and valves 2-MS-TV-201A, 201B and 201C located in MSVH approximately 24' above effective grade, were evaluated by BS vs. GRS comparison. The RC-Internal Structure and the Service Building are both rock founded. Although the Unit 2 MSVH is founded on soil, the major portion of the building rests on concrete fill and structural backfill.
(c) Compare GERS vs. CRS Although limited, there were cases where equipment capacities were based on GERS. For example, Class 8B GERS were used for the capacity of several wall mounted SOVs located in the Reactor Containment building at elevation 308 feet (at this elevation the CRS is not s enveloped by the ABS).
(d) Compare Existing Documentation (DOC) vs. CRS I There were cases where existing documentation was used to determine the capacity of the equipment. For example, many components have been qualified to IEEE Std. 344-1975, especially equipment that was installed after 1980. Although limited, in other cases other available existing test or analyses documentation was used. Refer to Section 10 and Appendix D (SVDS) for a discussion on equipment qualified to IEEE Std. 344-1975 and other available data.
6.3 EQUIPMENT CLASS DESCRIPTIONS The GIP identifies and has developed SEWS for twenty-two (22) unique equipment classes. The equipment on the SSEL was addressed by nineteen (19) of these equipment classes. The three classes for which there are no SSEL equipment are as follows:
Class 9 - Fans (several fans were part of Class 10 - Air Handlers, and are treated as ROB)
Class 12 - Air Compressors Class 13 - Motor Generators O
V 6-2
o The equipment class for each component is provided on the Seismic Review SSEL (Appendix A).
( )
6.4 EQUIPMENT ANCHORAGE in earthquake experience data, lack of anchorage or inadequate anchorage has been identified as a cause of equipment failing to function properly. Therefore, the confirmation of adequate anchorage is a significant part in verifying the seismic adequacy of mechanical and electrical equipment.
Verifying the seismic adequacy of equipment anchorage was based upon a combination of field inspections, analytical calculations, and engineeringjudgement. The SCEs selected the appropriate combination of these elements for each anchorage installation based on the available information.
During field inspections, the SRTs noted anchorage attributes such as equipment characteristics; type, size, and location of anchorage; concrete condition; spacing and edge distance; and gaps. At this time, a review of the structural load path was performed by the SRT. If the SRT could not conclude the adequacy of the load path during the field inspection, load path details were gathered for later analysis. Additionally, a tightness check was perfomied by the SRT or the craft for almost l all accessible expansion anchor bolts. The tightness of the expansion anchor bolts checked were l adequate. This check is documented on the SEWS. Based on this representative sample, there was reasonable assurance of adequate expansion anchor tightness.
l The typical types of anchorage used for the SSEL equipment include concrete expansion anchor bolts, cast in-place bolts, and welds to embedded structural steel (i.e. channels, angles, and Unistrut).
The types of expansion anchor bolts observed were Hilti Kwik-Bolts, Phillips Redhead Self-Drilling i
/9 V
anchor bolts, and Drillco Maxi-Bolts. Based upon review of plant drawings, embedded structural I steel was anchored to the concrete with studs or strap anchors. A few electrical panels were mounted to block walls. Although the exact anchorage for these panels could not be determined, anchorage was determined to be adequate based upon the light weight of the panels (small distribution panelboards) and a " tug test" A tug test was also performed on other components but only on lightweight components where the anchorage appeared robust.
1 In many cases, existing calculations were used to verify anchorage adequacy. Ifexisting calculations l
were utilized, the SRTs would ensure that anchorage configuration noted in the field was the same !
as analyzed and that appropriate seismic accelerations were used. If existing calculations were not {
used, a calculation was performed for all SSEL components with the exception of the few cases ,
where a tug test was performed or where anchorage was judged to be robust by the SRT. !
i information collected during the walkdowns as well as existing plant documentation was used in the verification of the equipment anchorage. Where possible, components in the same equipment class with similar anchorage details were reviewed for a worst case bounding condition. Unless plant documentation showed otherwise, for expansion anchor bolts the minimum embedment depth listed in Appendix C of the GIP was assumed. To date, there have been no cases where existing plant documentation identified embedment depths less than the minimum listed in the GIP.
i in general, equipment anchorage was quite adequate, however, there were a few cases where the i
o 3
(/ 6-3
i
- .1 equipment anchorage was modified or enhanced. Equipment whose anchorage did not meet the GIP j screening criteria was classified as outlier and is discussed in Section 11. '
i 4
6.5 SEISMIC INTERACTION '
1 During the walkdowns, the SRT reviewed the potential for seismic interaction with nearby
! equipment, systems, or structures. Using the guidelines of Section II.4.5 and Appendix D of the GIP, the SRTs documented on the SEWS all credible and significant interaction concems. If simple modifications were possible, such as removing an adjacent unanchored component or an unused and not well restrained flexible conduit, Station Personnel were informed and corrections were made.
4 Typically, Work Orders were issued to correct these type of concerns. 1 i
a Seisinic concems that were not easily corrected were identified on the SEWS and were reviewed j- - further. Several of these concerns were subsequently resolved by plant modifications. Examples of j this include connecting together adjacent electrical cabinets that contain essential relays and l relocating a " stiff" pipe support that was very close to a valve operator. Equipment that could not
- be screened due to a seismic interaction concem was classified as an outlier and is discussed in more ,
- detail in section 11.
t 2,
4 i
i \
)
(Q 6-4
1 Table 6-1 O Buildings Containing SSEL Equipment Building Abbreviation Building Bounded Elevation i
(Note 1)
} AFPH Auxiliary Feedwater Pumphouse All elevations i
AB Auxiliary Building 243' (Note 2)
}
s j RC Reactor Containment (Internal) 252' i
j RC (Ext) Reactor Containment (External) All elevations i
j MSVH Main Steam Valve House 271' (Note 3)
SB Service Building 275' (Note 4) 1 SFGD Reactor Safeguards Structure All elevations I
l SWPH Service Water Pumphouse All elevations SWVH Senice Water Valvehouse All elevations FOPH Fuel Oil Pumphouse All elevations Notes:
- 1. At this elevation and below, the ABS envelopes CRS.
- 2. At elevations 259' and 273', the CRS exceeds the ABS at around 2 Hz and only slightly. l
- 3. The building structural model for the MSVH included the Quench Spray Pumphouse (QSPH)
The ABS envelopes the CRS in these areas.
6-5
1
\
- 7. TANKS AND IIEAT EXCIIANGER REVIEW
- O
7.1 INTRODUCTION
AND
SUMMARY
l Tanks and Heat Exchangers included in the SSEL at NAPS Units 1 & 2 were reviewed in accordance with Section 11-7 of the GIP for the resolution of USI A-46, except for two components - Charging i Regenerative Heat Exchangers 1/2-CH-E-3, which are located in locked room because of high
! radiation, in the containment, for which Virginia Power's Videodisc Information Management System (VIMS) and existing documents were used for evaluation.
l j A total of 110 Class 21 components (tanks and heat exchangers) are identified in the NAPS SSEL.
l Of these,71 components, including 11 rule-of-the-box items, are in NAPS Unit 1; and the remaining j 39 components, including 5 rule-of-the-box items, are in NAPS ' Unit 2.
Field walkdowns were performed by SCEs from Virginia Power (VP) and EQE Engineering Consultants. The SRT members consisted of a minimum of two trained SCEs, at least one of whom was a PE. The field walkdowns and analyses identified 22 components which were outliers. All of these were resolved by analytical evaluations or modification. Section 11 discusses the resolution j of the outliers.
4 44 7.2 DISCUSSION OF REVIEW i
3 The SVDS (Appendix D) provide a summary of the evaluation for tanks and heat exchangers.
Additional details and the methods used to evaluate the acceptability of the USI A-46 criteria for
! those components that were walked down, other than outliers, are discussed below.
Those items of equipment which are mounted on a host component are defined as rule-of-the-box .
(ROB) items per GIP. The seismic adequacy of the ROB items was evaluated along with the host l J component. I i
For all class 21 components, especially large flat-bottom and vertical tanks, the SRTs verified that 4 I
attached piping has adequate flexibility to accommodate vessel displacements.
j Summary of Evaluation of Class 21 IIost Components i
j Component Cooling'. Water Heat Exchanger (1/2-CC-E-1 A /!B) i
?
l-CC-E-1 A & IB are located in the Auxiliary Building. The Heat Exchangers (Hx) were designed by Stone & Webster Engineering Corporation (SWEC). A USI A-46 evaluation of the component and anchorage was performed and found acceptable.
7-1
-. -- - . . . - - . - - _ - -._. - _- . - - - __ - . - . - . - . - . - ~
l l
l
- Seal Water Heat Exchanger (1/2-ClilE-1)
U Both these Hx's are located in the Auxiliary Building. The Hx's were designed by SWEC.
' Subsequently, calculation CE-1170 Rev. 0 was performed and the component, its anchorage and structural sub-components were found acceptable.
Sample Coolers
- There are 24 sample coolers in the SSEL locat:d in the Auxi:iary Building. High temperature l samples pass through these coolers. The coolers are light weight, rigidly mounted on structural frames, which are anchored to wall. They are seismically qualified to IEEE Std. 344-1975. The mounting of the components on the frame, and the anchorage of the frames to the wall wasjudged
- adequate by the SCEs.
4
- Regenerative Hx (1/2-CH-E-3)
J j These components are located in locked recms, because of high radiation, inside the Unit 1 and 2
- Containments respectively. The components were reviewed using existing drawings, documentation ana VIMS. The component was designed by SWEC. Based on the review of a calculation (no.
52308.02-C-007) performed by EQE, it was concluded that there is sufficient margin to meet the USI
, A-46 requirements. The components and anchorages are determined adequate for USl A-46.
Excess L.ctdown Hx (1/2-CH-E-4)
- These components are located inside the Unit I and 2 Containments respectively. The components were designed by SWEC. Based on the review of a calculation (no. 52308.02-C-010) performed by i EQE, it was concluded that there is sufficient margin to meet the USI A-46 requirements. The components and anchorages are determined adequate for USI A-46.
Primary Drain Transfer Coolers (1/2-DG-E-1)
These components are located inside the Unit 1 and 2 Containments respectively. The components were designed by SWEC. A USI A-46 evaluation was performed.. The components and anchorages were found adequate.
Nitrogen Reserve Tanks (1/2-GN-TK-I A/IB)
These components are located inside the Unit I and 2 Containments respectively. The components were designed by SWEC. An existing calculation,12050-DC-16-002 Rev.2, performed by SWEC
, was reviewed, and it was concluded that the components and their anchorage are adequate for the USI A-46 requirements.
4 4
!. O 2-2
Shroud Cooling Coils (1/2-HV-E-6A/6H/6C)
O These components are located in the Unit 1 and 2 Containments. They were designed by SWEC.
During the walkdown, corrosion was noticed on the base plates for the Unit 2 cooling coils. It was judged that the corrosion did not compromise the structural integrity of the base plates. Cleaning, 1 repairing and repainting of the base plates have been performed under Work Orders # 024361,
- 024377 and #024398 for mark numbers 6A, 6B and 6C respectively. The existing SWEC !
calculation was reviewed, and it was concluded that the components and anchorages are adequate for the USl A-46 requirements.
Neutron Shield Tank Coolers (1/2-NS-E-1 A /IB)
These components are located in the Unit 1 and 2 Containments. The coolers are made of 8" diameter pipe, and were designed by SWEC. A USI A-46 calculation was performed and the components and their anchorages were found to be acceptable.
Pressurizer Relief Tanks (1/2-RC-TK 2)
These are horizontal tanks,9'-6" dia. X 20'-0" long, each supported on two saddles on reinforced concrete piers. The tanks are located inside the Unit I and 2 Containments. The tanks were designed by SWEC. The base plate of the saddles had slotted holes in the longitudinal direction for thermal expansion. Calculation CE-0946 was performed to check the adequacy of the anchorage, which was found to be inadequate. Modifications to the anchorage has been performed under DCP-V 92-13-3.
Residual Heat Removal Hx (1/2-RH-E-1 A/1B)
These are vertically supported cylindrical vessels, located in the Residual Heat Removal (RHR) flat, inside the Unit I and 2 Containments respectively. The vessels were designed by SWEC. Upon I reviewing calculation nos. 13075.17-2 and 12050-DC-16-006 performed by SWEC, it was concluded that the anchorage was adequate. Also, EQE calculation 52182-C-034 was reviewed for further verification of the Hx capacity.
Inside Recirculation Spray Coolers (1/2-RS-E-1 AllH/IC/lD)
These are vertically supported cylindrical vessels 3'-2" dia. X 41'-9" tail, located inside the Unit 1 and 2 Containments. The vessels were designed by SWEC. Calculation 11715-NM(B)-297-CBD for the anchorage was performed by SWEC Upon reviewing this calculation, it was determined that the existing anchorages were adequate. During the walkdown, a concern regarding edge distance between 1" diameter Hilti expansion bolt and concrete edge was noted for Unit I component IC only. A USI A-46 evaluation was performed and it was determined that the component and its anchorage were adequate. ;
( 7-3 l
_ _ _ _ . . _ . _ . _ . _ _ . _ _ _ _ _ . _ _ . . _ ~ _ _ _ _ _ _ . _ . _
Chilled Water Expansion Tanks (1/2-HV-TK-6A/6B)
O These are small horizontal tanks with elliptical heads, which are caged within very rugged steel frame, suspended from the ceiling, located in the Service Building. These tanks were designed by SWEC. During the walkdown, the components and their anchorages were judged to be adequate.
Fuel Oil Day Tanks (1-EG-TK-1H/1J and 2-EG-TK-2H/2J)
These are horizontal tanks 9'-8" long, with elliptical ends. The cross section has major diameter of 4'-6" and minor diameter of 3'-9", The capacity of each tank is 1000 gallons. They are located in the Service Building, Diesel Generator Rooms. Each tank is supported on two saddles, which are
. mounted on concrete piers. The tanks were designed by SWEC. A USI A-46 evaluation of the anchorage was performed, and the components and their anchorages were found to be acceptable.
O l
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8.0 CAHLE AND CONDUIT RACEWAY REVIEW t
8.1 INTRODUCTION
Section 3.3.11 of the GIP, Cable and Conduit Raceways, defines that all cable tray and conduit i raceway systems which support electrical cable for equipment on the SSEL should be included in the walkdown. In lieu ofidentifying specific routes of cable runs by plant drawings, etc., the GIP recom. mends that an entire plant walkdown be performed. A seismic verification global plant walkdown was done for all cable tray and conduit raceway support systems with the exception of those areas fed strictly by normal bus feeds (i.e. Turbine Building). The walkdown addressed the inclusion rules, seismic performance concems, and seismic interaction issues as identified in section 8.0 of the GIP. Additionally, outliers that required fixes were addressed by work orders which were issued to correct any observed deficiencies. The Limited Analytical Review of conduits and cable trays selected approximately 20 representative " worst case" conduit and cable tray supports as a result of the walkdown and use of as-built documentation including sketches and calculations.
In accordance with section 8 of the GIP, Cable and Conduit Raceway Review, the review consisted of two parts as follows:
- 1. A plant walkdown in which raceways were evaluated against a set of Walkdown Guidelines.
- 2. An analytical check of the selected worst-case supports using a set of Limited Analytical Review O Guidelines.
V The general screening of conduit and cable raceway systems took into account engineering judgement which is based on assessing these systems in accordance with the GlP Inclusion rules, seismic performance concerns and guidelines developed as a result of earthquake experience data.
The selected worst case examples were then evaluated using a Limited Analytical Review as defined by the GIP in section 8.3. Also, seismic spatial interaction concerns were identified as delineated in section 8.2.5 of the GIP. Items were identified as outliers, which could potentially compromise the seismic adequacy of any portion of the cable and conduit raceway system. Additionally, in accordance with the GIP, all walkdown team members were trained Seismic Capability Engin'eers.
It should be noted that every attempt was made to perform a 100% walkdown, hov ever due to access problems and ALARA concerns in certain areas, drawings were reviewed and judgements were made. Since design fabrication was done by one organization, and the entire conduit and cable raceway system was covered by one set of design criteria, limited walkdown could achieve representative samples for evaluation.
The walkdown of Raceway Systems included use of photographs and preparation of walkdown sketches. Further, remote visual devices such as Binoculars were used during the walkdown.
8-1
8.2 RESULTS OF WALKDOWN d 8.2.1 INCLUSION RULES CHECK
- 1) Conduit and Cable Tray Spans The length of all unsupported spans between adjacent supports were field verified to ensure that they did not exceed the limits identified in GIP. Where the length exceeded it was verified to ensure that the structural integrity of the raceway system including the supports was not affected. There was no exceedance of the cable tray span requirements outside the GIP criteria observed. There were a few instances of conduit span exceedance, however these exceedances were deemed acceptable after limited analytical review.
- 2) Raceway Member Tie-downs Cable tray and conduit systems were inspected to ensure that for cantilever bracket type supports, the trays or conduits were secured to their supports such that they would not slide during a seismic event. No cable tray or conduit systems that had cantilever bracket supports were found with cable trays or conduits not secured to their supports with one conduit exception, in which a work order was issued to correct this deficiency.
' 3) Channel Nuts
\ There were no channel nuts observed without teeth or ridges stamped into the nuts where they bear ou the lip of a channel.
- 4) Rigid Boot Connection There were no conduit or cable tray supports with rigid boot type connection, based upon walkdowns and drawing reviews, as delineated in GIP. ,
- 5) Beam Clamps No beam clamp outlier type supports were noticed during the walkdown.
- 6) Cast-Iron Anchor Embedment No cast iron embedments could be identified during the walkdown. Existing documents were l
reviewed and no cast iron embedments were located. I I
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8.2.2 SEISMIC PERFORMANCE CONCERNS CHECK V
- 1) Anchorage Based upon walkdown and limited analytical reviews, it was noted that cable tray and conduit supports were well anchored, with capacity exceeding demand. SWEC, the primary Architect /
Engineer for North Anna Power Station, performed a study on the seismic capacity of rod hung cable tray supports. The study evaluated many bounding multi-span rod and unistrut hung cable tray supports. A rod fatigue evaluation was performed on the supports and as a result lateral ductile-type braces with clip angles were added to provide lateral support for multispan rod and unistrut hung cable tray supports and thus minimized fatigue affects on rods. l The limiteo snalytical review shows in all cases sufficient anchorage capacity. l
- 2) Cracks In Concrete No visible cracks in concrete at the location of anchorage were found during the walkdown.
There were some evidence of surface cracks, however these were judged insignificant from ,
their size or location with relation to the supporting system.
l
- 3) Corrosion
\ Corrosion of conduit support clamps and conduits were noted in some locations. These areas were generally located in areas where general dampness exists, such as the Service Water Pump House and Auxiliary Feedwater Pump House. Only surface rust was noted and no significant degradation of supports and raceway was observed.
- 4) Sag of Conduit and Cable Trays No noticeable sag of conduits or cable trays were observed.
- 5) Broken or Missing Components Several broken and missing components of the conduit and cable tray and their supports were noticed. Several work requests were issued to correct these deficiencies. All of the broken and missing components were identified and will be repaired or replaced as defined in the work orders as listed in the unresolved outlier section of this report. The condition of the raceway system were evaluated with the broken or missing components and found by engineering judgement to not constitute an operability concern.
8-3
- 6) Restraint of Cables O All cables were found to be adequately restrained when they were found to be above the top of the side rail or in cable trays that have vertical drops. There were a few instances though of cable coiled up in cable trays to be used in future cable runs in the Emergency Switchgear room.
These were noted and work orders were issued to correct this excess abandoned cable. No operability concerns were determined from the abandoned cable.
l 7) Aging of Plastic Cable Ties Plastic type cable ties were found to be adequately connecting cable to cable trays during the
, walkdown. The plastic ties were in good condition and did not exhibit any deterioration. Some tug tests were done to randomly sample these ties with no occurrences of failures.
{
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- 8) liard Spots One potential hard spot on the cable tray run was noticed as a possible lateral hard spot to the 3 cable tray in the Emergency Switch Gear room. This was reviewed as part of the Limited j Analytical Review and was determined to be not a concern. No hard spots such as an isolated rigid support in a long run of raceway were found during the walkdown.
8.2.3 SEISMIC INTERACTION
. Seismic Interactions were verified during the walkdown. The interactions that were verified were:
j Potential Proximity Effects, Structural Failure and Falling, and Flexibility of Attached Cables.
l The effect of proximity of cable tray and conduits near a block wall was evaluated under Block i Wall Evaluation that is being performed by EQE Engineering. There were seismic interaction concerns found during the walkdown, however all concerns were covered during the SSEL 4
equipment walkdowns and were addressed in the SSEL Walkdown Section of this report as either 1
housekeeping or interaction outliers.
8.3 LIMITED ANALYTICAL EVALUATION Several typical Raceway supports were selected for limited analytical evaluation. One of the typical l type includes a fixed-end rod hanger trapeze support . This was evaluated for fatigue efTects. Other
! types of supports selected for review include floor-to-ceiling supports and base-mounted supports.
, There were a few heavily loaded conduit supports in which cantilevered sections were examined.
. The following criteria was used in determining and selecting worst case surorts for the Limited
- Analytical Review
In accordance with the criteria provided in the GIP Section 8, Cable and Conduit Raceway Review, 4 there are two basic types of supports, ductile and non-ductile. Each type of support has its own characteristics which defines it as will be stated later and its own potential failure mechanism. In 8-4 4
_ _ . . . _ _ . _ . _ _ . - . _ . _ . . _ . _ . . _ . _ . . _ _ _ _ _ _ . - _ _ _ ~ _ .
3
!' selection of the worst case (bounding) support calculations for North Anna, extensive walkdowns as well as the research into existing support calculations were performed. Using this combined !
4 method of selection, it was most apparent which examples would bound the worst case examples and
- thus meet the intent of the GlP criteria.
8.3.1 SELECTION CRITERIA OF NON-DUCTILE SUPPORTS The following listed criteria was generally used in selection of the representative samples of non-ductile supports.
)
- 1. The supports chosen were the most heavily loaded with cable or conduit and braced rigidly.
- 2. All types of supports, i.e. floor to ceiling, free standing base mounted frames, cantilever, etc.
were considered in making selection of bounding calculations.
- 3. An examination of anchorage conditions was performed to determine vulnerability to failure. In general bolted connections were chosen over embedded unistrut type connections which tend to generally have greater capacity.
8.3.2 SELECTION CRITERIA OF DUCTILE SUPPORTS O
V The following listed criteria were generally used in selection of the representative sample of ductile type supports:
- 1. The supports chosen were the most heavily loaded with conduit or cable trays and represented worst case configuration. ,
- 2. For evaluation of fatigue effects, the threaded rod type supports with the shortest distance between conduit and/or cable trays to the ceiling and the most number oflaterally unbraced bays were chosen as the representatives.
- 3. Since there were several types of hybrid ductile type supports, the worst case geometry and fixed I end conditions were examined. Those seem most susceptible by judgement to lateral effects, especially on anchorage end conditions were chosen.
- 4. All types of. ductile supports were considered, ceiling hung, combination wall and ceiling, I cantilevered threaded rod, and etc.
- 5. An examination of anchorage size and rod size was performed to select the worst case examples.
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1 Mi 8.3.3 EXAMPLES OF LIMITED A.NALYTICAL REVIEW O The following is a list of examples that were chosen for Limited Analytical Review of cable tray and ,
conduit supports per the GIP procedure and criteria:
Example 1: Ceiling mounted heavily loaded portal ductile conduit support frame located inside Unit 1 Containment.
Example 2: Base / Floor mounted unistrut post supporting 4 layers of 3" conduits located inside
- Unit 1 Containment. This was considered as a non-ductile support.
- Example 3: Floor to ceiling conduit support frame inside Unit 1 Containment. This was
) considered as a non-ductile support.
j Example 4: Wall mounted rigid conduit support located inside Unit 1 Containment. I j Example 5: Base / Floor rnounted non-ductile frame cable tray support located inside Unit 2 ;
i Containment. l
- Example 6
- Ceiling mounted 6 tier trapeze ductile cable tray support located inside Unit 2 j Containment.
)
i Example 7: Welded to floor steel beam junction box and conduit support frame located inside Unit 1 Containment.
l Example 8: Base / Floor mounted multiple bay non-ductile conduit support frame located inside )
! Unit 1 Containment.
]
j Example 9: Ceiling supported trapeze short rod hung cable tray located inside Unit 2 I l Containment, i
! Example 10: Rod hung 7 tier trapeze ductile cable tray support in the Cable Tunnel area.
Example 11: Ceiling mounted 6 tier trapeze ductile support for 36" wide cable trays in the L Emergency Switchgear Room. One side of the trapeze is rod hung and the other side is supported by unistrut.
4 i
- Example 12
- Wall mounted L frame non ductile seismic conduit support located in various
,i buildings.
i j Example 13 : Ceiling mounted L frame non-ductile seismic conduit support in various buildings.
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1 J
s
Example 14 : Ceiling mounted portal frame seismic non-ductile conduit support in various O
V buildmgs. i Calculations for the above listed examples are maintained in the USI A-46 project file. :
8.4 CONCLUSION
S i The results of the walkdown and review of documentation of cable tray and conduit supporting >
systems showed that all systems were adequately supported in accordance with GIP Section 8 i guidelines. Additionally, the intent of the inclusion rules were met and the seismic performance concerns and seismic interactions showed general compliance with a few outliers noted. Work orders were issued and / or analytical reviews were used to address outlier concerns. !
The Limited Analytical Review showed most ductile & non-ductile supports met the three times deadload check. Additional checks on the lateral load and redundancy were used when the deadload check was exceeded and all bounded supports met these criteria. , Fatigue evaluation was ;
performed on rod hung supports and found acceptable. Non-ductile supports were shown to have significant capacity and were generally found to be the conduit type supports. l In conclusion North Anna Unit 1 & 2 has adequate seismic capacity ofits cable tray and conduit ,
supporting systems to meet seismic demand requirements.
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~- . - . - - . - - - _ _ _ . - - - - - . - - - - - - - - - - -
2 9. THIRD PARTY AUDIT
- A third party audit or peer review was conducted by Structural Mechanics Consulting, Inc. for the S USI A-46 program at North Anna Power Station. The review was integrated with the IPEEE-l Seismic program at North Anna. The purpose of the third party audit was to obtr.m an independent i assessment of the walkdowns and analyses by audit and sampling. The rr, view took place in February 1996, and consisted of about three days of plant walkdown feilowed by review of -
documentation. Approximately 20% of the items from the Unit 1.md l' nit 2 SSELs were pre-selected by the peer reviewer and Virginia Power SCEs representing all classes of equipment. -
Review comments were made on generic issues and 148 specific Unit I and 2 components.
I l [
j It is noted that at the time this review was conducted, the walkdowr,s of electrical and mechanical '
I equipment, tanks and heat exchangers, and cable and conduit raceways were essentially complete. )
However, the preparation of OSVS, SVDS, and closure of upen issues including anchorage evaluations and other analyses were still in progress. The reviewer, while indicating that the seismic 3
walkdowns at North Anna were performed in an excellent manner, noted a few generic and component specific open issues. The results and conclusions of the peer review are provided in Appendix C. The resume of the peer reviewer is provided in Appendix E.
l Subsequent to the third party review, the open issues iaentified by the reviewer have been resolved, j with a few minor exceptions. The resolution o the proposed resolution of the generic and
- comnonent specific open issues identified in the r,eer review are noted below. It is also noted that l several of the issues identified by the peer reviewer were resolved immediately following the' peer
, review, but prior to the issue of the peer rev:ew report. Therefore, the closure of such issues is j discussed by the peer reviewer in Appendix C. l i
)
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! Larn_e Transformes:
1 j The 4160/480 transformers were quMified by seismic bi-axial, multi-frequency shake table testing i
by ITE. Thus the transformer coils not being top-braced laterally is not an issue. An analysis of the j bounding case of the anchorage of all 8 transformers together with the emergency bus switchgear
' (which is part of the unit supphed by ITE) has been ferformed. The transformers are determined to be adequate for operability, however, the io!Sw;ng issues are outstanding, as is also noted in the i outlier section of this report. (a) In some of the transformers, a slight gap exists between the friction
, hold down clip and the base channel which holds the coils. This gap will be closed, as needed, (b)
The transformer anchorage and/or load path to the adjacent cabinets will be further reviewed, and
! (c) Some of the nuts were found loose on the bolts which connect the heavy coils to the base
- channel. The nuts have been tightened for six of eight transformer units. The nuts will be inspected
, and tightened, if r'. quired, on the remaining two transformers.
i
- Florescent Liehts and Fire Extineuishers i
Upon further review and walkdown, all the Virginia Power SCEs agreed with the peer reviewer that
{ 9-1 4
4
I i
covers or other attaclunents are not required on the florescent lights. The light tubes are not heavy enough and would not be expected to cause a hazard to SSEL components. In addition, the SCEs also concluded that fire extinguishers on hooks cannot become loose during a strong shaking. These issues are considered closed.
Spacers for Batteries 5
A subsequent walkdown was performed by the SCEs for the batteries and it was found that there is i
~
no cell in any battery assembly at North Anna adjacent to which there are no spacers or tie rods.
Thus the cells cannot impact each other. The battery manufacturer was contacted and stated that new batteries which have been seismically tested, contain only tie rods between cells but not necessarily 4
Styrofoam spacers. Therefore, this issue is considered closed.
I Control Room Issun
- The control room ceiling support arrangement is planned to be further reviewed as stated in section l 11.2. The indicator lights on vertical boards were revisited by a trip to the North Anna Station ;
i Control Room on March 17,1997 by three SCEs. Control Room operators were interviewed j
)
regarding their reliance on the annunciator lights and other vertical board indicator lights. It was j stated by the operators that procedures exist, such as procedure 1-AP-6, that would allow them to l l
- shut the plant in case of failure of some of the indicator lights during a strong motion earthquake.
i Based on this information, this issue is considered closed.
l l Specific Comnonent Related Issues For a few components, an anchorage calculation was not available at the time of the peer review.
This was noted by the reviewer. These calculations have now been completed. Other component specific issues have been resolved or are planned to be resolved as follows:
4
! Vertical Pumps (Equipment Class 6): i 4
2-RS-P-2A,2B (Outside Recirculation Spray Pumps): Anchorage and other issues have been resolved.
I Fluid-Operated Valves (Equipment Class 7):
i i
$ l-MS-TV-109 and 110 (Containment Isolation valves - IPEEE scope only): The previous interaction j concern due to small clearances was re-evaluated by a walkdown on 3-17-97 by two SCEs and j determined to be acceptable. No further action is required.
1
! 2-CC-TV-200C (Return from Cooling Coil - Cont. Isolation Valve - IPEEE scope only): A re-l walkdown on 3-17-97 by two SCEs concluded that the %" clearance is sufficient considering the
- support configuration. Therefore, the interaction issue is considered to be resolved.
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Air Handlers (Equipment Class 10):
1-HV-AC-1,2; 2-HV-AC-8,9 (Control Room Air Conditioners): All caveats have been resolved.
Therefore, all issues associated with these components are considered closed.
Flow Switch (Equipment Class 18):
1-HV-FS-1215C (Flow switch): The previous interaction concem due to small clearance was re-evaluated by a subsequent walkdown by the SCEs involved and was determined to be acceptable.
Control Panels and Cabinets (Equipment Class 20):
1-El-CB-18A, B, C (P250 Computer I/O Cabinets): It was unclear to the SCEs and to the peer reviewer if the computer cards inside the cabinets are well restrained. However, an evaluation was performed to determine if these cabinets would be required for safe-shutdown. It was concluded that these cabinets can be removed from the SSEL. Thus no further evaluation of the cards is required.
1-EP-CB-28H (SW Logic Cabinet l A): This cabinet contains essential relays. A clearance of 3/8" in the front and 3/16" in the back is noted with an adjacent cabinet. The cabinet was analyzed and it was concluded that the cabinet deflections during the strong motion portion of an SSE will be small so as to preclude any impact with the adjacent cabinet. Therefore, this interaction concern is resolved. In addition, an anchorage evaluation of this cabinet has been performed.
I l-El-CB-301 C (EI/ Control Panel): Housekeeping issues in the vicinity of this cabinet were identified in the SEWS. There are other SSEL items which have similar concerns. The Station has been notified regarding this issue and section 11 discusses the proposed action and schedule. "
Tank (Equipment Class 21):
1-CC-TK-1 (Component Cooling Surge Tank): The potential interaction of a handrail with the tank was reviewed in a subsequent walkdown by the SCEs, and it wa.s determined that the interaction is not credible.
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i
- 10. SIGNIFICANT AND PROGRAMMATIC DEVIATIONS FROM THE GIP
-v -
There are no significant deviations from the GIP that were used in the USI A-46 program at North Anna Power Station. The following two programmatic deviations from the GIP and SSER-2 were identified to the NRC staffin Virginia Electric Power Company letter Serial No.92-763, dated June 29,1993, and were used during the implementation of the USI A-46 program:
(a) When a component on the safe shutdown list is seismically qualified per the criteria of RG 1.100, Revision 1 and IEEE Std. 344-1975, this qualification was used in lieu of conducting an evaluation per GIP. Further, ifit was found that the anchorage / mounting of the equipment was similar to the anchorage / mounting during testing, then no further evaluation of the anchorage was performed. However, a walkdown of each item of equipment on the seismic review SSEL was performed to verify any interaction concerns.
l (b) Where previously performed anchorage calculations existed, they were reviewed. This review t
was performed to ascertain that the seismic acceleration used before are equal to or greater than the accelerations from the approved in-structure spectra for the USI A-46 program. If these previous calculations were in conformance with the licensing or design basis criteria and methodologies of North Anna Power station, no revisions were made to bring them into conformance with ie UIP and SSER- 2 criteria and methodology, unless walkdowns or review indicated non- conformance to the design basis configurations or criteria.
O Examp!cs of the above and a few other minor exceptions / deviations from the GIP that were used in the seismic verification of equipment, including tanks and heat exchangers, are listed below.
J' (a) Emergency Condensate Storage Tanks (1/2-CN-TK-1) are flat bottom tanks which are l unanchored. No guidelines are provided in the GIP for their evaluation. These tanks were evaluated using an industry approved method identified in " Seismic Design and Evaluation Guidelines for the Department of Energy High Level Waue Storage Tanks," prepared for the U.S. Department of Energy by Brookhaven National Laboratory (BNL), BNL 52361, January 1993. The tanks are adequate for North Anna's DBE condition. In addition, using the median centered spectra of NUREG/CR-0098 evaluated as the Review Level Earthquake in the IPEEE-seismic program, the tank HCLPF capacity is 1.33 times the pga of North Anna's DBE.
l (b) A similar method as the Emergency Condensate Storage Tanks (i.e., use of report BNL S2361) was also used for the evaluation of flat bottom Refueling Water Storage Tanks (1/2-QS-TK-1).
- These tanks are, however, anchored to concrete foundations. Using the BNL approach, these tanks have adequate safety margin for North Anna's DBE condition. In addition, using the j median centered spectra of NUREG/CR-0098 evaluated as the Review Level Earthquake in the IPEEE-Seismic program, the tank HCLPF capacity is 1.5 times the pga of North Anna's DBE.
l (c) Service Water Pumps and their supports were qualified using an existing vendor seismic j qualification report which was supplemented by an in-house calculation. The qualification 10-1
p)
( .
concluded that the operability of the existing pumps is maintained in accordance with GL 91-
- 18. However, the pumps are beina modified by replacing the A 307 flange bolts with A-193 Grade B7 bolts and the pumps n also being replaced by new pumps. These modifications are being implemented by a design change package. The modified / replaced pumps will meet seismic qualification and all other design basis requirements.
(d) Westinghouse Reactor Trip Breakers 1/2-EE-BKR-RTA, RTB, BYA, BYB were qualified using Westinghouse Seismic Test Report WCAP - 7817 which is based on IEEE Std. 344-1971 requirements. Since the testing enveloped the CRS in the applicable frequency ranges (sine beat test), the testing was acceptable and is considered to meet the requirements of the 1975 version of this IEEE Standard.
(e) Several Rosemount transmitters and ASCO solenoid valves were qualified using existing vendor qualification reports which indicated that the equipment is qualified to the IEEE Std.
344-75 requirements.
-(f) A few items of equipment such as 1-RC-PT-1472,2-RC-PT-2472, and 2-RC-PT-2457 are qualified using seism;c qualification performed under Regulatory Guide 1.97.
(g) A few valves, such as 1-GN-PCV-125A-1,125A-2,125B-1,125B-2; 1,2-RC-SOV-1455C-1, 1455C-2,1455C-3,1456C-1,1456C-2,1456C-3,1-SS-TV-107A, and 1-SS-TV-109A have been qualified using previously completed effort documented in Design Change Packages (DCP) that O were used to install these valves. The DCPs indicated that these valves are qualified to IEEE Std. 344-1975 requirements.
(h) A few transmitters, such as 1-FW-LT-1475,1484,1485,1486,1487,1494,1495,1496 and 1-QS-LT-100A,100B,100C,100D have been qualified using DCPs that were used to install these transmitters. The DCPs indicated that these transmitters are qualified to IEEE Std. 344-1975 requirements.
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,_ 11. DUTLIERS
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11.1 RESOLVED OUTLIERS As a result of the USI A-46 walkdowns, several outliers not meeting GIP caveats and/or criteria were determined. These outliers were resolved by analysis and/or modifications to meet the USI A-46 requirements. In accordance with section 5.2 of the GIP, resolved outliers are grouped by electrical '
and mechanical components on the SSEL, tanks and heat exchangers, relays, and cable and conduit
- raceway systems. Listed below are the resolved outliers for each of the four sections described above.
I1.1.1 ELECTRICAL AND MECHANICAL EQUIPMENT 1
j Outliers in this group are for active electrical and mechanical equipment in classes 0 through 20.
An outlier is defined when any portion of the four sections of the Screening Evaluation Work Sheets
, (SEWS)- Capacity vs. Demand, Caveats, Anchorage, and Seismic Interactions - does not meet the l c3tablished screening criteria. Table 11.1-1 provides the list of the resolved outliers for Electrical / Mechanical components.
Table 11.1-1 List of Major Resolved Outliers - Electrical / Mechanical Equipment ITEM CLASS MARK NUMBER DESCRIPTION OF RESOLUTION NO. OUTLIER I 01 1-EP-MC-21,22 Motor Control Centers MCCs were connected to
- 2-EP-MC-21,22 (MCC) cabinets containing each other or to the wall,
- 2-EP-MC-50,51 essential relays, have as required, by DCP 95-j interaction between 017 and the outliers were cabinets, and in some resolved a
cases with adjacent wall
! 2 02 1-EE-BKR-BYA, BYB Reactor Trip Breakers, WCAP-7817, rev. 6 data 1-EE-BKR-RTA, RTB concern over side-to- side showed adequate capacity 2-EE-BKR-BYA, BYB breaker restraint of restraint design 2-EE-BKR-RTA, RTB 3 04 1-EE-ST-lH,1) Transformer mounting Transformer mounting 1-EE-ST-l H 1, IJ 1 nuts were found loose and nuts were tightened.
2-EE-ST-211, 2H 1 required tightening 4 07 1-GN-PCV-125 A-3, Loose nuts attaching Nuts tightened per station 125B-3 PCV's to base plates were issued work orders found l
O V 11-1
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f 1
- Table 11.1-1 (Continued) 1 4
ITEM CLASS MARK NUMBER DESCRIPTION OF RESOLUTION e NO. OUTLIER l
5 07 2-MS-TV-201 A,B,C Grating adjacent to air Air lines were not required lines was not proper'y for proper operational secured mode per Systems Engineer
?
6 07 2-RC-PCV 2455C Seismic interaction DCP 94-012 corrected 4
concern with adjacent interaction concerns structure 7 08A 1-SW-MOV-101 A,B,C,D Concern over Capacity Capacity exceeds detrand l
, 2-SW-MOV< 201 A,B,C,D vs. Demand by less than 10% in the narrow frequency
- range (10.5 to 11,5 Hz),
3 therefore intent of the GIP is met
- 8 08B 2-RC-SOV-2455C 1,2 Seismic interaction with Interaction resolved per
! adjacent SOV's DCP 94 012 i a
' l 9 08B 2-RC-SOV-2456 Seismic interaction with SOV was replaced with adjacent SOV's Nuclear Grade ASCO and fixed to prevent interaction
\ 10 10 1-ilV-AC- 1, 2 Anchorage has greater Anchorage evaluated and
- 2-IIV-AC. 8,9 than 1/4" gap, adjacent found acceptable; interaction concern. One interaction concern l anchor bolt missing on 2- removed. Missing anchor
- HV-AC-9 bolt installed on 2-HV-A C-9, f
- 11 14 l-BP-SW-1,2 Mounted to block wall Anchorage found 2-BP-SW-1,2,3,4 acceptable l 12 16 1-VB-I-04 Transformer missing two Missing Bolts replaced bolts
, 13 20 l(2)-El-CB-23 A,B C All Cabinets contain All cabinets connected
- l-El-CB-44 essential relays and were together by DCP 93-015-3, j l(2)-El-47A,C,E,F not attached to adjacent j 1-E P-28 A,B,C.E.F,G,H,J cabinets, therefore were l 2-EP-28A,B,E,F interaction outliers due to l 1(2)-EP-48A essential relays i 1(2)-El-64 A,B i
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J 11.1.2 TANKS AND 11 EAT EXCIIANGERS
{Q The tanks and heat exchangers included in the SSEL at NAPS Units 1 and 2 were evaluated in i
accordance with Section 11-7 of the GIP. A total of 110 components were evaluated in this equipment class, including rule-of-the-box items. Twenty-two components with outliers were identified. All the outliers have been resolved via modification (1-CC-TK-1) or analysis.
4 j Table 11.1-2 summarizes the outliers and their resolution for tanks and heat exchangers. Additional i discussion is provided below.
1 j Component Cooling Surge Tank (1-CC-TK-1)
The tank is a 7'-6" diameter x 10'-6" high cylindrical overhead steel tank supported on four W6x20 column legs in the Auxiliary Building, Unit 1. The tank serves as a make-up tank to Units 1 and 2.
The tank was originally designed by SWEC. An evaluation of the tank support legs concluded that the existing supports did not meet the plant design basis. Further evaluation and necessary hardware modifications to the supports have been perfomied per DCP 96-020 to meet the design basis requirements with sufficient margin. A USI A-46 evaluation was performed with the modified supports and anchorage and they were found to be acceptable.
Boric Acid Storage Tanks (1-CII-TK-1 A/IB /1C)
O The tank is a 12'-0" diameter x 12'-11" high cylindrical overhead steel tank, supported on four W8X31 column legs. Tank 1 A and 1B are at elevation 244' and 274' respectively, in the auxiliary building, Unit 1. Tank IC is at elevation 274' in the Auxiliary Building Unit 2. The tanks were originally designed by SWEC The support legs & anchorage were evaluated per guidelines of the GIP, and were found to be acceptable.
Chemical Volume Control Tank (1/2-CH-TK-2)
The tank is a 7'-0" diameter x 9'-6" high cylindrical overhead steel tank, supported on four W6X20 column legs. Both tanks are located in the Auxiliary Building. The tanks were originally designed by SWEC. The support legs & anchorage were evaluated per guidelines of the GIP, and were found to be acceptable.
Boron Injection Tank (1/2-SI-TK-2)
The tank is a 4' diameter x 13'-4" high cylindrical overhead steel tank, supported on four W10X45 column legs. Both tanks are in the Auxiliary Building. The tanks were originally designed by Westinghouse. The support legs and anchorages were evaluated per the GIP guidelines and were found acceptable.
O Q l 1-3
l Air Compressor / Air Receiver Tanks (1-EG-TK-111A/IIIB/lJA/lJB and 2-EG-TK-( 211A/211B/2JA/2JB)
The tank is a 2'-6" diameter x 8'-7" high cylindrical overhead tank, supported on four 4"x 4"x 5/8" angle legs with 5/16" thick steel skirt around. The tanks are located at elevation 270' in the Diesel -
Generator Rooms in the service Building. The tanks were originally designed by SWEC. The i support legs & anchorage were evaluated per guidelines of the GIP, and were found acceptable.
)
EDG Underground Fuel Oil Storage Tanks (1-EG-TK-2A/2B)
These are 8'-0" in diameter x 53'-0" long underground buried tanks, with 50,000 gallon capacity, located in the yard area. The tanks were originally designed by SWEC. Since the piping was buried, the flexibility of the piping was assessed, which wasjudged to be adequate, hence acceptable.
Emergency Condensate Storage Tanks (1/2-CN-TK-1)
These are 28' diameter x 29'-9" high, flat bottom, vertical tanks, each with 110,000 gallons of condensate water storage capacity. The tanks are located in the yard, on concrete mat foundation, t
and are unanchored. The tanks are protected by a 2'-0" missile shield concretejacket wall all around, !
which itselfis anchored to the foundation. There is a 2" rattle space in between the outside of the )
tank and the inside of the concretejacket walls, which is filled with 2" rotofoam. The tanks were 1 l originally designed by SWEC. The tank shell and tank stability were evaluated per the guidelines
' O of Brookhaven National Laboratories report, " Seismic Design and Evaluation Guidelines for the O Department of Energy - High Level Storage Tanks and Appurtenances", BNL-52361, January 1993.
- This report contains guidance for the evaluation of unanchored tanks. The intent of the evaluation was to provide an estimate of the tank capacity for SSE, and the tank was determined to be acceptable. In addition, using the median centered spectra of NUREG/CR-0098 evaluated as the Review Level Earthquake in the IPEEE-seismic program, the tank HCLPF capacity is calculated to be 1.33 times the pga of North Anna's DBE.
l Refueling Water Storage Tanks (1/2-QS-TK-1) i The Refueling Water Storage Tanks are large flat bottomed water storage tanks 38' dia. x 62'-7" high, !
mounted in the yard, with a nominal capacity of 480,000 gallons. The tanks were designed by SWEC. A similar method as the Condensate Storage Tank was also used for the evaluation of flat bottom Refueling Water Storage Tank. This tank is, however, anchored to a concrete foundation.
The tank has adequate safety margin for North Anna's DBE condition as documented in EQE calculation 52308.04-C-004. In addition, using the median centered spectra of NUREG/CR-0098 evaluated as the Review Level Earthquake in the IPEEE-seismic program, the tank HCLPF capacity is calculated to be 1.5 times the pga of North Anna's DBE.
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n Table 11.1-2 Tank and IIcat Exchanger Equipment Outlier Description and Resolution Summary Equipment Location Outlier Description Outlier Resolution Status Mark No.
1 -CC-TK-1 Aux. El. 298' Tank on Legs Analysis / modification - Closed calculation # CE-1092 ,
1-CH-TK-1 A Aux. El. 244' Tank on Legs Analytical evaluation Closed 1-CH-TK-1 B Aux. El. 244' Tank on Legs Analytical evaluation Closed i
1-CH-TK-1 C Aux. El. 274' Tank on Legs Analytical evaluation Closed 1-CH-TK-2 Aux. El. 274' Tank on Legs Analytical evaluation Closed 2-CH-TK-2 Aux. El. 274' Tank on Legs Analytical evaluation Closed 1 -SI-TK-2 Aux. El. 274' Tank on Legs Analysis-EQE calculation Closed 52308.04-C-002 2-SI-TK-2 Aux. El. 274' Tank on Legs Analysis-EQE calculation Closed
- 52308.04-C-002 1-EG-TK-1 HA SB. El. 270' Tank on Legs & Skirt Analytical evaluation Clcsed 1-EG-TK-1 HB SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 1-EG-TK-1 J A SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 1 -EG-TK- 1J B SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 2-EG-TK-2HA SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 2-EG-TK-2HB SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 2-EG-TK-2JA SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 2-EG-TK-2JB SB. El. 270' Tank on Legs & Skirt Analytical evaluation Closed 1 -EG-TK-2 A Yard Buried underground Qualitative analysis Closed 1 -EG-TK-2B Yard Buried underground Qualitative analysis Closed 1/2-CN-TK-1 Yard Unanchored tank Analysis-EQE calculation Closed
- 52182-C ')38 1/2-QS-TK-1 Yard Tank on concrete Analysis-EQE calculation Closed foundation # 52308.04-C-004 11-5
11.1.3 RELAYS
\ )
In accordance with Section 5.2 of the GIP, the outliers in this group are classified as not meeting Capacity vs. Demand, being of a specific type, being located at an undesirable seismic location, or mounted improperly. No Outliers were found as a result of the relay review.
I1.1.4 CABLE ANI) CONDUIT RACEWAY SYSTEMS In accordance with Section 5.2 of the GIP, the outliers in this group are classified as not meeting inclusion rules, seismic performance concerns, or not meeting the Limited Analytical Review process. As a result of the walkdowns of Cable tray and Conduit Supporting Systems, outliers were identified and categorized. The resolved outliers are listed below.
- 1) Cable tray splice connection plates were missing in 12 cable trays at different elevations in the annulus of the Unit I containment. The cable trays were, however, adequately supported so that they could continue to perform their function during a seismic event. Work Requests 8458 and 8501 were issued and these splice plates have since been installed.
- 2) Vertical cable tray cover approximately 6' above floor elevation near column 13 in the Unit 1 Containment was found to be not adequately clamped. Work request 8492 to clamp the cover was issued and the cover was properly clamped.
, C 3) Loose conduit support clamps were noticed - one (1) in the Unit 1 Contairunent and to i (2) in the Unit 2 Containment. Work Requests 8465 and 8490 were issued to correct this deficiency and the clamps have been tightened.
- 4) Conduit support clamps were missing at 3 locations inside the Unit I containment. Work
- Requests 8462,8463, and 8466 were issued to install the missing clamps and the missing clamps were installed.
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- 5) Spare conduit next to conduit ICK903XC against the loop room C wall in Unit 1 Containment was found to be broken at one place. Work Request 8467 was issued and the broken conduit was replaced.
- 6) Conduits at four locations inside the Unit 2 Containment was found to have long spans. Work requests 8495 and 8497 were issued to add additional supports to reduce the unsupported length of conduits. Additional supports have since been installed.
- 7) Seven long cantilever conduit spans in the Unit 2 Containment were noticed. Work Requests 8494 and 8497 were issued to install additional supports. The installation of new supports has j been completed.
(Oj 11-6 l i
- 8) Armor cable at two locations in the Unit 2 Containment were found to have broken armor cover
( ,)
at the connection to thejunction box. Work Requests 8491and 6498 were issued to correct these deficiencies. The armor cables have been repaired.
- 9) In the Unit 2 Containment, JB-3599-2 located in loop room B had some cover screws missing.
Work Request 8495 was issued to install the missing screws and they were installed.
All of the above outliers / issues were reviewed to ensure that they do not compromise the structural integrity ofraceway systems and do not impact any safety functions of the equipment and structures in their vicinity. The review indicated that these outliers / issues do not compromise the structural integrity of the raceway systems or impact other safety related items functions during a seismic event. These outliers / issues were, however, resolved to enhance the seismic capability of the raceway systems.
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11.2 UNRESOLVED OUTLIERS AND PLAN FOR RESOLUTION O Several outliers from the GIP criteria were identified by the SRTs during the walkdown, screening, I and evaluation of equipment and cable and conduit raceway systems. Most of these outliers have been resolved as stated in section 11.1. The majority of the remaining outliers are related to i proximity effects or are maintenance related. These outliers are described below.
]
11.2.1 Electrical and Mechanical Equipment A description of each outstanding outlier or unresolved issue related to electrical and mechanical equipment is summarized in Table 11.2-1. It is noted that seismic verification or qualification of the components listed in this table has been performed and the components are found to be adequate, exclusive of the outliers or issues listed.
11.2.2 Cable and Conduit Raceway Systems Several condulet covers were missing in the cable vault and tunnel area and in the Service Building.
In addition, cables in several locations were hanging loose from the cable trays in these buildings.
Work Orders 30686,30687,30688, and 30689 have been issued to correct these deficiencies.
I1.2.3 Safety Significance and Resolution Plan
,O Each of the outstanding issues has been evaluated for operability and it is concluded that the ability V to safely shutdown the plant and maintain it in a hot shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following an SSE is not compromised. Therefore, none of these issues is considered to be a safety concern and they will have no significant impact on the health and safety of the public.
These outliers and issues are planned to be resolved by the end of the North Anna Unit I refueling outage currently scheduled to commence in April 2000.
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a g Table 11.2-1 b List of Outstanding Outliers and Issues ITEM DESCRIPTION OF EQUIPMENT RESOLUTION NO. OUTLIER / ISSUE MARK i NUMBER 1 Housekeeping Issue: Movable CO2 In the vicinity of This issue is being fire extinguisher carts on wheels, {
several resolved via an l l
unanchored tables, trash cans etc. components - Engineering Transmittal are a few inches away from SSEL refer Appendix No. CEM-97-0032 to the cabinets housing essential relays in D, SVDS note 1 Station.
the ESGR room and IRR room.
2 Control Room (CR) ceiling panels CR cabinets CR ceiling panels will be
- may require reinforcement to containing reviewed. If required,
! prevent their falling during an SSE essential relays; they will be tied together 1
also CR operators with clips to prevent may be affected their falling during SSE 3 (a) Some of the friction clips used in 1-EE-ST-l H Further inspection and transformer cabinet anchorages have 1-EE-ST-lH1 review will be performed a small gap with the base channel. 1-EE-ST-1J to verify anchorage The coils are not laterally restrained 1-EE-ST-1J1 adequacy and/or load at the top, however, the transformer 2-EE-ST-2H path. The gap between has been seismically tested. 2-EE-ST-2H1 friction clips and base (b) The transformer anchorage 2-EE-ST-2J channel will be closed and/or load path to the adjacent 2-EE-ST-2J1 via modification, as cabinets, which are bolted to the needed. To tighten the transformer cabinet, require nuts, a work order has additional review. been issued to the (c) The nuts for the bolts connecting Station, the transformer coils to the base channels may need to be tightened for transformers 2-EE-ST-2J and 2-EE-ST-2J1.
4 Cabinets contain essential relays and 1-El-CB-08B The cabinets will be have the potential of side-to-side 2-El-CB-08B bolted with adjacent impact with adjacent cabinets 1-EE-EG-OlC cabinets to prevent 1-EE-EG-02C potentialimpact 1-EE-EG-03C 1-EE-EG-04C C
11-9
Table 11.2-1 (Continued) k List of Outstanding Outliers and Issues ITEM DESCRIPTION OF EQUIPMENT RESOLUTION NO. OUTLIER / ISSUE MARK NUMBER 5 A space heater is suspended on 1-EG-B-01 A The requirement for the
- long rod hangers over the battery 1-EG-B-03C space heater in the EDG chargers and near the batteries in 2-EG-B-02B room will be reviewed, j the EDG room. Swaying of the 2-EG-B-04D and if required the
- heater during a seismic event may heaters will be laterally break the connecting restrained to the adjacent
- steam / condensate line and spray concrete walls the batteries.
6 A clamp support on an adjacent 1-HV-FS-1215B Engineering transmittal unistrut is close to the flow switch CEM-97-0012, and
] and has a potential for interaction Work order no. 008954 I have been written to move the clamp assembly about 1" away 7 Potential interaction exists 2-FW-FCV-2479 Further review of the between valve operator limit operator displacement is switch support bracket and planned. If required, the platform support beam. The valve existing support beam has cast iron yoke will be notched to clear f the interference
! 8 Pressure gage / regulator assembly 2-RH-FCV-2605 Further review of the which is mounted to valve operator displacement is operator is approximately 5/8" planned. If required, the away from post for adjacent hand rail will be moved handrail away from the valve operator 9 Valve operator cantilever length 1-RC-PCV-1455C Further review of the exceeds limits of Figure B.7-1 of 1-RC-PCV-1456 valve / yoke is planned.
the GIP 1
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n 12.
SUMMARY
AND CONCLUSION As discussed in the preceding sections, seismic walkdowns and other efforts were integrated for USI A-46 and IPEEE-seismic programs for cost effectiveness. The seismic verification walkdowns were performed primarily by trained and experienced in-house Seismic Capability Engineers, and in some cases, they were augmented by senior industry consultants. The lessons leamed and insights gained from the walkdowns by in-house SCEs are expected to be significantly beneficial to the plant safety on issues such as future maintenance, system and component modifications, and seismic verification of new and replacement equipment.
The seismic verification walkdowns and evaluations were completed for both Units I and 2 for a total of 1340 items of equipment, as identified in the seismic review SSEL which is provided in Appendix A. Those outliers / deficiencies found during the walkdowns as potential operability concems were resolved immediately in accordance with the Station procedures. Most of the othe.r outliers were also resolved expeditiously. Outliers for approximately 180 items of electrical and mechanical equipment, and tanks and heat exchangers were identified. Of these, outliers for about i 85% of the components have been satisfactorily resolved. The resolution consisted of design modifications such as side-to-side bolting of cabinets, and analysis. Fifty-four (54) pieces of equipment required modification, and the remaining outliers were resolved via analytical evaluations. In addition, the majority of minor cable tray and raceway related deficiencies discovered during the walkdowns have been resolved via Work Orders. The unresolved issues 3 which remain consist of housekeeping items, Control Room ceiling issue, a few minor modifications (V needed for cable and conduit raceway systems, and enhancement / resolution of outstanding outliers for 23 items of electrical and mechanical equipment. These issues are described in Section 11.2.
None of the outstanding issues is considered to be a safety concern, however, their resolution may 1 lead to enhancing the plant safety. These issues are planned to be resolved by the end of the Unit I second refueling outage from the time of this submittal, currently scheduled to commence in April 2000.
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- 13. REFERENCES O 13.1 Seismic Qualification Utility Group (SQUG), " Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment, Revision 2, Corrected February 14,1992".
13.2 USNRC, " Supplement No.1 to Generic Letter (GL) 87-02 that Transmits Supplemental i Safety Evaluation Report No.2 (SSER No. 2) on SQUG Generic Implementation Procedure, Revision 2, as Corrected on February 14,1992 (GIP-2)", May 22,1992 l 13.3 Virginia Electric and Power Company (VEPCO) Letter to USNRC, "Surry Power Station (SPS) Units I and 2, North Anna Power Station (NAPS) Units 1 and 2, Response to l Supplement 1 of GL 87-02 SQUG Resolution of Unresolved Safety Issue (USI) A-46",
j September 18,1992 - Responded to Reference 13.2 (120-day Letter).
J 13.4 USNRC Letter to VEPCO," Safety Evaluation of NAPS Units 1 and 2, SPS Units 1 and 2, 120-day Response to Supplement No. I to GL 87-02, November 20,1992 - Responded to Reference 13.3.
13.5 VEPCO Letter to USNRC,"SPS Units 1 and 2, NAPA Units I and 2, Supplement Response to GL 87-02 Implementation of GIP Guidance", June 29,1993 - Responded to Reference 13.4.
13.6 VEPCO Letter to USNRC, "SPS Units 1 and 2, NAPA Units 1 and 2, Supplement Response k to GL 87-02 Implementation of GIP Guidance", August 13,1993 - Supplemented Reference 13.5.
13.7 VEPCO Letter to USNRC, "SPS Units 1 and 2, NAPS Units 1 and 2, Supplemental Response to GL 87-02, Status and Schedule for USI A-46, Supplement I to GL 87-02, and IPEEE (Seismic), GL 88-20, Supplement 4", October 11,1994 - Supplemented Reference 13.3.
13.8 VEPCO Letter to USNRC,"SPS Units 1 and 2, NAPA Units 1 and 2, Schedule for Summary Reports for USI A-46, Supplement I to GL 87-02 and for IPEEE (Seismic), Supplement 5 to GL 88-20", November 20,1996 - Supplemented Reference 13.7.
13.9 Brookhaven National Laboratory (BNL) Report BNL 52361, " Seismic Design and Evaluation Guidelines for the Department of Energy High Level Waste Storage Tanks",
prepared for the U.S. Department of Energy, October 1995.
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r-APPENDIX A Safe Shutdown Equipment List (SSEL) Report, Composite SSEL, and Seismic Review SSEL l This Appendix contains the SSEL Report MPR-1201, Revision 1, prepared by MPR Associates,Inc.
As discussed in Section 4, the composite SSEL and the seismic review SSEL in report MPR-1201 were revised as a result of the walkdowns and further review. Therefore, the current versions of these lists are provided in this Appendix. It is noted that Report MPR-1201 contained additional components for the IPEEE-seismic program. The composite and seismic review SSELs in this Appendix include components which are only in the USl A-46 scope.
Documentation of review and approval of the USI A-46 SSEL by the Operation Department is also included in this Appendix.
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SAFE SIIUTDOWN EQUIPMENT LIST (SSEL) REPORT t
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- SAFE SHUTDOWN EQUIPMENk' LIST NORTH ANNA POWER STATION UNTIS 1 AND 2 i
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. MARCH 1993 i
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APPROVED: '#m 8dNf. Virginia Power Engineering Date N APPROVED: Oud/'d-/o& 8/f/fV . Virginia Power Engineering in Date i
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7 APPROVED: B IN T Virginia Power Ope:r t'ans' rAoy. s. cru a Date Operations approval applies only to the USI A-46 portions of this report.
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i North Anna Power Station
! USl A-46 and IPEEE
! Safe Shutdown Equipment i 1
j MPR-1201 j Revision 1 l t
! Volume 1 of 3 March 1993 i
Principal Contributors P. Hayes D.Jacobs D. Werder O
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. Prepared for l Virginia Power innsbrook Technical Center 5000 Dominion Boulevard i Glen Allen, VA 23080 !
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O REVISION
SUMMARY
MPR-1201 I l
North Anna Power Station Identi6 cation of Safe Shutdown Equipment for USI A-46 and IPEEE Revision No. Date Reason fbr ('h==*a A October 1990 Initial draft for Virginia Power review (Unit 2 Decay Heat Removal SSEL only)
B April 1991 Added SSELs for all Units 1 and 2 safe shutdown functions
( 0 December 1991 Incorpointed comments from:
- 1. April 12,1991 review meeting
- 2. Preliminarywalkdowns
- 3. Simulator results and Operations Department comments
- 4. Updated P&ID revision reconciliation
- 5. Relay evaluation effort ,
1 March 1993 Incorporated comments from VA Power Operations review (comments forwarded via VA Power letter dated November 24,1992). Added missing ;
data as nece*ary to complete SSEla for USI A-46. Documented selection of safe shutdown equipment for seismic IPEEE.
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! Revision 1 f
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, SAFE SHUTDOWN EQUIPMENT LIST i NORTH ANNA POWER STATION UNITS 1 AND 2 3
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! APPROVED: M d-/o11- 8[f/fV . Virginia Power Engineering i Date APPROVED: B IIMT Virginia Power Operations
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Revision 1 4
? ) CONTENTS l
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4 Volume 1
- f. age I
- Section i
j 1. GENERAL DESCRIPTION 1-1 1.1 Purpose f 1-1
1.2 Background
I 1-2 1.3 Report Organization f 1-2 l 1.4 General Methodology l l
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< 2. IDENTIFICATION OF SAFE SHUTDOWN EQUIPMFNr FOR USI A-46 2-1 i,
2.1 Purpose 2-1 l ,)
2.2 Methodology 2-3 l l Safe Shutdown Systems l 23
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- 3. IDENTIFICATION OF SAFE SHUTDOWN EQUIPMENT FOR IPEEE 3-1 3.1 Purposs 3-1 .
3.2 ' Methodology 3-3 3.3 Success Paths, Safe Shutdown Systems,
! and Safe Shutdown Equipment 3-5 ;
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' 3.4 Containment Functions
' APPENDIX A Description of Safe Shutdown Equipment Lists I
APPENDIX B Reactivity Control Function APPENDIX C Pressure Control Function APPENDIX D Inventory Control Function (Intact Plant)
APPENDIX E Decay Heat Removal Function (Intact Plant) 4
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}, Revision 1
- CONTENTS (Continued) i Volume 1 (Continued) l
! Section
- APPENDIX F Supporting Systems
! APPENDIX G Electrical Systems i APPENDIX H Small Break LOCA and Containment Systems 1
! Volume 2 ,
! Section j APPENDIX I Composite Safe Shutdown Equipment Lists (SSEL)
APPENDIX J Safe Shutdown Equipment Lists (SSEL)
! for Seismic Walkdown i '
- - APPENDIX K Safe Shutdown Equipment IJsts (SSEL) for Relay Review
- APPENDIX L Notes for all Safe Shutdown Equipment Lists
! APPENDIX M References and Drawings Used for SSEL Development i
l Volume 3 j Section APPENDIX N Piping & Instrumentation Diagrams and Electrical Drawings Used for SSEL Development t)
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1 Revision 1 lO l FIGURES 1
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! 2-1 Safe Shutdown Alternatives for Reactor Coolant ReactMty 2-5 l Control Function of North Anna Power Station Units 1 and 2
- 2-2 Safe Shutdown Alternatives for Reactor Coolant Pressure 2-6 Control Function of North Anna Power Station Units 1 and 2 2-3 Safe Shutdown Alternatives for Reactor Coolant Inventory 2-7 ;
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- Control Function of North Anna Power Station Units 1 and 2 1 2-4 Safe Shutdown Alternatives for Decay Heat Removal Function 2-8 j of North Anna Power Station Units 1 and 2 e 3-1 Success Path I.ogic Diagram, North Anna Power 3-7 l, Station, Intact Reactor Coolant System Pressure Boundary J~
j 3-2 Success Path I.ogic Diagram, North Anna Power Station, 3-8 i Small LOCA i
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i J INDEX OF ACRONYMS AND ABBREVIATIONS i
! AC - Alternating Current i AC RM - Air Conditioning Room
- ACCUM Accumulator i AFW - Amiliary Feedwater l AFPH - Auxiliary Feedwater Pump
- House AS - Amiliary Steam System j AUX- - Amdliary Building BAST - Boric Acid Storage Tank BATP - Boric Acid Transfer Pump
- BD - Steam Generator Blowdown System BIT - Boron Injection Tank BP - Bypass Switch
- BRS - Boron Recovery System
, BY - Batteries *
- CC - Component Cooling Water System
\ CCP - Centrifugal Charging Pump '
CCW - Component Cooling Water CH . Chemical and Voluule Control System
- CN - Condensate Sjhi'e m*
CONTMT - Containment CP - Condensate Polishers CCW - Component Cooling Water CPCW - Charging Pump Cooling Water System CR - Control Room
- CR - Control Rod Drive Systems CSD - Cold Shutdown CST - Condensate Storage Tank ,
CV - . Atmospheric Cleanup System CVCS - Chemical and Volume Control System DA - Aerated Drain System
- DG - Gaseous Drain System ECST - Emergency Condensate Storage Tank EDG- - Emergency Diesel Generator EE - Electrical Equipment EG - Emergency Generator
- O .SSEL system designation
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- INDEK OF ACRONYMS AND ABBREVIATIONS (Cont)
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! EI - Electrical Instrumentation *
! E/P - Electropneumatie
! EP - Electrical Panels
! FOPH - Fuel Oil Pump House
GN - Primary Plant Gas Supply System l HC - Hydrogen Recombiner System i HCV -
Hand Control Valve
- HRS - High Radiation Sampling System *
! HV - Heating and Ventilation System j HVAC - Heating, Ventilation, and Air Conditioning HX - Heat Exchanger IA - Instrument Air System *
) jlNST -
Instrument ISOL - Isolation i IPEEE -
Individual Plant Examination of External Events i JB - Junction Box
- LHSI - Low Head Safety Injection
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i LM - Leakage Monitoring System
! LOCA -
loss of Coolant Accident l MCC - Motor Control Center j MDAFWP - Motor Driven Amiliary Feedwater Pump .
j MOV - Motor Operated Valve MSVH -
Main Steam Valve House i MS - Main Steam System *
. MSIV -
Main Steam Isolation Valve l NAPS -
North Anna Power Station j NCRODP - Nuclear Control Room Operator* Development Program i i ND - In-Core Instrumentation System ;
i NS -
Neutron Shield
- i P&ID - Piping and Instrumentation Diagram i
PCV - Pressure Control Valve i PDTT - Pressurizer Drain and Transfer Tank PORV - Power Operated Relief Valve 0l 0 Viii
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- 1 i Revision 1 l INDEX OF ACRONYMS AND ABBREVIATIONS (Cont) !
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! PRT - Pressurizer Relief Tank PZR - Pressurizer
- OS - Quench Spray System
- l QSPH - Quench Spray rump House
,i RC - Reactor Coolant System
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RCP - Reactor Coolaut Pump .
4 RCS - Reactor Coohnt System l RH - Residual Heat Removal System *
. RHR -
Residual Heat Removal Syste,m j RM - Radiation Monitoring System
. RR -
Relay Room ,
i j RS -
Recirculation Spray System i RVLIS - Reactor Vessel Level Indication System !
! RWST - Refueling Water Storage Tank ;
3'3,] SFGD - Safeguards Building l
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Steam Generator SI - Safety Injection System
- l SMA -
Seismic Margins Assessment l 4
j SME - Seismic Margin Earthquake SOV - Solenoid Operated Valve l SQUG - Seismic Qualification Utility Group
! SS - Sampling System
, SSEL - Safe Shutdown Equipment List i SV - Steam Vent System l SW - Service Water System
- l Te -
T eo g, cold leg temperature l Th -
Thot, hot leg temperature i TDAFWP - Turbine Driven Auxiliary Feedwater Pump l TEMP -
Temperature i TRANS -
Transformer
- i USI - Unresolved Safety Issue .
VB - Vital Bus *
'.. VCT - Volume Control Tank*
! VG - Gaseous Vent System 1.
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- INDEX OF ACRONYMS AND ABBREVIATIONS (Cont) l VIMS - Virginia Power's Video Information System on Plant 4 Systems / Components
] WR - Wide Range XMTR -
Transmitter k
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!O l Section 1 4 i f
GENERAL DESCRIPTION l
L1 PURPOSE
! This section provides the regulatory background and general methodology for identifying j equipment to be evaluated in order to resolve USI A-46 " Seismic Qualification of
- Equipment in Operating Plants" and to complete the seismic portion of the Individual
! Plant Framination of External Events for Severe Accident Vulnerabilities. l l
1.2 BACKGROUND
i /
! 1.2.1 Umesolved Safety Issue (USD A-46 l USI A-46 was initiated by the NRC in 1980 to confirm the seismic adequacy of essential l equipment in older operating plants. In response to this USI, the Seismic Qualification l . Utility Group (SQUG) was formed and, working with USNRC representatives, developed a practical and cost-effective experience-based approach for verifying the seismic j- adequacy of equipment in nuclear plants. This methodology is defined in the SQUG j Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant
! Equipment. This method was approved by NRC Safety Evaluation Report (SER) in l May 1992. This NRC SER requested utility commitments to perform the seismic j evaluations prescribed by the GIP and to complete these reviews in a three-year period. !
1.2.2 Individual Plant Examination of External Events (IPEEE) '
l i The need for evaluation of a nuclear plant's capability to withstand external events is a - 4
! product of the NRC's severe accident policy. As a follow-on program to the Individual 1 l Plant Examination (a program to evaluate the capability of plants to withstand internal '
l accidents) the IPEEE covers r,eismic, fire, and flooding hazards to the plant. The seismic
! IPEEE may be performed by a seismic probabilistic risk assessment (PRA) or by a j seismic margins assessment (SMA) in accordance with guidance provided by the NRC in
{ NUREG-1407, Procedural and Submittal Guidance for the Individual Plant Fnmination
! of External Events for Severe Accident Vulnerabilities. Virginia Power has elected to l use the SMA methodology for North Anna Power Station.
f
! The SMA is based in large part on the experience-based seismic evaluation approach
} some equipment in addition to safe shutdown equipment required by USI A-46, (namely, j NSSS, containment isolation, and certain LOCA mitigation equipment). For most plants,
, the earthquake review level is higher for IPEEE than the licensing basis SSE. The i
! 1-1 1
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' Revision 1 i IPEEE is required by Generic letter 8820, Supplement 4, which requires completion of ;
j the review in three years and which encourages integration of the A-46 and IPEEE
- seismic reviews and walkdowns in order to minimim duplication of effort and impact on i the plants. NUREG 1407 also encourages coordinating A-46 and Seismic IPEEE i activities.
4 1.3 REPORT ORGANIZATION Because of the advantage of coordinating equipment selection results for A-46 and j IPEEE, a single report has been prepared to describe the Safe Shutdown Equipment j Ilsts (SSEla) for both A-46 and IPEEE. The report consists of 5 parts as follows:
b Section 1 (this section) provides a general description of the equipment identification ymcees. :
i l
- Section 2 provides a specific description of the process for identifying j l '
l equipment for resolution of USI A-46. -
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- Section 3 provides a specific description of the piucess for identifying j equipment for seismic IPEEE. !
i 1
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'O + A series of appendices contain the equipment lists for each safe shutdown j and support function for both USI A-46 and seismic IPEEE and explanatory 1
information on what equipment has been included in these lists. ,
- PC Diskettes containing SSELs for both USI A-46 and IPEEE for use with i the SSEM database program. The use of these diskettes is diced further f in Section 1.4.
! 1.4 GENERAL METHODOLOGY q .
i 1.4.1 Previous Actions i
l In December 1991, MPR submitted a preliminary North Anna Power Station (NAPS) l safe shutdown equipment selection report to Virginia Power for resolving USI A-46. The ,
! submittal was identified as preliminary because:
!
- The NRC had not issued a final Safety Evaluation Report (SER) for
! Revision 2 of the GIP.
- Some information required to complete the SSEL had not been provided.
i
- The NAPS Operatior.s Department review of the SSEL had not been l..
j, completed.
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. . - _ - - . = - - - _ . . . .- _ - - -.--. _-
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Revision 1 Subsequent to the submittal of the preliminary report, the NRC issued an SSER for GIP
- Revision 2, the NAPS Operations Department completed a review of the preliminny
! SSEL and progress on Virginia Power's Passport databaseisystem provided a new j resource for completing SSEL information fields.
l l 1A.2 Summary of Current Actions i
l The SSEL preparation effort described in this report consisted of Snalizing the
! Praliminary SSEL submitted in December 1991 to:
i-l
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- Reflect NAPS Operations Department Comments on the Preliminary SSEL
- for A-46.
. 4 l
- Complete missing information fields in the preliminary SSEL for A-46. !
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- Incorporate equipment items necessary to satisfy seismic IPEEE l requirements.
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The final SSEL resulting from this effort has been prepared as a composite list that
, contains equipment satisfying both USI A-46 and seismic IPEEE requirements. Separate j SSEle have been compiled for Unit I and for Unit 2 with equipment in shared systems j being included in the Unit 1 SSEL In addition to several representative sorts of the
- SSEL provided in hard copy form in the Appendices to this report, the SSEL is also
- provided on PC~ Diskettes for use with the SQUG developed SSEM database program. !
i -
I L4.3 'Ibe SSEL Database l 1
l The database provides SSELs which contain the data fields described in the GIP and in
! Appendix A of this report. Further, the database is capable ofidentifying safe shutdown ,.
! equipment which requires:
j
- A seismic evaluation for USI A-46
!
- A seismic evaluation for Seismic IPEEE l
- A relay evaluation for USI A-46 i
- A relay evaluation for seismic IPEEE (if required)
At present, the results of the preliminary NAPS relay evaluation for USI A-46 are sufficient to satisfy seismic IPEEE relay evaluation requirements in NUREG 1407. If this conclusion should change as the USI A-46 relay evaluation is finalized, then the .
- 1-3
Revision 1 SSEL can be used to identify the additional seisraic IPEEE equipment which should receive a relay evaluation.
) The SSEL distinguishes components required for seismic IPEEE but not by USI A-46 by
! an T in the notes column. All items in the SSEL are required for IPEEE. Only those i items without an T in the notes column apply to USI A-46.
i
! The following paragraphs describe the general procedures used to develop a final SSEL applicable to both USI A-46 and seismic IPEEE from the preliminary SSEL applicable i only to USI A-46.
l L4.4 Finalize the USI A-46 SSEL i
i This step involved revising the praliminary SSEL to reflect NAPS Operations
- Department comments and the completion of data fields, particularly those involving ~
l equipment locations, using Virginia Power's PASSPORT equipment database. The
, resolution of Operations Department comments was discussed with Virginia Power
! engineers at a series of visits by MPR engineers (documented in references listed in l Appendix M),
j 1.4.5 Pavparine the Seismic IPEEE SSEL
! The initial step in this process involved developing the success path logic diagrams and i
identifying the systems and functions required by EPRI NP-6041 and NUREG 1407. The systems selected were reviewed by Virginia Power engineers at a meeting with MPR engineers (documented in references listed in Appendix M). The selected systems were i then traced on system diagrams to identify equipment items for inclusion in the seismic
- IPEEE SSEL I
l Each item of equipment required to satisfy seismic IPEEE requirements was compared
- against the equipment in the USI A-46 SSEL This comparison led to several possible j actions as follows
i l If the equipment item was in the USI A-46 SSEL and if the required equipment function
! was the same for both USI A-46 and seismic IPEEE applications then the USI A-46 l SSEL was not changed.
! If the equipment was in the USI A-46 SSEL but the equipment functioned differently in
- the USI A-46 application than in the seismic IPEEE application, then the USI A-46 i SSEL was revised as follows:
t A second entry of the equipment item was made, retaining the equipment i line number and equipment identifier entries unchanged but revising other fields as necessary to reflect the seismic IPEEE function.
l 14 i
- l Revision 1
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i An "I" was inserted in the Notes column (Column 11) for this new l equipment SSEL entry. An example of this type of SSEL revision might be a motor operated valve that is no.Tely open and in the USI A-46
- application for safe shutdown remains open. In accordance with the GIP, i such an equipment item would be listed for a relay evaluation but not a
! seismic evaluation. On the other hand,if the seismic IPEEE application
- requires the valve to be closed, the valve would be listed for both a seismic i evaluation and a relay evaluation in accordance with EPRI NP-6041 requirements.
j If an equipment item selected for seismic IPEEE was not in the USI A-46 SSEL but is in
- . a system for which other USI A-46 items are listed, then the seismic IPEEE equipment j item is typically inserted in the portion of the USI A-46 SSEL containing other
- equipment in that system. The seismic IPEEE equipment item entry is designated by an i "I"in the Notes data field.
i l l If an equipment item selected for seismic IPEEE was not in the USI A-46 SSEL and the j system application or function is unique to seismic IPEEE, then the equipment item is
- assigned a 7000 series line number. Such equipment entries are also designated by an "I"
- in the Notes data field.
! {V The process described above results in the evolution of the SSEL from a USI A-46 only database to a composite database including both USI A-46 and seismic IPEEE l
l equipment. Using the capability in the SSEM program, a USI A-46 SSEL can be i compiled by sorting those equipment items which do not contain the letter "I" in the !'
! Notes data field. A seismic IPEEE SSEL includes all equipment entries in the SSEL
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Revision 1 Section 2
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IDENTD1 CATION OF SAFE SHUTDOWN 4 EQUIPMENT FOR USI A-46 2.1 PURPOSE i
- The purpose of this section is to document the selection of North Anna Power Station (NAPS) equipment needed to achieve and maintain a safe shutdown condition following a Safe Shutdown Earthquake (SSE) as required to resolve Unresolved Safety Issue (USI)
A-46.
t .
i The equipment identified is that required to bring the plant to a safe shutdown condition j following an SSE and maintain it in a safe shutdown condition during the first seventy-two hours following the SSE.
j 2.2 METHODOIDGY
' The safe shutdown equipment identified in this report was selected based on the rules and requirements of Section 3," Identification of Safe Shutdown Equipment," and the
- guidelines of Appendir A, " Procedure for Identification of Safe Shutdown Equipment" of
- the Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant
[ Equipment1.
Four functions should be accomplished to achieve and maintain a safe shutdown l condition following an SSE. These functions are: (1) reactor reactivity control, (2)
- reactor coolant pressure control, (3) reactor coolant inventory control, and (4) decay heat j- removal. The systems best suited to perform these safe shutdown functions at North .
Anna Power Station are identified in this report. The supporting systems necessary to
. operate the safe shutdown equipment are identified as well.
i Some of the more significant GIP criteria and assumptions used in selecting the safe shutdown systems are as follows:
l - Safe shutdown is defined as bringing the plant to, and maintaining it in, a hot i shutdown condition during the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following an SSE. However, for
- this analysis, Virginia Power has chosen to include additional equipment
- capable of bringing the plant to cold shutdown.
1 i
d LO I SQUG document, " Generic Implementation Procedure (GIP) for Seismic Verification of l
Nuclear Plant Equipment," June 1991, Corrected Revision 2 and NRC comments on the GIP documented in Supplemental Safety Evaluation Report No. 2, May 22,1992.
! Revision 1
!p
- V . The safe shutdown equipment should not rely upon off-site power. All i identified equipment needing electrical power should be powered by the j diesel generators or station batteries.
l . Redundancy should be provided for each item of equipment whose failure to j perform its active function would prevent accomplishment of any of the four safe shutdown functions. This is so that out-of-service equipment or a single, ;
j active failure of any item of equipment does not preclude the fulmiment of i the safe shutdown function.
4
! - The safe shutdown systems chosen should be of minimal complexity .
j and effort to operate.
. The safe shutdown systems chosen should be consistent with the ,
normal and emergency operating procedures which are used to bring l '
the plant to a safe shutdown condition.
]
. With the exception of loss of off-site power, no accidents or i extraordinary events are postulated to occur concurrently with or j sequentially to the safe shutdown earthquake.
1 i: . Operator action is permitted, if necessary, to accomplish the safe shutdown
) - function provided that sufficient manpower and time are available and
- proper procedures are in place.
l Selection of safe shutdown equipment has also been based on avoiding reliance on
- instrument air and service air systems to the maximum practical extent. -Although not a j GIP requirement, selecting flowpaths not dependent on the availability of instrument or
- service air was judged to result in a higher level of confidence in acceptable operation of j safe shutdown equipment following an earthquake.
- A Safe Shutdown Equipment List (SSEL) was made for each of the four functions
- identified above for safe shutdown. SSEls were also developed for supporting systems
! and for electrical systems, for a total of six SSELs for each unit. These SSELs are contained in Appendices B through G. They were then compiled into one composite list,
[ the composite Safe Shutdown Equipment List, contained in Appendix L An attempt has j
- been made to avoid duplicate equipment entries in Appendices B through G. For i example, many Chemical and Volume Control System components are required for
- - boration (reactivity control) and for reactor plant makeup (inventory control). Such i components are listed only once and are listed in the reactivity control function.
l
) A separate SSEL for each safe shutdown function was generated for each unit.
j Equipment and systems shared by Units 1 and 2 are listed with the Unit 1 SSELs (e.g.,
service water system).
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i Revision 1
, 4 4
2.3 SAFE SHUTDOWN SYSTEMS The purpose of this section is to describe the approach to achieve and maintain safe i
shutdown conditions following a postulated safe shutdown earthquake. Specifically, this section describes what systems are selected for controlling the following four functions
- during shutdown-1 l
) . Reactor reactivity control, i
. Ret etor coolant pressure control, !
i <
- Reactor coolant inver',ry control, and l
- . Decay heat removal. ,
l
! The approach selected for shutting down the plant following an SSE starts with a turbine j trip and reactor trip as a consequence of the postulated loss-of-offsite power. Initial
- reactivity control is achieved by insertion of the control rods. Long-term reactivity is j, controlled by boration of the reactor coolant system to cold shutdown levels using the j Chemical and Volume Control System (CVCS). The CVCS is also used to control i l reactor coolant inventory. Pressure control is achieved and maintained through the j pressurizer by controlling the pressurizer heaters or activating the power operated relief
- valve (PORV). Initial decay heat removal is accomplished by bleeding steam from a i steam generator (s) to atmosphere through one (or more) PORVs. Steam generator water inventory is maintained by the Auxiliary Feedwater System using water first from the Emergency Condensate Storage Tank (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) and then from the Condensate
! Storage Tank. When the pressure and temperature of the RCS are less than 450 psig j and 350*F, respectively, the Residual Heat Removal System is initiated and continues the decay heat removal function.
The safe shutdown alternatives for each function for a pressurized water reactor are l
! shown in the schematics of Figures 2-1 through 2-4. These schematics, adapted from the l j GIP, are highlighted to show those safe shutdown alternatives selected for North Anna l l Power Station Units 1 and 2.
l The USI A-46 requirements would be met by maintaining the plant in the hot shutdown i condition by bleeding only enough steam from the steam generators to offset decay heat generation. However, Virginia Power has elected to cool the reactor plant by bleeding i more steam than necessary to offset decay heat and then transferring the decay heat removal function to the Residuail Heat Removal (RHR) system. Consequently, the safe shutdown equipment lists developed in this report are sufficient to place the plant in a cold shutdown condition.
l 2-3 4
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Revision 1 lg A more detailed discussion of the systems involved in achieving each of the four safe l
shutdown functions is contained in Appendices B through "E which provide the SSE14 for 2
the four safe shutdown functions.
The flow paths for the safe shutdown systems are highlighted in pink on marked up schematic drawings in Appendix N. Each item of equipment whose mark number is highlighted appears in a safe shutdown equipment list (SSEL).
i O
O 2-4
"l."J.Sos '7/Ic) 12/o2^' a REACTOR REACTIVITY CONTROL (PWR)
INITIAL AND CONTINUED CONTROL u
CONTROL ROD INSERTION LONG-TERM CONTROL DURING COOLDOWN OF REACTOR COOLANT O
INJECTION OF BORATED WATER u
SAFE SHUTDOWN ALTERNATIVES FOR REACTOR REACTIVITY CONTROL FUNCTION NORTH ANNA POWER STATION UNITS 1 AND 2 f]
FIGURE 2-1
MP!t A5500ATES F_114-05-01 (D) 12/02/91 ,,
i REACTOR COOLANT PRESSURE CONTROL (PWR)
- JO
! DECREASE PRESSURE i o i r--------- --
T-------- 7
- 1 I l U ll U y i
r-------7 1-- - - - -
l l l i I PRESSURIZER I PRESSURIZER DISCHARGE SRV DISCHG. I PRESSURIZER 1 l I PORV l(At SRV Set Point,i
' l AUXIUARY I l l(At SRV Set Pointi DISCHARGE Spgy ;
Pressure Only) i l l Pressure Only) l T > 350 F l
i T av 350*F, i
- i
! I T > 350'F l g P av i25_PSy_ _3 t _ _ _ T _ _ _ _; ,
t _ _ _ T _ _ _ _j T l
I l l l y u v u INCREASE PRESSURE v
_ _ __ _ _ _ _ _ __ _ _ __ _ q l
u u U p _ _ _ _ _ _ __ _ q l I I '
CVCS PRESSURIZER LHSI FEED FEED HEATERS I(Low I
Press. Only)l '
(HHS1 Feed) ,
t _ _ _ 7 _ _ _ _J l
y u y y
SAFE SHUTDOWN ALTERNATIVES FOR REACTOR COOLANT PRESSURE CONTROL FUNCTION O NORTH ANNA POWER STATION UNITS 1 AND 2 FIGURE 2-2
MPR ASSOOATES
'-"yg%3 2m REACTOR COOLANT ;
- INVENTORY CONTROL (PWR)
!O Feeo isTO sysTeu y .
l
__________q r-- 1--
. l u
CVCS I LHSI FEED I FEED l(Low Press.l i
(HHSI Feed) i Only) I
- t-- "
T--
l U
_ _ _ _ _ _ _ _ _ __ _ J i .. .. .. .. .. .. .. .. .. .. ..
ITEMS TO CONTROL'TO l MINIMlZE DISCHARGE FROM SYSTEM U
l I I i ,
q U l y I y l j
- C I I I
REACTOR COOT. ANT PRESSURIZER OTHER f l ; ,
l j PUMP SEAL i PORV l VENTS AND LEAKOFF I DISCHARGE I DRAINS j t I
,_ _ _ _ _L _ _ _ , ,_ _ _ . . _L _ _ _ , .
I PRESSURIZER l NORMAL AND l l bRV D S HG ;
l EXCESS LETDOWN I I g
l PATHS
- l l l Pressure Only) l l u____g___a u____g___a U y U y U T
1
- , u i SAFE SHUTDOWN ALTERNATIVES FOR i REACTOR COOLANT INVENTORY CONTROL FUNCTION NORTH ANNA POW'ER STATION UNITS 1 AND 2 i
!'O i
FIGURE 2-3
' U//o$'8 $ DECAY HEAT REMOVAL (PWR)
~~ ~~ ~ ~ ~~
O~~~ HIGH PRESSbRE OPERATION STEAM GENERATOR COOLING l t _ __ _ _ ,
U c _ _ _ _J._ _ __ , ;
MAIN STEAM MAIN STEAM ATM. STEAM l SRV DISCHARGE l I I DUMP VALVE (AT SW SET POINT I PRESSURE ONLY) 1 DISCHARGE I I u _ _ _ y _ _ __ _.
U _ _ __ _ _f U
AUX. FEEDWATER FEED TO STEAM GEN.
'? _ _ _ _ __ __ __ __ _ _ __ __ __ __ __
LOW PRESSURE OPERATION l l
lf U
RESIDUAL HEAT REMOVAL SYSTEM u
COMPONENT COOLING WATER SYSTEM u
SERVICE WATER SYSTEM u n SAFE SHUTDOWN ALTERNATIVES FOR DECAY HEAT REMOVAL FUNCTION O
t NORTH ANNA POWER STATION UNITS 1 AND 2 FIGURE 2-4
Revision 1
)O Section 3 i
IDENTH1 CATION OF SAFE SHUTDOWN
- EQUIPMENT FOR IPEEE l
! 3.1 PURPOSE
) The purpose of this section is to document the selection of North Anna Power Station
- (NAPS) systems and equipment needed to achieve and maintain a safe shutdown
! condition in accordance with the Nuclear Regulatory Comminaion's (NRC) Individual l Plant Framination of External Events (IPEEE) program.
t
! The equipment identi5ed in this report is that requkM to bring the plint to a safe shutdown condition and maintain it in that condition during the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a l
- Seismic Margin Earthquake (SME).
1 Per Virginia Power's request, additional equipment l~ yond that required by IPEEE is l also identified in this report to bring the reactor plants to cold shutdown condition.
l- 3.2 METHODOLOGY i The success paths, safe shutdown systems, and safe shutdown equipment identi5ed in this i section were selected using the Seismic Margins Method of EPRI NP-6041. The Seismic
! Margins Method is one of the seismic analysis methods permitted by NUREG-140'T,
" Procedural and Submittal Guidance for the Individual Plant Framinetion of External l
Events (IPEEE) for Severe Accident Vulnerabilities." This method has been used j successfuDy in a trial application of the seismic margin method at Catawba Nuclear j Power Station which, like North Anna Power Station, is a Westinghouse PWR.' The .
! a.2 1ysis performed at Catawba is documer?-d in EPRI NP-6359, " Seismic Margin Assessment of the Catawba Nuclear Station," Volumes 1 and 2, April 1989.
Four functions should be accomplished to achieve and maintain a safe shutdown condition following a Seismic Margin Earthquake (SME). These functions are: (1) reactor reactivity control, (2) reactor coolant pressure control, (3) reactor coolant inventory control, and (4) decay heat removal. The frontline systems best suited to perform these safe shutdown functions at North Anna Power Station are identi5ed in this report. In addition, as required by NUREG-1407, the systems and components required to ensure that containment can continue to perform its design function following an SME are identi5ed in this report. The supporting systems and monitoring equipment that are necessary to operate the frontlins safe shutdown systems and containment
.)
systems / components are identi5ed as well.
3-1
Revision 1 EPRI NP-6041 requires that one preferred and one alternate safe shutdown success path be chosen for seismic analysis, and that one of the paths be capable of accommodating a ;
small I.DCA. The Catawba Analysis identified the following success paths:
- Steam generator cooling via auxiliary feedwater with subsequent closed loop decay beat removal via the residual heat removal system (the preferred path for no LOCA).
- Feed and bleed with subsequent open loop recirculation using the residual beat removal system (a small LOCA can be accommodated in this mode).
These paths were reviewed for applicabDity at North Anna Power Station based on operational and design considerations; specificaDy,WAPS systems designs, procedures, operator training, system complexity, reliance on off-site power, and available instrumentation and indicators. The paths were adapted based on these considerations, and are discussed in more detail in Section 3.3. /
Some of the more significant criteria and assumptions used in selecting the success paths, safe shutdown systems, and containment systems / components are as follows:
- Safe shutdown is defined as bringing the plant to, and maintaining it in, a hot iD this analysis, Virginia Power has chosen to bring the plant to cold shutdown.
- The safe shutdown equipment should not rely upon off-site power. All identified equipment needing electrical power should be powered by the diesel generators or station batteries.
- Non-seismic caused component or system unavaBability is not explicitly addressed in EPRI NP-6041. However, safe shutdown systems having i multiple or redundant trains have been preferentially selected in developing !
the safe shutdown equipment list.
- The safe shutdown systems chosen should be consistent with the normal and 1 emergency operating procedures which are used to bring the plant to a safe shutdown condition.
- Operator action is permitted, if necessary, to accomplish the safe shutdown function provided that sufficient manpower and time are available and proper procedures are in place.
A small (one-inch) LOCA inside containment is assumed. ,
I Selection of safe shutdown equipment has also been based on avoiding reliance on instrument air and service air systems to the maximum practical extent. Although not an
% 3-2 1
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- Revision 1 O se 1 *e-6a411 a ir - *. > ti=S <> r ta et e r o
- e= *8 instrument or service air was judged to result in a higher level of confidence in ii sitier er j acceptable operation of safe shutdown equipment following an earthq.2ake.
l A Safe Shutdown Equipment List (SSEL) was made for each of the four functions j identified above for safe shutdown. SSEb were also developed for containment systems, j supporting systems, and electrical systems, for a total of seven SSEb for each unit.
l These SSEb are contained in Appendices B through H. An attempt has been made to j avoid duplicate equipment entries in Appendices B through H. For example, many
- Chemical and Volume Control System components are required for boration (reactivity 1 control) and for reactor plant makeup (inventory control). Such components are listed only once and are listed in the reactivity control function.
l A separate SSEL for each safe shutdown function was generated for each unit.
Equipment and systems shared by Units 1 and 2 are listed with the Unit 1 SSELs (e.g.,
- service water system).
i 5
3.3 SUCCESS PATHS, SAFE SHUTDOWN SYSTEMS, AND SAFE SHUTDOWN EQUIPMENT i
The following four functions must be controlled after a Seismic Margin Earthquake to
?
achieve safe shutdown:
!O
}
- Reactor reactivity, l
j
- Reactor coolant pressure, l
Reactor coolant inventory control, and i
! The systems required to control these functions are shown in Figures 3-1 and 3-2
! (Success Path Imgic Diagrams) for an intact reactor coolant system pressure boundary l and for a small (one-inch) Imss of Coolant Accident (LOCA) respectively. Each diagram i shows the preferred path and an alternate path to safe shutdown. The safe shutdown j success paths were chosen based on the requirements in NUREG 1407 and EPRI NP-l 6041, insights developed from the pilot application of the seismic margins method to the i Catawba plant as described in EPRI NP-6359, and previous work performed to develop i NAPS safe shutdown equipment lists for USI A-46. Descriptions of the preferred and
! alternate success paths are included later in this section.
i j A more detailed discussion of the systems involved in achieving each of the four safe l shutdown functions is contain;d in Appendices B through E which provide the SSEb for j the four safe shutdown functions.
+
3
. 3-3 4
s
i Revision 1 The flow paths for the safe shutdown systems are highlighted on marked-up schematic i drawings in Appendix N. Each item of equipment whose mark number is highlighted appears in a safe shutdown equipment list (SSEL). Items shown in pink are required for j USI A-46 and seismic IPEEE; items shown in blue are required for seismic IPEEE only.
i 1
The NUREG 1407 requirements could be met by maintaining the plant in a hot l shutdown condition; however, Virginia Power has elected to cool the reactor plant to cold shutdown. Con <aquently, the safe shutdewn systems and equipment selected are
{ sufficient to place the plant in a cold shutdown condition.
l 1 i l 3.3.1 In*=e* R=eter Coolant Pe===re Bon =% Success Paths (Finem 3-1) 3.3.1.1 F.-lM S=== Path (U==*r Path on Fleure 3-1). Plant shutdown starts with a j turbine trip and a reactor trip as a result of the postulated loss-of-ofbi> wwer. Initial
^
reactivity control is achieved by insertion of the control rods. Long-term reactivity is controlled by boration of the reactor coolant system to cold shutdown levels using the Chemical and Volume Control System (CVCS). The CVCS is also used to control i j reactor coolant inventory. Pressure control is achieved and maintained through the pressurizer by controlling the pressurizer heaten or activating the power operated relief l
valves (PORVs). Initial decay heat removal is accomplished by bleeding steam from the
{; , steam generator (s) to atmosphere through one (or more) PORVs. Steam generator feedwater inventory is maintained by the Amiliary Fe:dwater System using water first j from the Emergency Condensate Storage Tank (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) and then from the Condensate l l
- Storage Tank. When the pressure and temperature of the RCS are less than 450 psig 1 and 350*F, respectively, the Residual Heat Removal System is initiated and continues the j) decay heat removal function.
Electrical power, component cooling water, and service water systems are also included l in this success path as support systems.
3.3.1.2 Alternate Sea Path (Iower Path on Firure 3-1). Plant shutdown starts with a turbine trip and a reactor trip as a result of the postulated loss-of-offsite power. Initial reactivity control is achieved by insertion of the control rods. Decay heat is removed by bleeding steam or coolant from the pressurizer PORVs to the Pressurizer Relia.f Tank.
A rupture disk on the Pressurizer Relief Tank will burst and the PORV discharge will flow to containment. Decay heat is removed from containment by the Recirculation Spray System. This success path requires electrical power, service water and component cooling water as support systems. The reactor coolant inventory lost through the pressurizer PORVs is made up by the safety injection system. Borated makeup water from the Safety Injection System also controls long term reactivity.
This success path is not preferred when the reactor coolant system pressure boundary is ,
intact because it results in avoidable discharges of reactor coolant into containment thus O causing unnecessary containment contamination.
3-4
1 4
i j Revision 1 1
3.3.2 Seismic Induced One-Inch Pipe Break Success Paths (Firum 3-2) l
! 3.3.2.1 Prefemd Soccess Path (Upper Path on Firare 3 2), Plant shutdown starts with a
, turbine trip and a reactor trip as a result of the postulated loss of off site power. Initial reactivity control is achieved by insertion of the control rods. The reactor coolant i inventory lost through the postulated one inch pipe break is initially made up by the '
i Safety Injection System from the Refueling Water Storage Tank (RWST). When the j RWST is depleted, inventory is maintained through sump recirculation using the I.aw l Head Safety Injection Pumps. Borated makeup water from the Safety Injection System
- also controls long term reactivity. Initial decay heat removal is accomplished by bleeding i
steam from the steam generator (s) to atmosphere through one (or more) PORVs.
)
1 Steam generator feedwater inventory is maintained by the Amiliary Feedwater System l using water first from the Emergency Condensate Storage Tank (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) and then from j the Condensate Storage Tank. When the pressure and temperature of the RCS are bss j than 450 psig and 350*F, respectively, the Residual Heat Removal System is initiated and j continues the decay heat removal function.
Electrical power, component cooling water and service water systems are included in this
! success path as support systems.
i
- 3.3.2.2 Alternate Success Path (Lower Path on Firure 3 2), Plant shutdown starts with a j turbine trip and a reactor trip as a result of the postulated loss of offsite power. Initial
! reactivity control is achieved by insertion of the control rods. The reactor coolant i i inventory lost through the postulated one inch break is made up by the Safety Injection I j System. Borated water from the Safety Injection System also controls long term '
i reactivity. If the coolant leak rate is insufficient to transport decay heat from the l Reactor Coolant System to containment, the flow of reactor coolant to containment is l increased by opening a pressurizer PORV. Decay heat is removed from containment by i the Recirculation Spray System.
I i
l This success path requires electrical power, service water and component cooling water -
! as support systems.
This success path is not preferred because it involves intentionally increasing the flow j rate of reactor coolant to the containment to transport decay heat. In addition, it
- involves operation of the Recirculation Spray Systems which would contaminate l equipment in containment.
3.4 CONTAINMENT f
! NUREG 1407 states that each licensee should develop a plan to assess containment j performance during a seismic event to identify vulnerabilities that involve early failure of
! containment functions. NUREG 1407 lists containment integrity, containment isolation, prevention of bypass functions, and some specific systems depending on containment F
3-5 i
i l Revision 1 design. NUREG 1407 also states that the internal events IPE should be used to determine the scope of systems for the eramination.
{. .
Based on the guidance provided in NUREG 1407, the following actions were taken to
' identify the systems and functions that determine the equipment to be included in a j containment SSEL (note that the SSEL nomenclature has been retained although the l
containment function is not restricted to safe shutdown scenarios):
i Review of NAPS containment systems as desenhed in the FSAR and in systems j training modules. l
!
- Review of NUREG 1150," Severe Accident Risks, An Assessment for Five U.S.
. Nuclear Power Plants," to identify characteristics affecting containment j performance in severe accident scenarios. NUREG ?.150 was used because an ;
i assessment of severe accident risk was not available for NAPS. -
1 1
The review described above resulted in the following systems / functions being identified as i providing the basis for a containment SSEL: l t
a l
Isolation of containment piping penetrations Quench and Recirculation Spray Systems Hydrogen Recombiners i
i 4
a 1
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I i
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!, O 4
3-6
--m.._... .. ~ _ . . _ ..m.. ..m . .. _ _ . __ , , , , _
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ResHluol Heat -
Removal System Chemkal Reactor Steam %
- and Coolont Generotors Condenoote -
- Vo8vme -
Pressurisw _ p _ g _
Auniriory _ g _ _
Control System SG PORYs I'*d
T W ond (Notural c o System Greulation) Condenoote !
Storage j .
3 Tonk Service -
e Support Systems:
O AC Power Control _ , -E
.5 DC Power e - Rod S.rvice mer insed e
- $ Compor=ent ca"a5 **
E L
5 to- Head Saeeir 5a ini.euon _
,,,,,,, _ ,,;e2'n _ Ree:reuionen
,,,PORVs (Sump SP'*F (C M ) Recirculation)
Figure 3-1. Success Path Logic Diagram, North Anna Power Station, Intact Reactor Coolant System Pressure Boundary
-N Yp O
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aed**
Hoot -
sF* tern ,
Steem Dnorgency Rooetor Generators
- -m !
consent - and - - storage - -
i System SG Ponve FWw y ,,g ,,yg i consenom. j -
"* I. -
service wd-
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e Nc-oc Power Contnst seet,
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t Figure 3-2. Success Path Logic Diagram, North Anna Power Station, Small Break Loss of Coolant Accident !
i t
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! Revision 1
- O
- Appendix A -
DESCRIPTION OF SAFE SHUTDOWN EQUIPMENT LISTS The purpose of this section is to describe the format of the safe shutdown equipment lists (SSEls) contained in the Appendices to this report. Safe Shutdown Equipment IJsts in Appendices B through K of this report list safe shutdown equipment for resolution of both USI A-46 and seismic IPEEE. Since the format requirements for SSEIJ in the GIP are more speci5c and more rigorous than those in NUREG-1407 and EPRI NP-6041, all SSEL items are listed using the GIP format.
There is at least one record for each item of equipment included in' each SSEL This section describes the information included in each field in the SSEL Entry DipGon of Contents
- 1. Iine No. This column contains a four digit record number. The furthermost left digit corresponds to the SSEL number.
q The remaining digits comprise a sequential number which identi5es the equipment along the flow path.
- 2. Tain This column contains one of the following " train" numbers which serves to group components required to complete the path for the safe shutdown function:
1= Train 1; can be considered the primary train.
Required by the GIP. .
2= Train 2; can be considered the secondary, or redundant, train. Required by the GIP for active equipment. The notation "1,2" has been used to denote equipment items that are not redundant.
3 and up = Train numbers greater than 2 are not required by the GIP, but are functionally equivalent to Train: 1 or 2.
- 3. Eculoment This column contains a number between 0 and 23. The Qas_t number corresponds to the equipment class which relates an equipment item to the seismic experience data base.
O- An R in this column indicates the item is a rugged piece of equipment for which no verification is required to A-1
I I, Entry Description of Contents i
l resolve USI A-46. Equipment classes 0-22 are common
- to USI A-46 and seismic IPEEE. These classes are defined in Chapter 3 of the GIP. Equipment Class 23 l has been used for NSSS equipment and applies only to seismic IPEEE.
l l 4. Mark Number This column contains a NAPS component number, the
- plant-= pere unique identifier as contained in the l drawing used to prepare the SSEL l For several of the items identified for safe shutdown, a i component number could not readily be assigned from or
! found on the P& ids or electrical drawings. Therefore, a
! unique identifier was assigned for each such item. Such component numbers are marked with an asterisk (*).
i
! 5, System / This column contains an abbreviation for the system in l Equipment which the item of equipment is a part. A slash (/)
- . Descriotion separates the system designation from a description of n the equipment. See the Index of Acronyms and
!k Abbreviations found in the front mhner for the meaning of the abbreviations used for the sys'. ems.
l
! 6. Drawinn Nol This column typically contains the P&ID or electrical Rev) Zone drawing number (and sheet) which identi6es the
, equipment described by the database record. When
- included, the zone where the equipment is identified on j the drawing is indicated with a letter (row) and a number
, (column).
t
- 7. Buildine This column identifies the building where the equipment is located. See the Index of Awouyms and Abbreviations for the meaning of the abbreviations.
- 8. Floor Elevation This column contains the elevation of the building Door from which the equipment can be seen.
- 9. Room or This entry identifies the room or nearest building Row / Column row / column intersection where the equipment is locatei
- For equipment inside containment, an azimuthal designator from 1.0 through 18.0 is used. In some cases a note is specified in this column. The notes are listed in Appendix L and give a detailed location of the item.
A-2
0 i
i .
Entry Description of Contents
- 10. Sgn This field assists in manipulating the database. This field contains any one of the following four options:
. (-)-No seismic or relay review needed,
. "S"-seismic review only,
. "R"-relay review only,
- "S R"-seismic and relay review needed.
- 11. Eglsa This column may contain a number which identifies a note (applicable to the equipment) found in Appendix L.
An "I" entered in this column indicates that the line applies only to IPEEE concerns and does not apply to USI A-46. An "A" in this column indicates that the line applier to A-46 and intact plant IPEEE scenarios. All lines with an "A" in the Notes column will have a
~
corresponding line (with the same line no.) with an "I" in the Notes column.
- 12. Normal State This entry identifies the normal state of the equipment during normal operation of the plant (e.g., open, closed, or op/cl for valves; running or off for pumps; on or off for electrically powered instrumentation and controls, etc.).
- 13. Desired State This entry identifies the desired state of the equipment required for the safe shutdown function.
- 14. Power Reo'd? This entry identifies whether electrical control or .-
operating power is needed to achieve or maintain the desired state of the equipment. A "Yes"in this entry indicates that power must either be maintained or provided to the equipment to have it operate as desired.
- 15. Supporting This column contains the electrical drawing or instrument System Drawing loop drawing which identifies the operating and control NoJRevision power sources and the corresponding drawing re.ision used in developing the SSEL The column is for convenience in preparing the SSEL and has not been used for every item.
O A-3 1
t
Entry a .
Descriotion of Contents 4
] 16. Required This column includes the supporting equipment (by i Interconnec- equipment mark number) or, in very few cases, the
{ tions and supporting instrument loop (F-flow, T-temperature, P-l SupportinF Pressure, etc.) needed by the equipment desenhd in this Components data base record for it to perform its safe shutdown
, function. Since each suppodng or associated component
! has a separate data base secord, this column is for i convenience in preparing the SSEL and has not been
! used for every item.
i 4
i i.-
i !
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i I
1 i
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1,-
j '
4 Y
l A-4 3
l i
Revision 1 l
iO Appendix B l -
i REACITVITY CONTROL FUNCTION I
- This appendix identifies the safe shutdown equipment required to control reactivity in the reactor core. Initial reactivity control results from control rod insertion (SCRAM) initiated by either an automatic Reactor Protection System Mp or from an operator- !
l initiated manual trip. Boric acid addition is then used to compensate for zenon decay
- )
i and plant cooldown. l
- j. When the unit is at power, the quantity of boric acid retained in the refueling water j storage tank (RWST) or the boric acid storage tank (BAST) exceeds.the quantity j i required to compensate for xenon decay and subsequent reactor cooldown. The l l availability of sufficient boron is required by plant technical specifications. )
i j Boration to cold shutdown conditions will be provided by the Chemical and Volume i Control System .(CVG) from the BAST. l When the unit is shut down, two separate and independent flow paths can be used for V reactor coolant makeup and boration: the seal injection lines to the seals of the reactor !
coolant pumps (RCP), and the normal charging line to the loop 2 cold leg. The equipment of the CVCS required to operate to achieve the system safety function is listed in the SSEL For plant shutdown, charging and boration will be accomplished by operating a minimum
~
of one charging pump per unit. The pump for the affected unit will take its suction from
. the BAST and inject borated water to the loop 2 cold leg or the RCP seal injection lines :
into the RCS.
By procedure, boration is required to cold shutdown (GD) boron concentration before cooldown commences. By accounting for xenon concentration, cold shutdown reactivity is initially achieved by control rod insertion. This permits boration to rucced in parallel with cooldown and avoids the need for discharge from the RCS to the Boron Recovery System (BRS) via the CVG. Taking credit for xenon in the cold shutdown reactivity determination requires that boration be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reactor shutdown to offset the natural decay of xenon. This time restriction can be readily satis 5cd by the proposed safe shutdown actions.
Monitoring the reactor coolant temperature, the reactor coolant boron concentration, a
- nd the control rodr position
- tee is an acceptable te eri alternative to monitoring neutron flux f O r c*ivi*7ce*rei r c*ie *r- *ir-iii rr*i>
B-1
1 1
- ! Revision 1 t,
i) loss of sampling capability; however, sufficient sampling will stul be possible from the j RCS hot leg, cold leg and RHR system. ,
i
- Power range, intermediate range, and source range nuclear instruments and the sampling i system (for boron concentration) are used to monitor the reactivity control function. GIP l i does not require neutron detectors to be listed in the SSEL for USI A-46, however, these
) stems are included for seismic IPEEE.
i
! The Dowpaths used for the reactivity control function are highlighted on the flow i diagrams in Appendix N and safe shutdova equipment items in these flowpaths are listed i on the SSEL provided in this Appendix. All items listed in the Reactivity Control SSEL i have line numbers from 1001 to 1999.
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Page No. 6 IGITN A10lllIffli 1 Data Base File Name/DateAlee: NL155fl.0EF
~ / 03/11/93 / 09:33:18 tepert DataAlee: 03-11-93 / 14:39:32 SAFE $ NUT 00WI E8UIMNT LIST (55EL) Sort Criteria: Llee Ikuter REACilVITY CONTROL FISETION Filter Criteria: (Llee llumber<*2000')
(5erted by Line thmber) Program File Name 8 verstem: 5500 v0.0 LIRE E8UIP SY3fDs/IOUIMMT < EQUIMNT LOCATION -> <- OP. ST. -> PIRER 5trPERTIE $15. ret'D INTEtussECTICI5
- 10. TRAIN CLA55 l#Et 10. OEstalPTION Dug. lio.!tev./Zene Building Ftr.Elv. to. er tou/ Col. Smi leTES Heruel Bestred REpi out. Itl./ REY. 8 StrPotilE CIpf01ENTS (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) ,
116S 2 14 1-CN-FT-1113 CP. MAST TO ET Flolf 117154409581/21/34 M 278' 8.5/J $t - CII Cil ES WA WA 1169 2 07 1-C54tV-11134 CN/tAST TO ET CIsifROL 11715-Fil-09581/21/t3 AtR 278' 8.5/J - A,3 CPDI OPDI VES 11715-tWG17/11 1-05-50V-1113A1:1-08-50 T-111342 1169 2 07 1-01-FCV-11134 CM/945T TO ET CONTE 0L 117154509581/21/C3 AIR 278' 8.5/J $ I,3 OPDI CLOSED 10 11715-01417/11 1-08-50V-1113Al 1-DI-30V-111342 1171 2 088 1-05-50V-1113Al DI/ BAST TO KT CONTEDL PILOT 11715-05-017/11 AIR 278' 8.5/J t A Alt Alt E5 11715-01-017/11 1-EP-CS-264 1171 2 0e8 1-08-50V-11111 01/ BAST TO ET CONTtot PILOT 11715-01-017/11 AtR 278' 8.5/J 5t1 Alt VDff 10 11T15-08-017/11 1-EP-CS-284 1172 2 008 1-Cl-50V-131342 DI/tAST TO ET Colfrt0L PILOT 11715-01-017/11 AMI 278' ;.5/J t A Ait Alt VES 11715-01-017/11 1-EP-CS-2tA 1172 2 Ge8 1-CN-50V-111342 OI/ BAST TO ET CONTROL Pitti 11715-08-017/11 Alm 270' 8.5/J $t i Alt VDff in 11715-Cll-017/11 1-EP-CS-2EA 1176 2 t 1-05-241 DIAeNept DEREDEY OctATE VALVE 11715-f509581/21/94 AUK 274' 8.6/J - 15 CLD5ED IPDI IB WA WA 1177 1 18 1-Ol4T-1110 Ol/ BAST TO ET Flolf 117154M-09581/2144 ACE 200* 8.5/JC 5t- Gli 151 TES 11715-Cll 015/4 II/A 1178 1 20 1-CII41-1110 CPJSAST TO ET FL0if 11715-05-015/4 58 277' CR 5t- 151 011 VES WA WA 1179 1 OOA 1-DI-IWV-1350 DI/DEREDEY OctATE VALVE 117154M-09581/21/t$ AIR 276' 8.5/J $t- CLD5EB OPDI Vt3 II/A WA 1191 2 07 1-tC-NCV-15574 RC/tC XS LET00lfi 150L 11715-fE09R1/19/E7 CollM 242' 1A - 28 CLO5ED C105ED le 11715-RC-051/4 1-at-50V-1557A VIN 527749-27750 117154K-1E 1192 2 008 1-AC-50V-1557A RC/tc Is LET00 Mil 150L PILOT 11715-tC-051/4 CONTIIT 2a5' 11 A E - VDft VUli le VIM 527749-27750 II/A +
117154K-001E 1193 2 07 1-tC-IICV-15578 RC/tc 25 LET00lst ISOL 11715-fE09342/19/F7 ColffMT 243' 13 8 - 28 Closed CLO5ED In IR15-RC-052/4 1-at-50V-15578 VIH528215-28211 117154K-18 1194 2 008 1-tC-30V-15578 RC/tc IS LETD01Al 15sl PILOT 11715-tC-052/4 Colmit 243' 13 8 R - VDif VElff 10 VIII528208-28211 II/A 11715-ft-0010 1195 2 07 1-tC-NCV-1557C RC/RC 25 LETD0lAl 150L 11715-4N3 Colmit 243' 7.5 C - 28 . CLO5ED CLOSEC 10 11715-RC-053/4 1-AC-50V-1557C VIME20516-2es18 11715-FK-0010 1196 2 088 1-SC-50V-1557C RC/tc 25 LET00lst 150L Pitof 11715-tC-053/4 CONINT 243' 7.5 C t - VDfr VDit le VIH520516-28218 II/A 117154K-0010 CERTIFICATI(pt:
The leforsettee Identifying the egulperet regelred to bring the plant to a safe shutdeun tendities on this Safe Shutdeum Egstpment List (SSEL) '
Is, to the krst of our kasuledge and belief, carrect and occurate. (thee or more signetures of Systeme or Operettees Eaglesers)
DNAlIf. JACIss / DEllEER h Intul 11.1993 04V10 J. IIERDER / DEINEtt lutui 11,1993 l
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$$EL.9BF / 03A1/93 / 89:33:18 Report Dete/ flee: 03-11-93 / 14:39:32 5AFE 51R#00181 ElllIFIEM Llif (15EL) Sort Crttarla: ths Itsuber REACTIVITY CSEEOL FIRET!IRI filter Criterts: (time itsbert'2000')
(5 rted by time ihmeer) Progree Flie name a ser:1.e: 55el vs.s (IE EQUIP 5YSTDE/Eglittlett < EqlflPElli LOCATISI -> <-IP. IT. -> PEREt SWftRTI4E SYS. req'8 IWtatmECTIlp5 C3. TRAIN CLASS lelAK 10. DESCRIPTilpI esp. Ile./tevJrone Building fir.Elv. Re. er Rou/Cel. SIRT WTES Normal Distred REW7 95. ID./REV. & SWPORTils termelTS (1) (2) (3) (4) (5) (6) (7) (s) (9) (le) (11) (12) (13) (14) (15) (le) 1270 1, t 23 1-tC-le2* RCMEl# toll MTECTOR 11715-fM-07955nt Cumit 242' - 5 l 14 WA TE5 WA II/A 11, II/A 1271 1, 2 23 1-8C-23' RCMEIRRet KTECTOR 117107164725/11 Colmit 242' - 1 I,14, 11/A II/A TES II/A II/A 13 1272 I, 2 23 1-tC-8EM* RCMEWRGE KTECTot 11715-7447W5/11 Celmit 242' - 5 1,14. II/A WA M5 II/A WA 13 1273 1, 2 23 1-AC-le5* RCMEuratui KTECTot 11715-fM4F985/11 CelmIT 242* - 1 I,14, WA II/A M5 R/A 11 / 4 13 1274 1, 2 23 1-tC-lee
- RCMEWeel KTECTOR 11715-fil47W5/11 CamIT 242' - 1 I,14. II/A II/A TES N/A II/A 13 1775 1, 2 23 1-tC-le7* RCMemieu KTEtiet 1171bfM479B5/11 Cnimff 242' - 5 I,14, II/A E/A TES II/A II/A 13 12d 1,2 23 1-at-let* RCMemioll KTECTot 11715-FM-87W5/11 Celilltf 242' -
1 I,14. II/A WA TES II/A II/A 13 1200 1, 2 23 1-88-Il81P le*/ilEDtt IIKT BRIVE lAlli 1171bl.M 3GIE5 Celmit M3' 4 5 I,14,4 N/A II/A 15 ll/A II/A 44 1281 1, 2 23 1-se-IIT05* IEP/IIKORE IET 5-PATIl TRAIEFER 11715-1.26 SGIES CCMll! M3' 4 5 I,14,4 WA 11/ 4 le II/A WA , 44 1252 1, 2 23 1-ID-IIT10* IEP/lEIRE IIST IS-PATM TRAIETER 11715-1.M 58tES ColmiT M3' 4 5 I,14,4 R/A II/A ID 11 / 4 II/A i' 44 1203 1, t 23 1-88.IIST* IO*/IIEUtt IIET SEAL 1ABLE 11715-1.26 5 HIES ColmIT M3' 4 5 1,14,4 II/A II/A 10 IL/A II/A e 1204 1, 2 23 1-le-IICT* IS*/IIECRE 1115T CINK TISE1 11715-1.26 SHIES Camli 217' 4 5 I,14,4 II/A 11/ 4 le 11/ 4 II/A ; 44 i I l i CSTIFICATION: The leforsetten Idrettfying the equipment regstred to bring the plant to a safe statduum tenditles se this safe Shutdeva Equipment List (15EL) : I Is, to the best of car kneuledge and telle , correct and accurate. (One er more slysetures of Systans or Operstless Eaglesers) bltBI W. JACIB5 / EIEllEER />b IIWCli 11, 1993 l t david J. UtilDER / DEllEtt IslRCII 11, 1993 , 7 signature "
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Page Ils. 6 O Report Dete/Ilse: 83-11-93 / 15:29:59 IRIRTN Alee lst!T 2 SAFE SitROcWN EQUIPIOff LIST (55tt) O Date Base File 'Isse/Dete/Ilse: 182 Sert Criterle: Ller Ibester
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CttilFICAllSA: The leforsettee Identifyleg the splpment reptred to bring the plant to e este stetdemo condities se this Safe Stutdoom Egelperet List (SSEL) Is. to the test of eer kneeledge and tellef correct sad occarote. (One er more signeteres of Systems or Operstless Eaglesers) RMAI W. JRuss / DEIEtt Ub leADI 11,1993 RAVit J. uttett / EEIIEtt lusal 11,1993 Y UPetere _ - - - _ - _ . _ - . _ --_-a -- - - . - - . - - - - . - - - . _ . - - _ - . . . _ - - - - _ - _ - _ _ - - _ - - _ - - - - - - _ _ - - . _ - _ - - -- _ - _ . _ _ - - . _ _ _ _ - _ - _ - - - - - - - - - - - - - _ _ _ _ _ _ _ - - _ _ _ - - - . _
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O cata sese Flie It:me/sete/ tire: Im2 O~ sstt.ser / et/11/9s / e9:3e:3s Po,e No. s untiN men oli 2 - separt sete/itae 93-11-93 / 15:29:59 SAft suflacial EqulPMEM LIST (1521) Sort Criterto: Llas moeur RfACTIVITY CONTROL FIAEil011 Filter Celterle: (Line materc'2me') (Sorte4 by Llue aster) Program Flie ame 4 9erslee SSSI ve.0 LIE EQUIP 3YSTIM/tqu1 PENT e EqlftplEE LOCATIGI -> <- W. ST. -> PRER SINWillE SY1. Ett'9 INGCNBEtfl85 E. inals Ctass last le. stsCRIrrier amt. IIe./Rev./2.ne seindlag tic.tiv. an. er sem/tet. suf Wrts mirent mestre4 sta es. Is./ett. a wPailE usesEms (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (N) 1251 2 et 2-G-52-Rita CR*/REAC1cR TRIP IREMD I 12000-1.27-40EA $8 294' CABLE $t- CL85tB WG1 WS II/A WA 1252 1 82 2-G-52-31A* CE*/ REACTOR TRIP SREAKER IVPA$$ A 12850-1.27-4024 58 2M' CABLE $R- CLS5tB EPIN WS II/R II/A 1253 2 82 2-CE-52-81t* CR*/ttACIM 1 RIP SttAttR B1PAtt B 12005-1.27-4004 $8 294' CABLE $R- EL85tt. WOI WS II/A II/A , 1200 1, t 23 2-at-t-1 RC/ttAC15 WSstL IN50-flH81G/8/t$ CONIN 29E' ~ $ I,14 II/A WA le II/A II/R INI 1, 2 23 2-AC-FA* RC/fML At198 Lits 12050-5.13 $ttit$ C5mli 242' ~ $ I,14 WA II/A le 11/ 4 WA IN2 1, 2 23 2-8C-LAl* BC/lDER MAC1R INBumLS 12850-5.11 shits CONIM 231' - 5 f 14 II/A II/R le WR 11/ 4 1, 2 23 2-at-ut!* 12050-5.11-5ttit$ CONINI 262' - 3 I,14 II/A WA le Il/4 II/A IN3 RC/WPER RfACTER INERIELS IN4 1, 2 23 2-G-GP CR*/CCIIIROL RB ORIVE BEOuull9E uttilm $18J795 & CENIM 271' - S I 1 4 , 11/ 4 II/A le 11/ 4 II/A 614J795 li 1, 2 23 2-8C-ES-1 K/IEWRSI $NIELD TAE 12958-fM-879A5/17 Celmli 242' - $ I,14 II/A II/A le WA RfA
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sJ n.v w l Page No. 9 NORTN Afeet IMIT 2 Data Base File Ilume/Detentee: Inf~ $$EL.ter / 01/11/93 / 09:30:35 Report Dete/itee: 03-11-93 / 15:29:59 1 Aft SNUTDouN [WIPMENT Lisi (Sitt) Sort Criteria: Lies ihmter REACTIYlTY COWit0L FifETION Filter Criteria: (Llee Isabere' feet') ($erted >f Lies Ankr) Program file Ihme 8 #srstse 3581 v0.8 LINE EWIP $Y37tWigU17 TENT < - pnsMITT LOCAT!oll -> <~ CP. ST. -> PWER SirPIRillE SYS. Ett'8 INTERCEIBECTl0E ! W. TRAIN CLA$$ MNtt10. DE3CRIPTICII lbsg. liedRev./Zeee blidleg Fir.Elv. Is. er Rom / Col. Soti Mits itsrael testred REWT 95. Is./REV. & SIFFIRIIIE CIBRBENTS (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 1291 1, 2 23 2-ID-IITO5* IEP/IIEORE IET 5-PATN TRAf6FER 12050-1.M SERIts CONTIfi 263' 4 5 I,14, il/A WA 10 WA WA 44 1282 1.2 23 2-85-11T10' IEP/IIEORE Illii 10-PATM itANSFtt 12050-1.M $Et!Es Ct4mIT 263' 4 5 I 14. WA WA 2 WA WA 44 1283 1. 2 23 2-IS-IIST* ID*/IIEEE 15i SEAL TABLE 12054-1.M Sitit$ Celmfi 263* 4 5 I,14, WA WA le li/4 WA 44 2-le-I!GT* Is*/IIEORE IET Culgt TWE1 120$$-1.M SERIts CelmIT 21T* 4 S WA le II/A II/A 1204 1, 2 23 gl4. II/A e l CERTIFICATION: The leforestlee Idrettfyleg the equipment regelred to bring the Plant to a safe stutdeum tsaditles en this $afe $hutdeum Egulpment List ($5tL) is, to the test of our kasvledge and tellef, correct and acts! rate. (One er este signetsres of Systees er Operstless E'l l eem) t Ofest W. JACOBS / EIEIIEtt h IURCH 11,1993 l 94TIO J. VUBER / EIElllEER IgGCII 11, 1993 7 -l.P. L
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3 Revision 1 i j l Appendix C l
- PRESSURE CONTROL FUNCITON l
\ l This Appendix describes the equipment required to control Reactor Coolant System l (RCS) pressure. The RCS is the primary system used to achieve pressure control To j increase the RCS pressure, control is achieved by using the pressurizer heaters and by l use of the charging pumps for RCS injection. l The pressurizer has two power-operated relief valves (PORVs) in parallel that provide overpressure protection during normal operating conditions. Operation of the pressurizer PORVs is ensured by a backup nitrogen supply should there be a loss of instrument air used to normally operate the PORVs. Reactor coolant system pressure is used to monitor the pressure control function. l The SSEL is based on the premise that failure of the Pressurizer Relief Tank (PRT) rupture disks due to PORV actuation will not negate the ability to maintain safe O shutdown. Based on this premise, the equipment related to the PRT which are included in the SSEL have been limited to the PRT pressure and level monitoring instruments. The flowpaths selected for pressure control exclude use of the auxiliary pressurizer spray. This normal method for pressure control is excluded in order to shut down without reliance on instrument air. HCV-1142 (HCV-2142), which supplies spray water from the charging pump via the regenerative heat exchanger, would assume the " Fall Close" position in the absence of operating air. The flowpaths used for the pressure control function are highlighted on the flow diagrams in Appendix N and safe shutdown equipment items in these flowpaths are listed on the SSEL provided in this Appendix. All items listed in the Pressure Control SSEL have line numbers from 2001 to 2999. C-1
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l i Revision 1 5 I i l Appendix D i , 4 INVEN'IDRY CONTROL FUNCTION (INTACT PLANT) l l l i j This section describes the equipment required to control Reactor Coolant System (RCS) j inventory for an intact plant. The charging portion of the CVCS accomplishes reactor
- coolant inventory control by providing makeup water to compensate for RG shrinkage i and reactor coolant pump (RCP) seal la=%
1 The normal and excess letdown flowpath used for reactor coolant volume control and i purification would be lost due to loss of instrument air. The demineralizers are not vital l j to the safe shutdown of the plant for the 72 hour time period and are also isolated with l the letdown flowpath. Also, it is neither practical nor desirable to seismicaDy qualify l these components in such high radiation areas. _ l l Two separate and independent flow paths can be used for reactor coolant makeup: the l seal injection lines to the seals of the RCPs, and the normal charging line to the loop 2 cold leg. These two flowpaths will be used as required to maintain the pressurizer level
- in an acceptable range. 'Ibe CVG flow path which is available for charging to the RCS
!- is shown on the diagrams. The CVCS equipment required to operate to achieve and , maintain reactor coolant inventory control is listed in the SSEL l ! Charging will be accomplished by operating a minimum of one charging pump per unit. l The pump for the affected unit will take its suction from the RWST and inject borated ! water to the loop 2 cold leg or the ACP seal injection lines into the RG. l l l In addition to the CVCS which has an active role in accomplishing the inventory control j function, the RCS and several connected systems (e.g., safety injeccan, sampling) have passive roles since they form parts of the fluid boundary. Equipment items which constitute the fluid boundary required for inventory control are also shown on the diagrams and the SSEL It should be noted that a discharge path is not required from the plant for the inventory control function because the plant temperature (and coolant volume) will be decreasing. If prolonged seal injection increases pressurizer level beyond the acceptable range, the pressurizer PORVs can be periodicaDy opened. Reactor vessel level, pressurizer level, "olume control tank (VCT) levels and RWS'r level indication will serve to monitor the inventory control function. The flowpaths used for the inventory control function are highlighted on the flow diagrams in Appendix N and the safe shutdown equipment items in these flowpaths are listed in the SSEL provided in this Appendix. All items in the Inventory Control SSEL for an intact plant have line numbers from 3001 to 3999. The inventory control function for a small break I.OCA is addressed in Appendix H. D-1
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- Appendix E
! DECAY HEAT REMOVAL FUNCITON i l The safe shutdown requirements for the decay heat removal function with an intact l j reactor plant are initially satis 6ed with the reactor coolant, main steam and auxiliary . l i feedwater systems; heat is transferred by natural circulation of the reactor coolant from l the core to the steam generator; heat is released from the secondary side of the steam i generators by releasing steam to the atmosphere via the steam generator PORV. When l reactor coolant temperature and pressure have been reduced sufBeiently, decay heat is removed with the reactor coolant system and residual heat removal system. The Reactor Coolant System (RCS) is the primary system used to achieve decay heat i removal. The system is a Westinghouse three-loop design capable of natural circulation i heat transfer. This provides a means of decay heat removal when the reactor coolant { pumps are unavailable, i { While in natural circulation, adequate heat transfer and coolant flow are dependent on
- an adequate inventory in both the primary and secondary systems. Confirmation of flow while in natural circulation is accomplished through the use of loop temperature indications. These indications are Te (TJ and Thot (Th). Subcooling within the RCS is ;
{ maintained by keeping system pressure greater than the saturation pressure which j coincides with the hot leg temperature. Subcooling is veri 6ed by monitoring RCS ! pressure and loop hot leg temperature (Th)- i The Main Steam (MS) System is used to remove heat from the reactor coolant system by l releasing steam from the steam generators via the steam generator PORV. The system j will be isolated by operation of the main steam trip valves. The MS system flow paths ' i are shown on the flow diagrams. The MS system components required for safe shutdown are listed in the SSEL l The MSN is shown as the system boundary as it does not require a backup. The MSN l is highly reliable due to the logic of the pilot valves associated with the MSN. As the l pilot solenoids are powered by on-site electrical power sources and will be available, an ! MSN shuts when any of the following conditions (excluding Appendix R isolation 3 conditions) exists: I j . Either the Train A or B button on the Safeguards Panel is depressed,
. Intermediate Hi Hi containment pressure (17.8 psia on two of three channels), or
.j r
. Either Train A or B safety injection signal on high steam line flow coincident with l Ie IA T or Im steam line pressure.
1 s El
- - . - - -. - - - - -~.- _-- _ -- . - _.- - . -
Revision 1 i i O In addition, the MSIV is also expected to close due to the fact that the normal steam flow assists in closing the MSIV, especially if there is a loss' of compressed air (used to
- keep the MSIV disc open).
i l The MS system is also designed to deliver steam to the turbine of the Turbine-Driven l Auxiliary Feedwater (TDAFW) pump. Steam to this turbine is supplied via two parallel, ( air-operated valves upstream of the main steam trip valves. Either line is sufficient to l supply steam for the AFW pump turbine, but two are provided for redundancy. The valves fall open on a loss of instrument air or power. l A PORV is provided on each main steam line. Each of these valves are capable of l releasing sensible and decay heat to the atmosphere. The PORV can be used for plant
- cooldown by steam discharge to the atmosphere. These valves have a relief capacity of j approximately 10 percent of the maximum steam flow of one steam generator. Only onc
! PORV is needed to cool down the RCS. i )
- Controls for the steam generator PORVs are provided in the Control Room and the l
auxiliary shutdown panet The valves may also be operated locally and therefore are not l dependent on an external power source. The three installed PORVs provide sufficient i redundancy to accomplish the decay heat removal function. i O T* ^ xiii tr era- ter <^vw> s 1r - i r 9 ir a a=ri=> *e*
- tae-plant cooldown to support RCS decay heat removal. Secondary system (steam ar ter l generator) inventory control is provided by the AFW system. The AFW system consists j of one TDAFW pump and two Motor-Driven Auxiliary Feedwater (MDAFW) pumps.
l The pumps have the capability of providing flow required for decay heat removal against 1 a steam generator pressure coinciding with the lowest steam generator safety valve set j point. The AFW system flow paths are shown on the flow diagrams. The AFW system j components required for safe shutdown are listed in the SSEL t } The TDAFW pump is driven by a single-stage non-condensing steam turbine. Upon j opening the steam inlet valv% the turbine will be controlled by the mechanical speed i governor. The AFW pump turbine has its own self-contained lube oil system utilizing a - i shaft-driven oil pump. The turbine oil coolers receive cooling water from the discharge l of the pump. All three of the steam generators provide steam to the turbine for the AFW pump. The TDAFW pump is capable of operating down to the steam pressure which corresponds to the RCS temperature at which the Residual Heat Removal (RHR) System may be placed in service. t i j The MDAFW pumps are powered from the 4kV emergency buses. All AFW pumps receive their water supply from the 110,000 gallon Emergency Condensate Storage Tank j (ECST). A backup source of water is the 300,000 gallon Condensate Storage Tank
- (CST); local administrative control will be used to ensure the necessary volume in this l tank. Another backup source of water is from the service water system.
I
- E2 i
l Revision 1 I l !O 3 ECST level will be monitored via the mechanical level at the tank. Valves associated with 1 pump suction and discharge can be locally operated. , l l The EGT, which is kept full at all times, has sufficient volume to maintain hot shutdown I , conditions for eight hours. Ample time is available for a local re-alignment of the l i normally closed valve that isolates the 300,000 gallon CST. If the CST is not available, l and RG conditions are not suitable for initiating Residual Heat Removal Systems j operations then service water can be aligned to the suction of the AFW pumps. 4 i The Residual Heat Removal (RHR) system removes residual and sensible heat from the l core to reduce and maintain the temperature of the RCS following plant shutdown. The j RHR system will be used for long-term decay heat removal. 1 ! The RHR system consists of two RHR heat exchangers, two RHR pumps and the
- associated piping, valving, and instrumentation necessary for operational control The l RHR system is located completely inside the containment. The RHR system flow path is
! shown on the flow diagrams. The components required for safe shutdown are shown in , the SSEL , 3 During cold shutdown operations, reactor coolant flows from the RCS to the RHR , pumps, through the tube side of the RHR heat exchangers and back to the RCS. The O h * >e a i tr r treo er ** ana me t ch r te ta co-ve
- ceeti -
- r which is circulating on the shell side of the heat exchangers. The inlet line to the RHR
! system is located in the hot leg of RG loop 1, while the return line is connected to the ! cold leg of RG loops 2 and 3. l Two motor-operated valves m series isolate the inlet line to the RHR system from the i RCS. Each of these inlet line motor-operated valves has the capability of local manual l j operation and consequently satisfies GIP redundancy requirements for postulated single j failures of active equipment. Each of the two redundant return lines are isolated by a !- motor-operated valve in series with a check valve. i The RHR system can be placed in operation when the pressure and temperature of the ! RCS are less than 450 psig and 350'F, respectively. If one of the pumps and/or one of { the heat exchangers is inoperative, safe operation of the plant is not affected. i i The flowpaths for the decay heat removal function are highlighted on the flow diagrams ! in Appendix N and safe shutdown equipment items in these flowpaths are listed on the
- SSEL provided in this Appendix. All items in the Decay Heat Removal SSEL for an l intact plant have line numbers from 4001 to 4999. The decay heat removal function for a small break LOCA is addressed in Appendix H.
l0 l L3
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(1) (2) (3) (4) (5) IB 11/ 4 II/A 117154N-8BIA/16/C5 Celmet 291* 2 5 I.14 II/A II/A 4002 1 23 ~ 1-tC-E-1A IE5/5fDel GDERATOR A 11715-fM4FEBl/19/D7 45Pil 255' 3/t4 5t9 III el MS 11715-115-144/6 RACK 1-40s 4003 1 18 1-1E5-F1-1474 IE5/5G A $1EAll PRE 35WE 277' CR $ t 9. 36 ON . EII WS 11715-1E5-144/6 1-El-CO-04 IE5/58 A STDelPRES3mE 117154N-8POB1/IM7 $8 4004 1 20 1-IES-PI-1474 r 256' 4/tB $t 9 WI CII YE5 11715-LEE-15W5 RACK 1-802 4005 2 18 1-1E5-P7-1476 IE5/5G A STEAIE PRES $ Wit 117154164FW1/19/C6 45Pil 277' CR $ t 9. 36 ON WI WS 11715-1E5-156/5 1-El-CS-04 II715-FN-874Bl/19/C6 SB 4805 2 20 1-M541-1476 1E5/55 A $i001 PRESSWE 250' 4.5/08 5t- ERI el MS 11715-1E5-412/7 WA 4007 1 18 1-LEE-PT-1914 IE5/5C A STDft PRE 55mE 117154N4FW1/19/ts tsPR 277' CE $R- ell el MS II/A II/A l 4004 1 20 1-lE5-PIC-It1A IE5/5C A 51001 FRE55WE 117154N4Fel/19/ts 38 306' - 5 I.8 Cle5EB CL85EB W li/4 II/A 90/5C A ?4ETY VALVE 11715-fM-8 Pal /19/E6 IE5111 4005 1 of 1-M5-SV-191A 305' - $ I.8 CLD5EB CL85EB le li/A II/A 4010 1 SF 1-H5-SV-leBA IE5/54 A SAFETY WALK 11715-fl44FeBl/It/E5 IE5til 306' - S I.8 E105EB (LASEB No WA WA or 14sV-ne34 11715498-ePEBl/19/E6 MW 40f1 1 IE5/54 A SAFETY VALE l 386' - $ 1.8 CLOSEB CLg5EB W Wk II/A DE5/54 A SAFEIT VnLM 117154N47W1/19/E6 H5W C12 1 0F 1-ME-SV-1944 306' - $ I.8 CL85EB CLA5EB W II/A II/A 1 115/58 A SAFETT VALM 11715-flHPW1/19/E5 IEENI , 4013 1 97 1-LEE-SV-1954 IE5/5C A A18e5PRERIC STDet else' 11715-fM4FeBl/19/E5 H5111 306' 4.5/CA $ t 25 CLOIES EPOI IS 11715-1E5-812/7 IIEET Alt t C14 1 SF 1-H54CV-ISIA litLtt I 272' 4/E8 $t- el el MS II/A WA H5/5C A STDet alst MVE E/P 11715 4 412/7 SFGO ! 4015 1 18 1-IE5-PY-101A isasteurre
- 3 Closta CL85EB le II/A II/A 117154W470B1/19/D5 IE5111 297* 5 . 6 /11 4 W16 1. 2 a 1-ns-343 IE5/lesamt 31PA$1 MALVE i
11715-fH-0FW1/19/C4 M5N1 205' 5.5/ts s - Orel CID5EB YES 11715-1E5-110/5 1-LEE-50t-191Al.2.3.6.7 ! 4017 1.20 1-LEE-TV-101A LEK /5C A IE5IV 11715-fM-87W1/19/E4 05P11 200' 4.5/EB $t - Alt V0ff MS 11/ 4 II/A , CIS 1, 2 08B 1450t-101A1 IE5/5C A IE51V PILOT VALVE f 11715-fM-87Wl/19/E4 45Pil 200* 4.5/E8 $t- Alt VUlf YES II/A N/A Gl9 1. 2 Cet 1-LEE-30V-141At IE5/58 A IEftV Pltei MVE 11715-fM4751/19/T4 q$Pil 290' 4.5/E8 33 - Alt VDif YES II/A II/A 4828 1. 2 cet 1-IE5-50t-lelA6 IE5/54 A IE5IV PILOT MVE I 11715-fM4Fel/19/93 q$Pil 290' 4.5/58 $t- Alt 10lf YES II/A II/A 4021 1, 2 est 1-se5-30t-itlA7 ME/SC A SE5IV PILOT MVE 11715-FN-5FW1/19/F4 q$Pil 200' 3/EA $R- Alt VUlf TES II/A II/A 4022 1. 2 est 1-lE5-30W-181A3 IE5/5C A M5IV PILOT MWE s 1,14 II/A II/A le ll/A II/A 11715-fM-801A/16/D4 CONNit 291' 14 4028 2 23 1-RC-E-It IE5/$iEAll GDERATOR e r CEti!FICAileN: The leforestles Idsettfylag the egulpment required to bring the plant to e safe shutdeun tendities se this Safe Shutdeum Equipment List ($5EI) , Is. to the best of our knuuledge and tellet correct and acaurate. (One er more sigastures of Systsee er Operetless Engineers) luRCN 11,1951 BAAAI W. Janes / EEIIEEE . _ l IMACE 11.1993 CVID J. WERDER / EEllEER [
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NORTN Afen INIT 1 Beta Base File Name/Date/ Time: 91 S5EL.seF / $1/11/91/ 39:33:18 Page Ils. 2 5AFE 51RficOlet EgiflPIEW LIST (55EL) Sort Criterlo: Line shuter ' toport Oste /Ilme: 01-11-93 / 15:01:54 DECAT IEAT EDGent f1AEilSi filter Criterlo: (Llee DeterW4M') SIS (Line Ibsetorc'Sem') Progree File llame 8 serstem: 5581 we.$ (Sarted by Llee ihmter)
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(E) (F) (1) (2) (3) (4) (5) 5t 9 WI si VES 11715-415-14E/5 II/A 11715-fM-87W2/19/C7 45P91 256' WEA 4029 1 14 1415-PT-1405 1t5/58 3 57001 PRES $WE 277' 01 $ 2 9, 35 ON 81 W5 117154E5-14E/5 1-EI-CO-04 115/56 B STDet Ppts5WE 11T15-FN-GFEB2/IS/97 5e 4030 1 20 1-lE5-PI-1405 256' 448 $R 9 WI 01 WS 11715415-150/4 II/A 11715-fl44732/19/ts qsPN 4831 2 la 14PT-1406 115/54 8 STDel POESSWE 277' CE $ t 9,36 WI EN WS 11T15415-158/4 1-El-Ce-04 II5/5G S STEAM PRE 55WE 11715-fu-EPS2/19/tE 58 4832 2 20 1 115 4 1-1485 256' 4.5/58 $t- el GI M5 11T15415-013/9 RACK 1-400 IE5/5G S STDel PRESSWE 11715-fM-GFW2/19/t5 SFEB 4033 2 18 1-145-P1-1918 ll/A WS II/R 277' CR $E - 51 GI e 1-ill-Ph10 115/5C B STDel PK55Jif 11715-Fil-87W2/19/C5 SO esN 2 20 N/A l
- - 5 I,4 C105G CLOSEB le ll/A 1 IE5/5G B SAFETY VALE 11715-FN-87W2/19/ts ItIWI 40 5 2 07 14E5-SV-102 II/A
- - 1 I,8 CL85EB CLO5EB IB ll/A 11715-fM-47W2/19/95 II5W 4s2 2 87 145V-left M5/5C B SAFETY EVE II/A
- - S I,8 CL95ER CLOBEB 15 II/A IE5/54 8 5AFETY taLW 11715-ftt-8FEB2/19/9611591 es37 2 ST 1-II5-5V-1835 II/A
- - 5 1,4 CLSIEB CLO5EB B ll/A II5/5G 8 SAFETY MW 11715-f144732/19/9511541 45 S 2 07 1-II5-5V-10EB II/A
- - 5 1,8 CLg5EB Cle5EB B 11 / 4 1E5/56 8 5AFETY MW 11715-fM-eFW2/19/95115W 4e39 2 ST 1-LEE-5V-1055 I
305' 4/EB $ R 25 CLSSEB 190I le 11715-4E5-013/9 111ET AIR i NE/58 9 ADUIPERIC STDet mer 11715-fM-SM2/19/E6 IE5WI 4000 2 el 1-LEE-PCV-1918 MvE 272' 4/t8 $t- 81 GI TES II/A N/A 11715 415-013/9 SFCB ! 40t1 2 18 1415-PT-lels 1t5/58 5 STEAft 999 MVE E/P N
- - - 3 CLc5ES CLO5EB 10 II/A II/A IEIAIRIIlilIvPASS MW 11715-ftt-07W2/19/9418541 eget 1, 2 R 34352 285* 4.5/E8 5 - WOI CL85EB WS 1171545-111/9 1415-50t-le191,2,3,5,7 4843 1,20 1-LEE-TV-10lO IE5/58 B IE5IV 11715-fl44FS2/1M4 IttVN Alt VDif VES 11715-115-111/9 II/A = l 11715-flE-sFW2/19/E4 05Pil 250' 4.5/EB $R-4004 1, 2 SIB 1415-50t-19181 115/54 5 IE5tV PILei VALVE 200' 4.5/EB $R - Alt VDII VES 11715-1E5-111/9 II/A 1, 2 OIS 1-IEE-50t-19182 1E5/58 8 IE51V PILOT WLVE 11715-FN 8782/19/E4 95PN 4045 200' 4.558 5t- Alt VOIT WS 11715-8EE-111/9 h/A 1, 2 ceB 1-LEE-50t-10305 N5/5G S It51V PILOT VALW 11715-FN-SPN2/19/E4 $5PN 4046 280' 4.5/EB $t- Alt VDit W5 11715415-111/9 II/A 115/58 8 It5!V PILO! 1RLVE 11715-fl44 FIB 2/19/T4 05PII 4047 1, 2 ceB 14EE-50t-18187 1, 2 est 1-145-50t-18151 115/5G B li31V Pilot VALVE 11715-fl447W2/19/F4 ESPN 240' 3/E8 1R b Alt VDif MS 11715-1E5-111/9 II/A 4048 5 1,14 II/A 11/A 10 II/A N/A 11715-fM-eslA/16/95 CsMNT 291' 8 4054 3 23 1-AC-E-3C IE5/5fDel GUERATOR C 256' 3/54 $8 9 51 GI VES 11715-115-140/5 RACK 1-800 IE5/5G C 57001 PRE 551stE 11T15-fM-0FeB3/23/57 65Pfl 4055 2 la 1-LEE-PT-1494 CERTIFICATION: i P t The leformattee identifyleg the egelpment required to bring the pleet to a safe stetduce candittee em this Safe Shetdsum Egel uest List (SSEL) t one accarete. (ese er more sigestores of Systsee or Operstless Eaglesers) ts, to the test of eer kesuledge sud tellef, f
181A0111,1981 88101 W. JADES / EMIIEER i B4VID J. MDteER / EMIMER Q luRui 11,1953 I [' I
__...__-m _ _ _ _ _ _ . _ _ _ _ _ . _ _ . - . . _ _ - - - - _ - - - . .__.-_.._~~.----.~....__..m.-__-_.~ _ _ . . - ._...m _ m.____ ISRTN AISE IIIIT 1 Sete Sees File lhme/ Bete /Ilue: IRI~ 15EL.00F / 85/11M5 / 90:33:N Pap IIn. 3 1AFE 52f100100 EgillMM LIST (SSEL) Sort Celterle: Llee moeur Report 3ste/ Time: 03-11-93 / 15:01:54 Filter Celterle: (Ltee lhaharW4000') JOB (Lime thshmec'5000') SECAT NEAT EDWWAL fM110R (Serted by time thaner) Program File than 8 Worstem: 558E W.0
< IquinsW tKAr1W --o c- w. si. -> Put 5apPWTIS sv5. req's turEnCagstilas tim taulP sv5fDE/Egittretin Im. TRAIN CLA11 lett ID. K5CRIPilGI Dsg. lle./Rev./Zene Belldlag Fir.Elv. Sm. er tem /Cel. $1Ri NKES Norsel Oestred IEpf M. W./REV. 8 SWPWilm Upm (6) (7) (0) (9) (IS) (11) (12) (13) (14) (15) (N)
(1) (2) (3) (4) (5) 11715-fE47003/23/97 50 277' CE $ t 9, 35 mi si W$ 117154-MS/5 1-El-(0-48 405E 2 20 1-115-P1-1404 III/5G C STENl PN55mt 11715-ftl-GFW3/23/CE (spil 256' 4/ES $89 51 OK WS IIFI5-05-NR/5 80EK 1-402 4057 1 18 1-Its-PT-3405 1E5/56 C $TENE PRESSIRE 11715-fEOfW3/23/06 58 277' tt $ t 9,3E WI .W H5 117154-N0/5 1-El-G-48 4058 1 20 1-stE-PI-MI6 16/58 C stEml PRE 55WE 11715-fEerW3/21/06 45Pil 256' 3/5 5E - Gl N WS 117154-414/5 BACK 1-801 4059 3 le 1-IEE-PT-NK 85/58 C STENE PRES 5WE 11715-71647W1/23/05 5B 277' CE $R- 81 88 WS 11715-IS-SM/t 14/4 4000 3 20 1-les-P!C-10K 1E5/58 C STENl 70E$5WE ' 11715-fts-4733/23/951E54l 305' - 5 f,4 Cte5EB C10$EB W WA N/A l 4061 3 0F 1-LEE-SV-10K 16/58 C 5AFETY MVE 11715-fE8FW3/23/tt 3154 306' - $ I,8 CLSEEB CLO5EB 15 II/A II/A 4052 3 07 1-Iti-SV-10tC 115/58 C $AFETY 1ALVE 30$* - S I,8 CteEW CLg5EB W II/A II/A 4063 3 07 1-lE-SV-lek IE5/58 C $AFETY MUE 11715-ftl-0FW3/23/96 Itse t 305' - S I,8 CLeBER Cle5EO W II/A II/A 4054 3 07 14-SV-teOC 115/56 C $AFETY VALVE 11715-fE07W3/23AE IE5W 305' ~ $ I,8 C185EB C1053 m 11/ 4 il/A , 400f 3 07 1-Its-SV-185C 115/56 C $AFETY WW 11715-fil4733/23/95 IE541 t 16/58 C Allc5PNERIC STEM OWP 11715-fE8FW3/23/E51641 300' 4.5/Eb 5 t 25 CtWEB WEN W 11715-15-414/5 INT Alt - 400G 3 OT 1-IIE-PCV-10E WILE 11715-1E-414/S SFCS 200* 4/GA St- M 51 1ES II/A 11/ 4 y 4057 3 18 1-It5-PY-10K 815/58 C STENT 010F WRLVE E/P inamarse 11715-fil4FW3/23/D4 31541 207' 4.9/CA - 3 CL85EB CLO5EB IB ll/A 11 / 4
- eggs 1, 2 t 1 4 -351 IEEAIIIRIRL SWAss 150L WOI Cla5EB WS 11715-05-112/9 1-lE-Set-NK1,2,3,4,5, f 11715-fEOFW3/23/C4 NEVII 205' 5/EB $ -
4000 1,20 14-TV-10K IE/5G C IELIV s,7 l 11715-fEOFWa/23/94 45PII 200' 4.5/t8 $t- Alt VUt MS 11715-08-112M llM , 4070 1,2 08 1-II5-50t-lek 1 115/5C C li1IV PILOT WVE 11715-fil47W3/23/94 45Pil 200* 4.5/E8 st- Alt 10K WS 117154-112/9 II/A 40F1 1, 2 000 1-Its-50t-10K2 IE5/58 C ltEIV PILOT taLVE 11715-ftl47W3/23/D4 45PN 200* 4.5/t8 5t - Alt VDK VES 117154-112/9 II/A l 4072 1, 2 008 1-Its-50v lek 4 IE5/5G C IE5IV PILOT tRLVE 11715-f48793/23/94 45PR 200' 4.5/E0 $t- Alt VIIK WS 11715-15-112/9 II/A 4073 1, 2 000 1-ItE-50t-1 TIC 5 1E5/58 C IEEIV PILST MVE 11715-715-8F53/23/94 (SPE 200' 4.5/98 5t- Alt UDK H5 11715-15-112/9 N/A 4074 1,2 08 1-II5-50V-lents 16/58 C 115IV PILOT talVE l 11715-Fil-8FW3/23/D4 45PR 200* 4.5/ta $t - Als VEm VES 11715-16-112/9 II/A 1, 2 008 14-50t-lek 7 4075 16/56 C IIIIV PILOT WALVE 200* 3/EB St - Alt VDE VES 11715-1E5-112/9 RAEK 1-901 f 4076 1, 2 008 146-50v-ItK3 15/58 C IELIV PILOT 1RLVE 11715-fEeF003/23/E4 QSPN I i CERTIFICAT1Gl: f the leforsetten identifyleg the equipment required to bring the Plant to e safe shutduun toeditien es tH. Safe Shutdeme Equipment List ($5EL) is, to the test of our kneuleep ame talte terrect and accurate. (eme er more sigesteres of Systems en Operattoes Eaglesers) OM01 W. JAOB5 / DEIIEtt U b 101001 11, 1983 10E0111,1903 ; DRV10 J. MERDER / DEIKER
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(6) (1) (2) (3) (4) (5) 11715-fil-8 Fit /13/t4 M 259' 7 . 7 /11 - 15 WIN Cle5ES IS WA 11/ 4 4116 1 E 1-4546 A5/A5 MisentY 222' - - 15 Cle5EB WGI 15 llM II/A 4117 1 t 1-N-142 fW/tseBEAff STWAGE IM ISOL 11715-HI4443/29/33 AFM IWit it 5 - IBM , II/A 15 II/4 II/A CN/teleDEAft siglast TAIK 11715-fMM4h3/29/93 TAN 271' elle 1 21 1411-it-1 274* - $t- II/A I4/4 MS 11715416871/3 II/A 4119 1 le 1-Cl-LT-leIA CII/tseUEAff SIERAst im Livil 11715-fM4443/29/93 AFril 274' - St- II/A II/A its 11715415401/1011/4 41 3 1 le 1-014T-less til/tenusmit $1eRest TAIK LIVtt 11715-fM4443/29/93 AfM SB 2T7' tt 5 5 3E M St MS 11/ 4 1-tf-ts-84 4121 1 M 1-0141-18 5-1 CII/tseDEATE $1514Et TAIK LEVEL 11715416-851/1e
- - 5 36 II/A m/A 15 14/A 1-N+ 7s 4122 2 ft 1-N-PI-19et' NMSANP SIEilGI (LOCAL) 11715-film 4A3/29/95 AFM 272' - 5I - WI el MS 11715-fW-est/5 II/A 4121 2 18 14 *T-15 fuMERFW SutitellPats i 11715-M4443/M/t3 AFM
'b NASAFW SIEilel Petssutt 11715-fMM4A3/29/t3 $8 277* tt S R 36 W SI WS 11715-N40t/5 1-tI48-el 4124 2 28 1-fv-PI-1E N/3IIIEURML ISOL TO MAfW 11715-fME443/29/95 AFM - - - 15 Cle5EB Wel 18 IIM II/A 4115 2 R 1-N-lee 11715-716-87443/29/94 AFPil
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- - 3 3s IIM 11/ 4 le II/A 1-N-P-m M 1-N#1-1988 FII/leRFW SIEileu (LetAL) 11715-fM-GF443/29/DE AFru 41M 2 11715-fM-8F4A1/29/tl AFPil 272' - 5t - WI WI WS 11715-N-881/4 Il/A 41M 2 le 1-N-PT.lem FU/IERFIF SIEilWI Ptt$$1Htt 11715-ftbeF443/29/t6 38 277' tt $ t 36 31 St WS IIM 1-t143-84 4138 2 28 7 fv-PI-lee FWMcAFWP SIEilgi PRES 35tt
- - - 15 C185EB #91 IB 11/ 4 IIM 4131 2 R 1-7W-182 FWN IEURIIL 198L 18 ISAFW 11715-7144443/19/95 AFM s
- - - 15 W8f Cle5EB m IIM WA 4132 2 8 1-fW-1m FII/5lf IEUGHL ISOL 18 ISAFW 11715-fMM443/29/94 AFM
- - 5a - OFF IWWHE WS II/4 II/A 4133 2 05 1-fv-P-3A NAWflR-ORIVUI AIKILIAti 11715-fM-sF443/29/96 AFM Ftslinitt PIEF (letFW) 11715-fM4443/29/97 AFM - - $ - IIM RM 15 WA WA 4134 1 28 1-N-PI-15EA fWithfW SIEilWI (tetAL)
- 11715-Ht4F443/29/tf AFM 272' - SE-' si el MS 11715-fv-883/3 IIM 4135 1 18 1-N-PT-1934 N/TIAFW SIEf tel PttS5WE 11715-fM-sP4A3/29/C718 277' tt 3 t 35 el el MS 11715-N-ee3/3 1-tI48-04 4DE 1 20 1-N-P1-1934 N/itAFW SIE".Sl PRESSIRE 4117 1 t 1-FV-145 IWsu IceAmt ISOL To itnP 11715-HI-GF443/M/97 AFM - - - 15 tiestB eP98 le llM ll/A titilFICATIW:
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11715-fEeF4A1/32/Et 38 277' G $t- el SI WS 11/ 4 14148-84 41M 1. 2 28 1-N4t-1477 N/5G 1A. 8. C WIst RAIEE LR I WS tl715-N-eBl/7 RAtt 1-112 ! IIF15-fEOF441/32/F8 CONINT 247' A 1.5 5t - SI WI 4178 1 le 1-fv4T-1477 N/1C A LEWL 11715-ft-8918 i e 11715-N-erent/3tN7 temII IE3' 2 5t- ON WI WS Ilfl5-fv-sttM 11/4 4182 1 M 14W4f-1474 fv/54 4 LEWL 117154K-SSM ; 11711-fEeF441/3t/E7 38 277' G S E 36 51 si MS 11715-N-e98/9 1-El-tt-04 4M3 1 N 1-N41-1474 N/16 A LEVEL 11715-fEOF4A1/32/F6 telNNt 253' A 18.5 5 t -. cN ON WS 11715-N-188/9s ll/A . 4104 1 18 1-fv4T-1475 N/58 A LEWL 117154K-eBIA r 117154EeF441/32/E6 58 277' tt 1 a 36 si EN WS 11715-fElet/9 14I-CS-04 4105 1 2e 1-fv41-1475 N/56 A LEVEL Ilf15-fEeF441/3t/F6 Opmit 261* 1 5t - ON SN WS 11715 fW-lee /B; IBM f' 410E 1 le 1-N-LT-1476 FW/5s A LEVEL 11715-ft-selt i [EtflflCAilet: , i The loferentlee identifyleg the egelsment required to bring the plant to e safe shutosua esadittee se this Safe Statasun Epigment List (SSEL) j ts, to the test of our kamelsege end tellef. t omd scarote. (Sue er more signatures of Systses or Sperstless Eaglesers) SAMI W. JAEWS / DEIIEER U 18 8 11 11. 1993 e WCE 11,1953 94tl0 J. WROEt / DEIIEER
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_..____7 4 Revision 1 1 l lO I Appendix F , 4 i SUPPORTING SYSTEMS t 1 L j The systems listed in this appendix each support more than one of the four safe shutdowns functions addressed in the pe-:+Lg appendices. The major functions 1- addressed under this category of supporting systems are: k i
- Component cooling and decay heat sink systems, i I
- HVAC systems.
L . f l Another reason for listing these systems separately from the safe sh'utdown systems is ) j that some of these systems are shared by both NAPS units and can be most effectively ; i i analyzed for inclusion in an SSEL by preparing the SSEL on a site rather than a plant ! basis. Emergency electrical power supplies are listed in Appendix G. ) Comoonent Cooline and Decay Heat Systems 4 i The Component Cooling Water (CCW) System is designed to: (1) remove residual and ] i sensible heat from the RCS, via the RHR loop, during plant cooldown; (2) provide ! cooling for various pri, nary plant components.
~
( The CCW system contains four CCW pumps and four CCW heat exchangers and is ! common to both units. The CCW Dow path is shown on the Dow diagrams. The l j components required for safe shutdown are shown in the SSEL During normal full power operation, one CCW pump and one CCW heat exchanger for each unit accommodate the heat removal loads for each unit. The standby pumps and heat exchangers provide 100% backup during normal operation. Two pumps and two j heat exchangers are normally aligned to remove the residual and sensible heat during l cooldown of a single unit. The essential component cooling water loads, other than the residual heat exchangers, are normally open to the supply header. The cooling loads discharge to the suction of ' the CCW pump. Component cooling water is circulated continuously through the j essential loads during normal operation. For safe shutdown, isolation of nonessential 3 loads is not required as long as two pumps are available.
; Two of the CCW pumps are powered from the Unit 14kV emergency buses and the r8 ccw e -g ee--e et s r -
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.' l Revision 1 l 2 l header contains manually operated cross-connect valves. During normal operation the l i system is split between units. The Service Water (SW) System is required to supply cooling to certain safe shutdown l components which are utilized to achieve the four safe shutdown functions described in Appendices B through E. I Water is circulated through the heat exchangers that remove heat from the CCW System and Recirculation Spray System, as well as the air conditioning condensers. ! The SW system flow path is shown on the flow diagrams. The components required for
- safe shutdown are listed in the SSEL 4
.I HVAC Systems
- Several areas of the plant require ventilation during safe shutdown operations to protect !
! electrical equipment from heat damage and allow access for operator actions. These l i areas are as follows: ! . Control Room, j - Emergency Switchgear Rooms,
- . Auxiliary Building, I . Main Steam Valve House, i . Service Water Pump House,
. Auxiliary Feedwater Pump House, and 4
i
. Emergency Diesel Generator Rooms.
i ! The ventilation equipment required for safe shutdown is listed in the SSEL ! The containment air recirculation and the shroud cooling systems will not be available for containment cooling because of the loss of cooling water and dampers which would result l j should there be a loss of instrument air. Individuals requiring access tn the containment within 72 hours after the seismic event, !n order to manually operate equipment, should . use ice vests. The Control Room and Emergency Switchgear Rooms are cooled by air handling units l located in these rooms. The air handlirg units are served by three chillers and their j supporting equipment. f The Auxiliary Building ventilation system is divided into two systems. The central l exhaust system provides ventilation for the charging pump cubicles and other centrally l located cubicles. The general exhaust system serves the remainder of the building. The { general exhaust fans are not emergency powered. The central exhaust fans must be j operating to provide adequate ventilation to the critical areas of the Auxiliary Building. i
- < O 4 .
I F-2 l t _. .- _
Revision 1 As a result of the Appendix R evaluation, additional fans are stored on-site. These portable fans will assure continued operation of the pumps during shutdown.1
- O l The required ventilation of the Service Water and Auxiliary Feedwater Pump Houses can i be achieved by opening supply and exhaust dampen whici) can be operated locally. Use j of these dampers, in conjunction with propping open doon in the building, provides
- adequate cooling in both areas.
] The supply air dampen in the Emergency Diesel Generator Rooms are used to cool i these areas. \ l The flowpaths for supporting systems are highlighted on the flow diagrams in ! Appendix N and safe shutdown equipment items in these flowpaths are listed on the j SSEL provided in this Appendix. Supporting system SSEL items have line numben from l 5001 to 5999. I i i J t !O 1 1 1 < l i 4 1 i 1 i 4 l 2 lO i 1 10CFR50, Appendix R Report, Sections 3.7.9 and 6.I-12, Revision 6. 4 F-3 2
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(1) (2) (3) (4) (5) . (E) (7) (0) (9) (le) (11) (12) (13) (14) (15) (N) ; Sept 1 05 14C-P.IA CC/tlpr0NDIT ECOLIE unTER P10F 11715-FM-8F941/17/E7 AEK 247' O.7/ Ell St 1 WI 91 WS II/A R/4 5002 1 21 14C-E-14 CC/ Der 0EE COOLIIE InnfER H 11715-Fil-8?IR1/17A5 Aut 263' t.5A 5 - liML 11/ 4 W 11/A E/4 5003 1 le 1-CC-FT-1994 CCACN M OW!LET FLOW 11715-ftl-8F941/17/E4 M 2E3' O.5N $t- El , 0 11 H5 117154C-063/3 II/A i 5004 1 14C41-1994 11715-ftt4P941/17A4 30 277' CR $E 35 51 m MS 11715-CC4E3/3 1-El-CO-88 20 CC/CDI M OffLET FLOW { 50 5 1 85 1-CC-P-N CC/tW90ENT COOLIE IILTR PWF 11715411-8Fthl/17/ST A10[ 247' O.7/CII $t 1 Se SN WS R/A II/A 5005 1 21 14C-E-10 CC/DerWEllr C00 Lim ISITER Ilt 11715-716-8P941/17/05 M 2E3' O.5A $ - 11/ 4 II/A m II/A R/A 500T 1 le 1-CC-FT-10E CCADf M OpitET Fleu 11715-fts-8F941/17/04 AIK 2E3' O.5A $t- WE W1 W5 117154C-063/3 WA ; CCADIIII OUILET Flmf 11715-fil4P941/17/04 30 277' CR $ R 35 WI ell _ WS 117154C-053/3 1-El-CO-84 5000 1 20 14C-F1 105 11715-715-87941/17/03 AIE 257' O.3/E St- el el MS 117154C-106/3 II/A , 5005 1 19 1-CC-TE-100 CC/CDI M OWILET 19F 5010 1 20 1-CC-TI-100 ECADI NK OffLET 19F 11715-f18-079n1/17/03 Se 277' CR $ t 35 WI el WS 11715-CC-10E/3 s-El-CO-04 { le 11715-fl8-873n1/17/03 Aut 245' O.54 5t- 91 WI W$ 11715-CC-859/8 II/A 5011 1 1-CC-PT-100 CC/CDf HK OUILET PRE 151RE 11715-fil-treL1/17/03 50 277' CR $ a 38 el el W1 11715-CC-809/E 1-El-CO-04 $312 1 20 1-CC-PI-100 CCADI E OUTLET PRES 3RRE 5016 1. 2 R 14C-310 (C/EMEI 5ftlPPER IMIRInL ISOL 1171549WF9t1/13/E0 AIK 205' 7.3/E - 15 9 91 CLAIES W II/A WA i 1917 1. 2 E 1-CC-859 CC/1(2)-CV-E-N B000mL 150L 11715-flL4F9C1/13/E3 AIK 274' 9.6/L - 15 Wel CL85ES IS N/A WA 259' 04 - 15 Wel CLOSES W RfA EfA 5010 1.23 1-CC-374 CC/5E00 IE 1000mL 190L 11715-fil-GF9C1/13/C5 Am
$5/CAS STRIPPER Liquit EFFLEDit M 11715-flWF9C2/13/E7 AMI 204' 9/K $ 23 II/A 11/ 4 le E/A 11/ 4 5019 1. 2 21 1-51-E-5A
$$/EAS STRIPPER Llquit EFFLEIII E 11715-ftt4F9C2/13/07 AIK 204' 94 $ 23 11/ 4 II/A 15 II/A II/A
- 5020 1, 2 21 1-51-E-50 SS/ LOW 3 SW M ll715-fil-879C2/13/F4 M 204' 9/K s 23 II/A II/A 10 II/R ll/A 5023 1. 2 21 2-SS-E-3C 11715-fil-8F9C2/13/E4 ARE 204' 54 5 23 II/A II/A 10 RfA II/A 5024 1. 2 21 1-35-E-3C $$/ LOW 3 SC00 HK 2-$5-E-M $$ADW 2 SESS 1t1 11715-ftl-8F9C2/13/E4 AIK 204' S/K $ 23 II/A II/A le E/A N/A l 5025 1. 2 21 1-ss-E-N SSAalt 2 $C00 M al715-Fll-879C2/13/04 M 204' 9/K $ 2'1 m/A II/A le 11/ 4 II/A ,
5026 1. 2 21 t II/A i 5027 1. 2 21 2-31-E-34 $5AOW 1 $EW llK 11715-flHP9C2/13/C4 AIR 204' 94 $ 23 PfA IB ll/A 11/ 4 11715-fl6-OF9C2/13/t4 AIK 204' 9/K $ 23 II/A N/A le II/A N/A 5020 1. 2 21 1-11-E-34 SSAalF 1 SCOS Ilt I f CEfflFICATION- l The leformetles identifying the equipment regulfed to bring the plant to a safe shutdeue conditles es this $sfe Stutduum.Espelpment List ($5EL) ! Is. to the test of our kasuledge end tellef correct and accurate. (Sue er mere slpeteres of Systems er Operstless Englesers) 01001 W. JCOBS / DEIEtt U IpetN 11.1953 , DEIS J. ISett / EIEIEEE 188CN 11.1953 7 sica-= 7
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b t ( Page us. 2 Intfit Assen Wili 1 Seta Base file lisme/este/Tlen: Im1 $$tL.OOF / 03/11/93 / 09:31:18 Report Oste / flee: 03-11-93 / 15:03:38 SAFE $NUTODIAI t00lFMENT Lisi ($$tt) Sort Criteria: Llee Ihuber SIFFORilE SY51085 Filter Celterls: (Line lhuterW5000') afb (Llee theter<'8000') (sorted by Line Itseher) Program File lemme a version: 3508 v0.0 SYSTDl/EgU! PENT < EOUIPMUIT LetATIGE -> <= fr. St. -> pmEt SirFWilE SYS. att'8 INTERClugEtileN5 LIE IQUIP
- m. TaAIN ctAss test m. etStelPriaN est. Ms.new.n ne solidles f ar.tiv. an. er es /tel. sent Inits Ihrust sentred etes? sus. m./stv. a ssProlTIE tereENis (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (14) 1-1$-t-14 $$/5G 51RfAtt III 11715-fM-879t2/13/t4 Am 204* 9A $ 23 WA WA IB II/A WA 5829 1. 2 21 5030 1, 2 21 2-55-t-14 $5/5C SIRFAtt NI 11715-FM-87902/13/94 AME 204' 94 5 23 II/A II/A ID II/A WA 5831 1, 2 t 1-CC-848 CC/1(2) tv-t-18 legemL Isol 11715-fM-87901/13/F3 Am 274' 9.6/L - 15 trel , CLO5t3 W II/A II/A 11715-fM-OF901/13/t3 m 205' 7.34 - 15 WBt CLO5EB le WA IL/A
$832 1. 2 t 1-CC-373 CC/IIRIBl STRIPPER IEWIML ISOL CC/5sge lit ImlamL 15el 205' 7.E/E - 15 SPGl CLO5ES IB 14/A II/A 5033 1. 2 t 1-CC-387 11715-fM-87901/13/C3 AM 1-tt-273 11715-FN-8F903/13/E7 AIK - - - 15 1r91 CLOSER 15 WA II/A 5034 1. 2 R (C/TutL Pli COOLER leWRAL ISOL 5835 1. 2 t 1-CC-308 CC/FEL Pli COOLtt leuemL ISCL 11715-fM-eF9t3/13/t4 AM - - - 15 1r91 CLOSEB IS II/A II/A 5835 1. 2 E 1-CC-458 CCM57 (URP III time Iwant 150L 11715-fM-87E4/15/A6 Alft 259' 10/F - 15 trDI CLO5ES 15 WA IVA 5837 1, 2 R 1-CC-491 Ct/geRON typP Disi taOLER leutmL 11715-fM-GF9C4/15/B5 Am 274' 10.5 4 - 15 1r91 CLestB le IVA II/A e Iset 503B 1,22 1-CC-473 CCA0Rell EVAP St$i Coettt IEURML 11715-fM-8FE4/15/95 AW 274' 18/E - 15 WD1 C105EB IR II/A WA r i
ISOL 5039 1. 2 R 1-CC-490 CC/IIRtBI EVAP DIsi COOttt legemL 11715-fM4F904/15/F0 Alpt 20$* 18 4 - 15 1r91 CLD5EB 15 II/A WR
- 15eL 5000 1,28 1-CC-50s Et/tottui typP Otsi TOOLER leURML 11715-FN-GF904/15/F8 AIK 259' 19 4 - 15 trGI CLOBEB 15 II/A II/A l 130L I
5041 1,22 1-CC-472 ttAGRON EVAP DIST COOLER IWWREL !!715-fM-OF904/15/as M 2ER' 10 4 - 15 crel CL85EB In 11/ 4 II/A 150L 5042 1. 2 A 1-CE-410 CC/DORENI EVAP PWP1 luftmL ISOL 11715-fM-879t1/18/tt Am 244' 10/E - 15 SP91 CLO$tt ID ll/A 11/ 4 t CC/tottBI EVAP PWF5 IUURIRL ISOL 11715-fM-OF905/14/43 AK 244' 10/C - 15 1r91 CLOSEB 15 II/A II/A , 5843 1. 2 E 1-CC-455 i 29B' 9/F $ - II/A II/A 18 II/A 11/ 4 5047 1, 2 21 1-CC-it-1 CC/tt SIRGE TAIGC 11715-fM-879R1/17AS ARE CC/tt $1RCE TM TO LIqulO MASTt 11715-fM-87941/17/IE AM 291' 8.3/5 - 3 CLg5EB CLOSED IS II/A WA 5048 1. 2 t 14t-443 IguemL 150L ! i CC/tt SIRGE TM LEVEL 11715-fM4F941/17/DF ARE 29B' 9/F $t - ON ON Its 117154t-857/8 II/A , 5009 1. 2 18 1-CC-LT-101 1, 2 2C tt/EC 3RRGE TAIK Livil 11715-fM-079R1/1747 3B 277* CR $t- ou 01 its 11715-CC-857/8 II/A i 5058 1-CC41-101-1 CC/tt SIItGE TALK LtW'. 11715-FN-OF941/17/97 38 277' tt st- cN CII Its 11715-tC-857/8 N/A 5051 1. 2 20 1-CC41-101-2 i Citi!FICATIGI: A t ine leforestles identlfyleg the egulpment regstred to bring the plant to a safe shutduus tenditles se this $afe Shutdeue Epigneet List (SSEL) ' is, to the best of our kasuledge and hellef correct and accurata. (ese er more signatures of Systems er operstless Eagleeers) 010A1 U. JatIES / tEIEtt / b 198 01 11. 1993 [ 04V10 J. WERDER / EKIEft IEWCN 11.1991 ,
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~ / 03/11/93 / 09:31:10 O ,
1AFE SMlTTOOWII EQUIPIEW LIST (S5tt) Sort Criteria: Llee Ember Sepset Date/ Time: 03-11-93 / 15:03:38 filter Crlteria: (Lime ihmterW5000') AS (Llae Ember <'8000') 5LFPotilE SY11 DIS (serted by time mater) Program Elle Ilsme a verstem: 55el et.0 i SYSTDl/Egil!PIENT < EgulPIElfi LOCAT10ll -> <- 17. ST. -> PEREt StrPERTIE SY5. ret'8 IMERDNSECTIGIS LT:2 toutP Bug. Ne./tev./Zene Sulldlag Fle.Elv. Es. or Reu/Cel. 50RT ICTES lhrus1 Bestred REqsf IIE. ID./REV. 8 StrPORTIE CWF01EllTS
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(1) (2) (3) (4) (5) 11715-f407951/21/T5 58 277' CR 52 35 Gl GI W5 11T15-CC-111/5 1-El-CE-04 , 5097 1 20 1-CC-FI-133-1 CC/CC lit FLOW TO RIR III 5099 1 004 1-CC-4EN-1008 CC/RIE Il10UTLET Colfft0L VALVE 11715-fE07981/21/A3 Colmff 243' 7 5 t IT CLOSEB 1791 MS WA N/A 11715-FH417901/21/97 M 252' 7A 5 1,27 CPDI _ CLOSED lt 11715-CC-002/4 1-CC-30V-1938 5100 2 07 1-CC-TV-103B CC/lut 10t CUTLET ColmIT 150L 11715-7407901/21/97 ARE 252' 7A - A 27 OPDI 17 01 le 11715-CC-082/4 1-CC-50V-102 5100 1 87 1-CC-TV-103B CC/R!R lol CUTLET Colmli ISOL CC/RIR lit CUTLET CONmf 150L PILOT 11715-IWO7W1/2147 AIR 252' 7A 5t I,27 Alt VDIT 10 11715-CC-082/4 II/A 5101 2 Ces 1-CC-50t-10E 252' 7/L t A.27 Alt Alt MS 11715-CC-082/4 II/A 5101 1 ces 1-CC-50v-1938 CC/mt ilt OUTLET ColmfT 150L PILOT 11715-fE07951/21/C7 ALE VES 11715-CC-101/4 II/A Ct/RIR lit COOLIE linter CUTLET 11715-fE07181/2147 Aut 254' 7/KL 5t- 51 GI 5102 1 19 I-CC TE-1498 l TDF CC/Illet III COOLIE tRTER OUTLET 11715-FM-07951/2147 58 277' CR $ t 35 GI ON MS 11715-CC-101/4 1-El-C8-04 5101 1 20 1-CC-TI-1498 TDF 11715-7407951/21A8 Aut 274' 94 5 23 N/A WA 10 WA N/A , 51048' 1 21 1-51-E-34 15/5mFLE C00LR 11715-fE47901/21A8 Aim 274' la 5 23 II/A II/A le 11/A N/A 5105 1 21 1-55-E-35 55/$mFLE C00LER 274' 9/K 5 23 WA WA 15 II/A II/A 5105 1 21 1-55-E-36 51/5mFLE COOLER 11715-f407151/21A8 ALE 291' 7.84 - 15 CPDI CLO5ED 15 II/A II/A 5107 1,22 1-CC-629 CC/5Cs0 VDIT DNSDistt MURAL 150L 11715-f407943/14/I5 Aut 291* 7.7/E - 15 OPGI CLO5ED 10 WA N/A 510B 1, 2 t 1-CC-634 CC/50B0 VDIT CeleDI5ER Iulent 150L 11715-f407943/14K5 Aut 259' 9/L - 15 CPDI CLOSED le N/A II/A 51004 1 2 1-CC-67 CC/lelREGDI III CC IUWERL 150L 11715-1407t43/14/[7 ARE 259' 9A - 15 17 01 CLO5EB 10 II/A II/A e 51000 1 E 1-CC-74 CC/IEBREGDIIlX CC teltmL 150L 11715-fM-07943/14/E5 Aut OE/PRIIGRV IRAIN TamI5FER C00Lp 11715-f407185/21/A6 toimIT 226' 5 5 23 II/A 11/ 4 10 11715-7 4 0918 II/A . 5111 1 21 10G-t-1 11715-1407W5/21/A7 Colmff 262' 15 5 23 II/A II/A 10 WA N/A 5114 1 21 1-II5-E-1A II5/IEUTRWE 5HIELD TmK C00ltt 11715-f507985/21A5 ColmIT 262' 15 5 23 II/A II/A le 11 / 4 II/A 5117 1 21 1-il5-E-15 II5/IEUTRoll sillELD TAIK C00LER 11715-f507105/2144 Colmff 237' 5 5t- ON GI Hs 11715-CC-023/3 WA 5123 1 19 1-CC-TE-1504 CC/RIR PWF SEAL C00LER CUTLET TDF 11715-7407985/21/94 ColmfT 237' E $t ' 0 11 0 11 W5 11715-CC-024/3 II/A 5119 1 19 1-CC-TE-150s CC/Itle PWF SEAL COOLER OUTLET i TDF i CERTIFICATION: The infernstlee Idrettfying the equipment regelred to bring the plant to a safe shttduun condities es this safe Shutdeus Egulpment List (55EL) ; 12, to the best of our kasuledge and hellef correct and accurats. (One or more slynetures of Systees or Operattens Eaglesers) DNAl W. JACIBS / EEllEER J IGRDI 11,1993 DAYlt J. WERCER / DE14EER IURDI 11.1993 7 signataPe
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Oq1 O O I Page Ms. 6 NotTN AISIL Iffli 1 Data Base ille Ihme/ Bete /fler: 1111~ $$EL.00F / 03/11/93 / 09:33:18 Report Dets/ Time: 03-11-93 / 15:03:38 SATE Suuttost EgulMENT List (53EL) Sert tritetta: ttee iluster 53rPORilE SYSTDt1 filter Criteria: (tlee ihmter> '5000' (5orted by Llee Ilumber) Program Flie Ihme & 9erstes: 5591 v0.s) Alt (Llee lhaber<'0000') LINE SYSTDIASUIMENT < EQUIMelf LOCA11018 -> <- CP. ST. -> PERER 51rMRTIE SYS. ret'D INTERC010Etf10N5 EQUIP
- 10. 1 RAIN CLASS MNIK W. DESCRIPIl0N Dug. Ile./Revd2ose Bulldlag F tr.Elv. Es. er tou/ Col. SINT WTES IIsrael Bestred REWF SE. W./REV. & StrMRilE CIpflNEllT5 (1) (2) (3) (4) (5) (6) (7) (8) (9) (18) (11) (12) (13) (14) (15) (16)
SW/lpf!T 12ECIRC $ PRAY N1150L 265' IGTE IK 5t- C105EB 1701 YES II/4 1-EPK-21 t 5178 1 08A 1-5W-let-1010 11715-FM-07844/43/93 45PIB 5178A 2 OIA 1-5W-let-1034 $U/RECIRC SPRAY C00LH A IEET 11715-fM-07081/20/E3 45Pli 265' - R - OPUI CPUI e il/A II/A ISOL 265* - R - 17 91 trUl 10 WA II/A 51788 2 dea 1-5W-N"" 7 SW/RECIRC SPEAY C00LH 8 IEtt 11715-FM-07El/20/E4 QSPN 150L 11715-FN-078Bl/20A6 45P11 265* - t - OPDI OPDI le II/A II/A 517st 2 004 1-5W4et-103C SWAECIRC SPRAY COOLER C IEET 1511 11715-FM-07081/2057 tsPN 265' - t - OP01 CP91 m II/A II/A 117W 2 084 1-5W-MOV-103D SW/RECitt $PtAY COOLER 0 LEET 150L 11715-fM-07eA4/43/C3 45PN 265* ICTE IK R A C105ED CLOSED le ll/A II/A 5179 1 004 1-5W4ev-105A SWAECIRC $ PRAY COOLH A OUTLET 150L , SWAECIRC SPEAT COOLH A OUTLET 11H5-FW07tW43/C3 QSPN 265' leTE IK $t I Ct05ED GPEN YE5 WA 1-EPK-M
$]p 1 084 1-5W4ef-1054 150L 265' ICTE 1K t A CLD5G CLD5EB 18 IL/A II/A 5100 1 OsA 1-5184ct-1055 SM/RECIRC SPEAT COOLER 8 CUTLET 11715-flN17044/43/C3 45PN 150L 265* IcTE IK 5t I CLOSED GP01 YE5 II/A 1-O'K-21 5100 1 08A 1-5W-MOV-1055 SWAECitC SPEAY COOLH 3 OUTLET 11715-flNIF0A4/43/C3 45Pil 150L 11715-fM-07844/43/C3 QSPN 265' IIDTE 1K R A C105ED CLO5EB m II/A II/A 5141 1 014 1-5W4et-195C SW4ECitt $PEAY COOLEt C OUTLET 150L 11715-FWO7844/43/C3 45PN 265' ICTE IK $tI CLOSEB OPUI YES II/A 1-EP-E-19 5181 1 08A 1-5W4er-105C SWAECitt 5 PRAY C00 lek C OUTLET
- ISOL 265' Imit IP R A CLOSED CLOSED 15 11 / 4 II/A s 5182 1 004 1-5W-let-1050 SU/RECIRC SPEAY COOLER 0 OUTLET 18715-f407844/43/C3 45Pil 150L 11715-fM-07eA4/43/C3 tsPIB 265' IDTE IP $t I CLOSED GP01 YES 11 / 4 1-EPK-21 5182 1 084 1-5184ct-105D SWAECIRC SPRAY COOLH 0 CUTLET 150L ,
EI/DERG 54GR WI DC 150L PAIEL 11715-FE-Of7A/22/E4 58 254' 7/B $ R 6.41 II/A II/A YES II/A II/A 51834 1 20 1-El-CS-202 (E-TRAIN) 5201 1 dea 1-5W-lev-1104 SWAstIT 1 RECIRC Alt COOLIE Colt 11715-f407844/43/D4 38 265' - t - CLOSED CLOSED 10 II/A N/A 150L i i chi!FICAi!ON: The leforsettee identifyleg the equipment required to bring the plant to a safe shutdeun coedittee se this Safe Stutdeue Equipment List (55EL) II, to the best of our knowledge and tellef, t and accurate. (One er more signatures of Systaus er Operstless Eaglesers) OftAl W. JAtlR5 / EEllEER // b letal11. 1993 RAY 10 J. HERGER / EEllEER g/ g IIMtCN 11. 1993 [/ signature
O gutin AleIA tpIlf 1 tota case Tlle llame/tute/Tlue: m1 ~ $5tt.ser / c1/11/93 / m:33:le . o Page No. 7 5AFE 98ReIMI E9EIPIEE LIST ($3EL) Sort Criteria: Llee IIsaber Report este/ Time: 83-11-93 / 15:03:38 SWPetilE SY57915 filter Criterla: (Lime ItsuherW30se') Ale (Llee Insuberc' esse') , i (Sertet by Ltme Insuber) , Program File IIsme & Darstes: 3591 v0.9
< - EllllPPill! LetAllGI -> <- W. St. -> PSER SWFWits $YS. ett's luttetsettil0E tiet SY5fD W4WIPENT j EQUIP DESCtlFiles bg. Ils./Rev.Rene sulldlag iIr.Elv. Es. er tem / Col. SWI INft$ Nurmel testred SEW M. M./REV. & WFWilm GM W. TRAIR CLAt$ IWAC lt' I
(9) (le) (11) 1 12) (13) (14) (15) (16) (6) (7) (8) (1) (2) (3) (4) (5) i 2E5' - t - tiesEB Cle3Et is ll/A II/A 5202 1 tea 1-Sil4rM-110e SIEMAIIT 1 RECIE Alt C00 LIE COIL 11715-f4-878A4/43/D4 38 .[ 130L ! 285' - E - CLOSER Cle5EB W II/A II/A te4 1-Su4WW-li44 SilApiti 1 RECIE Alt CEOLIE telt 11715-FH470A4/41/D4 Se 5203 1 , INL 6
- t - ClosEB Cle5EB IB 11/ 4 II/A PE5' 5204 1 00A 1-SIl4Wt-114e su/WIli 1 REttet Alt teOLIE COIL 11715-fM-ePGA4/41/D4 38 ,
ISOL l 205' 5.5/tA - - CisEEe Cle5ER M 11715-35-e37# II/A t 5285 2 87 I-35-TV-lelA SUMBIli 1 RECISC Alt (20 LIE telt 11715-fW-eFOA4/43/94 38 ISOL i 265' 5.5/EA E - Vult 1Dit 15 11715-N-037# II/A 5285 2 ese 1-311-300-191A-1 SMARIlf 1 RECIE Alt GMLIE C0ll ll715-fM-0F044/43/94 38 IseL P!Lef SuMAlli 1 REClK Alt t00 LIE Celt 11715-FM-eFRA4/43/D4 Se 265* 5.5/EA t - TDlt vult le 11715-Ee37# ll/A 5207 2 ese 1-Su-30t-lelA-2 t ISOL Filet 265' 5.5/EA - - Cle5Es Cl05EB e 11715-Su-83e/7 II/A SM 2 97 1-ETV-lele suMIlli 1 REttaC Alt COOLIE CDIL 11715-fM-eFeA4/43/D4 38 150L [ 265' 5.5/EA R - VDK 10ft 15 11715-Eelen 11/4 c 5288 2 ele 1-E3et-lele-1 SMAalli 1 RECIE Alt COOLIE Colt 11715-f14478A4/43/D4 38 t ISOL Pilot 205' 5.5/EA I - VOR VGlt W 11715-38-831# It'A S2ie 2 ele 1-Su-30t-lete-2 SMMElit 1 attlet Alt COOLIE C0tt 11715-f14478A4/43/94 38 ISE Pilet US* - 5t - CLe5EB WDI TES II/A 2-EP-E-19 est 2-Su-let-2SIA Su/WIIT 2 RECIE SPRAY E Iset 11715-fu-eF044/43/E7 OSPIB 5211 1 254' - 1E- Cle5ES WBt IES II/A 2-EPK-21 SII/lfili 2 RECIE SPRAY IEE ISOL 11715-FM-eF0A4/43/E7 45PIl 5212 2 004 2-W4WW-20le 25E' - 5t- CLs5E3 W91 TES II/A 2-EP4r-19 5213 1 gen 2-3540t-201C SUABIIT 2 REtlE SPEAT IIE ISOL 11715-fl44FeA4/43/E7 45PR s 256' - 3R - CLe5EB WOI 1ES II/A 2-EP-K-21 [ est 2-Su495-2919 SIIABIli 2 REttE SPRAY $213el 11715-fMEGA4/43/E7 43PIl i 5214 2 11715-fM47083/21/E7 43PII 2E5' - R - SPGI WOI 15 11/ 4 II/A 52144 2 804 2-Su4ct-2834 Su/RECIE SPEAY COOLit A IEET Isel Iyn 11715-fM-eFes3/21/E6 43PIl 265' - R - WOI Wel In II/A 5214e 2 een 2-354er-2em Su/RECIRC SPRAY teeLER e Itti I3et f gen 2-Su485-203C SU/RECIRC SPEAT CDOLH C IEET 11715-fu-epee 3/21/E5 45PIB 265' - E - SP91 WUI m M/A II/A [ 5214C 2 ISOL i l l CEtilFICAllOI: The leformatles Idsettfyleg the equiparet reqletred to erleg the plant to e safe shutdeun tendittee r* this Safe Shutdeus Egelpuret list ($$H) IJ, to the best of our knowledge amo tellef, corrett and etterate. (ene er sure signatures of Systems or operstless Eaglesers) l luROI 11,1993 RAIII u. JIGB$ / EEllEft DAVID J. UERett / IEIIEft gy IWAOl 11.1933 7 5senstere i I
_ , . . . . . - _ _ _ - ~ m._ _ _ _ _ . . _. . . _ - . . . . . - _ . J w Page No, a sEmfu Alsta titli 1 Deta lane Tile llame/ tete / fleet fell~ $$tL.08F / 03/11/93 / 09:33:18 i SAft SMWTOUWI EWIPMENT LIST ($3tL) Sort Criterls: Lise Ihmter RePert Datettlee: 01-11-93 /15:03:M 5trPollillir. SYSTEMS FlMer Cetterta: (Ltee ihmter>.'5000') Am (Llue Itaterc' esse') , ($orted by Llee Ilseher) Program File name & Verslee: $585 we.e 3 I
< EOUIPENT LOCATION -> <- 17. 5T. -> PWER 5trPIRTIE SYS. ht4*3 INTttageECTIIN15 >
t!It felitP SYSTDl/EWIPMENT W. TRAIN CLASS IWWE 10. DESCRIPTIoll thg. Ile./Rev./Zene Building iIr.Elv. Re. er towKel. Soti 10f!! Ilsrael Desired Rt4Bf 8E. IS./ RET. & StrPOtilE CipplN NIS i (1) (2) (3) (4) (5) (6) (7) (e) (9) (10) (11) (12) (13) (14) (15) (16) I 52140 2 004 2-3N49t-20B SuMEC!K SPtAY C00LR D IEET 11715-fM47053/21/E3 45PR 205' - R - 17 91 170t ID II/A 11/ 4 130L 256' - t A CLD5ES CLO5ES Im II/A WA I 5215 1 004 2-3W40t-2054 SilAfili 2 ftttK SPRAY lit ISOL Il715-FM-0?tA4/4M7 45PN 5215 I 804 2-3N4st-205A suMilli 2 ettitC $ PRAY M Isol 11715-FM4FeA4/43/t? 45Pe 256' st I C105ES 1r01 YES II/A 2-EP4E-19 5216 2 004 2-3u4ct-2058 SNMElli 2 RttlRC 3PtAT lit ISOL 11715-fM4FeA4/4M7 45Pil 256' - t A C10$ES CLO5ES le ll/A II/A 5216 2 004 2-3M4Wt-2950 SNMAlli 2 RECIE SPRAY III ISCL 117154447044/43/E7 45Pil 256' SR I G05ES 1r01 ft5 II/A 2-EP-lE-21 5217 1 OBA 2-3W4Wt-205C $NMAlti 2 RECIK 3 PRAY III ISOL 11715-fM-0FeA4/43/E7 $$Pil 256' - t A CLO5ED CLO5EB R8 II/A WA 5217 1 004 2-Sil4WW-205C SW/lBiti 2 ttCIRC $ PRAY HI I30L lif15-fM-0FeA4/43/E7 $$Pil 256' SR I CLOSEB 1701 Its li/A 2-EP4E-19 11715-fM4Fe44/43/tf tsPil 256' - 2 A C105E5 CLOSEB IS 11/ 4 II/A 5218 2 GBA 2-3M4Wt-2050 Su/lfili 2 RECIRC $ PRAY lit 150L SWAfili 2 ftCIRC $PHAT lit ISOL 117154le-OFIA4/43/t7 45Pil 256' 5e I CtEED 1701 ft1 II/A 2-EP-lE-21 52g 2 004 2-3114Wt-2050
- t - CLOSES CLO5ED 18 II/A II/A 5219 1 OtA 2-su4et-flet 3MARIli 2 atCIK AIR C00LilE COIL 11715-fM-0 Fen 4/43/F8 45Pil -
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- - R - CLO5ED CLOSE5 le II/A II/A 5220 1 OtA 2-3W4WF-2105 SNMSIli 2 RECIE Alt COOLIE COIL 117154M-07044/43/F8 45P11 130L 5221 1 004 2-3W4WF-2144 3N/Islit 2 RECIK Alt COOLIE tell 117154M-07eA4/43/F8 45PM - - R - C105EB CLOSEB 18 II/A II/A )
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- - R - C105EB C105EB In 11/ 4 II/A 5222 1 004 2-384WW-2145 SuMBili 2 RECIRC Alt COOLIE Cett 11715-fM4FeA4/43/F8 45Pil '
I30L 5229 1 05 1-3u4-10 SM/luetATION Iepit1ORIE PWF 11715-fM47eA4/43/t3 Te 254' - t I 0FF 0FF IB 11/A II/A s llF15-fM4FeA4/43#3 il 254' - R - CLO5ED C105EB IS II/A II/A
$230 1 004 2-3540W-2204 SWMADIATICIIIGNITORIE PifF sutLET ISOL sN/RSIAi!CllIGNITORIE PlfF 11715-fM-07844/43/F3 TO 254' - t - C10$fB CLO5ED 18 II/A II/A $231 1 004 2-3N45t-220s OUTLET ISOL 11715-7M-07844/43/57 AUI 244' S.3# t CLOSED CLO5tB IS II/A II/A 5232 1 ORA 1-Su4ct-1134 35/CClf flEL PIT COOLUS ISOL ,
ll715-fM-0?eA4/43/97 AUK - - R - C105ED CLOSED 10 II/A II/A 5233 1 004 2-3N45W-2134 Sil/tDf FIEL Pli C00LDS ISOL 244' 4.7/F R - ClosEO Cl0SEB 15 II/A II/A 5234 1 004 1-Su4107-113B SW/ tar FUEL PIT C00LEts 150L 11715-FM 07044/43/95 AME CRitFICATIcit: The leforsettee idrettfyleg the eWlpment required to brleg the plant to a safe shutdeue condities se this Safe Shutduum Egulparet List (13tt) ; 1s. to the best of our kasuledge and tellef carrect and accurate. (One or more signatures of Systems or SPerstless toglesers) Diegt V. JACINS / EEIIEER _. Ub IGROI 11.1991 l sAvle J. vomer / tElutta ImRCu n. 19t3 u3 at.re j 7 ! I i __.__-s--_ _ _ _ - _m._ _ m__=. __-_____. .___m..m._.___. _ . _ . _ . _ _ . _ _ . _ _ _ . _ _ _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _ - _ __ _ _____ _ .__._ _ _- m -- __' _ e -.- -
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r t h J ; Page No. 9 Itain alsut Iglli I tota Base Flie Name/gatentue: Ist- $5EL.WF / 81/11/93 / 09:33:N ' Beport OsteMine: 03-11-91 / 15:83:38 SAFE SIIfrealal EqulPIEut lisi ($$EL) Sort Criterta: Llas muster 3MP9WIIE $Y5fBE Filter Criterte: (Llee number > '5EOD') Am (Llas number <*eget') j (5orted by Line Nester) Program file IIsme 8 Wurstee: SSSI se.9 - LIIE Equip $Y5791/f8tflFIElft e HIRFIEIIF LOCAileN -> <- W. $i. -> PWER SWFWTIE SYS. ret *5 IINsarnamsrilWE I IB. TRAlt CLASS fuSK 15. BEstRI?ilm Sug. he./Bew./Zene Bulldtag Ftr.Elv. Am. er Reu/Cel. Seti IstE5 IIsrael testred SEpf M. W./DEV. & SIFFWIIE (SpWWR$ (I) (2) (3) (4) (5) (6) (7) (8) (9) (N) (II) (12) (13) (N) (15) (N) 52N I OIA 2-15-let-21N Su/ tor tuft PIT teoLEtt !$0L 1171FfM4FBh4/43/35 AIK 244' 9.5/F t - Cle5ES CLO5EB B WA II/A f 52N 1 0 1-DI-PSC-1Al* (WDuGGIE Pier IA SEAL COOLER 1 11715-fM4FICIA2/93 Am 245" 9.5/J $ - WR II/A le II/A II/A f 5237 1 8 1-CB-P5C-142' CE/DunGIE PWF 1A SEAL COULB 2 11715-8I1-41081/12/93 M M5' 9.5/J $ - E/A , R/A 2 N/A 11/ 4 , 5238 I e 1-Cl-PEBC-1A* 01/0u08115 PWF 1A EEAR SOE 11715-711-87081A2/93 AIII 245' 9.5/J $ - E/A WA W R/4 II/A tesLR 5239 1 18 1-35-FS-10EA SM/ttP SEAL A EEM BOE COOLE Fleu !!715-fM4FOGIS2/tt AE 244' M SE - WI W YES 11715-58-50/2 II/A i 5248 1 8 1-Cl-P5C-M1+ 01/05088E Pier N SEAL COOLR 1 11715-fM-8Fest/12/t$ AIK 245' 2.5/J S - 4/4 II/A W N/A N/A 5241 1 0 1-01-PSC-182* CE/UURGIE Ptfr N SEAL tegLE 2 11715-fM4FOGin2/B5 Am 245' 9.5/J s m/A WA le n/A N/A 5242 1 0 1-Ol4Est M* OI/UgnElsE PWF N GEAR IOK 1I715-7E0F8E1A2/95 Am 245' 9.5/J $ - II/A 11/ 4 W II/A WA (sets i 52 6 1 M l N-TS-NES SM/ttP SEAL & EUR B04 COOLR Fiel liftl-fM-4FeSin2M Am 244' t.5/K $t- W W IES 11715-IN-eBl/2 11/4 ! 5244 1 0 1-Cl-P5C-K1* 01/tIIIRCIE PlfF K SEAL COOLR I 11715-fN-OF881n2M AM 245' 9.5/J $ - 11/ 4 WA le n/A II/A v 5245 1 9 l-CR-PIC-E2* EWDIIAGIIE PIfr K SEAL COOLE 2 11715-fM-4FIE1/12/97 M 245' 9.5/J $ - WA WA W WR N/A , 5245 1 0 1-DI-PEIC-K* OI/DuntlE PWF K CDA teK 11715-f487061/12/97 AIK 245' 9.5/J $ - m/A RfA W WA N/A (EILE 5247 1 N 1-5N45-10EC SE/ttP SEAL A GUE Ind COOLER TLer 11735-7H-075E1/12/D7 AE 244' 9/K $R - W W VES 11715-55-452/2 II/A . I 3248 1 0 2-01-P5C-Bl* OI/UNEGIIE PWF 2A SEAL COILE I 11715-ftt-8 FOG 2MS/B3 Aut 245' 9.5/J s - R/A n/A W E/A WA 5249 1 0 2-CE-P5C-M2* 01/058G15 PWF M SEAL CEOLR 2 11715-fg44 FIG 2/10/33 AIK 245' 9.5/J 5 - 5/A 11/ 4 15 11/ 4 11/ 4 5250 1 ' 2-CR-PESC-M* OI/DIIAGIE PWF M SEAR BOK 11715-fM4 FIG 2/10/B3 AIK 245' 9.5/J 5 -- 5/4 R/A W WR ll/A ! cEOLR 5251 1 N 2-35-FS-letA Su/ttP 3EAL & CEM IM (80LR FLN 11715-FN-878C2ne/57 ARE 248' 9/K $t - W gi YES 1153-3g-gIE/2 WA 5252 1 0 2-Ol-PSC-N1* 01/DIIRGIE PIfF M $EAL COOLR 1 Ilf15-fM470G2AS/95 AIK 245' 9.5/J 5 - 11/ 4 H/A 15 RfA WA 5253 1 e 2-01-PSC-192* 01/Dussils PWF M SEAL CEOLN 2 11715-fEsFOG2ne/95 Am 245' 9.5/J s 11/ 4 WA W II/A WA 5254 1 e 2-tn-Post-No EWDIMEIK PIBF 3 EUR SOK ll715-fM-8FeG2AS/WI Ae( 245' 9.5/J $ .- WA WA le E/A WA EseLR , CRilFICAll8H: ine saferusues identitvles the egoisment regstred to tries the Plant to a safe stutdeux condittee en tble Safe Stutdsus Egelparet List ($5EL) is, to the test of our kameledge and nel , correct and accurate. (eme er sure signatures et systems er sperstless Easteners) sem v. JItses / DElutta Oi lunts 11, less BWIS J. IERIER / BEIIER g.IW3p' IglRDI 11,1993
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O O J Page lie.11 - It1RTH Alett IMit 1 Data Base File Name/Dete/ flue: tell SSEL.BBF / 03/11/93 / 09:33:18 - Report Date/itue: 83-11-93 / 15:03:38 5 ATE SillTOOm EQUIPEE LIST ($$tt) Sort Criteria: Line skaber SWPotTIE SYST9ts Filter Criteria: (Llos IhmterW5008') AIS (Llos lhetsre'0000') (Sarted by Line lhuber) Program File Name & Berslee: SSSI vt.0 LINE EOUIP SY5TDl/tgulPMENT < EqulPMENT LOCA!!CII -> <- W. St. -> POWER SWFWi!IE SY5. Ett'8 ImitC018ECT!915
- 10. TRAIN CLA55 IglM 10. DESCRIPit0II lbg. Ile./tew./2sse 8vilaing iIr.Elv. to er ese/ Col. 50tf lefE5 IIsrael testred tite? SE.10./91V 8 StrPWTIE CIPFWENTS (1) (2) (3) (4) (5) (5) -(7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 5296 1 19 1-5U-TE-103C SW/tCP LWE CIL COOLEt COPROL 11715-5W-099/E M. 246' 9/J SI - ON WI TES II/A II/A 5297 1 18 1-W-TT-1034 SW/CCP LISE OIL C00 Lit control 117154M-070G1/12/D4 M 246' 8.2/J 5 t 35 ON WI Vt3 11715-35-007/E 1-Cil-P-14 5298 1 18 1-55-TT-1938 SM/TCP LIBE DIL COOLD COEROL 11715-fM-478G1/12/Ils AllK 246' 8.5/J $ t 36 ON lu VES 11715-5W-008/5 1411-P-18 5299 1 18 1-5W-TT-193C SU/tCP LWE DIL C00 Lit COEROL 11715-fM47eC1/12/DB Allt 746' 9/J S t 36 el CN VES 11715-Su-est/5 1418-P-It 5300 1 18 1-SN-155-1934 SM/tCP LISE Ott COOLER CON 180L 11715-fM-870G1/12/D4 58 252' 6.b/9 , $t - ON Of its 11/ 4 II/A 5301 1 18 1-5W-T55-15 Sil/tCP LW Ott C00 Lit Comtot 117154M-078G1/12/DG SS 252' S.54 $t- ON 0 11 fts IL'A N/A 5302 1 18 1-3W-TW-103C Su/tCP LIBE OIL C00 Lit CONTROL 11715-FM-070GI/12/DB 58 252' 6.5/D St - CII CII VES II/A WA 5303 1 20 1-5W-il-1934 Su/tCP Ltat O!L COOLH COMEOL 11715-fM-078G1/12/D4 38 277* CR 5t 35 ON ON Yt3 11715-35-807/E 141-C8-05 5304 1 20 1-5W-fi-183 su/CCJ List GIL COOLER Com0L 11715-FM-cFsGI/12/DE 58 277' CR SE 3E ON ON TES 11715-58-808/6 1-El-CS-05 5305' 1 20 1-5U-fi-183C SE/tCP LISE Olt COOLER Coment 11715-fM-OFIG1/12/DB 58 277' CR S t 35 ON GI Its 11715-35405/6 14143-05 530E 1 21 24N4-5A CII/CCP Likt DIL IIlOLG 117154M-870G2/10/D4 AUK 244' 9.2A $ - WA II/A IS 12058-E034/2 Ott 5307 1 21 24N-E-58 til/ttr LIBE OIL COOLEt 117154M4FeG2/le/DE Allt 244' 9.5A $ - II/4 WA le 12 ele-su435/2 Oft 5308 1 21 2-CN4-5C Cil/ECF LW OIL COOLD 117154M479G2/10/98 AUK 244' 10A S - II/A II/A le 12050-EO3E/2 OIL 5309 1 07 2-Su-TCV-202A sal /tCP List OIL COOLER Comol 11715-FM47EC2/10/D4 AMK 244' 9.2A - - WDI 17 01 le 12058-55-834/2 II/A 5310 1 07 2-5W-TCV-208 SE/tCP LISE Olt COOLtt COEROL 11715-FM479G2/10/DE AUK 244' 9.5A - - 17 01 17 01 le 12058-Ee35/2 II/4 5311 1 07 2-5W-itV-202C SW/CCP LWE Olt C00Ll3 COEROL 11715-FM-079G2/10/DB AUK 244' 10A - - OPDI 17 01 le 12950-E036/2 II/A 5312 1 18 2-ETIC-20!A Su/tCP LIBE OIL C00 Lit COMEOL 117154M470G2/10/D4 auk 244' 9.2A 5t - GI GI Yt3 12058-Ee34/2 11/4 3 5313 1 18 2-Sif-ilt-2026 Sil/CCP LWE Olt COOLER COEROL 117154M-870G2/10/DE Alet 244' 9.5A 5t - SI 0 11 ft1 12c58-55-035/2 WA 5314 1 18 2-W-TIC-202C SW/ECP LW OIL COOLN CONTROL 11715-FM-OFeG2/10/DB Aut 244' lea $R - ON GI Vt3 12058-5W-83E/2 II/A 53]D 1 19 2-5N-TE-2034 Sif/tCP LISE SIL COOLER COMROL 12050-E022/5 Aut 24E' 9/J $t - al al v5 II/A st/A 5319 1 19 2-Eit-2038 Su/tCP LISE DIL C00Lft ComOL 12050-E023/5 AUK 246' 9.5/J $R- 31 et YES 11/ 4 II/A 5320 1 19 2-ETE-203C Su/tCP LISE OIL C00 Lit CCICROL 12050-SU-824/5 AUK 246' 10/J $R - 0 11 ON 115 IVA II/A 5321 1 18 2-5W-TT-2034 Su/tCP LISE OIL COOLH COm0L 11715-fM478G2/10/04 AUK 246' 9/J 52 - el UN Yt3 11850-E022/5 II/A ,
i CERTITICAllGE: , The leformellen identifying the egulpment regelred to Srlag the plant to e safe sinstesun condittee se this safe Shetdeue Egelsment List (ISEL) is to the best of ser kasuledge and hellef. correct end accurate. (One or more signeteres of Systems er Operstless Eaglesers) Omst v. JnCOBS / DIGlKtt h MIRCil 11. 1993 DAV10 J. WERGER / EIE1EER iuACII 11, 1993 7 Eignature _ _ _ _ . _ _ _ _ . . . _ _ _ . - . . .__. _ _ . - _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ . _ _ _ . . _ _ . _ . _ . . - . _ _ . _ - . _ _ _______.______.________..___.-_______.m_______.-_._.. _ _ _ _ _ _ _
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w . V 1 Page lie.13 IERTil Alett t!Illi 1 Data ease file Esme/DataAlme: 1E1 SSEL.leF / 03/11/93 / 89:33:18 i Report DateAlue: 03-11-93 /15:e3:M SAFE SMUT 90blu EQUIPMENT Lili (!$EL) Sort Criteria: Lies Iluster
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SWPotilE SYSTO6 (serted by Line lasuber) Filter Celteria: (Llee lessher>.'500s") AIS (Llee IIsaberc' esse') Progres File liame & Verstee: 5101 we.e i LIII feUIP $YSTD4/EQUIPMDit < EOUIPMENT LotAT10ll ----> <- OP. ST. -> PeuEt SWPetTIE $YS REQ'8 INTEttmeECTicNS , Is. TRAIN CLAll 80RC le. SE$ttIPTION lbsg. Its./tev./Zene solldlag F tr.Elv. Es. er tow /tel. $0ti leTES IIsrael Desired REDF ele. le./IET. 8 SirPERTIE tief9Elff$ i (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 5346 1 18 1-SU4T-104 $N/5B RETWilIIEASE1 Flow 11715-fM-075t/04/97 SIMI 32e' Itt 11 5t- GE ON WS Il715-W-81W3 II/A 5306A 1 20 1-5541-104A su/55 RETistilllEAREE FLOW 11715-FM47sI/04/97 5t 277' tt 5t - si cN TES II/A II/A 53els 1 20 1-Su4I-104e SW55 RETWN llEADER Flsf Il715-fM-878WD4/97 58 277* tt 5t- ON . 91 TES WA WA 5348 1 004 1-24Wr-1234 SN/51f MSEtt0It ISOL llT154M47 ell /94/E4 SIMI 326' ~ t - CPEN 87 08 le 11/A IL/A , I SMS 1 004 2-Su4et-22M Su/5W EESUVDit ISOL 11715-FM47 ell /04/D4 SIMI 326' - R - ePEN cPDI le II/A II/A l 558 1 een 1-W-let-12M Su/5U K59V0lt I1cl IIT154M478W94A8 SIMI 326' - R - CPDI 17 01 le II/A WA [ 551 1 004 2-SINWV-2234 Su/5W WESEncit !$0L 117154M4751/94/DB SIMI 326' - R - CPDE trDI le E/A II/A 553 1 004 2-5N4et-221A SU/5W 10 ARRAY 5 11715-FM-87W1/94/ts SIMI 326' - t - cPDI SPDB le II/A II/A 554 1 804 2-3540r-222A su/55 N AARAYS 117154M47 ell /04/E7 Snit 326' - E - trDI OPDI le IL/A 11/ 4 555' I set 1-56-set-122 Sil/5W 10 AnaAYS 11715-fM478WDS/C7 SIMI 326' - R - OPDI 17 01 10 II/A II/A 5356 1 804 1-Su4er-1225 SN/5U M AARAY5 11715-fM47eII/94/t6 SIMI 325' - R - OPDI 17 01 le ll/A 11 / 4 5M7 1 set 1-5N-Set-1384 51f/55 N Ser l'AL 11715-fM-87 ell /94/CE SIMI 326' - E - Cle5EB CLD5ES le II/A II/A 5358 1 set 1-3N-8st-121A W/5510 AARAYS 117154M47 ell /94/t3 SIMI 326' - R - CPUI trER le II/A 11 / 4 5359 1 ett 1-Su4er-1224 51f/5810 AARAYS 11715-FM-87st/94/t3 SIMI 326' - R - OPDI trDI le II/A II/A 5308 1 004 2-11Mer-2215 Su/5U 10 AAAAYS Il715-FM-878lI/94/C4 SIMI 326' - t - CPDI 17 01 IB II/A WA SMI 1 004 2-W 4ct-222B Su/5W 10 AftAYS 11715-fM-87st/et/t4 5tMI 326* - t - ePDI ePDI le II/A 11/ 4 5352 1 885 2-Su-30t-2105 3M/5W 10 ster ISol 117154M-87 ell /04/C3 3 mil - - R - CloSEB CLc5ED le WA 11/ 4 e 5363 1 004 1-W4ct-leet SW/tt M IEET 13cl 117154M-878C1/32/A4 AM 244' - R - OPDI (FBI le II/A II/A
$354 1 004 I-su4st-less SilAt 10( IEET ISOL 117154M-878C1/32/A4 Allt 244' - t - trDI tFDI le II/A II/A 5355 1 804 2-Su4st-20e4 SilAt M IEET 150L 11715-fM47eC1/32/A4 AM 244' 9.3/7 t - CPDI SPDI le II/A II/A 53E6 I 004 2-SIMer-20Is ss/tt M IEET ISOL 11715-FM-e7ett/32/A4 3nli - - t - CPDI OPDI le ll/A II/A 5357 1 20 2-5W-TI-2058 SNAC M IILET TDP 117154M-87st1/32A8 58 277' CR SE - ON 0 10 YES II/A II/A 53E8 1 20 2-5U-il-205A su/tt M IEET fBF 11715-fM-47st1/32/E7 :s 277* tt 5t - al St TES 11/ 4 It/A CGTIFICAi!Gl:
ite Inforeetten Ideetlfyles the equipmeet regelred to bring the plant to a safe slurtdeun canditten en this Safe Stutdeus Equipuret List ($5EL) Is. to the best of our kasuledge and tellef. and accarote. (0se er more sl9metures of Systaes or Operstless Eagleeers) IMARI W. J4tlet / EEIREEE 188 01 11, 1993 OAVID J. WEEcEt / DEIIER lelRDI 11. 1993 y at
tota Sese File Mme/ Bete / flue: Igt! $$tt.38F / 31/11/g3 / gg:33;}g ItlRf4 AfSIL Ifff f 3 - Page he. 14 5 Aft Simfflppi Equ1Petut LIST ($3EL) sort Crlteria: time itsster Report Sete/fler: 03-11-93 / 15:03 35 Sirrefilt $71TEMS filter Criteria: (Lime ilumberW5088') NO (Line limberc'8888') (Sorted by Ltne Ihmiter) Progree file IImme 8 9erslee: S$91 vt.4
<- CP. ST. -> PWit SIf9WTIE SYS, ttS's Illiterumasrticiss
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- Sum /Cel. SMT IOff! IIsrael testred Et97 35. le./ttV. 8 SIrretTIE CarWENTS 15 . itAIN CLAS$ Mtt 10. K5CalPil0Il (6) (7) (8) (1) (le) (11) (12) (13) (14) (15) (18)
(1) (2) (3) (4) (5) et MS II/A 2-SletlA-51M 11715-fts-078C1/32/tB $8 2H' CE $t- GI 5359 1 20 1-5W-11-1958 3M/CC M Itti T9F 11715-FIl478C1/32/E5 58 2H' Ot $t - CII CII WS II/A II/A 5370 1 20 1-5W-il-1954 Su/tt HK IEET 19F 2U' Ct $t- WI el MS II/A m/A 2-55-TI-N78 SWCC HKIUTLETTOP 11715-ftl478C1/32/E7 38 5371 1 28 2H' CR $t- ON GE WS WA N/A 2-Su-il-2974 SWCC ut elRLET 19F 11715-fts-878C1/32/tB SS 5372 1 20
$t- WI TES 11/ 4 II/A sif/tc ut Outtti 109 11715-HI-078C1/32/E8 58 2U' CE ON 5373 1 20 1-5W-it-1148 277* CR $t- CN SI W$ WA II/A Sil/tt NK ORLET T9P 11715-FIl478C1/32/E5 38 5374 1 20 1-58-11-1144 2U' CR St- II/A II/A WS II/A WA 141-C841 El/IDEN BOARS 1-1 117154E-0278/33/4 38 53U 1 20 277' CR $a- II/A II/A WS WA N/A tI/8010180ARI 1-2 11715-FE-8278/33/4 18 5378 1 20 1-El-C4-02 23' Ct $t- 11/ 4 11/A WS 11/ 4 h/A $379 1 20 14I48-83 ft/VttitCAL BOARS 1-1 Il7154E-8278/33/4 58 2H' CR $t- II/A 11 / 4 WS R/A II/A 117154t-0278/31/4 $8 53R 1 20 141-CS-04 EI/VttTICAL 80AAB 1-2 2H' $R- 11/ 4 11/ 4 WS II/A II/A 5381 1 20 14I48-85 El/WRTICAL 80AAS 1-3 117154t-et18/33/4 38 CR 254' 8/C8 $t- II/A II/A WS II/A II/A 14148-884 EI/NRILIAti 514fl801A1 PAIEL 117154t-027A/22/A3 38 5382 1 20 254' S/tB $t- II/A II/A W$ R/A II/A E!/NRillatY sinff00lst PAIEL 1171541-427A/22/43 $8 5383 1 20 1-El-CS-eIS 2H' CGF 82 $R- II/A II/A WS E/A 11/A 20 14148-104 (1/tX8FIRtt 1/0 CA8tIET 88 11715 4 1-0278/33/5 58 5384 1 2U' CGF 82 $R- 11 / 4 II/A WS II/A N/A $385 1 to 141-t8-188 EI/t991Rtt I/O CAtlalti el ll715-FE-0278/33/5 SS IU' CSF 12 $t- WA II/A WS II/A II/A 5388 1 20 1-tI48-18C El/tGruftt 1/9 CA8tlET 02 181541-8t78/33/5 S8 2U* LOSIC $t - N/A II/A WS II/A II/A ,
5387 1 28 1-fl-CS-21 El/tesROL PMEL 117154t-Of78/33/8 58 SN; lei AVAIUBLE Sil 252' 8.4/8 5t- II/A II/A WS II/A II/A 5388 1 20 1-II48-214 EI/ESIIESL PNEL 38 252' Ist 51 $ t 41 N/A II/A WS II/A WA 5389 1 20 141-CS-234 El/ PROCESS CASIIET A 117154t-setA/22 58 251' Itt 91 $ t 41 n/A N/A W$ WA II/A (I/pt0CES$ CA8tIET 5 117154t-40E8/28 5318 1 20 1-t148-238 38 252' let 81 $ t 41' N/A N/A WS II/A WA EI/P80 CESS CA81tET C 117154E-800C/24 SNI I 20 1-El-CS-23C let 51 5 a 41 II/A II/A WS N/A II/A 117154t-40e8/U 38 252' 5392 1 20 1-tl-CI-23 (1/PROCES$ CAtlIET 5 58 252* Ist 31 5 t 41 11/ 4 II/A WS II/A II/A II/PtoCESS CASIIET t 117154t-800t/18 1393 1 20 1-fl-CS-23E CitilFICAilWl: The leforentlee leestifylel the egulpuset regelred to bring the plant to a safe shotdeue condittee se this Safe Shotduum Egityment list ($$tL) Is, to the best of our knowledge and hellef. carrect and accurate. (One er omre signatures of Systees or Operations Englesers) SAlAlW. JAOR$ / DEllEtt h 188 01 11, 1993 IWA01II 1993 0 Avis J. uttett / DEIIEtt
. .m O s j
Data Saee File muse / tete / Time: IILI
~ S5EL.ISF / 01/1LT3 / 08:
33:14 Mfil A188I WII I Page No.15 5 Aft $11Gf00lst Egillf*ENT LIST i!5EL) 5ert Criteria: Llee lheter Report Dete/Ilse: 83-11-93 / 15:03:38 5trP0lillE SYSTD5 Filter Crtterlo: (Llee number >.'5000') AIB (Llee lhetorc'Oggt') (Sorted by Llee muster) Progree File huse & Uurstee: 5581 ve.e I I
< ESitMElli LEAillBI -> <-IP. ST. -> PERIER SWPWTIIE SYS. Ett'8 INTERCINEECilINE LIE EOUIP $Y5fDI/EOUIPENT IGRE 10. Ot3CRIPil0ll Dog. Ile./tev./Zeer Belldlag iIr.Elv. Re. er tes/tel. SWI lERE1 IIsrael testred Rtyt gut.15./ttv. & 51rPORTIIE CIpp0ENTS NO. TRAIN CLASS (6) (7) (8) (9) (le) (11) (12) (13) (14) (15) (15)
(1) (2) (3) (4) (5) II/A 277' LOGIC 5t - II/A 11/ 4 WS 11/ 4 , 5394 1 20 1-El-CB-25 El/ CONTROL PAfEL 11715-Ft-0275/33/4 58 IME ICT AMILABLE 58 277' 8.8/B $t- II/A II/A WS II/A 11/ 4 5395 1 23 1-tI48-308 El/CONIROL PAEL SK 252' 5.2/9E $R- II/A _ II/A WS WA II/A EI/tRNfROL PasEL 11715-FE-027A/22 530E 1 20 1-El-CR-181C 277' CR St- N/A WA WS II/A WA 5397 1 20 1-El-CS-34 EI/P051 ACC10DK lollfctING & 11715-it-0275/33/4 $8 CipITIOL PAfEL 11715-FE-OS4G/21 38 252' fat 91 $ t 41.42 II/A II/A WS II/A II/A 53g8 1 20 1-El.CS-44 EI/ PROCESS CABIET T EI/50LIS STATE PROTEtileIl IWUT 11715-1.31 $GIES 38 252' IAR 81 $ t 41 II/A 11/A TES 11/ 4 11/ 4 5399 1 20 1-E148-47A CaglEl (TRAIN A) 252' Itt 91 5 t 41 II/A - 11/ 4 WS 11/ 4 11/ 4 1-(145-478 (1/30Lle $1 Aft PROTECTION lerUT 11715-1.313GitS SS 5400 1 20 CAtlEl (ftAIN B) 252' Itt 31 5 t 41 II/A II/A VE5 II/A 11/ 4 20 1-El-tt-47C EI/50LIS STATE POOfttiloll LOGIC 11715-1.31 Stalts SS 549) 1 CABIIET (TRAIN A) 11715-1.31 SERIts 38 252' IRR 91 $ t 41 II/A 11 / 4 MS II/A II/A i 5402 1 20 1-EI45-475 El/50 LIB STATE PROTEttlON LOGit CAOlET (itAIN 8) I 252' IRR 91 $ t 41 II/A II/A Yt3 II/A WA 5483 1 20 1-tI43-47E (IP/50LIO $1 ATE PROTECil0N OUTPUT 11715-1.31 SGIES $8 CASIIET (TRAIN A) 252' IER 91 5 t 41 II/A WA VES II/A 11/ 4 5404 1 20 1-El-CS-47F tt/50LIO STATE PROTECTION OUTFW 11715-1.31 Sitit$ 58 (Jeluti (itAIN I) 252' IM 01 $ R 41 II/A WA TES II/A II/A EI/ARILIARY ttLAY RACE I 117154t-etTA $8 5405 1 20 1-tI-CS-eth 38 252' IER 91 $R - II/A II/A M5 11/ 4 11/ 4 EI/PfligtY Pusti PROCESS CABIET 1 117154E-SETV/1
$405 1 20 1-El-C5-31 58 252' Itt il st- II/A II/A WS II/A II/A 5407 1 20 14I-CS-52 EI/PflIGRY Puftf PROCESS CABIIET 211715-FE-047Y/1 58 252' IER 11 5t - II/A WA WS II/A IW 540B 1 20 1-E148-53 El/PtllWRT Pufli PROCESS CJ8IET 3117154t-8045/19 58 252' IER 81 $t - II/A 11/A TtS II/A WA 5409 1 20 1-El.C5-54 EI/PallWEY PUIK Plotts$ CASIET 4117154E-047Y/1 SO 252' let 91 $R - 11/ 4 II/A W$ II/A II/A 5410 1 20 1-tl-CB-55 ft/PRIlWRY PLAllt PROCtst CABIIET 5117154t-00Ed/11
$8 252' Itt il 3t- II/A II/A Yt$ 11/ 4 WA ;
5411 1 20 1-tI48-54 El/PtllWRY Pulli PROCESS CABIIET $ 11715-FE-00EV/16 i 252' Itt 31 $t- II/A II/A YES II/A II/A EI/PallWRY PufR PROCESS CABIIET T 11715-Ft-047Y/1 58 5412 1 20 1-fl-CS-57 CEtilFICAll0M: The leforsetten Idrettfyleg the agelpment regelred to bring the plast to a safe sketdess tenditles se this Safe Shetdues Egelperet List ($$tt) Is. to the best of our kneeledge and tellef. correct sad accerote. (One er more signeteres of Systees or Operettees toglesers) RinAl W. JACOB 5 / DEIIEtt b luRCt 11.1993 f IGRCII 11, 1993 94V10 J. MUSEE / DEIIEtt
/5tgesture
. - . -.. . . . . . . - . - - . - - - . - . - . .. - - - _ - ,~~ -. -. . - . .~ ~ . . - - . . . . . . . - - -~ O O i Page lie.16 IERTII AISE lAlli 1 Beta Base File Ihme/ Bete /Ilse: Iml- $$EL.NF / 03/11/93 / 09:33:18 Report Dete/Ilse: 03-11-93 /15:03:M 5 Art SIRframes EpJINN LIST ($$EL) Sort Criteria: Lies theter SIPPoltTIE SY5fD5 filter Criteria: (Llee heterse*5050') AIS (Llee thuberc'0000') (5erted by Line lhmber) Program File Name & 9ersten: SSSI se.0 LIE E0111P SY5fDl/EllflMNT < - ESMPIElff LOCATIGI -> <- W. ST. -> PRER SWPIEilE SYS. REI'8 INFERONECTISE t
- m. itAIN CLASS MARK M. DESCRIPfloll Sug. Ite./tev./Zene Bulldlag F tr.tiv. Re. er Rem /Cel. 50Ri IWfi$ Iternal Bestred MIST BE. IB./REV. 8 51rPORIIE OBOWEIIts (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (14) 5413 1 M 1-II-CS-58 EI/PRIIWAY PLANT P00C155 UBIET 8117154E-04TY/1 58 252' Itt Il 52 - WA WA M5 11/ 4 WA 5414 1 28 1-tI48-62A El/5AFEGatOS TEST 0011ET A 11715-I.31591E5 SB 25T IRR 91 $t- 11/ 4 WA VE5 11/ 4 II/A 5415 1 20 1-Et-C84IS !!/5AFittaIRDS itST CABIIET B 11715-1.31591ES 58 252' IEt il 5t- II/A _ E/A WS 11/ 4 II/A 5415 1 20 1-tI48-64A EI/50L18 STATE Past SYS AGE RELAY 11715/12058-1. 5 -458 58 52' Itt 81 $ t 41 II/A WA WS II/A II/A RACr 5417 1 20 1-tI-CO-648 ft/50 LIB 51 Aft PAST SYS ARE EtLAY 11715/12058-1.28-458 58 252' IRE II 5 t 41 II/A II/A WS 11/ 4 11/ 4 RAut 5414 1 20 1414P-84 E!/IIItalEROCES5R G8tlET 117154t-8278/33 38 277' CR SE- 11/ 4 II/A WS 11/ 4 II/A 5418A 1 20 14I-CP-7 EI/AMSAC LOGIC PAIEL 117154E-Of7A/22/G2 58 252' IRE 01 S E 8,41 II/A II/A WS II/A II/A 54108 1 20 14I48-201 EI/BIE5tL 150L PffEL (N-TRAIN) 11715-Ft-ME/3 38 272' ESC $ R 6,41 II/A WA WS II/A II/A 5410C 1 20 2-EI48-201 ft/ Bit 3EL ISOL PAIEL (N-TRAIN) 120lME-855F/lf 18 272* EOG $ t 6,41 11/ 4 II/A H5 WA II/A 5419 1 20 1-EP-CS-let EP/PR BI51RIOutics PfdEL 82 RE Ist AullASLE RGM 200' 12/K $t- 11/ 4 II/A WS 125184C-188/8 II/A 5420 1 20 1-EP-CS-NF EP/RCS PR ORIIt0L PAIEL BMG ICI AMILASLE RGM 200' 12/ 5t- II/A II/A WS 1254-IC-188/8 II/A 5421 1 20 1-IP48-204 EP/APPOSII t ISOL PAIEL 117154t-erFA/22/At 58 254' 8/C $t- 14/4 II/A Yt1 11/ 4 II/A 5422 1 M 1-EP-CO-204 EP/AINILIARY RttAY RACK A 11715-FE-EC/29 58 252' Itt 91 $ t 41 II/A II/A M5 11/ 4 II/A
$423 1 20 1-EP48-288 D/ldEILIARY RELAY RAEK B 117154E-M/M 58 252' Itt 01 $ t 41 II/A WA WS 11/ 4 WA i
5424 1 20 1-EP-CS-20C EP/AINILIARY RELAY RAut C 117154[-EE/26 38 252' IGE 91 $ t 41 II/A II/A M5 II/A II/A j 5424A 1 20 1-EP48-2OE IP/ARElllARY HLAY RACK E 117154t-ME/B 58 252' IRR 41 3 t 6,41 II/A R/A WS WA II/A s 54248 1 20 1-IP48-20F EP/AIEILIARY RELAY RACK F 11715-FE-M/9 58 252' Ist il s E 8,41 11/ 4 WA WS 11/ 4 II/A 5424C 1 20 1-EP48-20C EP/ARRILIARY RELAY RACK C 117154E-MI/15 58 252' let 31 $ e s,41 II/A II/A W5 WA II/A ; 5425 1 20 1-EP48-2WI EP/ sir LeEIC DOIIET 1A 1171541-MK/22 38 252' " II $ t 41 II/A WA WS WA II/A 54254 1 20 1-EP48-2EIIK EP/5tf LOGIC G8IIET 1A1 117154t-3IN11 38 252' lut 81 $ t 6,'41 14/ 4 WA WS WA II/A 54258 1 20 1-te48-28J EP/51f LOGIC G8IIET 10 117154E-ML/26 58 252' IRR 31 5 t 8,41 II/A WA WS II/4 II/A 5425C 1 20 1-EP48-283 EP/5N LOGIC U$llET 181 117154E-3L8/11 58 252' IRE 91 $ t 5,41 II/A IVA WS II/A WA l CERTIFICATIGt: The leforsettee lerettfyleg the egulpment required to brlog the pleet to e safe shutdeue tenditlen se this safe Shutdeue Egstparet List (SSEL) ' Is, ts,the best of our keeuledge end tellef, t and occurate. (One er sure signatures of systems er Operstless Eaglesers) BMAI W. JhttBS / EEllEER /7 IGRDI II,1993 84VID J. UDBER / EE!EER g r useet r* 15A0111,1981 l t i
_ . ~ _m . .- r m m. - . - ~ - .- - - - __ _- - _ _ . _ O J Data Base file Name/tute/ Time: IILI $5EL.50F / 01/11/93 / 09:33:18 o ' NDETR AlelA INIT 1 - Page No.17 5AFE SIEUTODIAI EgillMNT LIST ($$EL) Sert Criteria: Llee lheter feport Date/ flue: 03-11-93 /15:01:M Fliter Criteria: (Lies Ihubers '5000') AIS (Llee ihmtset'8000') 5trP0fflNG 515fDE5 (5erted by Line Ihaber) Program file Ihme & Wurstee: 5591 ve.8
< EllflP9ENT LOCATIGI w <- IF. ti. -> PmER SIrPaills $Y5. seq's INTEtaggECTIW5 t LI3 EglifP SY5TDL/Egl!!PIEW !
- 10. TRAIII CLASS NAtt 10. DESCRIPIION Dug. Ite./ter./2sae Bulldlag F tr.Elv. to. or tou/ Col. SMT IINES lbrael Bestred RES? lRE. Ig./9EV. 8 SirPWillE CGrWEWS '
(5) (7) (8) (9) (10) (11) (12) (13) (14) (15) (14) (1) (2) (3) (4) (5) 252' Itt 11 5t 6,41 II/A WA WS II/A WA i 54250 1 20 1-EP-CE4M EP/ LOOP Sitr MW LOGIC CABIRT 11715-1.32 5BIES 58 ! SACK A 252' let 91 5t 6,41 WA WA VES II/A II/A 5425E 1 20 1-EP-CS-EM EPA 00P STOP MVE LOGIC CASIIET 11715-1.32 SHIES 5t r RACK B 5425F 1 20 1-El-CS-11GC EI/tes ISOL ltlP MW RELAY 11715-TE-12K1/5/ts ALE 260' 11/K $t 5.41 WA WA IS 11715-SC-152/1 II/A
"" l 117154E-10EK1/5/F2 ARE 200* ELEC TWEEL 81 11 6,41 WA II/A WS II/A II/A 5425C 1 20 1-EP-G-1158 EP/t0NT 150L TRIP MVE RELAY [
PANEL A-1 117154E-188K1/5/J2 AIX 200' ELEC TWEEL 81 $ t 8,41 WA WA WS II/A II/A 5425N 1 20 1-EP-CB-115C EP/t0NT ISOL ft!P VALVE RELAY PAIEL A-2 ALE 277' LOGIC NI 91 S t 6,41 II/A II/A VES 11715-$$-0N/3 1-EP-C5-194 5425! 1 20 1-EP-CB-121A EP/ CONT 150L TRIP MW EELAY 13075-FE-M
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s CUTIFICATISI: , The leformattom lerettrying the egulpment regelred to bring tk plant to a safe sketduum candittee se this Safe Simrtdeus Egslament List ($1EL) Is, to the best of our kneuledge and tellef, correct and accurate. (One er unre sipatures of Systems or Operatless Engineers) DAIRIV. JAtl3$ / DElIE R b IgdCR 11,1991 18W0111,1993 DAVIO J. WEE 9Et / DEINEtt ;
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CERTIFICAllel: > The leformetlee identifyleg the egelpenet regelred to bring the pleet to e safe sketdeas condittee se this Safe $hetdeen Egilement List ($5EL) , is, to the test of ear kneeledge and belief, correct and occarate. (See or este sigesteres of Systems or Sprattees Eaglesers) lukui 11,1993 RAIII W. JACMS / UEllEER i 18W0111,19B3 C.VID J. MRSER / DElstit I
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(5) (7) (8) *1) (10) (11) (12) (13) (14) (15) (16) (1) (2) (3) (4) (5) 12.5 1 23 II/A IVA NO II/A II/A 5077 1 21 2-DG4-1 BG/ PRIMARY DRAIN TRAN5FER CDOLER 120504M-0716/17/A6 CONINT 216' 12050-fM-07945/17/E7 CONTMT 216' 17.5 $ 23 II/A R/A le N/A N/A 5082 1 !! 2-E-E-1A N5/EUTRON $NIELD TAIK COOLER 12050-fM-07945/17/E5 CONIMT 216* 17.5 $ 23 11/A , II/A le ll/A WA 5083 1 21 2-115 4 -18 E/NEU! Roll SNILLD TAIK COOLER CC/tIR FlpF SEAL COOLER CUTLET 1205HM-071M/17/C4 ColmW 231' 1 St - ON ON TES 120504C-0EE/1 II/A $084 1 19 2-CC-TE-250A TDF 120504M47945/17/C4 CONIMT 231* 1.5 $R - ON 04 TES 1205MC-027/1 N/A 5085 1 19 2-CC-TE-2508 CC/ Rut Pier SFAL COOLER OUTLET TDF
- - - - CLO5EB CLOSES 19 R/4 II/A 5086 1 07 2-Il54CV-201 Il5/IEUIRON $NIELD SIItGE TAE 12050-FM-07945/17/93 CamG CUTLET ISOL
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$148 1 20 241-CS-0EA EI/AINILIARY $11UTD01A1 PAEL 120504E-027A/20 58 254' DER $1RR $R- II/A II/A YE! II/A II/A 5149 1 20 2-El-CS-Ost EI/AINILIARY SHUTD0lel PAEL 5t - N/A TES II/A II/A e 117154E-0278/33 $8 277' CSF 82 N/A 5150 1 20 241-CS-laA El/CerVTER 1/0 CASIET 00 117154E-0Z?t/33 $8 277' CGF 12 5t- H/A N/A H5 II/A N/A $151 1 20 2-El-CS-let El/CD9 UTER t/D CA8tlET 01 11715-TE-0275/33 58 277' CSF 12 5 t -. R/A II/A WS N/A II/A 5152 1 to 2-EI48-let El/CGruftt 1/0 CASIIET 02 11715-FE-0275/33 58 277' LOGIC $R - II/A II/A W5 N/A II/A r 5153 1 20 241-CS-21 EI/ CONTROL PAIEL CNG leT AVAllattt Sit 252' 8.4/D $R - m/A N/A TE$ II/A II/A $154 1 20 2-El-C9-21A El/ CONTROL PAllEL 58 252' Itt 92 $R 41 II/A N/A TC$ II/A II/A 5155 1 20 2-El-CS-234 El/PROCE13 CASIKT A 12050-TE-027A/20 120504E-027A/20 $8 252' Itt 92 $ t 41 11/ 4 N/A TES II/A II/A 5156 1 20 241-CS-23 EI/Pil0 CESS CASIKT S CERTITICATIGt:
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- u. TRAls CtAss nut le. EsCRIPitcIs cup. no./see./zene seiktine rir.tiv. to. er tow /Cel. sett mits threat nestrud unor sE. Is./ttv. a sappetits aprenDas (1) (2) (3) (4) (5) (6) (7) (t) (9) (le) (11) (12) (13) (14) (15) (16) 5405 1 21 2-ts-E-It R$/IEIN RECIE SPEAT COOLit 5 120!io-f40flA3/21Ut3 Colmff 216' 5 N 14/ 4 IVA le 11715-516-87303 $Uvitt mig Sees 2 21 2-t$-E-3C R$/IEIN RECIRC SPEAT CDOLER C 12058416491A4/21/98 Celmff 216' $ 26 IL/4 11/ 4 IB 11T15-7487m3 $ttVICE IItTIR 5887 2 21 2-t$-E-10 ts/IEfE RECIRC 3 PRAY COOLIE D 12950-ftt49144/21/57 Cipmff 2N* 5 26 II/h IVR le 11715-ftt-87W3 $Elvitt mia 9
i CInflTICAfl0ll: The Infersettee idrettfying the egulparet required to 6rtog the plant to e safe statesse condittee se tels Safe Shutdeme Egulparat List ($3E1) is, to the best of our knemledge and belief, correct and accurate. (One or more signatures of Systees er Operettees Eaglesers) Buff W. JAtles / DEIEtt bl IWAuf 11,1993 BRVIO J. WERDER / DEIEER 198D111,1993
l I Revision 1
- O l Appendix G ELECTRICAL SYSTEMS l d
b i This appendix describes the emergency electrical power supplies used to support more ; j ' than one of the four safe shutdown functions addressed in Appendices B through E. De electrical systems were listed separate from the supporting systems of Appendix F to facilitate database manipulation. The electrical drawings used to develop the SSEL are .l
- included in Appendix N. ,
I Each unit's AC Power Distribution System consists of three normal 4kV buses (A, B and [ l C), a single 4kV bus (G) in the intake structure, and two emergency 4kV buses (H and ,
- J). The equipment which has been selected for safe shutdown is directly or indirectly l powered from the emergency buses. The 4kV emergency buses can be supplied from tie diesel generators or off-site power. This ensures a reliable supply of electric power to the safe shutdown equipment. The electrical distribution system required for safe
! shutdown is shown on the electrical one-line diagrams. The electrical distribution ! components required to function are listed in the SSEL The emergency diesel generators (EDGs) are an on-site power source which can supply { power to the essential safe shutdown equipment if the normal off-site power sources are j unavailable. There are two 100% capacity diesel generators for each unit. Each diesel ! generator has a continuous 2000-hour rating of 3000 KW and a half-hour rating of 3300 l KW. The capability exists to provide power to all the safe shutdown equipment required
- to shut down both units.
l The diesel generators are located in individual rooms and are supported by completely
- separate auxiliary systems. Each diesel can be started by either of two redundant
- compressed air starting systems.
I The diesel engines are each fueled from day tanks located within the EDG Rooms. The day tanks are replenished via underground fuel lines from two 50,000 gallon storage ! tanks. i l There are two redundant pumps for each diesel generator to transfer fuel oil from the storage tank to the diesel generator day tank. Each set of pumps is powered from the emergency bus associated with the diesel to which the pumps supply oil to ensure a
- continuous supply of fuel. In addition, a 210,000 gallon above-ground fuel oil storage i tank is used for transferring fuel to the buried tanks.
Diesel engine lubrication is provided by engine-driven and motor-driven lube oil pumps. l The engine-driven pump has sufficent capacity to provide the required lubrication. i
- G-1 i
1
i 1
- Revision 1 During EDG operation, ventilation is provided by the main diesel cooling fan. The main diesel cooling fan is located on the engine skid and is powered by a mechanical power ,
takeoff on the diesel engine. - l Diesel engine cooling is provided to dissipate the heat produced by the engine and the lube oil coolers. An engine-driven pump circulates coolant through the engine to a , radi7.ior to maintain the required temperature. The diesel generater radiator cooling i syst em is completely self-contained within the Emergency Diesel Graerator Room. , 1 i The elcrical distribution system used for safe shutdown is highlighted on electrical diagrams h: Appendix N and safe shutdown equipment is listed in this Appendix. j Electrical distribution system SSEL items have line numbers from 6001 to 6999. i l b i d f O O G-2
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- Revision 1
- O Appendix H 4 SMALL BREAK IDCA AND CONTAINMENT SYSTEMS 1 :
i This appendix describes the equipment required to support the inventory control and j decay heat removal functions to achieve safe shutdown with a seismic induced one-inch small break IDCA. EPRI NP-6041 postulates such an event in defining requirements for i safe shutdown success path selection. l Reactor coolant makeup to replace coolant discharged to containment by the leak is
- initially provided by the high head safety injection pumps drawing from the refueling
- water storage tanks (RWST). If RWST reaches a low level, inventory control is continued by recirculating coolant from the containment sump using-the low head safety i injection pumps and the high head safety injection pumps in series.
Decay heat is transported from the RCS to containment by the leaking coolant. The containment recirculation spray system is used to transfer decay heat from containment to the service water system which is the ultimate heat sink. This Appendix also describes equipment required to support the containment function. The containment function has been looked at independently of the Safe Shutdown functions to identify those systems nece==y to avoid early containment failure. This is discussed further in section 3.4 of this report. The flowpaths for small break LOCA and containment systems are highlighted on the flow diagrams in Appendix N and individual equipment items are listed in the SSEL provided in this Appndix. Small break LOCA and containment system SSEL items have line numbers from 7001 to 7999. S H-1
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O O Page Ski. 2 IRRTN Alem talf 1 Data Base File nue/Dete/flme: tell~ 35EL.NF / 01/11/13 / 50:21:14 Report Dete/ Time: 03-11-93 / 16:51:24 SAFE SMiemm EtulPYWit LIST (SSEL) sort Criteria: Ller number DELL StfAK LGEA AfD CONIAIIDEuf $Y11815 Filter Criteria: (Ller laeter>='7000') (5orted by Llee ihmter) Progree File haue & Verslee: 5501 ve.8 LIE E9UIP SYSTEM /EQUIPENT < EQUIPIGIT LSEAi!GI - > <-(F $1. -> PGER 5WMRf!IE SY5. RES'S fulHONMCT!G15
- 10. TRAIR CLAs$ lett 30. DEstt!PIION Dsg. No./tev./ Zone Bulldlag Fir. Ele. Re. er tem / Col. SIRT IDTE5 Ihreel Sesired REW7 55. le./ REY. B StrPWIIE CWFlpWITS (1) (2) (3) (4) (1) (6) (7) (8) (9) (IS) (11) (12) (13) (14) (15) (16) 70M 2 004 1-5W-IEV-101D SW/tttitt $ PRAY COOLH D 01501 11715-FM-8FOO1/20/tf S$Pil 255' IRTE 10 SR 1 CL'EER 1r01 YE5 II/A 1-EPK-19 ISCL 7027 2 004 1-RS-IEV-1555 ts/0Uf5tBE RECIRC SPRAY MN 8 11715-FM-891A4/24/A6 SFS 267' - E I EP01 IFDI IO WA 1-EP4-21 IEET ISOL 7025 2 SE 1-25-P-25 IS/Duts!K RECIRC SPRAY Mfr 8 11715-fM4 PIA 4/24/B3 5FW 257' 3.5/K SR I 0FF SI YES WA 1-EE-$s-St 7829 2 tes 1-t$4et-15ER ts/Clif5IBE REtitC SPEAT MSF 3 11715-fH-891A4/24/95 SFEB 25E' - t I trEN SPUI 10 11 / 4 1-EP4-21 91501 ISOL 7831 2 084 1-Su-Ict-100C Su/RECIRC SPEAY COOLER C OIS01 11715-HI-87801/28/CE ESPII 265' IDTE IV 5t I CLD5EB IFDI WS WA 1-EPK-21 ISOL 7932 2 21 1-tS-TK-1A* RS/0Uf510E RECIRC SPEAY Ptfr A 11715-FIHl91A4/24/04 SFEB 267' 3.2/LM I 16/4 II/A 10 N/A WA SEAL TM '
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$AFE SHUTDmel EWIPION LIST ($$EL) Sort Criterie: Llee lhMer SIIntL OREM LotA An UNKAIISWII $Y5fDl5 filter Critsels: (time thaber>.'7me*)
(Serted by Line thaner) Program file Mme a terslem: S5DI vs.4 LIE EQUIP SY5fDl/EWIPMDIT < E4111PEIK LKAflW -> <- W. $T. -> PEREt SWPIRTIE SYS. EU 'O IREIGNIECTItBI5 te. TRAIN class IIREK 10. DESCRIPTION Sug. Its./Rev./Zene telldlag Fir.Elv. Im. er tem / Cal. Soti scTES threal Bestrid REST But. ID./IEV. S 1 PPtRTIE CWWEEES * (1) (2) (3) (4) (5) (E) (7) (8) (9) (18) (11) (12) (13) (14) (15) (16) 7046 1 008 1-NC-50V-104B IIC/CONTAllteft ATM PIRGE ISOL 11715-N-892A1/1/t4 ARE N4' E/II $t I,N, VUlf Alt W3 13075-NC-803/1 1-EP-CS4N Pitoi 38 7046 1 set 1-E-50V-10EB K/CONIAll0OK Am PtREE 150L 11715-fE-et2A1/1/tt AME 244' G/II t I,N, 1 Der WNT im 13875-NC-003/1 1-EP-CS-as PILOT 39 7tP47 1 2 1-K-4 NC/MROGDI UBSIIER 1 IEET ISOL 11715-fit-89tA1/1/93 ARE 274' IS/f - I 15, CLg5EB IPDI W II/A 14/ 4 3B 7048 1 0 1-K-HC-5 K/MROGDI te5IIER 1 11715-fE-ettA1/1/93 AIK 214' 11.2/91 $t I.38 0FF WI WS 11/ 4 1-tP411 7009 1 R 1-E-10 K/MROEDI(WWINER 1 DISDI 150L 11715-M-sttA1/1/93 REto WI 2 270' - - I,15 CLOSEB OPUI 10 II/A II/A I 7050 1 07 1-E-TV-1058 K/tfulTAIIIeK Am RETulMI 150L 11715-fE-st2A1/1/E7 AtB N4' 7A S I,N, CLO5EB 4PUI WS 11715-NC-405 1-E-50V-le55 3B 715 0 1 07 1-E-TV-1958 K/ttRifAltfEK Am RETI2tl !$0L 11715-M-402A1/1/E7 AIK M4' 75 - I N. CLD5EB CLO5ED 10 11715-E-eel 1-K-50V-le58 39 7051 1 Det 1-IIC-30V-1058 K/t0NTAll00ft AT!I RETWN ISOL 11715-M-082A1/1/E8 AtlE M4' 7A 5 t 1,N, IUlf Alt MS 11715-NC-055 1-IP-C84N FILoi 3e 7051 1 Set 1-E-50V-lels K/CONTA1800K ATM REftIMI 150L 11715-fE-SEEA1/1/E8 AH 244' 7A E I,M, VUII VUK le 11715-K-805 1-EP-CS-8N Pltet 39 r 7052 1 07 1-E-TV-105A K/CONTAIIeIDIT Am SETWN 150L 11715-fit-9BEA1/1/E7 Am 244' 7A $ I.N. CL85ED IPDE W3 13875-E-004/1 1-E-50V-1954 38 7052 1 07 1-K-TV-185A K/EINITAllOOff Am Reil 5MI ISOL 11715-fE-estA1/1AF ARE 244' 7A - I,N, CLO5EB CLO5ES le 13075-E-004/1 1-E-50V-185A I 39 7053 1 ses 1-at-50V-1954 K/t0NTAIISElf A1N RETWil 150L 11715-fE-49tA1/1/E8 AIR N4' 7A $t I,N, VUK Alt WS N/A 1-EP-CB-80E ' , PILOT 3B i 7053 1 ges 1-HC-30V-105A K/[0NTAlI00ff Alli RETWN 150L 11715-Fist-estA1/1/ES ARE 244' 7A R I N 191t VUK le 11/ 7, 1-EP-Cl-set PILOT 30 t l 7054 2 07 1-E-TV-10EA K/tDNTAlleIDK ATH PWGE 15cl 11715-fE-et2A1/1/t3 ARE M4' 5/J $ I,M. CLO5ED IPDI WS 13075-HC-40E/1 1-NC-50V-10EA I 38 - i 7054 2 07 1-HC-TV-10EA IIC/Colf!AlleIDif ATM PURGE 150L 11715-fE-092A1/1/t3 AtB N4' 6/J - 1,N, CLO5EB CLOSED ID 13875-Itt-80E/1 1-IIC-30t-10EA 39 CERIITICAil0N: The leforsetten identifying the egulpment regelred to bring the Fleet to a safe shutdsua condittee se this $sfe Skuldene Equipuret List ($$EL) Is, to the best of our kneuledge and tellef, correct and accurate. (One er unre signatures of systems er Operstless Eagleeers) 91181 W JAtts$ / DEIEER - IEECE 11,1993 DAVID J. MERCEt / DEIEtt 158D811,1993 r f signature i r
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$Y5ilW1001PMENT < EQUIPENT LOCAllOli -> e- OP. Si, -> POWER StrPtRitt $V5. Ett'0 tuittttNECiteit5 tile EQUIP
- m. TRAtu CLASS wC m. Ot3CRIP110sl e.g. ne./rev./2ene nellding iIr.tiv. es. er sev/Cel. SOtt IOfts IIsrael sesired Itq07 es. no.stEV. s Sirrentis DyeomWis (1) (2) (3) (4) (5) (6) (7) (t) (9) (10) (11) (12) (13) (14) (15) (16) 7076 2 deb 2-K-50V-2OEA K/tMit 2 CONT. ATM Pt#LE 150L 11715-fK-892A1/1/C3 M 244' 11.8/J t I.38 VDif VENT 10 WA N/A P *.~ .
7076 2 08B 2-K-50V-206A K/JitIT 2 CONT. Afit PLRCE 150L 11715-FMC-002A1/1/C3 M 244' 11.8/J $t I.39 VDif Alt 111 E/A 2-tF-CR-80C Pit 0T 7077 2 07 2-K-TV-20EB K/tfili 2 CONT. AIM PLRGE 150L 11715-FE-es2A1/1/C2 M 244' 11.8/J - 1,3B CLD5G CLO5ED 10 R/A 2-IIC-50V-28E8 11715-TE-OS2A1/1/C2 M 244' 11.8/J 5 I.39 CLO5ED UPUI VES R/A 2-IC-50V-20ER 7077 2 075 2-Ilt-TV-20E0 KAffli 2 CONT. ATM PtRGE ISOL 7078 2 ost 2&50V-20EE KAMIT 2 CONT. ATM PtFGE 150L 11715-FE-092A1/1/C2 M 244' 11.8/J t I,38 VDif 1981 NO WA II/A Pitoi 7078 2 088 2-E-50V-20EB MC/Ullii 2 CONI. ATM PIR;E 150L 11715-TE-092A1/1/C2 M 244' 11.8/J $t 1,39 VDIT Alt VES II/A 2-tP-(843 Pit 0T 7101 1 67 1-M5-TV-109 IIS/STIAM ORAIR ColmIT ISOL 11715-FM-870A1/26/A8 ftSWi 273' 4 5/G4 5 I OPDI CLO5ED 10 11715-815-113/5 1-8ts-50V-10th 1-ME-SL9-1915 0 7102 1 088 1-MS-50V-10th Its/5fDet ORAlt Colmti 150L Filei 11715-fWafeA1/26/A8 MSVil 273' 4.5/CA 5t 1.5.36 Alt VDit m 11715-915-113/6 II/A 7103 1 008 1-8ES-50V-105B les/5ftAM DRAlli CONINT ISOL Pit 0i 11715-fW670A1/26/AS M5VII 273', 4.5/CA 5t I,5,36 Alt utilt 10 11715-Its 113/6 II/A 7104 1 07 1-M5-TV-110 M5/5s anneum C smit 150L 11715-f407053/23/A4 M5VN 271' 4.5/EA $ I OPDI CLOSED 10 11715-8tE-114/3 1-fts-50V-110A 1-8EE-50V-1108 7105 1 088 1-st5-50V-110A 1t5/5C SLOWolst Dilmti 150L PILOT 11715487083/23/A4 M5Vil 271' 4 5/CA $I I AIR VDif 10 11715-815-114/3 II/A 7105 1 Ges 1-#ts-50V-1105 M5/5G BLOWERAI Gimli 150L PILOT 11715-f*07tR3/23/A4195V18 271' 4.6/CA 1B I Alt VEY le 11715-8tl-114/3 II/A 7107 1 07 1-80-TV-1004 OD/5G BLOWoldt Colmit ISOL 11715-fWee8A2/16/C5 M 244' 7/J $ I CPDI C105tJ 10 11715-80-801/5 1-ID-50V-1904 flot 1 ces 1-BD-50V-1004 00/5G 1A BlonOlst C0lmti 150L 11715-F4880A2/16/D5 M 244' 7/J $t 1 Alt VDit 10 11715-88-001/6 II/A = PILDT 7109 2 07 1-80-TV-1005 90/5C BLOWOI8I Coimli 150L 11715-fWegeA2/IE/CE Coimtf N1' 8 $ I 1r01 ClostB 10 11715-88-802/101-80-50V-100s file 2 Det 1-go-50V-1005 30/5G anneum toimt! 150L PILOT 11715-fWegBA2/16/DE Colmit 241' 8 $R I Alt VDIT IID 11715-31M102/10 II/A fill 1 07 1-80-TV-100C 3D/5G SLOWOIAI CollIMI 150L 11715-f40geA3/15/C5 m 244' 7/J s I. OPEa. CLOSED 10 11715-08-803/E 1-OD-50V-100C 7112 1 000 1-90-50V-100C 50/5C 18 Stomolal Coimit ISOL 11715-718-090A3/15/D5 M 244' 7/J 5t I Att VDIT 10 11715-80-803/E II/A Pit 0i 7113 2 07 1-8D-TV-1000 90/54 18 BLOWOlAl CONfMT ISOL 11715-fM-egeA3/15/CE Colmit 241' 8 5 1 OPDI CLOSDI 10 11715-80-004/101-80-50V-1000 CitilflCAiloll: The leforsettee Ideettfying the egulpment required to bring the plant to a safe shutdsve tendittee se this safe Shutdeum Equipment List (ISEL) Is to the best of eer knowledge and hellef, correct and accurate. (One er more slysatures of Systees er Operstless Engineers) DMAI V. JACOtt / EEIEtt - b Igna
- 95W0111,1993 CAVID J. Iltt0ER / EEtEER ItutG 11,1993 Ugnaasre
/
O O O Page No. 9 IUlfM Nelt 19111 tepert Dete/ flue: 83-11-93 / 16:51:24 Data Base file llume/Dete/ flue: IRI*SSEL.WF / 83/11/93 / 09:33:18 5 Aft SNUTDOW4 EgUIPIEW LIST (SSEL) Sort Criteria: Line thuber
$1mLL OstAK toCA afb CENIAfteWit SYSTD6 Filter Criteria: (tlee ihmterW70e6')
($orted by Llee ihmter) Program file llame & Werstem: 550s v8.0 LIIE EQUIP SYSTEM /EOU1 MENT < HUIPElli LOCATIsl -> <- 17. ST. -> PmEt SWPRTIE SYS. 34*8 INERC0leECTIGI5 te. TRAIN CLASS IWWC W. DE5CRIPTION thsg. Ms./tev./Zeee Bulldlag F tr. Ele. Re. er tou/ Col. SERT IWits Iturnal Oestred Itm RE. IB./REV. & SIPMRIIIE DBrWEWS (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (II) (12) (13) (14) (15) (16) 7114 2 OBE 1-80-50t-100D 50/5C lt K0lmoWI CONmf ISOL 11715-Fil-09eA3/15/B6 Colmff 241' 8 5I I Alt VDif 15 11715-8B-804/10 II/A PILOT 7115 1 07 1-80-TV-100E 80/5C IC passess C0lmt! ISOL 11715-716-85B44/17/D4 AdE 244' 7/J 5 I EPDI CLD5tB 10 11715-85405/5 1-85-30V-leet 7116 1 Ges 1-80-50t-100E 90/5C 3C K0emel Colmti 150L 11715-fil45B44/17/95 AIK 244' 7/J 5t I Alt velf ID 11715N WA PILOT 7117 2 07 1-80-TV-100F 80/541C gammal Colmff ISOL 11715-738-89e44/1746 Colmff N1' 8 5 I 19 01 CLO5ED W 11715-08-80E/181-8B-50t-180F 7118 2 Det 1-80-50V-100F B0/5G 3C aa mmmes Com! 150L 11715-fil-8Eas4/17As (Olmer N1' 8 5t I Alt VDif 2 11715-88-006/10 WA PILoi 7119 1 07 1-51-TV-100 SI/hift0GDilEADER C01mfr I5CL 11715-fil-Ogel/17A3 AIK NE' 4.7A 5 I CPDI CLO5EB le 11715-SI434/5 1-51-50V-1804 1-SI-30V-leet 7122 1 07 1-11-TV-101 SI/IIISTE EA5 FILTER CONT ISOL 11715-Fit-8981/17A4 AIR 244' 7A 5 I CPDI CLO55 10 11715-51-813/5 1-51-50t-181 71fl4 1 tes 1-SI-30t-180A SI/IlliROCD1IIEASER C0lm8f 150L 11715-ftt-Ogst/17A3 AIR NE' 4.74 5t I Alt VDIT 30 11715-1I-834/5 II/A Pit 0i 712 3 1 085 1-SI-30t-105 SI/IIIIIOGDIIIEAllEt C0pmff 150L 11715-fle OgIB1/17A3 AIR NE' 5.7A 5t I AIE VDft IO 11715-51-834/5 WA PILOT 71N 1 Ges 1-SI-30V-101 SI/leisit CAS FILTER Clumfr 150L 11715-Fil-8tN1/17A4 Cemet 244' 7A 5t I Alt VDit 10 11715-51-813/5 II/A PILOT 7125 1 07 1-57-TV-1859 $I/ACCWI TEST LIIE Colmff 150L 11715-ftl-89E42/23/T7 SFG0 257' -
- I CLO59 CLOSEB le 11715-SI-835/7 I-5I-30t-1859 71M 1 005 1-51-50t-1959 SI/ACCist Test LIIE CWmer 150L 11715-798-89EA2/21/F7 5FCO 2E7' -
t I VDIT VDif IC 11715-SI-835/7 WA Pitof 7127 2 07 1-SI-LEV-1935 51/linsit CA1 Flit RETulu Colmfr 11715-fit-OgeB1/17A5 Colmff MI' 8 - I CLSEED ClosEB le 11715-51-814/5 1-51-505-193E ISOL TIM 2 Ost 1-SI-30t-1936 SI/IRSTE CAS Flit RETulli C0pmit 11715-716-88181/17A5 Colmli N1' 8 2 1 VDit vert IC 11715-51-814/9 WA 150L PILDT 7129 2 07 1-SI-TV-1842 11/ACCist TEST LIIE C0imfr ISCL 11715-F18-03E51/1744 C0lmt! 252' 13 - I CLO5ED CLOSEB 10 11715-51-833/7 1-11-50V-1942 7130 2 085 1-5I-30t-1942 SI/ACCWI TEST LIIE Colmer 150L 11715-H6-88131/17A4 toimfr M2' 13 t I VDE VDit le 11715-51-833/7 WA Pltei 7131 1 07 1-G-TV-12044 DIAET80lel LIIE COmi ISOL 11715-pl-895C1/1443 C0pmrt N1' 8 - 1 CLOSEB C105EB le 11715-08-180/1 1-01-509-1104A Ctti1FICATICll: The leformetles Idrettfylag the egallmeet required to bring the plant to a safe shutosue condittee se this Safe Shutdeum Equipment List (55EL) is, to the best of our kesuledge and hellef, correct and occurate. (One er sure slynetures of Systees or Operstless Eng1 seers) BRiel W. JAtlE5 / DEllKtt - h i 18ADI 11,1993 BATIO J. IfERSER / DE18EER IWADI 11,1993
/ signeere S
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s s ' Page Ib 10 NORTN APtn ISIIT 1 Beta tese File home/bote/fler: IIll~53EL.ger / 83/11/93 / 3:33:18
- Report Dete/16me: 03-11-93 /16:51:24 5 Aft SIEfTIMMt EtulMilf LIST (55tL Sort Criteria: Llee number 519tL SREAK LOEA AIS CONTAIIDENT $Y1}10E5 Filter Criteria: (Line aster >.*783')
($orted by Line ihmher) Program File Rome 4 turslem: 550t we.e i LIIE EQUIP SYSTDt/E90lPMENT < EqlflPIEllT LOCAfitBI-> <- tr. $T. -> PWER SWFWTIE SYS. Ett'8 INT 90peECTieI5 le. TRAIN nAS$ MK W. K5GIPTICII Bug. Ile./ter./Zene Sullding Fir.tiv. Re. er Rom /tel. SORT lefts IIsrest Bestred afpt IE. W./tfV. 4 StrfetTIE CWWWENTS (1) (2) (3) (4) (5) (6) (7) (8) (9) (le) (11) (12) (13) (14) (15) (16) 7131A 1 008 1-CN-50V-12004 Ot/LETB0181 LIIE CGImET ISOL PILOT 11715 418-100/1 ColmET N1' 9 R I VDIT VENT IS 11715-01-18t/1 WA i 7132 2 07 1-CR-TV-12005 01/LETOOlfl LINE Colmff 150L 11715-FN-89544/17/B3 AIK M5' 6.5/J S I (FDI CLOSEB W 11715-01-EN/5 1-CR-50v-1204 i
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7132A 2 OSI 1-01-30t-129dB Ol/LETOOlsl List ColmfT 150L PILOT 11715-08-8F8/5 Am M5' 6.5/J $R I Alt . VDit le 11715-CII-878/5 II/A i 7137 1 07 1-EC-TV-15194 RC/Ptf N FILL CONINT 150L 11715-fM-8932/23/It Alst MG' 6.5/J - I Cle5EB nosEB W 11715-at-83E/s 1-at-50t-151m 713B 1 085 1-EC-30t-15194 BC/ PET N FILL DIlmtT ISOL PILOT !!715-RC-e3E/5 ARE 244' 8.5/J t I VDft VDif 10 11715-at-m/s In/A 7139 1 07 1-CV-TV-1584 CV/ Allo 5 CLEAltr CCImIT ISOL 11715-fM-etEA2/13/94 Alst 244' E/J $ I t*DI Closes W 117154V-est/5 14V-50t-15e4 [ 7140 1 008 1-CV-50t-1584 CV/ADES CLEAIEF OBmff 150L PILOT 11715-7489242/13/94 AR N4' E/J $R I Al? VDff 15 11715-CV-80t/6 II/A 7141 2 07 1-CV-TV-1508 CV/ATIe5 CLEAIRF CCImfT 150L ll715-FN-ettA2/13/95 M 244' S/J $ I IFTA ROSED 10 11715-CV-sel/7 1-CV-50t-15ss 7142 2 085 1-CV-50t-1500 CV/ATIES CLEAIRF COImit !$0L PILOT 11715-HI-ettA2/13/B5 AIRt N4' &/J $R I All VDIT IS 11715-CV-803/7 II/A 710 1 07 1-CV-TV-150C CV/A11e5 CLEAlar telmti 150L 11715-fM-etEA2/13/94 AIR 244' E/J $ I (FDI Closet le 11715 4 1-804/7 1-CV-50t-150C l 7144 1 est 1-CV-50V-150C CV/ATIOS CLEAIAF LamfT 150L PILOT 11715-fWet2A2/13/C4 AGE 244' 6/J $t I Alt VOIT W 11715-CV-804/7 WA 7145 2 07 1-CV-TV-153 CV/ATICS CLEAfRF ColmfT ISOL 11715-74882A2/13/C5 AtX N4' &/J $ I (FDI CLD5tB ID 11715-CV-885/5 1-CV-50t-153 7146 2 COB 1-CV-50t-155 CV/AllW5 CLEAIRF ColmlT 150L PILOT ll715-fM-et2A2/13/C5 Att 244' 6/J $R I Alt VOIT W 11715-CV-OO5/5 WA 7147 1 67 1-aA-TV-1804 84/5ter 81508 Camff Isot 11715-fWetIA1/15/t? AIR 244' E/J - I ClosEB Cl0$fB W WA 1-84-50W-1804 7148 1 Ost 1-04-50t-1804 84/5GF DIsul OpmIT 150L PILOT 11715-fM-etB41/15/17 AE 244' E/J R I VDIT VDft le 11715-84418/4 II/A 7149 2 07 1-04-TV-1905 84/5GF D1501 telmff 150L 11715-FEsteC3/14/C3 CCImfT N1' 9 - I CL85ED CLOSED 15 11715-04-819/7 1-84-50t-lees 7150 2 000 1-04-50V-185 BA/58F 81501 Colmff ISOL PILOT 11715-fM-090C3/16/C3 CWmli MI' 9 t I VDit VDIT 15 11715-84-019/7 II/A e 7151 1 07 1-8G-TV-1904 BC/PtiltlRY DEAIIIIFit Colmff 150L 11715-74898C1/17/98 Alst 244' 7/J - I RO5ES Closet le 11715-0G-80E/5 1-8G-50t-1984 7152 1 est 1-05-30t-1904 91UPRIlmRY 8tAIN IFtt Ctfmff ISOL 11715-74898C1/15/I8 Alst M4' 7/J B I VOIT VOIT W 11715-85-SME/5 II/A PILOT 7153 2 07 1-8G-TV-1908 ' BC/PtimRY 8tAIN IFtt ColmlT 150L 11715-fWegeC1/17/97 Colmff N1' 7 - I. Cte5ES ClostB In 11715-85-005/5 1-84-50t-1808
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7154 2 0e8 1-OG-50t-lees BC/PtimtT otAIN IFER ColmlT I54 11715-74egeC1/17/97 Colmff N1' 7 R I VOIT VOIT W 11715-55-005/5 II/A t PILOT 7155 1 07 1-VE-TV-1J04 VE/PRIMRY VDiT IER ONmff ISOL ll715-fWegE1/17/F3 AIK 244' $/J $ 1 (PtN CLOSED 10 11715-VG-801/3 1-vG-Sov-loon CGTIFICATION: The leformattee idrettfylag the equipment required to bring the plant to a safe shutdeun tenditien se this Safe SIntesum Equipment List (15EL) is, to the best of our kasuleage met belief. currect and accurate. (One er sure sigasteres of systems or Operetteus Englaeers) 81888 W. JAC005 / EE"Ett - h inature IWA0111,1991 BAVIO J. WEROtt / EMIIEtt 18A01 11,1951 Ilimature 7 i I
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- 10. TRAIN CLAS$ 14 Wit W. OESCRIPTICII Bug. Ils./tev./2one Belldlag Fir.Elv. Re. er tem /tel. 50tf IcTES Ilsrael Bestred REST BE. ID.AEV. & 5Wo0tTIIE OppWENTS (1) (2) (3) (4) (5) (E) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 7202 1 018 1-15-50V-112A $5/5C SWTACE $MLE Colmti 150L 11715-5$-028/7 CONITET 253' 8.5 t I VDIT VDrT IS 11715-55-GES/7 WA 7203 2 07 1-$$-TV-1128 $$/54 suffACE SWLE aumtr ISCL 11715-FM-celt 3/16/t3 Allt 240' $/JK - I CLOSEB CLOSEB IS 11715-11-02W4 1-15-50V-1125 7204 2 OIS 1-55-3r*-1125 $$/5C SWTACE $WLE Colmff ISCL 11715-fM-eeW3/16/C3 AUK 240' $/K t I VDIT VDif ID 11715-5$-029/4 II/A PILOT 7205 1 07 1-$V-TV-102-1 $V/ Alt EJECT 0t 01501 Oumit 150L 11715-FH472A2/20/C3 Il5Vil 272' 4.8M14 - I CLD5ED CLG5EB W 11715-$V434 1-$v-50V-let-1A 7206 1 set 1-$V-50V-102-1 SV/ Alt EJECTOR D1501 DNmIT 150L 11715-fit-8724t/20/C3185118 272' 4.9MIA E I.34 VDIT VDIT Im 11715-$V418 II/A PILDT 7297 1 07 1-$V-TV-102-2 $V/ Alt EJECTOR DIS 01 Olimit ISOL 11715-FM472A2/20/93 78 307' 7/C - I CLD5ED CLOSED 10 11715-SV-809 1-SV-50V-Itt-2 7208 1 est 1-SV-50V-102-2 SV/ Alt EJEtiet DIS 01 Olimli 150L 11715-fM472A2/22/5318 387* 7/C E I,31 VDIT VDIT ID 11715-st-889 WA PILOT 720) 2 07 1-5V-TV-103 $V/tADIATI0liIOllietIE RETWN 11715-FM-872A2/20/931t51R 272* 4_SMI4 - I CLOSED CLOSED 15 11715-$V-411/5 1-SV 50V-183 i Colmti ISOL 7210 2 COB 1-SV-50V-103 STMIADIATION IEllifMIIE RETURIE 11715-FM-072A2/28/D3 II5VN 272' 4.9MIA E I VDIT VDIT le 11715-$V-011/5 II/A Colmff ISOL PILOT 7211 2 07 1-CC-TV-1004 E/CC RETWII FRWI COOLIE CDIL 11715-FM-079pt/22A4 ALE 244' 6/K 5 I OPDI CLOSEB le 11715-CC-871/4 1-CC-50V-teen temIT ISOL 7212 2 005 1-CC-30V-1904 CC/CC RETUDI FRWI C00LIIE talTNT 11715-fM-47904/22/E4 AUK 244' 7/K $t I Alt VDIT ID 11715-CC-871/4 11/4 Is0L Fitaf 7213 2 07 1-CC-TV-1000 CC/tt RETWN Fret C00LIls COIL 11715-fM41794/22/94 AUK 244' 6/J $ I WDI C105ED 10 11715-CC-872/4 1-CC-30V-148B Colmtf ISOL 7214 2 est 1-CC-30V-1005 CC/tt RETW4 flot COOLIIE Colt 11715-FM-071D4/22/94 AUK 244' 6/J 54 I Alt VDIT 15 11715-E-872/4 IVA e CamIT ISOL PILOT 7215 2 07 1-CC-TV-1000 E/tt REinstu Ftat t00LIls Cott 11715-fM-079D4/22/C4 AUK 244' E/t ! I WDR CLOSED 10 11715-E-873/4 1-CC-30V-100C Colmff ISCL-7223 2 008 1-CC-50V-100C CC/tC REfillN Ftoll C00LilE telt 11715-FM-075D4/22/C4 Allt 244' 7/K 5t I Alt VDff IC 11715-CC-073/4 IVA 03mff 150L PILOT 7217 1 07 1-CC-it-101A CC/T11EStil SAARIER D1508 Coimff 11715-FM47951/21/DT AUI 244' 7/K $ I WEN CLOSEB IN 11715-CC-057/ 3 1-CC-30V-101A !
150L CEtilFICATI0ll: The Informetles identifytog the egelpeest regelred to Iring the plant to a safe statdese esadittee se this Safe Statdoes Egelpment List ($5EL) is, to the best of eer koesledge and tellef correct and accorate. (One or more sigestores of Systems er Operatless Eaglesers) 94A1II. JACOBS / DEllEtt C/ h 19W0111,1993 94 TIS J. MEROEI / EEllEtt ! ISROI 11,19V3
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Page No.15 O teRTN #314 Iffli 1 O Q Data Base File lhme/ tate /Tlue: lut!* $$tt.8BF / 03/11/93 / 09:33:18 Report Dete/Ilse: 03-11-93 / 18:51:24 5AFE $st!TDtsil E9UIPENT LIST ($$tt) Sort Criteria: tine thmber SMALL OREAK LOCA Af8 CipffAllO0ft $T5fD15 Filter Orlteria: (Lise Ihnter>='70D0') ($orted by time thumber) Program file name 4 9erstem: $$98 ve.0 LIE EQUIP $Y5fD0TsulPENT < EQUIPM LEAT!III -> <- 1r.11. 4 PIREE SirPIRflE SY5. REG'8 INTERCIBBECTHBIS No. ItAIN CLAs$ M4RC W. K5CRIPTION Oug. Ils./tev./2sae Building Ftr.Elv. to. or tou/Cel. $cti Imits lesrael testred titB7 EE. W./ REY. & $1rPORTIE Optquelts (1) (t) (3) (4) (5) (6) (7) (8) (9) (la) (11) (12) (13) (14) (15) (16) 72 3 1 080 14C-30V-101A CC/TERMAL BAttlEt DISDI CONTNT 11715-407981/21/D7 AUK 244' 7/K $t I Alt VDft W 11715-CC-067/5 11/4 150L P!Loi 7219 2 07 14C-TV-1018 E/fMEWill BAttlEt DI$CE CONTNT 11715-E07951/21/96 CONTNT N1' s $ I CPDI C105!B m 11715-CC-074/5 14C-SOV-1910 130L 7220 2 008 14C-50V-1918 CC/iNENetL BAttitt 01301 COM 11715-E0721/21/DE COM N!' 8 $t I Alt VDff M 11715-CC-074/5 II/A 150L Filof 7221 1 07 1-E-TV-102A CC/RCP CC RfindtN CONTMT ISOL 11715-E07984/20/A5 AUK 244' 6.5/J $ I CPUI C105tB 15 11715-CC-078/4 1-CC-30V-1924 7222 1 000 1-CC-30V-102A CC/RCP CC RETistil almrt 130L PItat 11715-E07954/20/96 Allt 244' 7/J $R I AIR VDit le 11715-CC-078/4 II/A 7223 2 07 14C-TY-1923 CC/tCP CC RtinRif COIITNT ISOL 11715-E07954/20/A3 CDM 241' 8 $ I CPUI CLD5EB m 117154C-075/5 1-CC-30V-102B 7224 2 088 1-CC-50V-1028 E/tCP CC t!Tiptli CoulMT ISOL Pitot 11715-fM-07954/20/A3 Coimff 241' 8 $t I Alt VDif 11 0 117154C-075/5 II/A 7225, 1 07 1-CC-TV-102C CC/DCP CC Rtilitil Clpmli 150L 11715-fM-07983/20/A5 M 244' 5.5/J $ I 1r01 CLO5HI le 11715-CC-979/5 14C-30V-102C 7226 1 est 14C-30V-102C CC/tCP CC RETilut Colmtr 130L PILoi 11715-E07983/20/96 Allt 244' E.5/J $R I Alt VDif M 117154C-079/5 11/4 7227 2 07 14t-TV-102D CC/tCP CC RETifMI CCM 150L 11715-E07983/20/A3 COM 241' 8 $ I 1r01 CtestB W 11715-CC-07E/5 14t-50V-1020 7228 2 est 1-CL-50V-1920 CC/RCP CC REilitM Celmit 130L PILST 11715-FM-07983/20/A1 Colmli N1' 8 $tI Alt VDff ID 117154C-076/5 N/A 7229 1 07 1-CC-TV-102E CC/RCP CC RETiltli Celmt! 130L 11715-FM-079B2/21/A5 AIE N4' 6.5/J $ I 1r91 Closed 10 11715-CC-Ost/4 14t-50V-1921 7230 1 est 1-CC-30V-102t CC/tCP CC RETiltfl Colmft ISOL Fit 0T 11715-fM-07952/21/96 AUK 244' 6.5/J $t I Alt VUrr 10 117154C-800/4 4/A 7231 2 07 1-CC-TV-102F CC/tCP CC ttftstu CDimit 150L 11715-E07982/21/A3 CIsmff N1' 8 $ I IrtM CLOSEB le 11715-CC-077/E 14t-30V-102F 7232 2 088 14C-30V-102F CI/tCP CC RERRIl Colmti 150L PILOT 11715-E079B2/21/A4 Colm!T N1' 8 $tI Alt VDff 10 117154t-077/5 E/A 7237 1. 2 of 1-CC-TV-1044 tt/tCP CC COM ISOL 11715-FM-07W2/21/tt M 244' 5.5/J $ I OPDI CLOSED 10 117154t-053/4 1-CC-30V-194A1 14C-30V-104A2 7238 1 000 1-CC-$0V-104A1 CC/tCP CC COM 130L PILGT 11715-fM.ONO2/21/E8 AUK M4' 8.2/J $t I Alt VUlf 10 117154C-003/4 II/A 7239 2 000 1-CC-30V-104A2 CC/tCP CC Colmt! 150L PILOT 11715-E07902/21/ES AIR 244' 6.2/J $R I Alt VDif M 1171$4C-083/4 R/A 7241 1. 2 07 1-CC-TV-1048 CC/tCP CC ColmIT ISOL 11715-E079B1/20/ES AUK N4' 6/J $ I CPEN Closta m 11715-CC-004/4 1-tt-30V-18481 1-CC-50V-10452 7242 1 005 1-CC-30V-10481 CC/RCP CC COM ISOL PILOT 11715-407983/20/E4 AUI N4' E/J $t I Alt VUff 10 11715-CC-Oe4/4 II/A CitTIFICATIGII: The Informatten identifying the egulpment required to bring the plant to a safe shutdeus conditten se this Safe Shutdeue Equipment List (5SEL) is, to the test of our knowledge and belle correct and accurate. (One er more sigentures of Systems or Operstless Engineers) INI8l V. JACCES / EN;tlEER Uh lilRDI 11. 1993 DAVID J. IEt0ER / Dir.IEtt [ 80pDI 11. 1993 f ut .e I
s , i fage No.16 itulTH AlsIn IIIti 1 tota Base file hume/Bute/Tlass IE153EL.NF ~ / 01/1131/ OS:31:N l Report este/ Time: 91-11-93 /16:51:N SAFE sulminst HulppElit LIST (SSEL - Sort Criterle: Line thaber 9mLL MEAK LOCA AIS CipitAllSEN SV5)1915 Filter Criterla: Illee NumberW7eIt') , t (5orted by Line number) Program file name a gerstes: 5581 vs.e
$YsitM/EqulPIIElli e E4WIf9EHf LetAtlet -> <- W. $T. -> fMit SipfWillE SY1. reg'S Istversumsriles - l LI2 EqulP W. 19A15 CLASS IMRK 15. OE5GIPTIGI Bug he./tevJZene Sulldlag F tr.Elv, Es er tem / Col. SIRT WTES lisrael testred IESF WE. W AEV. 8 3W9mtIE CWWWEllFS (1) (2) (1) (4) (5) (6) (7) (4) (9) (le) (11) (12) (13) (14) (15) (M)
FN3 2 018 1-CC-Set-leIB2 CC/RCP CC GNiillt 150L PILOT 11715-twergB1/ft/Et AIR 244' 5/J $t i Alt VHIT W 11715-CC-eeeM II/A ; 7N5 3, 2 SF 1-E-TV-leIC CCACP CC Cemit ISOL 11715-fil-GFW4/2G/E8 ARE . 244* 6.5/J $ I 1r01 C18BE9 le 11715-CC-ee5/4 1-CC-Set-leet! 1-CC-30W-leEC2 { 7246 1 008 1-CC-10V-leICI CC/RCP E DBmit ISOL PILei 11715-fEGFW4/28/E8 AIK 244' 8.5/J 5t I Alt ' VEN 10 117154-W5M II/A Alt 10ll 5 i 7N7 2 ese 1-E-Sof-leeC2 CCACP CC Celmet ISOL Pitcf 11715-fil-efe4/ft/E8 AIK N4' E.5/J $R I 11715-CC-eIE/4 II/A 7209 1 SF 1-CC-TV-185A E/tt SE7 lag feel CeeLIE allt 11715-fbePWI/22A4 Ceuilli N!' 8 5 I WE4 Cle5EB le 11715-CC-eIE/7 14C-SOV-lela i Ce mli ISOL 8 $E I Alt MW 11715-CC-GIE/7 II/A f 7250 1 IIS 1-E-30t-le5A CCAC EfflAN FRIBl COOLIE Colt 11715-fts-GF9Bt/22/E4 CCImit . N1* CSIIMt ISEL PILet 7251 1 SF 1-E-TV-less CCAC REftes FRel CootlE COIL 11715-7487104/22/94 Cemit N1' 8 $ I trEII Cle5ED 2 11715-CC-eI7/8 1-CC-set-less tamit 15el ; 7252 ' 1 815 1-CC-$st-1958 CCAC RETWil fast COOLIE Colt 11715-fESFWE/72/94 Olutief N1' 8 5t I Att IDir W 11715-CC-887A II/A i CEImit ISOL Pltet N!' 8 3 I tree Cle5ES W 11715-E-est/t 1-E-9st-le5C [ 7753 1 SF 1-CC-TV-le5C EAC RETWII ftG1 COOLIE (Sit 11715-fl44FW4/22/C4 tamil talmit 15el l 7254 1 018 1-tC-10W-le5C EAC RETWII Fnet COOLIE Colt 11715-95eFW4/22A4 C3mit M1' 8 $tI Alt VHIT W 11715-CC-SIS /S H/A ' tWm8f ISOL Pilof 244' E/J - I Cle5EB Cle5EB IB 11715-IA-015,3 1-IA-30W-leEn 7255 1 ST 1-IA-TV-1924 IWIH519 Alt NEABER teNmf ISOL 11715-f48R2N1/343 AIR 11715-f18-802I11/943 AIR 244' $/J t i 105 VDif IS 11715-IA-015/3 II/A 7256 1 EIS 1-IA-SOV-leEn IA/IIstt Alt HEASEE C5mit 130L > Pitet 244' E/J - I CtelEB Cle5Es W 11715-14-016/3 1-IA-50t-leer s 7257 2 SF 1-1A-TV-lett IA/III51R Alt IEABER CWlHlf 13OL 11715-Re-8B2111M D1 AIK ! 7258 2 - geB 1-IA-Set-left IA/II6ft Alt IGR C5mli 150L P!Let 11715-ftl-8Banl/383 AIR 244' 5/J R I VDK VUK ID 11715-IA-e.6t3 R/A
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Pege No. 2 letTN Af814 Wili 2 Data Base File lieue/ Bete / flue 152* $$EL.IBF / 03/11/93 / 99:30:38 Reprt Dete/ flue: 03-11-93 / 15:40:14 SAFE SIRR00MN EtelFMENT LIST (1sEti Sort Celteria: Lies Iluster SHmLL 9 TEE LOCA AfD CONTAIIDEN! 5Y5tDI5 filter Criterlar (Llee IIssherW7000') (Serted by Llee itsster) Proy as File !tese & Wurstoa $5Elt v6.5 IINE EQUIP SYSTEWEOUIPMENT < Equ!PMEllt LOCATIG1 -> <- IF.17. -> PGER SIFFIRTIE SYS. req'D INTERCOMECfl0N5
- 10. TRAIN CLA$$ IEWtC W. DESCtlPTI0li bg. Ite./tev./ Zone Bulldlag Ftr.Elv Se. er tou/tel. SIRT BOTE! IIsrael Beslesd MOD 7 915. ID./t".Y. 8 $1FPSilE OpFIBEllf5 (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 70N 2 004 2-5W-lOF-200 SW/NECIE WAY COOLER 8 D1501 11715-FN-07851/20/t7 q$Pil 255' ~ $t F CLD5EB IFDI YES II/A 2-EPK-19 ISOL ,
7027 2 004 2-RS-lOV-2558 21/OutslOE RECa.'C SPRAY PWF S 120504M4flA4/18/A6 SFGD 267' WLR PIT t ! IFUI IFBI - le 11/A 2-EPK-21 IILET ISOL 7020 2 06 2-tS-P-25 R$/UplilOE RECIRC SPRAY PifF S 120504H-091A4/M/93 $FCC 267' PWF CWICLE $tI IFF st YE$ WA 24E-55-Of 7019 2 018 2-d1-lOV-2508 21/ OUTS 10E RECIE $ PRAY PUF 5 12E3-fH-091A4/14/D5 SFC8 256' - t I IFUI IPDI 10 WA 2-EPK-21 DIS 01 ISOL i 7011 2 004 2-3N40V-20ec 5M/RECIE SPRAY COOLER C D1501 117154W-0?ml/20/C6 45Pil 265' - $t I CLOSED GPUI YC3 11/ 4 2-EPK-21 ISOL 7032 2 21 2-t1-Tit-1A+ R$/OUTSIE MCIE SPRAY PWF A 120504W-8tlA4/18/C4 SFCD M7' PWF CWICLE $ I WA II/A 10 WA II/A i SEAL im ' 7ep 2 21 2-RS-tK-10* RS/OUTSIE MCitC SPRAY PWF S 12050415-091A4/18/t3 SFCD 267' -
$ I II/P. II/A 10 II/A II/A SEAL TM 70M 2 21 2-t$-t-24* ts/OIRtIDE REttet SPRAY PWF A 120504Il-89144/18/C4 SFW 267' 3.2/Ut $ I N/A II/A 10 WA II/A SEAL NE 7035 2 21 2-t$-E-20* RS/OUTSIGE RECIRC SPRAY PWF B 120584N-8BIA4/1A/t3 SFED 267* 3.5/JC $ I WA ll/A le WA II/A SEAL NE 7035E 1 05 2-55-P-$ SW/ItADIAlldt IONITot!IE PWF 117154H-47083/21/C8 45Pil 255' -
$ I 0FF 0FF M I4/4 II/A 7035F 1 05 2-$N-P-8 $N/WADIATION IWNiilRilE PWF 11715-fM-07N3/21/C6 45PW 2E5' --
$ I 0FF OFF le II/A II/A 70356 2 05 2-5U-P-7 Sil/RABIAil0Il MINITORIIS Pter 11715-fM-070B3/21/t3 $5PR 265' ~
$ I 0FT OFT 10 II/A WA 7035E 2 05 2-3W-P-8 Su/RatlATION IWNiiORIE PWF 11715-fM-07853/21/t4 QSPil 265' -
$ I 0FF 0FF le II/A WA
- 7036 2 21 2-ts-TC-1 RS/tA5115 CEOLIE iM 12006 fM-09101/10/C4 VfER/Tipt 270' S OF AFFIl - S I WA II/A 10 II/A WA ;
703EA 2 18 2-454T-2034 85/CASIE COOLIIE TAIIt LEVEL Mt 12050-fM-89181/10/4B CSCPN 270' - SE I WA II/A YES 1205041-029/7 2-EP-C5-048 7035 2 le 2-25 4 1-2434 RS/CA$lE CEOLilE TAfEC LEVEL 12056-fM-09101/10/M $8 277' S/C $RI, II/A WA YES 12858-85-029/7 2-tS4f-2034 i IISICAIOR 703E0 2 la 2-4545-2e34 IS/CASIE COOLIIC TAfE LEVEL 128504N-89tt1/10/M 38 252' 11/D $t i M/A ll/A 10 12050-t$-029/7 II/A > 3NITOI 703EE 2 IS 2-t34T-2038 R$/CA$llE C00LilE TAfEC LEVEL Mt 12050-fM-09101/10/4C C3CPN 270' ~ $ti 11/ 4 II/A YE5 12056-R3-030/6 2-EP-CE-000 CERilFICATIGl: The leforeettee Identifyleg the egulgeset regstred to bring the P antl to a safe shutdemo condittee se 161s Safe Shutdeue Equipuset List (15EL) is, to the test of our kaseledge and belief, t and accurate. (One or more slyetures of Systems er CPeratless Eagleeers) RAIAI W. JACOBS / DEINEER Ub leatore
& IslADI 11, 1993 04YIO J. WERGER / DEllEER IIIROI 11, 1991 flgesture 1
3 leltiN AleIA teelt 2 tota Base Flie nue/tste/ilme: In2 ~$$tt.ggF / 03/11/95 / 09:30:38 h Fage No. 3 Report Sete/Ilse: 83-11-93 /15:W:14 5 Aft SIRRomst EstIlpIEIR LIST ($$tt) Sort Criterla: Lise Itseer !
$1mLL Ostm LOCA Als CWRAlifENI SY5YBE Titter Criterla: (Llue thuberW7000')
(Sorted by Llae Ikuter) Program Flie Ihse S Unrstes: 3591 vs.e IqulP < Equ!PMEIK LOCAT1618 -> <- W. St. -> MRER 1ppWilm $Y$. reg'S IIRsarsmasrijgl5 y LIE $Y5 TEM /tWIMNT i G. TRAIN CLA$1 IWAK le. MSCRIPil0lt Det. Ils./ter./Zeae Bulldlag F tr.Elv. Re. er Rou/ Col. SOff left$ Ihreel testred RES2 35. m./REV. 8 SWFWills CGWWmR$ (1) (2) (3) (4) (S) (6) (7) (4) (9) (18) (11) (12) (13) (14) (1$) (16) [ 2R' 4/C $t 1 VES 12588-85-838/5 2-ES-ti-202 ! 703er 2 18 24-LI-203 RSKA5lE COOLIE TAlet LEVEL 12058-716 89101/14/3C 38 11/ 4 11/ 4 i IstCAlet 7slet 2 la 2-t$-LS-2em R$rAilE COOLIE iAlet LEVEL 12000-fM-SPIO1/It/3C 38 252' 11/3 $tI 11/ 4 II/A le 12WS-R$-830/5 II/A Sultal 7837 2 05 2-ts-P-34 R$KAsis COOLIE PipF A 128544N45151/10/97 CSCPN 271' - $E I 0FF SI YES II/A 2-EP-lE-N 7838 2 set 2-ts-let-NIA R5KASIE COOLIIE Pier A DISal 12EIS-FN-8BIII/1647 SFEB 256' - t I 1r91 WGI W ll/A 2-EP-lE-20 i ISet 12eOS-fM-8BIBl/10/E7 SFW 254' ~ $t I CLOSEB 1r91 Its II/A 2-EP-4E-20 I 7839 2 Se4 2-t$-IBM 904 R$4ASIE Coell!E Plfr A 91501 15sl l 271' - 5t I 0FF si its ll/A 2-EP-IE-22 7000 2 05 2-t$-P-E R$4ASIIE CEOLilE PlfF B 12058-FN-89101/18/96 CSCPil
'stel 2 004 2-85-let-29N RS/CASIIE COOLlE Plfr 8 D1501 12EINN-4Bitt/14/F7 SFG8 254' - t I W91 W91 le N/A 2-EP-lE-21 i=
7902 2 004 2-t$4et-20N R$/DI5IE COOLIIE PDF t 91501 INI64N-89101/10/F7 $FGD 256' - 5t I C185EB WEN MS II/A 2-EP-4E-21 IM . , IE/5ffal 8AAllt apmW I5OL 128584N-SPEA728/D316111 273* 13/EO $ I WBI CLO5EB 18 12516415-209/5 24-50t-20g4 fiel 1 87 2-M5-TV-200 2-II5-10W-20N 718E 1 est 24-50t-2ega 16/51031 utAlu Calmt 150L PILST 12el84N-OFeA3/28/W Illvil 273' 13/E8 5t I,$,35 Alt VDE le 120064-200/E II/A 7183 1 set 24El-50t-20N IS/5ffal WAIN OpmW 150L PILet 1N5HM 4FIA3/28/93 M5411 273' 13/E8 $t I,5,35 Alt UDit le 120184-19R/5 II/A 71W 1 87 24EE-TV-2N IS/5G Rescial Dumli ISCL 12WINN-SPW3/19/M 115111 271' 12.7 AIL $ I WBI CLO5ED le 12W84-210/2 2415-10t-2104 l 2-n5-197-218 7105 1 set 2-H5-30t-215 16/58 Bleggel CelmW ISOL PILOT 120lS-fM-87W3/19/A4115111 271' 12.8/IE $t I Alt VIN le 12W646-210/2 WA e fles 1 885 2-IE-Set-21W ME/5G KGemel Cemit 150L PILet 12850-fil-0PW3/19/M 18418 271' 12.8MR $t I Alt VOK le 12518415-210/2 II/A 7107 1 SF 2-OS-TV-20e4 IR/56 RHB'am temIt 150L 120564N-OtI42/14/C6 Jim 244* 11.5 4 S I WBI Cle5EB le 12e864-881/5 2-OB-50t-2084 7148 1 885 2-et-ser-2een 38/5E 14 KalSelRI Opmn ISet 12518-7H-88042/16/95 AIK 244* 11.5 4 SR I Alt VEIK le 12058-88-881/6 II/A i PILW 7let 2 07 2-88-TV-2 WEB OR/5s Ememel Opmn isOL 128584N-ele 42/16/t3 tamIR 241' le S I WOI CLOSES le 12e58-88-e8t/3 2-OS-30V-seet 7110 2 Set 2-ID-30V-28W 8h/5s KeesAl EsImit 150L Pilot 12050-fu-est42/N/95 Opelf 248' 18 5t I Alt VOIT W 128584-est/s II/A . t [ Citi!FICAllOI: The loferustles Idsettfyleg the agslpment regelred to bring the plant to a safe stutdeum condittee se this $efe Shutdeue Egelparet List (55EL) ! Is. to the test of our knustedge and tellef, t and occurate. (Guo er more sigastures of Systems er Operstless Eaglesers) 31181 W. JeteBS / DEIIEER V IWA0111,1993 lusal 11,1993 ! BAV10 J. EEnett / OstIEtt i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ ._ _
m_ ,m._ _ __ m-- 5 O 3 Page No. 4 LENTE AISE IIIli 2 Bete Base Flle lismeMete/ Time W2
- SSEL.WF / $1/11/93 / 09:M:3 Report Dete/ Time: 03-11-93 / 15:40:14 3AFE SWTOOlsi EgillMilt ilst ($$tt) Sort Criterla: Llee lheter 91RLL OREAK LetA AW CIpitAIINIll SYST915 Fliter Criteria: (tlee ihmters.*Fest')
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Page No. 2 IERTN AIS14 leIIT 2 ' Data Sase File lhme/ Bate /Ilme: m2~ $$EL.00F / 03/11/93 / 09:38:38 Report Bete /Ilse: 03-11-93 / 15:40:14 SAFE 58tf100181 EqulPIENT LIST (15EL) Sort Criteria: Lies hauber 3mLL OREAK LOCA NG CONIAIISEN! $YST915 fliter Celterla: (Llee lhuber>='7000') ($orted by Llee Ihuber) Program File Name & Verslee: 538130.8 LINE EQUIP SYSTDl/ EQUIPMENT < EqulPIEllt LOCAileil-> <- OP. 51. -> PWER SIfr0RTIIE SYS. ret'D INT!tDNEEti!0NS IE. TRAIN CLASS IutK 10. M3Ct!Pil0E Dug. lie./ter./2eee Bulldlag F ir.Elv. to. er tou/Cel. 30ti lOTES lhreat Bestred REEDT RE. W./REV. & StrPIETIE CSFINWITS I (1) (2) (3) (4) (5) (E) (7) (8) (9) (10) (11) (12) (13) (14) (15) (15) , 7025 2 set 2 5W-set-20ep SWAECIRC SPRAY COOLER D Dl301 11715-fM-078B1/20/C7 45PIl 2E5' - SRI CLO5EB IF01 W$ II/A 2-EP-K-19 150L 7027 2 004 245-let-2558 RSAluf510E RECIRC SPEAY PlfF S 12956 *1-ellA4/14/AE $fC8 257' IRLVE PIT I I IrDI WE" le ll/A 2-EP-IC-21 ! IEti ISOL v 7028 2 05 24$-P-20 25AWI$10E RECIRC SPRAT PWF 5 120C8-fM-SplA4/14/B3 SFW 26?' PWF CISICLE $e I 0FF INI WS II/A 2-EE-SS-SE 7029 2 est 2-ts-lev-25EB ESAlutsigt BEtttC SPRAY PipF 3 12050-fM-091A4/le/D5 SFCB 256' - t I CPDI OPUI W WA 2-EP-IC-21 DISCE ISOL 7031 2 084 2-$W-lev-200C SII/RECIRC SPRAY COOLER C DIS 01 11715-FII4FN1/20/C6 45PIf 265' ~ $t I CLO5EB CeEN W$ WA 2-EP-4C-21
- ISOL 7032 2 21 2-t$-TK-1A* RSAINT5IDE RECIRC SPRAY PWF A 12050-FM491A4/18/C4 SFCS 257' PWF CISICLE $ I II/A II/A W ll/A II/A SEAL iM y2 21 2-t$-TK-IS* R$/OWfilOE RECitC SPEAT Plfr 8 1205HM49144/14/C3 SFC0 267* -
$ I II/A II/A W ll/A II/A SEAL TAIK ,
i 78M 2 21 2-tS-E-2A* ES/OutsIBE RECIRC SPEAY PWF A 12850-FM-OplA4/18/C4 SFCB 267' 3.2/UI $ I N/A 11/ 4 W ll/A II/A SEAL M 7035 2 21 2-RS-E-20* 25/05t110E RECIRC SPEAY PWF R 12058-fM-OplA4/It/C3 SFC0 257' 3.5/X $ I II/A II/A in WA II/A I SEAL M ! 7835E 1 05 2-Su-P-5 SW/tADIATION IGNilotlE PWF 11715-FM4F853/21/CS 65Pil 265' - 5 I 0FF 0FF W ll/A II/A 7035F 1 05 2 3N-P4 SII/ RADIATION IGNIIIetilE PWF 11715-fM-ettW ?!/CE ESPIl 265' - S I 0FF 0FF 10 11/ 4 II/A i 7835C 2 05 2-su-P-7 SM/tWIAll0E IGNiittIE Ptfr 11715-fM-0FOBJ 21/C5 OSPN 265' - 5 I 0FF 0FF le II/A WA [ 703511 2 05 2-SU-P-4 Su/RABIAI1911ENiimilE PIBF 11715-fM-GFN3/21/tt 45PIl 265' - 5 1 0FF WF 10 WA II/A
- t 7035 2 21 24$ TK-1 ts/CA5IE COOLIIE TAIK 12 Wit-fM-00181/10/C4 YARS/TIBE 270' S OF AFPil $ I II/A II/A le WA II/A i 703EA 2 14 2454f-203L RS/CA111E COOLIIE IAIK LEWL Mt 1285HM-Opttt/10/4D C3tPN 270' ~
$t I WA II/A WS 12558-25-429/7 2-EP-CS-85 !
703EB 2 14 2-t541-2034 IS/tA51E COOLIE TAIK LEWL 12050-FM-89101/10/30 $$ 277' 8/C $R I. II/A II/A W$ 12850-85-029/7 24$4f-2034 ! IWICA10t l 78310 2 18 2-45-LS-2834 25/CA585 COOLIE TALK LEWL 12056 4 1-85301/10/ 2 58 252' 11/9 $t I II/A II/A le 12850-t5-029/7 II/A SulMR . l 703EE 2 18 2-454T-203 25/CASIE COOLIIE TAIK LEWL Jgitt 12058-fM-89101/10/4C CSCPIl 270' - 5tI WA A/A WS 12058-85-030/E 2-EP-CB-000 ' t CEtilFICAillNE: l The leformetles' idretlfyleg the egulgeset regelred to bring the plant to a safe shutduum condittee se 141s Safe Shutdeum Egstpaest List (15EL) i
- 13. to the best of our kaseledge and belief, rett and accurate. (One er more signatures of systems er Operstleen Eaglesers) ;
OMAIIf. JICIES / DEllEER Ub
- 191R0111.1993 i
IRYID J. IIEtatt / EEIIEER IIIRGI 11, 1953 flgestare i m__ _ _ . _ _ ___ _ _ . . _ . - _ _ _ _ - _
i I a ' Pope lie. 3 IEltTN Alen IBfli 2 Data tese File Ihme/Dete/ flue: Im2~ $$tL.MF / 93/11/95 / 08:30:38 ' Seport Dete/Ilme: 01-11-93 / 15:40:14 1AFE SIIKneist (Wiplegt LIST ($$EL) Sert Criterlo: Lien ihmter SlenLL OREAK LOCA AIS CONTAllfEft $YSTDE5 filter Criterlo: (Llee ihmterW7008') , (Serted by Lien ihmter) Program File IImme & 9erstes: $$81 vG.0 i LIIE EWIP $Y$1Dl/tWIrlWii < EWIPIGIT LOCAftSi - > w SP. St. -> PREE SWFWilE $15. Eft'B INTserumsriIgl5 le. TRAIN CLA$$ MAAK W. DESCRIPTIoll Dug. Its./tev./Zeee Bulldlag fir.tiv. Em. er tendel. SIRT Wit $ lisrael testred IEWT SE. W./ tty. & SWFWilE CSrgimit$ (1) (2) (3) (4) (5) (6) (7) (8) (9) (le) (11) (12) (13) (14) (15) (14) l 703EF 2 18 2-t$-LI-28B R$/ CASING CEOLIE 7** LEVEL 12058-FM-091SI'10/3C $8 277' 8/C $t I 11/ 4 II/A VES 12MS4$-038/5 2-t$-LT-283 IWICAlet 7038G 2 le 2-t$-LS-285 R$AA$ls COOLIE TAllt LEVEL 1205HM-09181/10/3C $8 252' 11/9 5t I 11/ 4 II/A IO 12950-t$-030/5 11/4 SWITOI 7037 2 05 2-85-P-34 R$KASIE COOLIE PWF A 3205HM4 BIB 1/10/B7 CSCPil 271' ~ $tI 0FF 51 ft$ II/A 2-INE-28 7038 2 004 24$-lEIV-291A R$NA$lE COOLIE Pier A DI506 12050-7509101/10/17 SFCB 256' ~ 2 I IFDI CPDI 10 - WA 2-EP-IC4 ISOL 7039 2 004 24$-lOf-2OO4 R$/CA$lE COOLIE Pl#F A DI501 1255HE89181/10/E7 SFC0 256' -
$t I CLOSES 1r81 Yt$ M/A 2-EP.MC-28 l Isot ;
7000 2 05 2-t$-P-38 R$KASIE COOLIE PWF $ 12950-FM-893Ol/10/96 C5CPR 271* - $R I 0FF ON VES 11/ 4 2-IP-IC-22 7941 2 004 2-t$-lWW-2018 R$AA$1E COOLIE Plfr 8 BISCN 12E58-fM-8BISI/IS/F7 SFEB 256' - t I IrDI GPDI W ll/A 2-EP-IC-21 !
, ISEL 7042 2 004 245-lWW-20E R$#ASIE COOLIE PWF 5 91301 1205HM-0BISI/10/F7 SFC8 256' -
$R I C105EB IFER ft$ N/A 2-EP*C 11 f ISOL . ;
7101 1 87 2-LEE-TV-20B IE5/$itAll ORAIN Opmit 150L 120lHE5FOL3/28/D3115411 273' 13/EB $ I SPUI C185ER le 1250-1E5-209/5 2-LEE-50t-20EA 2 4-10t-teIB j flat 1 SEB 24-505-20g4 M5/$ TEAM ORAIN Cemit 150L Pit 0f 12050-F507843/28/94 IE5WI 273' 13/H $t I,$,36 AIR 90ll W 12WIS-ME-205/5 11/4 i 7103 1 em 2-LEE-10W-295 IE5/$ftAll 884111 Celmfr I1et Pttet 12eit-fil-87843/28/D3 IE5W 273' 13/E8 $t I,$,35 Alt 1Dll le 12WOSM-20t/5 II/A 7104 1 87 2-IE5-TV-21e IE5/5E BLemoisi Cemit I$0L 12058-fES753/19/A4 M5111 271' 12.7/NL $ I 1r91 CLOSEB B 1288-1E5-210/2 2-115-30V-2184 ; 2-IEE-SOV-235 , 7185 1 GES 2-MS-30t-2104 IE5/5C ILOWOISI telmfr ISOL PILOT 1295HE47W3/19/A4 IE5111 211' 12.8/IIL $R I Alt VDit ID 12850-ME-214/2 II/A e fles 1 GIR 2-4EE-30t-21N MB/5G ILGemel Cemet ISCL Pilot 12010-7407E3/19/A4 M5411 271' 12.8 MIL $t I Alt VDit le 12E58-1E5-214/2 II/A + 710F 1 07 2-08-1V-2004 88/58 1L8888E DNmet liet 12e50-fM-ege42/16/C4 Am 244' 11.5 4 $ I 1r91 CLOSES 15 12058-88-8B1/5 2-8B-SOW-2 eat ; 71 5 1 815 2-ID-50t-2004 88/5G 1A Steesel Cemit ISEL 12854-fE8tOA2/16/DE AR 244' 11.$K $t I
- Alt VFilt le 12958-N-8Bl/5 II/A PItSt flot 2 07 2-80-TV-20m IR/5C airmsumes Dumli Isot 120iMEsgBA2/14/C$ Cemit 241' le $ I 17 91 CLOSED 10 12850-N-802/3 2-00-30V-205 File 2 088 2-88-SOV-208 88/5g kHusuR88 CWmIT ISOL PILOT 12450-7E85042/16/95 ColmIt 240' 10 $t I Alt VDif 10 1205HB-002/3 N/A CftilFICATIGI:
The leformetles ideett lag the egelpmeet required to bring the plant to a safe slutdeus conditles se this $efe Shutdeue Egulpment list ($5ft) is, to the best of our ledge and belief, t and occurate. (0me er omre signatures of Systems er Operettees Eaglesers) ; BAREl U JROR$ / DEIIEEE .- v IWA0111,1993 I i SAVID J. HERODI / DEllEtt , MRADI 11,1983 . P" i
Pope Ib. 4 IEIRTN AIER 1RNi 2 Data tese File Nume/9ste/ time: 22 $$EL.WF / 01/I1/93 / ep:N:M Report Dete/ Time: 10-11-93 / 15:40:14 SAFE SIRKacist EquffWilt LIST ($$EL) Sort Criterie: Llee master SIGLL OHAK LOCA AM GRifAl10mit $Y5fDIS Filter Criterle: (Llee thmber>='7We') ($erted by Ller ihmter) Progres Fik lhme & terslee $581 ve.0 LINE EqulP $YSTDl/EqulPHENT < E4WIPMEIK LGCAiled -> W. <- W. St. -> PWEt SWFWillE SYS. RES'S IWserummarilem TRAIN CLA$$ l#AK W. DESCtlPilG1 Aug. Ils./Rev./Zeme Sulldley Fir.Elv. an. er tou/Cel. Sui IOtt$ Nureel Bestred REST SE. W./REV. & SWFWills OppelEllf$ (1) (2) (3) (4) (5) (5) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 7111 1 07 2-88-TV-20sc as/5C BleWRAI CONINT Is0L 12050409043/14/C6 ARE 244' 12/J $ I WOf CLOSEB le 12W84001/5 24-50f-feet 7112 1 em 2-ap-30t-20eC IB/54 M tiemmet OpmW Isol 12058-F16-01841/10/96 ARE 244' 12/J $t I Alt UDK W 1250-08-081/5 II/A PILet 7113 2 07 2-et-TV-205 IR/5G 18 Stemmel aumit Isol 12E54-Fil4tIAFM/CS ONifilt MI' IS S I 8PD1 CLOSEB ID 12WN 24-50t-208 7114 2 GRB 2-80-50t-2OIB 10/58 M BLelSOW aumet 15el 1205NN-elen1/18/95 Camir MI' le $t I Alt IDK W 1285HB-004/7 11/4 Pilet 7115 1 87 2-eD-TV-200E 88/58 It aimamm DNmlf 15el 12058-f18-01844/1046 AIK 244' 12/J $ I WDI Cle5EB B 1250-68416/5 24-Set-20EE 71N 1 08B 2-85-50t-2eOE 18/58 X BLSABRI Opmit 15el 12858-fil-OleA4/M/95 AIK M4' 12/J $tI Alt VDK W 120564805/5 II/R FILM 7117 2 07 2-88-TV-2OOF B0/54 X ymmmer Osmit ISOL 12850401844/1845 GumK N1' 9 $ I WDI CLD5EB 18 t258HB40E/B 2-88-50t-2EIF 71p 2 IIS 2-88-50t-20er BB/5C lt tusemil GHmW ISOL 12WNN-6BbM/18/D5 agmit M1' 9 $tI Alt VEN W 12WSM-40E/B 11/4 Pilot 1 7119 1 SF 2-$l-TV-280 $I/HilRIEDIIEABER Opmst ISOL 12850-fM-841/17#3 ARE NE' 11/K $ I N01 CL95EB W 12WS-SI-8M/4 2-$l-50t-leet 2-$I-sor-2em 7122 1 87 2-$l-TV-201 $I/NR$1C CAS FILTS CWmit ISOL 12WHI64EN1/17A4 ARE 244' ll/K $ I W01 CLO5EB B 12WS-SI-013/3 2-SI-Set-201 71234 1 agB 2-$l-Set-teen $I/MITROEDIIEASER CGmit ISOL 12850-$l-034/4 AIK 246' II.5/K $t I Alt UElit W lle58-SI-038/4 II/A Pilot 7123 1 em 2-$l-30t-205 SI/MITEICDI NEABER Gpmit ISOL 12050-$1-034/4 AIK 246' 11.5/K $t I Alt 3DK IS 1250-SI-GM/4 II/R PILet 71N 1 890 2-SI-30f-201 $I/lR$ff GAS FILTR Opmit ISOL 1285 Hit-00ml/17/E4 AIK M4' 11/K $R I Alt VDK W 12EIS-$l-013/3 11/4 PILet s 71 5 1 87 2-51-TV-2050 $I/ACGff TEST LIIE numit 151F 12854-fM-09EA2/N#7 SFW 267' -
- I CLOSEB CLOSED IS 12050-$I-835/4 2-$l-50r-le59 71M 1 sie 2-51-SCV-2059 $I/ACI1!! TEST LIIE Gumit ISCL 12850-HI-01 eat /24#7 $FGB 267' -
t I ytlK VOK le 12E50-$I-835/4 II/A Pilot 7127 2 SF 2 51-LEV-2ME $li M CASFLitRETWNCamK 1285NN-Ogul/IFAS tumK Nt' 11 - I' Cte5EB CLO5EB W 12E50-51-014/5 2-SI-30t-2935 ISEL 7128 2 set 2-$I-50t-2935 $l/Ist$lt GAS FLTE RETWN tems 1285848951/1745 GumK 248' 11 R I VDK VDE W 12858-$l-014/5 IVA ISOL PItti CUTIFICATISI: The leformatten lesettfring the equipamet ragstred to bring the plant to a safe shutdeue conditles se this $efe Shutdeue Equipment List ($3EL) is, to the best of our boustedyr and beIIef, t and occurate. (One er more signetures of Systems er Operettoes Eaglesers) 31101 H. JRGR$ / EMIMM Uh "C IIWCN 11,1993 047I8 J. IERGER / DEllEER 185 01 11, 1981 i-
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O O O. T' age No. 7 NORTil AIBIA Imli 2 Data Base File Name/DateMles: Igl2* $$EL.OSF / 03/11/93 / 09:30:38 Report Date# lee: 03-11-93 / 15:40:14 SAFE $11UT00W E5f!PIENT Liti (55EL) Sort Criterta: Lies Ihaber SMnLL OREAK LOCA AE CONTAlWENT !Y1TEMS Filter Criteria: (Llee lheter>e'7000') (5orted by Llee lhaber) Program file name a merslee: SSDI v0.0 LINE Equ1P SY5fDl/tqUIPIENT < Equ!PMENT LOCATIoll -> <- OP. $f. -> POWER 3lpF0 tile SYS. RES'8 INTERCOIIEtil0N5 le. TRAIN CLASS mRK E. DESCRIPTION lbsg. No.Aevltene Sulldlag iIr.Elv. Re. er Rew/ Col. $0ti ICTES Ihreat Bestred req 07 OK. ID.AEV. & SWP90tflE C990NENT5 , (1) (2) (3) (4) (5) (E) (7) (8) (9) (10) (11) (12) (11) (14) (15) (16) 7170 2 ORO 2-lW50V-200D LMEAKAGE leilliotIE CONIMT 130L 12050-fM-092A1/1555 AUI 259' 11.5/t 5t I Att VDIT In 12050-tM104/5 II/A i PILOT j 7171 1 07 2-lM-TV-200E LWLEAKAGE leNITMIE Colmff ISOL 12050-fM-09tA1/15#6 AUI 259' II.5/J $ I IPEN ClostB le 12050-181-005/5 2-tW509-200E 7172 1 tet 2-tM-50V-200E IMEAKAGE Boll 10RIE CON!MT ISOL 12050-TM-OREAI/15#6 AUK 259' II.5/J $t I AIR VDit le 120584MPJ5/5 II/A PILoi 1173 2 C7 2-tM-TV-200F LMEAKAGE leltlictIE Colmtf ISOL 1205HE00241/1565 AUK 259' II.5/J $ I 19D1 CLOSEB le 12056-tM-006/5 24M-30V-200F t 7174 2 088 2-LM-50t-200F LWLEAKAGE MONITotill: Colmli 150L 12050-f4032A1/1565 AUK 259' 11.5/J $t I Alt VDit 10 12058-tMIOS/E M/A PILOT 7175 1 07 2-tM-TV-200G IMEAKAGE leNITORIE ColmlT ISOL 12050-fM-OttAln5/17 AUK 259' 12/J $ I CPDI CLO5EB E 1205445007/5 2-Lll-50t-200G 7175 1 008 2-LM-30V-200G iMEAKAGE leNITORIIIG Colmli ISOL 12054-fE0 BEAU 15#6 AUI 259' 12/J 1R I AIR VDIT 10 1205645007/5 II/A PILOT l 787 2 07 2-tM-TV-200N LWLEAKAGE tellIT0t!E Colmli ISCL 1205HM-OttAl/IS#6 AUI 259' 12/J $ I 17 01 CLOSS le 12050-(M-008/5 24ESot-200N 7178 2 005 24M-50V-200N IMEAKAGE leNITORIE C0lmff ISOL 12054-fM-Ot2A1/15#6 AUK 259' 12/J $t I AIR VDIT le 1205H5008/5 11/4 PILOT 7179 1 07 2-tWTV-201A IM/PH15 $DI51R Colmtf ISOL 12058-FM-StPAI/15/D5 AUX 244' 11/J $ I IFEN CLO5EB le 12050-tM-017# 24530F-201A 1100 1 008 2-tM-50V-201A LM/ PRESS SD150R CONIMT ISOL PILDT 12050-FM002A1/15/D5 AUK 244' 11/J 5t I Alt VDIT le 12000-tM-017# ll/A 7141 2 07 2-tM-TV-2018 LWPHIS 50150t Colmtf 150L 12050-fle-OR2nl/IMi$ AUI 246' IUJ $ I CPD1 CLOSED E 12058-tM-014/7 24550t-2010 ; 7182 2 GEO 2-tM-50t-20lt LWPRES5 $U150t Colmtf 150L PILOT 1205HM49 TAI /15/D5 AUK 246' IUJ SR I Alt VDIT 10 12054-LM-018/7 II/A 7183 1 87 2-tM-TV-201C LM/ PRESS SD151R Colmtf 130L 120$0-fEcstAl/15/D5 AIR 244' 11/J $ I lyDI CLOSEB 10 1205HM-017# 24M-50t-201C l
- i 7104 1 est 24550V-201C LWPRE55 50150t Colmtf 130L PILOT 12058-FM-002Al/15/05 AUK 244' 11/J $t I Alt VDIT le 1205H&G17# II/A -
7105 2 07 2-LM-TV-2010 LWPRE11 $D150t ColmIf ISOL 121NWFWettA1/15/D4 AUK 246' IUJ $ I OPUI CLOSEB le 1205045018# 2-t&30V-2013 7105 2 Ges 2-tM-50W-2010 tWPtts$ SDEIGR Colmit 130L PILOT 12058-nt-OstAl/15/05 AUK 24E' IUJ 5t I Alt VDif 10 120504M-018# N/A 7187 1 07 2-EM-TV-200A RM/tADIAil0N IGNITORIE RETulli Colmtf ISOL 12050-FM40202/03/C7 AUt 244' !!.5/K $ I' CPDI CLOSED No 4205G-AM-018/5 2-et-Sov-2004 1 r Ties 1 Det 2-88-50t-200A NE/WADIATION MON!TORIE RETutN 1205HM-002B2/09/C7 AIR 245' II.5/K st I Alt VDIT 10 12050-aM-018/5 II/A Colmtf ISOL PILOT ; f CERTIFICAfl0ll: , The leformattee identlfyleg the egulpeest regelred to bring the pleet to a safe shutdeus condities se this Safe Shutdeue Equipecet List (15EL) f is, to the best of our keeuledge sad tellef, t and accurate. (See er more signatures of Systems er Operations Estiseers) [ Duel W. JAC00$ / EEllEER U lifeCil 11, 1993 C'VID J. UERDER / DEllEER IgutDI II,1993 [ signature f
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t Pete lie.10 listfu AleIn IMIT 2 Data tese file lisme/ ente /Iles: Im2 $stL.seF / 03/11/93 / 09:38:38 Report Dete/ flee: 03-11-93 / 15:40:14 $Aff SWT00181 EWIPIEE LIST Sort Criterlo: Llee nyter SHILL STEAK LOCA AIS COMAI 9 15 Filter Criterle: (Llee skaber> '70BS') (sorte4 by Llue Ihmter) Program File Ilume 4 9erstem: $591 we.0 LIIE EWIP $YSTDl/EqlHPIEE <- Equ!PMDK LOCAflGI -> <- W. ST. -> PWER SWPIRTIE SYS. req'8 ImmtNSECTIGI5 ! M. TeAIN CLAS5 MNtt W. gESCRIPTION lbg. No./Rev./2eme Bulldlag F tr.Ely, ts. er RenKel. $0RT lOTf! Nurmel Sestred EEqBF BE. W./R(V. 4 SWPMTIE CEWmENTS l (1) (2) (3) (4) (5) (E) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) 7216 2 CIS 2-CC-10t-200C CCKC t[TtRN Ftpl COOLIE COIL 12050-FM-07983/14/t4 Alst 244' 11.3/L 5t I Att VDIT le 12W64C-852/5 II/A CONTNT 150L PILOT l 7217 1 07 2-CC-TV-201A CC/TIIENGL BAAtlEt 88501 CCImt 12WIO-FM-07941/19/II7 AllE 244' 11.4 4 5 I WDI CLD5EB le 120504C-853/5 24C-30t-201A ' is0L ; 7214 1 Ges 2-CC-30t-MIA CC/TIIEEMht SAARIER 9I501 CONINT 12050-79007941/19/D7 AIAI 244* 11.4 4 5t ! Alt VDR W 12050-CC 853/5 11/A i ISOL PILOT 7219 2 07 CC-TV-2918 E/flIENIRL BARRIER 01500 temt 12850-fM-87941/19/IE CONME 24B' 18.5 $ I CPDI CLO5ES 15 120504C-854/5 24C-SOV-2018 ISOL ' 7220 2 des 2-CC-30V-2013 CC/INEWut BARRIER 88508 CCImW 12050-fM-8F941/19/DE Colllit 249' 18.5 5t ! Alt VOIT *IS 120504C-854/5 WA I I 130L PILOT 7221 1 07 2-E-TV-20tA CC/IICP CC tiilmi CamK ISOL 12050-FM-GF944/IE/A5 AtSt 244' 11.3 4 5 I OPUI CLO5ES W 12050-E-855/5 24C-50t-2efA 71p 1 est 2-CC-30t-20th E/tCP CC RETINI CWmli 150L PILOT 1205HM-OF9R4/16/95 Allt 244' 11.3 4 $t ! Alt VDIT le 1205HC-855/5 WA 7223 2 07 2-CC-TV-Itte CC/tCP CC RETWHI GNmW ISOL IN5HM-87944/IE/A3 C0lmW 250' 10.3 $ 1 WD1 CLO5EB le 120le-CC-058/G 2-CC-30t-205 l 7224 2 000 24C-Set-20ER E/tCP K RETIRIl CCImE ISOL PILO! 120lHM-879A4/IE/A3 DNmW 250' 10.3 $R I Alt VDIT W 12El04C-858/E II/A t 7225 1 07 2-CC-TV-20EC CC/RCP CC REfist CCImt ISOL 12050-fM-87943/17/A5 AME 244' 11.7/K 5 I WDI CLOSEB W 12O504C-056/5 2-CC-30V-20ft ' 7226 1 Ogg 24C-30t-20tC E/ttP CC RETINI ColmR ISOL PILOT 1205HM-87943/17/96 AtEl 244' al.7/K 1R I Alt VDK 10 12E504C-85E/5 II/A 7227 2 07 2-CC-TV-20ft CC/RCP CC RETIml Camit 150L 1205HM-87943/17/A3 Colmli 249' 10.3 $ 1 WOI CLOSEB W 12050-CC-859/5 2-CC-50V-20ED 7228 2 008 2-CC-30V-20lO E/RCP CC ttTWN Cemn 150L PILOT 12050-FM-879A3/17/A3 CONRK 249' 10.3 $R I Alt VDK W 12050-tt-059/5 II/A , 7229 1 GT 2-CC-TV-202E CC/ECP CC RETWII 03mn 150L 12550-FM-87942/IE/A5 AMK 251* 11.8/JC S I WD1 CLOSEB W 120504C-8575 2-CC-50F-2eEE i 7230 1 est 24C-10v-202t E/RCP CC ttTIAll Dumli ISOL PILOT 12050-FM-87942/16/ts Alst 251' 11.8/JC $R I AIR VDK 15 120504C-8575 IL/A 7231 2 07 24C-TV-202F CC/ECP CC f(flesi C0lms Is0L 1285HM-87942/IE/A3 C0lmW 24t' 10.1 s I WDI Closes le 12050-CC-Get/E 2-CC-30V-202F f 7232 2 088 2-CC-30V-2stF K/RCP CC RE11211 CelmW ISOL PILOT 12050-fM-GF942/IE/A3 CGIDE 249' 18.1 $R I Alt VDK 10 128504C-4E0/6 11/4 7237 1. 2 07 2-CC-TV-204A CC/tCP CC CGmW ISOL 12050-fW-OF942/IE/t3 Atat 254' 12/J $ I- WDI ClosEB le 129504C-853/4 2-CC-50V-204AI i 2-CC-30V-20e42 i 7238 1 008 24C-50t-20041 CC/WCP CC ColmR ISOL PILOT 12056.fM-87942/IE/E8 Atit 254' 12/J $t I Alt VUlf le 12050-CC-853/4 II/A [ 7239 2 08B 2-CC-30t-20042 CCACP CC Caml' ISOL PILOT 12050-fM-87942/IE/E8 Atit 254' 12/J 5t I Alt VUlf M 12050-CC-063/4 11/4 CERTIFICAT!Gl:
}
The teforsetles identifyleg the egelpuret regelred to brleg the pleet to a safe shutdeum condities em this Safe Shutdeue Egulpment List ($5EL) f is, to the best of our kansledge end belief. terrect end accurate. (One er sure signeteres of Systems er Operettees Eaglesers) ; DIRBIII. JROSS / EEIIEEE b 191A0111,1993 IEV10 J. IIEECER / EEIIEER IIIA0111.1993
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. I i
(EttlFICAlleN: The loferustles identifyleg the equipuset ragstred to bring the plant to a safe shutdeus condities es this Safs Shutdeum Egmipment List ($$tt) is, to the test of our kasuledge end tellef, and accurate. (ene er more signatures of Systems er Operstless Eaglesers) ! SAISI W. JACMS / BEXIEtt &h IWAOI 11,1993 BAV10 J. IERett / DEIIEER gyp, lea 0111,1983 t 7 sis =st re t 1
i i Revision 1 i l O Appendix L ! NOTES FOR ALL SAFE SHUTDOWN EQUIPMENT LISTS 5 General SSEL Notes - See SSEL column 11 to determine applicability. l t l 1. The following CCW pump pressure indicators are local to the pump and therefore
- are not vital to the SSEL
- 1-CC-PI-101NB, -102A/B; 2-CC-PI-201NB, -202A/B.
7
- 2. Failure of this valve to operate will not result in a single failure of the system as it l can be manually operated with a bandwheel i
- 3. " Normal" position, as indicated on the SSEL, is based on the July 30,1990 l
meeting with NAPS operations personnel and differs from that shown on the l 3 P&ID. 4 i 4. Additional drawings associated with these components are: l f 11715-FE-6A, B, C, D, E, F, G ! 11715-FE-18N 11715-FE-9CJ, 9DL, 9FB l' .pd 11715-FE-67A, B i 11715-FE-78A, B i S. System boundary per July 30,1990 meeting. l i ! 6. These items are included on the SSEL as they are identified as a result of the j relay evaluation. 5
- 7. AP-22 would be used to align auxiliary feedwater flow through the MOV header l
i to the steam generators upon loss of instrument air to the HCV header. 1 i 8. The steam generator safety valves will not be challenged and are shown as a j boundary. Therefore, the flow elements are not needed for safe shutdown; j however, a seismic evaluation should be perfonned for IPEEE since the safety i valves are associated with NSSS equipment.
- 9. The steam generator steam pressure channels selected are the same as those for i Appendix R, with an additional channel selected for redundancy.
1 e
. 10 Additional drawings for the control rod drive mechanism can be found in the 11715/12050 - 1.27 series.
! L-1 i ) l 1
i s Revision 1 j 11. The service water system boundary excludes the auxiliary service water pumps as ; j the service water pumps do not need a backup. , I i 12. PORV block valves are indicated as active because of possible PORV failure. l 13. Additional drawings for the neutron detectors can be found in the 11715/12050-L 1.25 series. ! 14. These items are NSSS equipment and are included for IPEEE purposes only, i l 15. 'Ihese items are to be put in the desired position by use of administrative controls. l Those valves which require operator action will be included in an attachment to AP-36, i ] 16. All piping systems comprising the boundary of the pressurizer. relief tank need not ,
- be verified for safe shutdown since rupture of the tank safety heads is an
- acceptable consequence of discharge to the tank Level and pressure instruments
- are verified as optional items to permit the operator to assess margin to safety i head rupture.
L i 17. Offsite power is required to operate these valves; however, procedures are in place for manual operation. ! 18. This item is included on the SSEL as a result of the preliminary walkdown. l 19. Accumulator test isolation valves (1-SI-HCV-1850 D/F, 2-SI-HCV-2850 D/F), their l pilot valves (1-SI-SOV-1850 D/F, 2-SI-SOV-2850 D/F), and the accumulator outlet l isolation valves (1-SI-MOV-1865 B/C, 2-SI-MOV-2865 B/C) are listed for decay heat removal function. I j 20. Absence of a redundant seal parameter indicator will not preclude safe shutdown
- if the indicator fails.
I i 21. Backup not required per conference reported by MPR letter to Virginia Power j (NP-1146/NP-1147-V01-009), dated August 3,1990.
- 22. - Accumulator test isolation valves (1-SI-HCV-1850B, 2-SI-HCV-2850B, their pilot i valves (1-SI-SOV-1850B, 2-SI-SOV-2850B), and the accumulator outlet isolation j valves (1-SI-MOV-1865A,2-SI-MOV-2865A) are listed for pressure control 4 function.
'S lo w - -
4 i j Revision 1
- O 23 . These items of equipment are not required to operate but rather require a seismic
! review for system boundary integrity only. , o i
- 24. These valves will be inoperable upon loss of instrument air. Virginia Power will
- develop a method and procedure for manual operation.
i l 25. These valves have their own air accumulator and can be manually operated i locally, i l 26. These coolers are required to operate for the small LOCA scenario of IPEEE; i however, a seismic review for A-46 should also be performed because the coolers ! constitute a fluid boundary.
- 27. The RHR heat exchanger cooling water outlet containment isolation valves (1-CC-
- TV-103A/B,2-CC-TV-203A/B) will fail closed on loss of air. AP-28 includes a
! procedure for opening these valves with a nitrogen jumper when required. t , 28. These valves are used to ensure a system boundary in the event ofloss of 1 instrument or service air. t I
- 29. Additional drawings for EDG components can be found in the 11715/12050-1.30 series.
- 30. Additional drawings for heat trace cabinets can be found in the 11715/12050-1.42 series. -
- 31. Drawing unavailable for Unit 1. Information based on analogous valve for Unit 2.
- 32. Valve not shown on P&ID for Unit 1. Valve is shown on Unit 2 P&ID and is identified by Passport database and NCRODP-52.
- 33. A commitment to maintaining the nitrogen tanks pressurized or to the development of a procedure to supply high-pressure nitrogen via the supply line is needed.
- 34. The loop drawing for this item was unavailable during SSEL preparation. The operating position of this valve was assumed based on similar valves in the plant.
- 35. The loop drawing for this item was unavailable during SSEL preparation.
Information is based on an analogous item for Unit 1. O
I i h 1
- Revision 1 O 36. This item will be evaluated using the rule-of-the-box determination as discussed in l the GIP. The parent component, on/in which the ihm is mounted, is identified in
- column 16 of the SSEL i
4 l 37. This item does not require a relay review because during normal operation the ! item is isolated from its power supply by adaiini-hative control.
- 38. The hydrogen recombiner system is shared between Unit 1 and Unit 2. The j desired valve positions indicated in these SSEL lines are for use with Unit 1.
! 39. The hydrogen recombiner system is shared between Unit I and Unit 2. The j desired valve positions indicated in these SSEL lines are for use with Unit 2. i l 40. The desired position of these valves is "open" for sampling during safe shutdown, l but " closed" for containment isolation. i l 41. These cabinets / panels contain essential relays. ! 42. This item is listed in the relay report as cabinet 1-EI-CB-23F. I j 43. DELETED i
- 44. This item is included in the SSEL to address the Generic I.etter 131 concern in NUREG 1407.
i l
~O u
d i Revision 1 PO l Imation Notes. Unit 1 - See SSEL column 9 to determine applicability 1 . 1A. Three feet north of RWST,31/2 feet off ground. t IB. Three feet south of RWST,3 feet off ground. i IC. South wall, west end. i ! 1D. North of A and B boric acid tanks. 1E. Tank is connected to the AFFH. i 1F. Eight feet southwest of inside door, 4 feet above floor. ! 1G. .Two feet from handrail on stairs leading to upper deck. 4 j 1H. East side, first ladder down, second level down.
- IL West side, lowest level, 8 feet southeast of ladder.
1 !) IJ. North wall of Unit 1 piping penetration area. ! 1K. Second room, lower level between catwalks. T l IL DELETED. i ! 1M. Down ladder to second level,7 feet north ofladder. i ! IN. Down ladder to second level, 2 feet south of ladder. ! 1 ! 10. East side between MCCs west of P.V. blowers. IP. Second room, lower level, 3 feet inside. 1Q. Ten feet off floor,7 feet east of column 7 toward column 6. l 1R. DELETED i IS. DELETED i
; 1T. DELETED 4
1
Revision 1 1 !O
- IU. South side of catwalk,3 feet north of penetration.
IV. South side of catwalk,2 feet from south wall. 4 1W. South side of catwalk,2 feet north of penetration. i 1X. Three feet northwest of 1-RS-TK-1,4 feet west of casing cooling house. 1Y. Four feet from north wall, in-line with louver metal vent. i 1Z. One foot from northeast wall,30. feet from wall at entrance. ! 1AA. Fifteen feet west of door,4 feet from south wall,2 feet off floor. I 1BB. One foot from northeast wall,20 feet from wall at entrance. i Imcation Notes. Unit 2 - See SSEL column 9 to determine applicability. Five feet above floor,6 feet north of containment wall. 2A. 2B. Five feet above floor,22 feet north of containment. 2C. Five feet above floor,20 feet north of containment wall.
- 2D. Nine feet north of 2-IA-TK-4D against east wall.
'l 1 I i e T i l i
l 1 I Revision 1 i jW 2 l d Appendix M REFERENCES AND DRAWINGS USED FOR SSEL DEVELOPMENT I i j General i l Seismic Quali5 cation Utility Group, Generic Implementation Procedure (GIP) for i Seismic Verification of Nuclear Plant Equipment, Revision 2, June 1991 as corrected on ! February 14,1992. l l Supplement No. I to Generic Letter (GL) 87-02 that transmits Supplemental Safety i Evaluation Report No. 2 (SSER No. 2) on SQUG Generic Implementation Procedure, j Revision 2, as connected on February 14,1992 (GIP-2) dated May 22,.1992. l EPRI NP-6041-SL Revision 1. A Methodology for Assessment of Nuclear Power Plant j Seismic Margin (Revision 1). NUREG 1407 - Procedural and Submittal Guidance for the Individual Plant Framination j) of External Events (IPEEE) for Severe Accident Vulnerabilities Final Report.
- Electric Power Research Institute, Seismic Margin Assessment of the Catawba Nuclear j Station, EPRI NP-6359, April 1989.
Station Documents f l 10CFR50 Appendix R Report, North Anna Power Station Units 1 and 2, Revision 5. i Station Blackout Coping Evaluation: North Anna Power Station Units 1 and 2, prepared
- by Stone & Webster Engineering Corporation, dated June 1989.
! Corresoondence
~
i ! letter NP-1146/NP-1147-VO1-009, MPR (Cooper) to Virginia Power (Roth), North Anna Power Station Units 1 & 2: Preliminary Seismic Walkdowns of Equipment ! Selected for Safe Shutdown for Resolution of USI A-46 (Agreement Ne ER-MG-9005), i - dated September 24,1990. i l Ietter NP-1146/NP-1147-VO1-038, MPR (Cooper) to Virginia Power (Roth), North i Anna Power Station Units 1 and 2: Report of Meeting Concerning Draft Report MPR-l 1201, " Identification of Safe Shutdown Equipment" (Agreement No. ER-MG9005), dated PT April 25,1991.
- 'O M-1
Revision 1 f ! Memorandum from Virghtia Power (Roth) to MPR (Cooper), Station Operations l Comments on NAPS SSEL, deal July 22,1991. L l Letter from Virginia Power (Sorrell) to MPR (Cooper), NAPS 2 In-Containment Preliminary Walkdown Datasheets; October 19,1990, f NAPS 1 and 2 Outside Containment Preliminary Walkdown Datasheets, October 1991. Letter from Virginia Power to MPR Associates dated November 9,1992
Subject:
- Contract No. ER-LC 2003 Safe Shutdown Equipment List and Relay Evaluations for USI A-46 and IPEEE.
I
- Letter from Virginia Power to MPR Associates dated November 24,1992,
Subject:
Final i Safe Shutdown Equipment list (SSE11) for USI A-46 North Anna Power Station - Units i 1 and 2. . 1etter Serial 114-12-03 from MPR to Virginia Power dated January 27,1993,
Subject:
l Revised Trip Report from MPR's January 19,1993 Visit to Innsorook Technical center. j ! Ietter Serial 114-12-02 from MPR to Virginia Power dated January 27,1993,
Subject:
! North Anna Power Station USI A-46 and IPEEE 5efe Shutdown Equipment Selection. Letter from Virginia Power to MPR Associates dated February 1,1993,
Subject:
- Amendment No. 001 Contract No. ER-LC 2003 Safe Shutdown Equipment list and j Relay Evaluation for A-46 and IPEEE.
i letter Serial 114-12-04 from MPR to Virginia power dated February 3,1993,
Subject:
North Anna Power Station USI A-46 and IPEEE Safe Shutdown Equipment Selection. Ietter Serial 114-12-05 from MPR to Virginia Power dated February 10,1993,
Subject:
North Anna Power Station USI A-46 and IPEEE Safe Shutdown Equipment Selection. NAPS Drawines Used To Prepare SSEIS (See Table M-1)
. M-2
Revision 1 i
~
q ) TABLE M-1 i
- DRAWINGS USED FOR SSEL DEVEIDPMENT l
j The following is a list of piping and instrumentation drawings and electrical drawings - ! used to develop the North Anna Power Station Units 1 and 2 Safe Shutdown Equipment I List. ( f
- (Example: 11715-FB-006A1/19 is drawing number 11715-FB-006A, Sheet 1,
! Revision 19) {
- 11715-FB-024L1/11 11715-FM-078A1/36
- 11715-FM-078A3/28 i 11715-FB-040A1/13 11715-FM-078A4/43 11715-FB-040A2/13 11715-FM-078B1/20 11715 FB-040D1/15 11715 FM-078B2/14 l pd 11715-FB-040D2/13 11715-FM-078B3/21 1
11715-FM-078B4/15 I 11715-FB-044C3/07 ] 11715-FM-078C1/32 11715-FE-1A/21 11715-FM-078C2/27 k 11715-FE-1AE/13 11715-FM-078G1/12 l 11715-FM-078G2/10 l . 11715-FE-1AF/13 . i 11715-FM-078H/04
! 11715-FE-1E1/18 i i 11715-FM-078J/00 j 11715-FM-070A1/26 j 11715-FM-070A3/26 11715-FM-078K/00 l l
11715-FM-070B1/19 11715-FM-079A1/17 11715-FM-070B2/19 11715-FM-079A2/18 11715 FM-070B3/23 11715-FM-079A3/14 t
...O
, M-3
l l Revision 1
-11715-FM-072B/13 11715-FM-079D1/21 l 11715-FM-079B2/21
! 11715-FM-073A/31 11715-FM-079B3/20 11715-FM-079B4/21 ! 11715-FM-073B/13 11715-FM-079B5/21 11715-FM-074A1/32 - 11715-FM-079C1/13 ! 11715-FM-074A3/29 11715-FM-079C2/13 l 11715-FM-079C3/13 l 11715-FM-088A1/16 11715-FM-079C4/15 : l 11715-FM-079C5/18 l 11715-FM-089A1/16 i 12050-FM-073A/30 11715-FM-089D1/16 i 12050-FM-073B/11 11715-FM-091A1/20 j 11735-FM-091A2/23 12050-FM-074A1/27
- 11715-FM-091A3/20 12050-FM-074A3/29
- 11715-FM-091A4/24 11715 FM-091B/05 12050-FM-079A1/19 1 12050-FM-079A2/16 f) P 11715-FM-093A1/19 12050-FM-079A3/17
[\ 11715-FM-093A2/19 12050-FM-079A4/16
- 11715-FM-093A3/22 12050-FM-079AS/17 i 12050-FM-079B3/14
! 11715-FM-093B1/22 11715-FM-093B2/23 12050-FM-089B1/17 l 11715-FM-094A1/14 12050-FM-091A1/20 11715-FM-094A2/15 12050 FM-091A2/19 12050.FM-091A3/20 e 11715-FM-095A1/22 12050-FM-091A4/21 12050-FM-091B/10 11715-FM-095B1/21 11715-FM-095B2/24 12050-FM-093A1/24 ' 12050-FM-093A2/24 11715-FM-095C1/14 12050-FM-093A3/26 11715-FM-095C2/13 12050-FM-093B1/25 11715-FM-096A1/28 12050-FM-093B2/26 11715-FM-096A2/23 11715-FM-096A3/22 11715-FM-098A2/17 11715-FM-098A3/16 11715-FM-098A4/18 Q 11715-FM-096B1/17
. M-4 i
s
- Revision 1 11715-FM-096B4/17 12050-FE-1AE/10 4 11715-FM-108A1/03 12050-FM-094A1/15 ,
! 11715-FMC-106A/01 12050-FM-094A2/14 l 12050-FE-1A/10 12050-FM-095B1/22 12050-FE-1AF/09 12050-FM-095B2/25 12050-FE-1E/15 12050-FM-070A3/22 12040-FM-095C1/20 12050-FM-095C2/14 12050-FM-070B1/18 l 12050-FM-070B2/20 12050 FM-096A1/22 12050 FM-070B3/19 12050-FM-096A2/24
. 12050-FM-096A3/21 12050-FM-096B1/19 12050-FM-096B2/16 12050-FM-096B3/17 12050-FM-096B4/20 12050-FM-098A2/19 12050 FM-098A3/18 12050-FM-098A4/18 13075-FM-093C1/06 13075-FM-093C2/06 13075-FM-093D1/06 13075-FM-093D2/06
- M-5
_ _ _ _ _ _ _ _ ____ _ - . . . . -..-.. . .- _ . - . ..-.. . . . . . . . _ ~ . - - . _ - _ . . _ . - - . _ . . . . _ . - . . - _ - . _ . . i i
. I J,
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O O O Page No. I NORTH AISE LMIT I Report Date/ Time: 05-19-97 / 15:31:15 SAFE SHUTDOWN EQUIPENT LIST (55EL) COIFOSITE SSEL (Sorted try Equipment Class and Mark thaber) L112 EQu!P SYSTEMAQUIPMENT < IQUIPMENT LOCATION ----> <-- OP. ST. -> POWER SLPPORTIE SYS. REQ'O INTERC00 KEG 10N5 REG. W. TRAIN CLASS MARK NO. DESCRIPTION Ibg. No./Rev./ Zone 9911 ding Fir.Elv. Es. or Row /Cel. 53RT ETES Normal Oestred REQ 07 DWG. E./REV. & StPPORTIE COpF01ENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5238 1 0 1-CH-E-1A1 CH/ CHARGING Pt991A GEAR 801 11715-%07Eln2/D3 AUX 245' 9.5/J 5 -- N/A N/A E WA N/A COOLER 5236 1 0 1-CH-E-1A2A CN/ CHARGING PtMP 1A SEAL COOLER 1 11715-FM-07ElB2/D3 AUX 245' 9.5/J 5 - N/A N/A E N/A N/A 5237 1 0 1-CH-E-1A28 CN/CHAPGING Ptpf IA SEAL COOLER 2 Il715-%078G1n2/D3 AUX 245' 9 5/J $ -- N/A WA NO N/A N/A 5242 1 0 1-CH-E-181 CH/ CHARGING Fipf 18 GEAR BOX ll715-FM-078GI/12/D5 AUX 245' 9.5/J $ -- N/A N/A NO N/A N/A COOLER 5240 1 0 1-CH-E-182A CH/ CHARGING Pt4F 18 SEAL COOLER 1 11715-FM-078GI/12/D5 AUX 245' 9.5/J $ - N/A N/A NO N/A WA 5241 1 0 1-CH-E-1828 CH/ CHARGING Ptpf 18 SEAL COOLER 2 11715-FM-078G1/12/D5 AUX 245' 9.5/J $ - N/A N/A 10 N/A N/A 5246 1 0 1-CH-E-lC1 CN/ CHARGING Ptff IC GEAR 80X 11715-FM-078GI/12/D7 AUX 245' 9.5/J 5 - N/A N/A m WA WA COOLER 5244. 1 0 1-CH-E-IC2A CH/ CHARGING Pl#F IC SEAL COOLER 1 11715-%078GI/12/D7 AUX 245' 9.5/J 5 - N/A N/A NO N/A N/A 5245 1 0 1-CH-E-1C28 CH/ CHARGING Pl#F IC SEAL COOLER 2 11715-FM-078G1/12/D7 AUX 245' 9.5/J $ - N/A N/A E N/A N/A 1148 1 0 1-CH-H-6A CH/ BAST A STRIP HEATER 11715-FM-095A1/22A3 AUX 259' 7/J $R- ON ON YES 11715-CH-044/3 N/A 1149 1 0 1-CH 41-68 CN/ BAST A STRIP HEATER ll715-FM-095A1/22A3 AUX 262' 7/J $R - ON ON YES 11715-CH-045/2 WA 1150 2 0 1-CH-H-7A CH/8AST 8 STRIP HEATER 11715-FM-095Al/22N5 AUX 260' 11.2/J 5R - 04 ON YES IIT15-CH-041/6 WA 1151 2 0 1-CH-H-78 CH/ BAST 8 STRIP HEATER 11715-%095Al/22A5 AUX 260' 7/J 5R - ON ON YES Il715-CH-043/3 N/A 5523 1 0 1-EG-FF-H* EG/ FUEL OIL FILTER 11715-1.30-212C 58 270' EDG $ 36,29 N/A N/A NO N/A EDG-IN 5524 2 0 1-EG-FF-J' EG/ FUEL OIL FILTER 11715-1.30-212C 58 270' EDG $ 36,29 N/A N/A 10 WA EDG-lJ 4211A3 0 1-%FY-1479 ELECTRO-PNElfETIC CONTROLLER 58 294' D/4 5 421183 0 1-FW-FY-1489 ELECTRO-PNEtBETIC CONTROLLER 58 294' D/$ 5 4211C3 0 1-FV-FY-1499 ELECTRO-PKl# ETIC CONTROLLER 58 294' D/4 5 5476 1 0 1-HV-5AD-lH* HV/DG ROOM IX StPPLY Alt DMFER ll715-F8-024Ll/II/05 58 272* 14A 5 -- N/A N/A 10 WA N/A 5478 2 0 1-HV-SAD-1J* HV/DG ROOM IJ StPPLY AIR DMFER ll715-F8-024L1/II/D7 58 272' 16N 5 - N/A N/A 10 WA N/A 5248 1 0 2-CH-E-1A2A CH/CHARGIE Ptpf 2A SEAL COOLER 1 11715-FM-078G2/10/D3 AUX 245' 9.5/J 5 - N/A N/A 10 N/A N/A 5249 1 0 2-CH-E-1A28 CH/ CHARGING PLPF 2A SEAL COOLER 2 11715-FM-078G2/10/D3 AUX 245' 9.5/J $ - WA N/A NO N/A N/A 5252 1 0 2-CH-E-182A CH/ CHARGING Pt99 28 SEAL C00LLW I Il715-FM-078G2no/D5 AUX 245' 9.5/J $ - N/A N/A 10 N/A N/A
$253 1 0 2-CH-E-1828 CH/CHARGIE Pt#F 28 SEAL COOLER 2 11715-%078G2n0/D5 AUX 245' 9.5/J 5 - N/A WA 10 N/A N/A 5256 1 0 2-CH-E-lC2A CH/ CHARGING Ptff 2C SEAL COOLER 1 11715-FM-078G2/10/D7 AUX 245' 10/J $ - N/A N/A NO WA N/A
.-- _ _ .-- . _--. _ - _ - _ _ - _ _ _ - , _ _ - . - . . .~ -
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V ld Page No 3 WRTH Alma tmIT 1 Report Date/Tisa: 05-19-97 / 15:31.15 5AFE SHuTDOW EQUIPMENT LIST (SSEL) COF051TE SSEL (Sorted by Equipment Class and Mark NLisber) LIM EQUIP SYSTEN/ EQUIPMENT < EQUIPMENT EOCATION ----> <-- OP. 5T. --> POWER STPORTING SY$. REQ'O INTERCOWECTIONS REG.
- 80. TRAIN CLASS MARK 80. DESCRIPil0N Dwg NoJRev./ Zone Su tiding F tr.Elv . Ra. or Row / Col. 50RT 10Tli Normal Desired REQD? OWG. NO./ REY. & 5& PORTING COPPOENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (II) (12) (13) (14) (15) (16) (17) 6016 1 01 1-EP-K-41 IP/ EMERGENCY MCC IH1-4 Il7154E-00lII/14/D8 58 254' 9/C 5R 41 N/A N/A YES II715-FE-009EJ/ 1-EE-S$-01 13 6019 1 01 1-EP-MC-50 EP/ EMERGENCY MCC IHI-3A 11715-FE-00lTl/15/B8 SWH 3?S' --
5R 41 N/A N/A YES N/A 1-EP-MC-22 6026 2 01 1-EP-MC-51 EP/ EMERGENCY MCC IJ1-3A 11715-FE-00lT1/15/F3 SWH 326' -- SE 41 N/A N/A YES N/A 1-EPK-31 1252 1 02 1-EE-8KR-8YA CR*/ REACTOR TRIP BREAKER BYPASS A Il715-1.27-402A AUX 280' RCD $R - CLOSED OPEN YES N/A N/A 1253 2 02 1-EE-BKR-BYB CR*/ REACTOR TRIP BREAKER BYPASS B II715-1.27-402A AUX 280' RCD 5R -- CLOSED OPEN YES N/A N/A 1250 1 02 1-EE-8KR-RTA CR*/ REACTOR TRIP BREAKER A Il715-1.27-402A AUX 280' RCD 5R - CLOSED OPEN YE5 N/A N/A 1251 2 02 1-EE-8KR-RT8 CR*/ REACTOR TRIP BREAKER 8 11715-1.27-402A AUX 280' RCD SR -- CLOSED OFEN YE5 N/A N/A 6011 1 02 1-EE-55-01 EE/480V EMERGENCY BUS IN 11715-FE-001Al/21/82 58 254' 9/C 5R 41 N/A N/A YES N/A 1-8Y-B-01,-02;1-EE-ST-1 M 6013 2 02 1-EE-55-02 EE/480V EERGENCY BUS IJ ll715-FE-001A1/21/82 58 254' 8/C 5R 41 N/A N/A YES N/A 1-8Y-8-03.-04;1-EE-5T-1 J 6012 1 02 1-EE-SS-03 EE/480V EMERGENCY BUS 1H1 Il715-FE-001Al/21/82 AUX 280' RCD 5R - N/A N/A YE5 N/A 1-8Y-B-01 -02;1-EE-5T-0 3 6014 2 02 1-EE-55-04 EE/480V EERGEEY BUS IJ1 Il715-FE-001Al/21/82 AUX 280' RCD 5R -- N/A N/A YES N/A 1-8Y-B-03,-04;l-EE-ST-0 2 6005 1 03 1-EE-5W-01 EE/4KV EMERGENCY BUS IN (ORAEE) ll715-TE-008BC/13 58 254' 7/D 5R 41 WA N/A YES Il715-FE-01D/18 EDG 1R;1-8Y-8-01,-02 6006 2 03 1-EE-5W-02 EE/4KV [NERGENCY BUS IJ (PURPLE) 11715-FE-0088P/12 SB 254' 8/D 5R 41 N/A N/A YES Il715-FE-01D/18 EOG IJ;1-8Y-B-01,-02 6007 1 04 1-EE-5T-IN EE/4160/480 SERVICE TRANSFORMER IN 11715-FE-001A1/21/83 58 254' 9/D $R -- N/A N/A YE5 N/A 1-EE-5W-Ol;EOG IN 60C3 1 04 1-EE-ST-lH1 EE/4160/480 SERVICE TRANSFORER 11715-FE-001Al/21/82 AUX 280' RCD $R - N/A WA YES N/A 1-i't-SW-01;[DG IN IH1 6009 2 04 1-EE-ST-1J EE/4160/480 SERVICE TRANSFORMER IJ !!715-FE-001Al/21/82 58 254' 8/D $R - N/A N/A YES N/A 1-EE-SW-02;EDG IJ 6010 2 04 1-EE-$T-1J1 EE/4160/480 SERVICE TRANSFORER ll715-FE-001A1/21/82 AUX 280' RCD 5R -- N/A N/A YES N/A 1-EE-5W-02;EDG IJ IJ1 5551 1 04 1-EE-TRAN-llN / HEAT TRACE TRAN5FORER ll715-FE-0010/21 AUX 269' II/M $R - ON ON YE5 N/A N/A 5552 2 04 1-EE-TRAN-IIR / HEAT TRACE TRAN5FORER 11715-FE-00lR/21 AUI 269' -
$R - ON ON YES N/A N/A 5553 1 04 1-EE-TRAN-12N / HEAT TRACE TRANSFORMER 11715-FE-00lN/16 AUX 269' -
$R - ON ON YES N/A N/A 5554 2 04 1-EE-TRAN-12R / HEAT TRACE TRANSFORMER 11715- 4 -0018/16 AUX 269' -
SR -- ON ON YES N/A N/A 5555 1 04 1-EE-TRAN-13N / HEAT WACE TRAN5FORER ll715-FE-0018/16 AUX 284' 11/L $R - ON ON YES N/A N/A 5556 2 04 1-EE-TRAN-13R / HEAT TRACE TRANSFORMER 11715-FE-001R/21 AUX 284' 8.7/G $R - ON ON YES N/A N/A
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(! ,l Q_.,I Fage No 4 NORTH ANNA LMIT I Report Date/T 6me- 05-19-97 /15-31:15 SAFE SHUTDOWN EQUIPMENT LIST (55EL) CIN051TE SSEL (Sorted by Equipment Class and Mart Itimber) ll'I EQUIP SYSTEM /EQ'JIPMENT <------- - EQUIPENT LOCATION -----> o- OP. ST. --> POWER StFPORTIE SYS. REQ'O INTERCOMECTIONS REG. 10 TRAIN CLAS5 MARK NO. DESCRIPil0N Dwg. No /Rev./ Zone Building Fir.Elv. Rs. or Rou/ Col. SORI NOTES Normal Desired REQ 0? DC. N3./REV. 8 StFPORTilG COf0NENi1 ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5557 1 04 1-EE-TRAN-14N / MEAT TRACE TRANSFORMER 11715-FE-001Q/21 AUX 269' 9/LM SR -- ON CN YES N/A N/A 5558 2 04 1-EE-TRAN-14R / HEAT TRACE TRANSFORER ll715-FE-00lR/21 AUX 269' 9. 7/LM SR -- ON ON VE5 N/A WA 5559 1 04 1-EE-TRAN-41N / HEAT TRACE TRAN5FORMER ll715-FE-0010/21 AFPH 271' -- 5R -- ON ON YES N/A N/A 5560 2 04 1-EE-TRAN-41R / HEAT TRACE TRANSFORMER 11715-FE-001R/21 AFPH 271' - 5R -- ON ON YES N/A WA 6028 1 04 1-EP-TRAM-79A EP/4SO/120 VOLT. REG TRAN5FORER al715-FE-001AEl/13 58 252' 9/D 5R -- N/A N/A YE5 N/A 1-EPK-10 (79A) 6029 1 04 1-EP-TRAN-796 EP/480/120 VOLT. REG. TRANSFORMER ll715-FE-001AEl/13 58 252' 9/D 5R -- N/A N/A YES N/A 1-EPK-10 (798 ) 6030 2 04 1-EP-TRMts-80 EP/480/240 VOLT. REG. TRAN5FORER ll715-FE-001AEl/13 58 252' 9/D 5R - N/A N/A YES ll715-FE-009G5/ l-EPK-II (80) 17 6031 1 04 TRANS-Il8* EP/480/120 SEMI-VITAL TRAN5FORER 11715-FE-001AEl/13 58 254' EMER SWCR 5R -- N/A N/A YE5 N/A 1-EPK-41 (118) 6033 2 04 TRANS-Il9* EP/480/120 SEMI-VITAL TRAEFORER 11715-FE-001AE1/13 58 254' EMER SER SR -- N/A WA YES N/A 1-EP-MC-22 (119) 6032 1 04 TRANS-70* EP/480/120 SEMI-VITAL TRAEFORMER ll715-FE-001AEl/13 58 277' 8/D 5R - N/A N 'A YES N/A 1-EPM-10 (70) 6034 2 04 TRANS-71* EP/480/120 SEMI-VITAL TRANSFORMER ll715-FE-001AEI/13 58 277' 8/D 5R -- N/A N/A YES Il715-FE-00%5/ l-EPM-II (71) 17 50C1 1 05 1-CC-P-1A CC/00Pf0NENT COOLING WATER Ptw 11715-FN-079A1/17/E7 AUX 245' 8.7/GH 5R 1 ON ON YES N/A N/A 5005 1 05 1-CC-P-18 CC/COPPONENT COOLING WATER PM 11715-FM-079Al/17/07 AUX 245' 8.7/GH 5t 1 ON ON YES N/A N/A 1059 1 05 14H-P-IA CH/CENTRlFUCAL CHARGIE Ptw A; ll715-FM-09582/24/04 AUX 245' 9.5/J !R -- ON ON YES N/A N/A (CCP A) 1060 2 05 1-CH-P-13 CH/ CENTRIFUGAL CHARGING Ptw 8; 11715-FM49582/24/C6 AUX 245' 9.5/J 5R -- ON ON YES h/A N/A (CCP 8) 1061 3 05 1-CH-P-lC CH/ CENTRIFUGAL CHARGIE PLN C; ll715-FM-09582/24/C8 AUX 245' 9.5/J 5R -- ON ON ES N/A N/A (CCP C) 1161 1 05 1-CH-P-2A CH/ BORIC ACID TRANSFER PiNP (BATP) 11715-FM-095Al/22/B4 AUX 261' 9.5/HJ 5R -- ON ON YES N/A N/A 1162 2 05 1-CH-P-28 CH/ BORIC ACID TRANSFER PW (BATP) Il715-FM-095Al/22/85 AUX 261' 9.5/HJ 5R - 0FF ON YES N/A N/A 5482 1 05 1-EG-P-lHA EG/EDG IN LEAD F0 TRANSFER PW 11715-F8-035A2/21/87 FOPN 270' -- 5R -- 0FF RMIC YES N/A N/A 5483 2 05 1-EG-P-lHB EG/EDG lil STAf06Y F0 TRANSFER FlN 11715-F8-035A2/21/86 FOPH 270' -- 5R -- 0FF RMING YES N/A N/A 5484 1 05 1-EG-P-13A EG/EDG IJ LEAD F0 TRANSFER PM 1171548-035A2/21/D7 FOPH 270' -- 5R -- 0FF RMIIC YES N/A N/A 5485 2 05 1-EG-P-lJ8 EG/EDG IJ STAPCBY F0 TRANSFER Ptw 11715-TB-035A2/21/D6 FOPH 270' -- 5R - 0FF RMIE YES N/A N/A
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(JN (~' w O a < i Pa9e No. 5 ERTH A0004 LBi!T I Report Date/ Time: 05-19-97 / 15:31:15 5AFE SHUT 00WN EQUIPMENT LIST ($$EL) ' CopF051TE $5EL (Sorted by Equipernt Class and Mart haber) , I LI:I EQUIP SYsitM/ EQUIPMENT < EQUIPMENT LOCATION ----> <- OP. $T. -> POWER SUPPORT!lt SYS REQ'D INTERColelECTIONS REG. I E TRAIN CLASS MARK E DESCRIPil0N [haj. No./Rev./ Zone Building fir.Elv. Rs. or Row / Col. 50RT ETE$ Normal Desired REQD? DWG. E./REV. & SIFf0RTIE C(DF0lHTS 155tE ' (1) -(2) .(3) (4) (5) (6) (7) (8) (9) -(10) (11) (12) (13) (14) (15) (16) (17) , 5515 1 - 05 1-EG-P-609H - EG/DC FUEL DIL Ptpr 11715-1.30-212C SB 270' [DG $R 36,29 0FF Rt90 LING YES N/A EDG-1N 5516 2 05 1-EG-P-609J EG/DC FUEL Olt Pt#F 11715-1.30-212C 58 270' EDG $R 36,29 0FF ElBOIIIC YES ' N/A EDG-lJ I 5511 1 05 1-EG-P-610H EG/EEINE DRIVEN F0 PLDF 11715-1.30-212C 58 270' EDG 5 36,29 OrF R190llE NO N/A EDG-lH I 5512 2 05 1-EG-P-610J EG/ENGlE DRIVEN F0 PtDF 11715-1.30-212C $8 270' EDG 5 36,29 0FF Rt90 TIE E N/A EDG-lJ f i 41FJ l 05 1-FW-P-2 FW/TIFBINE-DRIVEN A"XILIARY 11715-FM-074A3/29/88 AFPH 274' -- S - 0FF R12011NG YES N/A N/A I TEEDWATER PLSF (TDAFWP) 7 4133 2 05 1-FW-P-3A FWMOTOR-DRIVEN ALIX;LIARY ll715-FM-074A3/29/86 AFPH 274' -- 5R - 0FF RipellE YES N/A N/A FEEDWATER Pt99 (EAFWP) .I t 4127 2 05 - 1-FW-P-38 FW/ MOTOR-ORIVEN AUXILLARY ll715-%074A3/29/85 AFPH 275' - 5R -- 0FF RLSellE YES N/A WA . FEEDWATER Pt9F (EAFWP) 5486 1 05 2-EG-P-2HA EG/EDG 2H LEAD F0 TRANSFR Ptpr ~ 11715-FB-035A2/21/C7 FDPN 270' -- 5R - 0FF RlBOIIE YE5 N/A N/A ! 1 5487 2 05 2-[G-P-2HB EG/EDG 2H stale)BY F0 TRANSFER PtpF 11715-F8-035A2/21/06 FDPH 270' --
$R- - 0FF RtlettlE YES WA N/A
$488 1 05 2-EG-P-2JA EG/EDG 2J LEAD FO TRANSFER PipF 11715-F8-035A2/21/F7 F0PH 270' ~ $R - 0FF R! Belle YE5 N/A N/A t 5489 2 05 2.EG-P-2J8 EG/EDG 2J STAIRIBY FO TRAN5FER Pt9911715-FB-035A2/21/F6 FOPH 270' - 5R - 0FF Rt90 LIE YES N/A N/A ! 5517 1 05 2-EG-P-709H EC/DC FUEL OIL PtpF 11715-1.30-712C 58 270' [DG SE 36,29 0FF RtBet!NG YES N/A EDG-210 l t 5513 2 05 2-EG-P-709J EG/DC FUEL OIL Ptfr 11715-1.30-212C SB 270' EDG SR 36,29 0FF RulfilE YES N. 4 EM-2J . 5513 1 05 EG-P-710H EG/EEIE DRIVEN F0 PM 11715-1.30-212C 58 270' EDG $ 36,29 0FF RifflIE 10 N/A EDG-2H 5514 2 05 2-EG-P-710J EG/EEIE DRIVEN F0 PipF 11715-1.30-212C 58 270' EDG 5 36,29 0FF Rt90t!E 10 N/A EDG-2J 544 % 1 06 1-HV-P-20A HV/ CHILLED WATER Pt#F 11715-F8-040A1/13 58 254' CHILLER RM $R - RUlftIE Rt90 LING YES N/A N/A 5449I 2 06 1-HV-P-208 HV/ CHILLED WATER Pt99 11715-F8-040A1/13 58 254' CHILLER RM 5/D-S R - Rt90 LIE RtNSIIE YES N/A N/A 5449Z2 2 06 1-HV-P-200 HV/CHIllLD kATER PtDF 11715-F8-040AI/13/D5 58 254' CHILLER RN 5/D 5 R - 0FF R100llNG YES N/A N/A 5428 1 06 1-HV-P-22A HV/CR & RR WATER SYSTEM BOOSTER ll715-F8-040Dl/15/E6 58 254' CHILLER RM $R - CN ON YES N/A N/A PtDF 5429 1 06 1-HV-P-228 HV/CR & RR WATER SYSTEM BOOSTER 11715-F8-04001/15/86 58 254' CHILLER RM $R - ON ON YES N/A N/A Pt9F 5430 2 06 1-HV-P-22C HV/CR & RR WATER SYSTEM 800 STER 11715-F8-000D1/15/06 58 254' CHILLER RM 5R- 0FF ON YES N/A N/A Ptfr 4205 1 06 1-RM-P-1 A RH/RHR Pter A 11715-%094A1/14/D7 CONiMT 231' RHR Flat 5R - 0FF RtsellE VE5 11715-FM-0010 . N/A 4249 2 06 1-RM-P-18 RH/RNR PtBF 8 11715-FM-094A1/14/D4 CONTMT 231' RNR Flat 5R - 0FF RtatlIE YES 11715- % 0010 N/A 5159 1 06 1-5W-P-1A $W/5ERVICE WATER Pt99 A 11715-FM-078A3/28/D7 Strll 328' SWPH $R - Rt00f!E RtB0f!IC YES N/A N/A i f
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V V V Page No. 6 NORTH ANNA UNIT 1 Report Date/ Time: 05-19-97 / 15 11:15 5AFE SMUTDOWN EQUIPMENT LI51 (55EL) 00Pf'05I1E $5EL (Sorted by Equipment Clast and Mark Number) L!i! EQUIP SYSTEM / EQUIPMENT <------- EQUIPMENT LOCATION ---> <-- OP. ST. -> POWER SWPORTING SYS. REQ'O INTERComECil0N5 REG. NO TRAIN CLASS MARK m DESCRIPil0N Ihtg. No /Rev./ Zone Building F tr.Elv. Rm. or RowAol. $0RT POTES Normal Desired REQD? DWG. NO./REV. 8 SWPORTIE CD4'ONENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (l* (12) (13) (14) (15) (16) (17) 5160 2 06 1-5W-P-18 SW/5ERVICE WATER PtH' 8 Il715-FM-078A3/28/D5 SWPH 328' SWPH $R - 0FF RUWIE YES N/A N/A 5161 1 06 2-5W-P-1A $W/ SERVICE WATER PtH' A 11715-FM 078A3/28/D4 $WPH 328' $WPH 5R - RtNilNG RtMING YES N/A N/A 5162 2 06 2-5W-P-18 SW/5ERVICE WATER PtH' 8 Il715-FM-078A3/28/D3 SWH 328' SWPH 5R - 0FF RumIE YES N/A N/A 5092 1 07 1-CC TV-103A CC/RHR HX OUILET CONTMT ISOL ll715-FM 07981/21/A7 AUX 252' 7/L - A,27 OPEN OPEN NO Il715-CC-081/4 14G-50V-103A 5100 1 07 1-CC-TV-1038 CC/RHR HX OUTLET CONTMT 150L 11715-FM47981/21/Il7 AUX 252' 7/L -- A,27 OPEN OPEN ND 11715-C0-082/4 1-CC-50V-1038 1169 2 07 1-CH-FCV-Ill34 CH/8AST TO VCT CONTROL 11715-FM-09581/21/C3 AUX 278' 8.5/J -- A,3 OPEN OPEN YES Il715-CH-017/11 1-CH-50V-Ill3Al;l-CH-50 V-Ill3A2 1075 1 07 1-CH-FCV-1122 CH/ CHARGING FLOW TO REGEN HX ll715-FM 095C1/14/C4 AUX 245' 12/H -- -- OPEN OPEN NO Il715-CH-001/7 1-CH-E/P-ll22;l-CH-FT-1 122 1200 2 07 1-CH-HCV-Il37 CH/ EXCESS LETDOW HX 150L 11715-FM-095C1/14/07 CONTMT 233' 6 -- 28 CLOSED CLOSED NO Il715-CH-077/3 1-CH-E/P-HCV-Il37 Il715-FK-001A 1091 1 07 1-CH-HCV-Il86 CH/CCP TO RCP SEAL IPUECTION II715-FM-095C2/13/F4 AUX 245' 8.5/L - - OPEN OPEN NO Il715-CH-068/1 R/A 1197 2 07 1-CH-NCV-1201 CHAXCESS LETDOWN HX 150L ll715-FM 095C1/14/06 CONTMT 236' 6 -- 28 CLOSED CLOSED NO Il715-CH-079/3 1-CH-50V-1201 Il715-FK-001D 1105 1, 2 07 1-CH-HCV-1303A CH/ SEAL LEAKDFF 150L RCP-1 11715-FM-095C2/13A8 CONTMT 219' 18.5 - 21 OPEN OPEN fe ll715-CH-065/3; N/A Il715-FK-001E 1106 1, 2 07 1-CH-NCV-13038 CH/ SEAL LEAKOFF 150L RCP-2 11715-FM-095C2/13/E6 CONTMT 219' 11.5 - 21 OPEN OPEN NO 11715-0H-066/3; N/A 11715-FK-001D 1107 1, 2 07 1-CH-HCV-1303C CN/5EAL LEAK 0FF 150L RCP-3 11715-FM-095C2/13/E5 CONTMT 219' 7 - 21 0 FEN OPEN NO ll7154H-067/3; N/A IIT15-FK-001D 1117 2 07 1-CH-HCV-1307 CH/ SEAL BYPASS OUTLET ISOL ll715-FM-095C2/13A4 CONTMT 255' A 8.5 -- - CLOSED CL35ED NO Il715-CH-074/4; l-CH-50V-1307 II715-FK-001D 1084 1 07 1-CH-HCV-1310 CH/ CHARGING TO LOOP 2 !50L ll715-FM-095C1/14/F6 CONTMT 222' 11.5 -- - OPEN OPEN N0 ll715-FK-001D l-CH-50Y-1310 2006 1, 2 07 1-CH-PCV-1311 CH/ AUX SPRAY 150L ll715-FM-095C1/14A6 CONTMT 220' 11 - 28 CLOSED CLOSED NO 11715-CH-003/4; 1-CH-50V-1311 11715-FK-0010 1206 2 07 1-CH-HCV-1389 CHAICESS LETDOWN FLOW DIRECTING ll715-FM-095C1/14/06 CONTMT 234' 6 - - VCT VCT NO ll715-CH-075/3; N/A Il715-FK-01D/ll 4210A 07 1-FW-FCV-1478 FLOW CONTROL TO 5/G 1A $8 294' 4/D $R OPEN CLOSED 4211A 07 1-FW-FCV-1479 A MFW REG VALVE 8YPASS FLOW $8 294' 3/D 5R 45 CLOSED CLOSED CONTROL VALVE 42108 07 1-FW-FCV-1488 FLOW CONTROL TO 5/G 18 58 294' 4/D 5t OPEN CLOSED 42118 07 1-FW-FCV-1489 8 MFV REG VALVE 8YPA55 FLOW 58 294' 3/D $R 45 CLOSED CLOSED CONTROL VALVE
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v . Page pb. 7 ERTH AfstA UNIT 1 Report Date/ Time: 05-19-97 / 15:31:15 SAFE 5HUTDOWN EQUIPMENT LIST (SSEL) : COW 0$lTE S5EL (Sorted by Equipment Class and Mark Number) i LIM EQUIP SYSTEM / EQUIPMENT < EQUIPMENT LOCATION -----> <- OP. ST. --> POWER SUPPORTIE SYS. REQ'D INTERCDimECT10N5 REG.
- 13. TRAIN CLASS MARK E DESCR!PTION Dwg. No /RevdZone Building F tr.Elv. Rs. or Rov /Cel. 50RT NOT[5 Normal Desired REQ 07 OWG. NO./ REY. 8 SLPPGRTING COWOMENTS 155UE '
(1) (2) (3) (4) (5) (6) -(7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 42100 07 1-FW-FCV-1498 FLOW CONTROL TO 5/G IC 58 294' 4/D 5R OPEN CLOSED , 4211C 07 1-FW-TCV-1499 C MFW REG VALVE BVPA55 FLOW 58 294' 3/D 5R 45 CLOSED CLOSED CONTROL VALVE 4169 1 07 1-FW-HCV-100A FW/AFWF HEADER TO SG A Il715-FM-074Al/32/A5 AFPM 275' -- 5 -- CLOSED OPEN ND ll715-FW-055/4 N/A 4166 2 07 1-FW-HCV-10(B FW/AFWP HEADER TO SG B ll715-FM-074A1/32/A6 AFPH 275' -- 5 -- CLOSED OPEN 10 11715-FW-056/4 N/A 4161 2 07 1-FW-HCV-100C FW/AFWP HEADER TO SC C ll715-FM-074Al/32/A7 AFPH 275' -- - - OPEN OPEN 10 Ilf15-FW-057/6 N/A r t.145 2 07 1-FW-PCV-159A FW/AFWP TO SG B CONTROL VALVE Il715-FM-074A3/29/F8 AFPH #71' - 5 - OPEN 0 PEN NO N/A N/A 4150 2 07 1-FW-PCV-1598 FW/AFWP TO SC C CONTROL VALVE 11715-FM-074A3/29/E8 AFPH 271' - 5 -- OPEN CPEN NO N/A N/A 2038 2 07 1-GN-PCV-125A-1 GN/PZR PORY N2 SUPPLY PRESSURE 11715-FM-105Al/20A6 CONTMT 308' 9.1 5 - OPEN OPEN 10 N/A N/A REDUCING VALVE 2039 2 07 1-GN-PCV-125A-2 GN/PZR PORY N2 StFPLY PRE 55tRE Il715-FM-105Al/20/E6 CONTMT 308' 9.1 5 -- OPEN OPEN ND WA N/A , REDLR'IE VALVE 2035 2 07 1-GN-PCV-125A-3 GN'PZR PORV N2 SUPPLY PRE 55tRE 11715-FM-105Al/20/E6 CONTMT 308' 9 5 - OPEN OPEN NO N/A N/A REDUCING VALVE 2036 1 07 1-GN-PCV-1258-1 GN/PZR PORY N2 StFPtV PRESSIRE Il715-FM-105Al/20/E4 CONTMT 308' 9 5 - OPEN OPEN 10 N/A N/A I r REDUCING VALVE 2037 1 07 1-GN-PCV-1258-2 GN/PZR PORY N2 StFPLY PRE 55LRE Il715-FM-105A1/20/E4 CONTNT 308' 9 5 -- OPEN OPEN NO WA N/A I REDUCIE VALVE 2034 1 07 1-GN4'CV-1258-3 GN/P2R PORV N2 SUPPLY PRE 55tRE Il715-FM-105Al/20/E4 CONTNT 308' 9 5 - OPEN OPEN NO N/A N/A ' REDUCIE VALVE 1240 1, 2 07 1-HRS-TV-1623 HRS /RC COLD LEG 5AWLE COOLER 150L 11715-FM-089D1/16/D4 AUX 259' 7.6/K 5 24 CLOSED GPEN ND ll715-HRS-014/31-HRS-50V-1623 , 1226 1, ? 07 1-NRS-TV-1625 NRS/ HOT LEG 5 APPLE COOLER IEET 11715-FM-08901/16/E6 AUX 259' 7.6/K 5 24 Closed OPEN 10 117154Rt$-016/31-NRS-50V-1625 I 150L 4268 1, 2 07 1-HRS-TV-1627 HRS /5APFLING SYSTEM 150L ll715-FM-08901/16/F4 AUX 259' 7.6/K $ 24 CLOSED GPEN 10 N/A 1-ittS-50V-1627 [ 4266 1. 2 07 1-HRS-TV-1628 55/SAPPLING SYSTEM 150L 11715-FM-108Al/03/E5 AUX 259' -- - -- CLOSED CLOSED NO N/A . N/A 5441 1 07 1-HV-PCV-1235A2 HV/CR & RR WATER SYSTEM FLOW 11715-FB-040D1/15/E3 58 - AC RM - - OPEN CPEN 10 11715-HV-058/2 N/A CONTROL ; 5442 1 07 1-HV-PCV-123582 HV/CR & RR WATER SYSTEM FLOW ll715-FB-04001/15/83 58 - AC RM - - OPEN OPEN 10 llF15-HV-059/2 N/A CONTROL 5443 2 07 1-HV-PCV-123502 HV/CR & RR WATER SYSTEM FLOW II715-FB-040Dl/15/D3 58 - At RM - - OPEN OPEN NO 11715-HV-060/2 N/A
- CONTROL 4014 1 07 1-MS-PCV-101A MS/5G A ATMDSPHERIC STEAM Otfr 11715-FM-07081/19/E5 M5VN 306' 4.5/GA 5R 25 CLOSED OPEN NO Il7134ts-012/7 INST AIR VALVE
[
% r Pag. No. 8 ' NORTH AINL UNIT I Report DateMine: 05-19-97 / 15:31:15 . SATE SHUTD0lm EQUI INT LIST (55EL) 00pF0511t SSEL '
(5orted by Equipment Class and Mart Number) LINE EQUIP SYSTDt/ EQUIPMENT < EQUIPMENT LOCATION ---> <- OP. ST. -> POWER SLFPORTING SYS. REQ'D INTERC018ECTIONS REG. . C. TRAIN CLASS M4RK W. DESCRIPTION Dwg. No./Rev./ lone Building fir.E lv. Rs. or Row / Col. 50RT NOTES Normal Desired REQD7 DWG. IRL/REV. & SLFPORi!NG CGPOIENTS ISSUE A (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (16) (15) (16) (17) ! 4040 2 07 1-MS-PCV-10lO MS/5G B ATW5PHERIC STEAM DtDF ll715-FM-07082/19/E6 M5W 306' 4/GD 5R 25 CLOSED OPEN ft) 11715-MS-CIF9 INST AIR VALVE 4066 3 07 14ts-PCV-101C MS/50 C ATptj5PHERIC STEAM CLIP ll715-FM-07083/23/E5 M5W 308' 4.5/Gb $R 25 CLOSED OPEN SR) 11715-MS-014/8 INST AIR VALVE l 4017 1, 2 07 1-MS-TV-101A MS/5G A MSIV 11715-FM-07081/19/C4 MSW 285' 5.5/GB 5 -- OPEN CLOSED VES Il7M-MS-110/8 1-MS-50V-101Al.2,3,6,7 4043 1, 2 07 1-M5-TV-1018 MS/5G B M51V 11715-FM-07082/19/C4 MSW 285' 4.5/G8 ? -- OPEN CLOSED VF5 117154ts-111/9 l-MS-50V-10181,2,3,6,7 4069 1, 2 07 1-MS-TV-101C MS/5G C M51v 11715-FM-07083/23/C4 M5W 285' 5/G8 5 -- OPEN CLOSED YES 11715-MS-Il2/9 l-M5-50V-101C1,2,3,4,5, , 6,7 - t 4083 1 07 1-MS-TV-Illa MS/TDArW STEAM ADMISSION ll715-FM-070A3/26/E5 MSW 274' 5.5 5 - CLOSED OPEN NO llT15-MS-115/8 N/A 4385 2 07 1-MS-TV-1118 MS/TDATW STEAM ADMISSION 11715-FM-07043/26/E4 M5W 274' 5.5 5 -- CLOSED OPEN ND 117154tS-Il6/10 N/A i 4099. 1, 2 07 14t5-TV-Il5 MS/TDAFW TRIP VALVE ~ 11715-FM-070A3/26/04 M5W 274' -- 5 - OPEN OPEN SR) N/A N/A 51194 1 07 1-It5-LCV-101 N5/IEUTRON SHIELD SURGE TAleC ll715-FM-07985/21/D3 CONTMT 262' 14 - -- CLOSED CLOSED NO N/A N/A OUTLET 150L 1191 2 03 1-RC-HCV-1557A RC/RC X5 (ETDOW 150L 11715-FM-093Al/19/E7 CONTMT 242' 1A - 28 CLOSED CLOSED ND 11715-RC-051/4 1-RC-50V-1557A VIM 527749-27750 > 11715-FK-lE 1193 2 07 1-RC-HCV-15578 RC/RC 15 LETDOWN mL 11715-FM-093A2/19/F7 CONTMT 243' 13 8 -- 28 CLOSED CLOSED NO Il715-RC-052/4 1-RC-50V-15578 VIMS 28208-28211 Il715-FK-ID 1195 2 07 1-RC-HCV-1557C RC/RC X5 LETD(WN 150L 11715-FM-093A3/22/F3 CONiMT 243' 7.5 C - 28 CLOSED CLOSED ND 11715-RC-053/4 1-RC-50V-1557C VIM 528616-28618 11715-FK-001D 2020 2 07 1-RC-PCV-1455C RC/PZR FORY 11715 FM-09381/22/03 CONTMT 308' 9.5 5 -- CLOSED OP/tt NO 11715-RC-111/12 1-GN-50V-1455C-1/2/3
;11715-FK-0010 2024 2 07 1-RC-PCV-1456 RC/PZR PORV ll715-FM-09381/22/E3 CONTMT 308' 9.5 5 - CLOSED OP/CL ND 11715-RC-109/11 1-GN-50V-1456-1/2/3
;11715-FK-0010 4259 1, 2 07 1-RX-FCV-1605 RH/RHR HX SYPA55 ll715-FM-09442/15/C7 CONTMT 234' 5 5 - CLD5ED CLOSED No ll715-RH-004/6 N/A L 11715-FK-001E 4257 1, 2 07 1-RH-HCV-1758 RH/RHR HX OUTLET 11715-FM-094A2/15/C5 CONTMT 228' 5 5R - OPEN OP/CL YES 11715-RN-005/4 N/A VIMS 29912 Il715-FK-001A 2046 1, 2 07 1-51-HCV-18508 SI/ACCtM TEST 150L ll715-FM-09681/17/A6 CONTMT 221' 1.5 - 21,19 CLOSED CLOSED it) 11715-51-022/3; l-51-50V-18508 .
Il715-FK-001E 4273 1, 2 07 1-51-HCV-18500 5I/ACCLM TEST 150L ll715-FM-09682/16/85 CONTMT 216' 13 - 22 Closed CLOSED NO 11715-51-024/2; 1-51-50V-18500 11715-FK-001D . I r
..__r__u -.z- _ _ _ u__.m___.___ ___.am._ _ _ _ _ _ . - . _ - _ 1_-_ _ - - . - m_ - - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ , _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -
I a Page No. 9 NORTH AfstA tMli i Report Date/ Time: 05-19-97 / 15:31:15 5AFE SHUTDOWN IQUIPENT LI5T (55EL) COPPOSITE $5EL (Sorted try Equipment Class ami Mark Number) LI:1 EQUIP SYSTEM / EQUIPMENT < EQUIPMENT LOCATION -> <-- OP. ST. --> POWER SIFFORTIE SYS. REQ'D INTERC010ECTIONS REG. K3 TRAIN CLASS MARK NO. DESCRIPil0N Dwg. No./Rev./ Zone Building . Fir.Elv. Re. or Row / Col. SORT NOTES Normal Desired REQ 07 OWG. NO]REV. & StPPORTIE CIDFONENTS 155tf (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (II) (12) (13) (14) (15) (16) (17) 4276 1, 2 07 1-51-HCV-1850F SI/ACCIM TEST 150L 11715-FWO9683/11/85 CONTMT 221' 7.5 - 22 CLOSED CLOSED NO 11715-51-026/3; l-51-50V-1850F ll715-FK-001D 5285 1 07 1-5W-TCV-102A SW/CCP LUBE 0!L COOLER CONTROL llT15-FM-078G1/12/D4 AUX 244' 8/K - -- OPEN OPEN ND 11715-5W-070/1 N/A 5286 1 07 1-5W-TCV-1028 SW/CCP LUBE Clt COOLER CONTROL ll715-FM478GI/12/06 AUX 244' 8.5/K - - OPEN OPEN - N0 llT15-5W-071/1 UA 5287 1 07 1-5W-TCV.102C SW/CCP LUBE CIL COOLER CONTROL ll715-FN-078GI/12/DB AUX 244' 9/K - - -- OPEN OPEN No ll715-5W-072/1 N/A 5205 2 07 1-5W-TV-101A SW/ UNIT 1 RECIRC AIR COOLING COIL 11715-FM-078A4/43/D4 58 265' 5.5/GA -- -- CLOSED CLOSED NO ll715-5W-037/7 N/A ISOL $208 2 07 1-5W-TV-1018 SW/ UNIT I RECIRC AIR COOLING Colt Il715-FWO7844/43/D4 58 265' 5.5/CA - -- Closed CLOSED NO 11715-5W-038/7 N/A 150L 5303 1 07 2-5W-TCV-202A SW/CCP LtEE Olt COOLER CONTROL II715-FM-078G2/10/D4 AUX 244' 9.2/K - - CPEN OPEN NO 12050-5W-034/2 N/A 5310 1 07 2-5W-TCV-2028 SW/CCP LUBE Olt COOLER CONTROL 11715-FN-078G2/10/D6 AUX 244' 9.5/K -- - OPEN OPEN W 12050-5W-035/2 N/A 5311 1 07 2-5W-TCV-202C SW/CCP LtEE OIL COOLER CONTROL 11715-FM-078G2/10/D8 AUX 244' 10/K -- - OPEN OPEN W 12050-5W-036/2 N/A 5091 1 08A 1-CC-MOV-1004 CC/RHR HX OUTLET CONTROL VALVE Il715-FM-07981/21/83 CONTMT 243' 7 5t 17 CLOSED OPEN YES WA N/A 5099 1 08A 1-CC-MOV-1008 CC/RHR HX OUTLET CONTROL VALVE Il715-FM-07981/21/A3 CONTNT 243' 7 5R 17 CLOSED GPEN VES N/A N/A 3045 2 OBA 1-CH-MOV-Ill58 CH/RW5T TO CCP INLET ISOL ll715-FWO9582/24/88 AUX 244' 7.6/J 5R - CLOSED OPEN VE5 N/A N/A 1053 1 08A 1-CH-MOV-1115C CH/VCT DUTLET TO CHARGIE PipFS ll715-FWO9581/21/C6 AUX 278' 9/J R - OPEN OPEN W N/A 1-CH-LT-1112 3044 1 ORA 1-CH-MOV-1115D CH/RWST TO CCP INLET ISOL 11715-F509582/24/88 AUX 244' 7.6/J $R - CLOSED OPEN VES N/A N/A 1054 1 08A 1-CH-MOV-Ill5E CN/VCT GUTLET TO CHARGIE Pt)FS IlF15-FM-09581/21/06 AUX 278* 9/J R - OPEN OPEN IR) N/A 1-CH-LT-Ill2 1055 1 08A 1-CH-MV-1267A CH/CHARGIE Pt#9 A LEET 150L 11715-FM-09582/24/C3 AUX 253' 8.2/J R - OPEN OPEN W N/A N/A 1056 2 08A 1-CH-MOV-1269A CH/CHARGIE Pt99 8 INLET 150L ll715-FWO9582/24/C5 AUX 253' 8.5/J R - OPEN OPEN E N/A N/A 1057 3 08A 1-CH-MOV-1270A CH/CHARGIE PLDF C INLET 150L ll715-FOO9582/24/C7 AUX 253' 8.6/J R - OPEN OPEN NO N/A N/A 1062 1 08A 1-CH-Mff-1275A CH/CCP A TO SEAL WATER XX HEADER ll715-FWO9582/24/D3 AUX 257' 8.2/J R - OPEN OPEN NO N/A N/A . 1063 2 DBA 1-CH-MOV-12758 CH/CCP 8 TO SEAL WATER HX HEADER ll715-FM-09582/24/D5 AUX 257' 8.6/J R - OPEN OPEN NO N/A N/A 1064 3 08A 1-CH-MOV-1275C CH/CCP C TO SEAL WATER HX HEADER 11715-FOO9582/24/D7 AUX 257' 8.6/J R -- OPEN OPEN NO N/A N/A 1065 1 08A 1-CH-MOV-1286A CH/ECP A TO Bli & REGEN HX ll715-FM-09582/24/E4 AUX 257' 8.2/J R -- OPEN OPEN NO N/A N/A 1066 2 CBA 1-CN-MV-12868 CN/[CP 8 TO BIT & REGEN HI 11715-FM-09582/24'E6 AUX 257' 8.6/J R - WEN OPEN E N/A N/A 1057 3 08A 1-CH-EV-1286C CH/CCP C TO BIT & REGEN HX 11715-FM-09582/24/E8 AUX 257' 8.6/J R -- OPEN OPEN W N/A N/A 1068 1 ORA 1-CH-MOV-1287A CH/CCP A TO LOOP FILL 11715-FWO9582/24/E4 AUX 257' 8.2/J R - OPEN OPEN NO N/A N/A
-.m . .. mm _. ._ - - - - - - - - - _ - - - - - - - - - - _ - - - - - - - _ - - _ - _ - - - - - _ - - - - - - - - - - - - - - - _ - - - _ - - - - - - - - - - _ - - - - - - - - - - _ - - - - - - - - - eu b p l-Page No.10 ' ORTH AINA telli 1 , _ Report Date/ Time: 05-19-97 / 15:31:15 SAFE SHUTDOWN EQUIPMENT tIST (SSEL) CDP 05ITE SSEL (Sorted by Equipment Class and Mart Number) LIE EQUIP SYSTEM / EQUIPMENT < EQUIPENT LOCAfl0N --> <- OP ST. -> POWER StPPORTING SYS. REQ'D INTERC0181ECTIONS REG. '
- 10. TRAIN CLASS MARK 10. DESCRIPTION Dug. No./Rev./ Zone Building Fir.Elv- Re. or Row / Col. 50RT NOTES Normal Desired REQD? OWG. ND /REV. & SLPPORTIE CGF0ENTS 155tE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 1069 2 08A 1-CH-MOV-12878 CH/CCP 8 TO LOOD FILL ll715-FM-09582/24/E6 AUX 257' 8.6/J R -
OPEN OPEN NO N/A ft/A 1070 3 08A 1-CH 40V-1237C CH/CCP C TO LOOP FILL 11715-FM-09582/24/E8 AUX 257' 8.6/J R - OPEN OPEN NO N/A N/A ICCI 1 08A 1-Cd-MOV-12894 CH/ CHARGING FLOW TO REGEN HX 11715-FM-095C1/14/D4 AUX 244' 6/H R - OPEN OPEN W N/A N/A 1074 1 08A 1-CH 410V-12898 CH/[ cps TO REGEN HX Il715-FM-095C1/14/C3 AUX 245' 7/K R - OPEN OPEN NO N/A It/A i 1179 1 GBA 1-CH-MOV-1350 CH/ EMERGENCY BORATE VALVE 11715-FM-09581/21/85 AUX 274' 8.5/J 5R - CLOSED OPEN YES N/A N/A 1090 1 08A 1-CH-MOV-1370 C4/CCP 10 RCP SEAL INJECTION 11715-FM-095C2/13/F4 AUX 259' 9/L R - OPEN OPEN NO N/A N/A > 1072 1, 2 08A 1-CH440V-1373 CH/CCP HEADER To SEAL WATER HX 11715-FM-09581/21/A8 AUX 250' 9/L R -- OPEN OPEN NO N/A N/A 1119 1, 2 08A 1-CH40V-1380 CH/5EAL WATER RETIRN 150L 11715-FWO95C2/13/F4 CONTNT 241' 8 R A,21 OPEN GPEN ND VIM 526641,26846 N/A 1132 1, 2 08A 1-CH40V-1381 CH/RCP SEAL WATER INJECil0N TO 11715-FM-09581/21/08 AUX 244' 7/J R A,21 OPEN OPEN NO N/A N/A SEAL WATER HI 4172 2 08A 1-FW40V-1004 FW/AFWP HEADER TO SG A 11715-FM-074A1/32/A5 AFPH 275" -- 5R 7 CLOSED GPEN YE5 N/A N/A 4158 2 08A 1-FW4q0V-1008 FW/AFWP HEADER TO SG B 11715-FM-074Al/32/A6 AFPH 278' - R 7 OPEN OPEN NO N/A WA 4165 2 00A 1-FW-MOV-100C FW/AFWP HEADER TO SG C 11715-FN-074Al/32/A7 AFPN 275' - 5R 7 CLOSED GPEN YES N/A N/A 4157 1 08A 1 FW-80V-1000 FW/AFWP TO SG A CONTROL VALVE Il715-FM-074A3/29/08 AFPH 270' - R - OPEN OPEN 10 N/A N/A j 54491 1 08A 1-HV40V-Illa HV/ CHILLER CUTLET ISOLATION VALVE 11715-FB-040A1/13 58 254' CHILLER RM 4/C R - OPEN OPEN 10 N/A N/A 5449N 2 08A 1-HV40V-1118 HV/ CHILLER OUTLET ISOLATION VALVE 11715-F8-040A1/13 58 254' CHILLEl t RM 5/D R - OPEN OPEN NO N/A N/A , 544927 2 ORA 1-HV40V-111C HV/ CHILLER OUTLET 150L 11715-FB-04041/13/D6 58 254' CHILLER RM 4/C R -- OPEN OPEN 10 WA N/A 5447 1 08A 1-HV40V-Il3A HV/CR & RR WATER SYSTEM 150L 11715-FB-04G)l/15/E3 58 -- At RN R - OPEN OPEN 10 N/A N/A 5448 1 08A 1-HV40V-ll38 frJ/CR 8 RR WATER SYSTEM ISOL ll?l5-FB-045)1/15/83 58 - AC RM R - WEN WEN 10 N/A N/A '[ t 5449 2 08A 1-HV40V-Il3C HV/CR 8 RR WATER SYSTEM 150L II715-F8-04001/15/D3 58 - AC RM R - OPEN OPEN 10 N/A WA 3069 1 08A 1-QS-MOV-101A 05/QUEEH SPRAY PiM' A OUTLET 150L ll715-FM-091A2/23/D5 SFGD 256' NOTE IN R A CLOSED CLOSED 10 WA N/A
- 3070 1 08A 1-Q5410V-1018 QS/QlJENCH SPRAY PipF 8 OUTLET 150L 11715-FM-091A2/23/E5 SFGD 256' ' NOTE IN R A CLOSED CLD5ED le N/A N/A
.3055 1 08A 1-QS-MOV-102A QS/REFUELIE WATER CHEN 400 TAlet 11715-FWO91Al/20/C5 YAR0/TtK 270' 2 FT N OF AFPN R A,21 CLOSED CLOSED NO WA N/A t 150L 3056 2 08A 1-QS40V-1028 QS/REPJELING WATER CHEM A00 TAls 11715-FM-091Al/20/06 YARD /TIML 272' - R A,21 CLOSED CLOSCO le N/A N/A
- 150L '5 3017 1 08A 1-RC410V-1535 RC/PORY BLOCK VALVE 11715JM-09El/22/E4 CONTMT 308' 9.4 5R 12 OPEN OP/CL YES 11715-RC-134/6 N/A f 3018 1 08A 1-RC-MOV-1536 RC/PORV BLOCK VALVE 11715-FWO9381/22/D4 CONINT 308' 9.2 5R 12 OPEN OP/CL YES 11715-RC-131/5 WA t
t t t _ _ _ _ _ _ _ _._ ____m_--_____u___________.__.____.__._-_.u_____.-_ . -__ u_aw ___ _ - - wwr4__ _ u^_ -w - _ - _ __ _ _ _ _ _ . _ _ _ _ _____.____._m_____._____. _ _ _ . _ . _ _ _ _ _ _ __ 2 ___m___ _ -
,s e\ 7 Page No.11 NORTH ANNA LMIT I Report Date/ Time: 05-19-97 / 15:31:15 SAFE SHUrDOWN EQUIPMENT LIST (SSEL)
CDP 9051TE SSEL (Sorted try Equipment Class and Mark Number) 11 3 EQUIP SYSTEM / EQUIPMENT < EQUIPMENT LOCATION -----> <- OP. ST. --> POWER SUPPORTIE SYS. REQ'O INTERCOPNECTIONS RES.
- 13. TRAIN CLASS MARK 90. DESCRIPTION Dwg. No /Rev./ Zone Building Fir. Elv. Rs. or Row / Col. 50RT NOTES Normal Destred RE007 OWG. lo./REV. 8 SLFPORTIE CJPf0NENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 4244 1, 2 084 1-RH40V-1700 RH/RHR PJe SUCTION 150L 11715-FM-094Al/14/A5 CONTMT 241' 2 5R 2 CLOSED OPEN YES VIMS 27905 14C-PI-1402 117154P-013A 4245 1, 2 OBA 1-RH40V-1701 RH/RHR PtN SUET 10N 150L ll715-FM-094A1/14/A4 CONTMT 236' 4 5R 2 CLOSED OPEN YE5 Il7154P-013A 1-RC4T-1403 4271 1, 2 08A 1-RH-t0V-1720A RH/RHR RETlRN 150L LOOP 2 11715-FM-094A2/15/C3 CONTMT 216' 12 52 -- CLOSED OPEN YES Il7154P-032A N/A 4272 1, 2 08A 1-RM NOV-17208 RH/RHR RETtRN 150L LOOP 3 Il715-FM 094A2/15/83 CONTMT 216' 7.5 5R -- CLOSED OPEN YES VIMS 30454 N/A 11715-FP-013A OR ll715-FP-032A 1135 1 OBA 1-5140V-1836 51/CCP TO COLD LEG 5 I, 2, 3 11715-FM-096A3/22/08 AUX 244' 6/J R A.21 CLOSED CLOSED 80 N/A N/A 1058 1 OBA 1-St-NOV-1863A 51/LH51 HDR TO CCPs ll7154M-096A2/23/05 AUX 244' 7.6/J R A CLOSED CLOSED NO N/A N/A 1058A 2 08A 1-51-MDV-18638 SI/tH51 TO CHARGING PtN A SUCTION ll7154M-09582/24/88 AUX 244' 7.6/J R A,32 CLOSED CLOSED NO N/A 14PK-21 X CONN 2048 1, 2 08A 1-5140V-1865A SI/ACCtM OUTLET 150L 117154M-09681/17/07 CONiMT 216' 15 5R 2,19 0 FEN CLOSED YES VIM 530186-30188 N/A Il715-FP-012A 4275 1, 2 08A 1-5140V-18658 SI/ACCtM OUTLET 150L ll715-FM-09682/16/06 CONTMT 216' 13 $R 2,22 OPEN CLOSED YE5 VIM 530711,30597 N/A Il7154P-012A 4278 1, 2 08A 1-514tV-18E5C 51/ACCIM OUTLET 150L ll715-FM-09683/13/06 CONTMT 216' 8 5R 2,22 OPEN CLOSED YES VIM 530380,30294 2J12N ll7154P-012A 1086 1 ORA 1-51-NOV-1867A SI/CHARGIE HEADER TO Bli 150L 11715-FM-096A3/22/D4 AUX 244' 7/J R --
CLOSED CLOSED !O N/A N/A 1087 1 08A 1-51-HOV-18678 SI/CHAMING HEADER TO Bli 150L 11715-FM-096A3/22/D4 AUX 244' 7/J R - CLOSED CLOSED NO N/A N/A 1087H 1 08A 1-51-NOV-1867C SIAi? 7 COLD LEG LOOP 150L 117154M 096A3/22/E7 AUX 244' 6/J R - CLOSED CLOSED #0 It/A N/A 10871 2 08A 1-5140V-18670 51/ BIT TO COLD LEG 100P 150t 117154M-096A3/22/D7 AUX 244' 6/J R - CLOSED CLOSED PC N/A N/A 1136 1 08A 1-51-MOV-1869A SI/CCP T0 LOT LEGS 1, 2, 3 Il7154M-096A3/22/08 AUX 244' 6/J R A,21 CLOSED CLOSED 10 N/A N/A 1088 1 08A 1-5140Y-18698 SI/CCP TO HOT LEGS 1, 2, 3 11715-FM-096A3/22/A8 AUX 244' 6/J R A CLOSED CLOSED NO N/A N/A 5175 2 OBA 1-5W40V-101A SV/lMIT 1 RECIRC SPRAY RX 150L ll7154M-078A4/43/C3 QSPN 265' IOTE IK 5R -- CLOSED OPEN YES N/A l-EPK-19 5176 1 08A 1-5W40V-1018 SW/tMIT 1 RECIRC $ PRAY HX 150L llT15-FM-078A4/43/C3 QSPH 265' 10TE IK $R - CLOSED OPEN YES N/A 1-EPK-21 5177 2 08A 1-5W-HOV-101C 5W/lMIT I RECIRC SPRAY liX 150L ll7154M-078A4/43/83 QSPH 265' IOTE IK 5R - CLOSED OPEN YES N/A 1-EPK-19 5178 1 OBA 1-5W40V-101D SW/ UNIT 1 RECIRC SPRAY HX 150L 11715-FM-078A4/43/83 QSPH 265' NOTE IK 5R - CLOSED OPEN YES N/A 1-EP J4C-21 5178A 2 08A 1-5W-MOV-103A SV/RECIRC SPRAY C00LE4 A INLET ll715-FM-078Bl/20/E3 QSPM 265' - R -- OPEN OPEN 10 N/A N/A 150L 51788 2 08A 1-5W40V-1038 SW/RECIRC SPRAY COOLER 8 INLET ll715-FM-07881/20/E4 QSPH 265' - R - OPEN OPEN 10 N/A N/A 150L
. _=..m . . _ _ . . ~ . . - - ..m ._.m.. . . _ . . . ..--.- -_ -- m_ m s_ _ . _ . . .. Page No.12 NORTH ANNA UNIT I Raort Date/ Time: 05-19-97 / 15:31:15 SAFE SHUTDOWN EQUIPMENT LIST ($5EL)
,- COPPOSITE SSEL (Sorted try Equipment Class and Mark Ibaber)
Ll31 EQUIP SYSTLM/ EQUIPMENT < EQUIPHENT LOCATION ---> <- OP. ST. -4 POWER StPPORTIE SY5. Rf0'D INTERC018ECT!Gl5 REG. CD. TRAIN CLASS MARK NO. DESCRIPIION Dwg. No /RevdZone Building Fir.Elv. km. er Row / Col. SORT NOTES Normal Desired REQD7 DE. IO./REV. & SLFPORTIE COPPONENTS ISSLE (1) (2) (3) (4) (51 (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5178C 2 08A 1-5WM-103C SW/RECIRC SPRAY COOLER C INLET 11715 FM-07881/20/E6 QSPN 265' - -- OPEN OPEN NO N/A N/A ISOL 51780 2 08A 1-SWM-103D SU/RECIRC SPRAY COOLER D INLET ll715-FM-07881/20/E7 QSPH 265' -- R - OPEN OPEN W N/A N/A ISOL 5179 1 08A 1-SW-MOV-105A SW/RECIRC SPRAY COOLER A OU!iET 11715-FM-078A4/43/03 QSPH 2K5' NOTE IK R A CLOSED CLOSED NO N/A N/A ISOL 5180 1 08A 1-5WM-109 SW/RECIRC $ PRAY COOLER 8 OUTLET ll715-FM-078A4/43/C3 QSPN 265' IOTE IK R A CLOSED CLOSED 10 N/A N/A 150L , 5181 1 06A 1-SW M-105C 5W/RECIRC SPRAY COOLER C OUTLET ll715-FM-078A4/43/03 QSPN 265' NOTE IK R A CLOSED CLOSED NO N/A N/A o' ISOL 5182 1 08A 1-5W-lOV-105D SW/RECIRC SPRA' COOLER D OUTLET ll715-FM-07844/43/C3 QSPN 265' NOTE IP R A CLOSED CLO5ED NO N/A WA 150L , [ 5353 1 OBA 1-SW40V-10BA SW/CC HX INLET ISOL 11715-fWO78C1/32/A4 AUX 244' - R -- OPEN OPEN W N/A N/A 5364 1 08A 1-SW-MOV-1088 SW/CC HX INLET 150L ll715-FM-07801/32/A4 AUX 244' - R -- OPEN OPEN 10 N/A N/A 5201 1 08A 1-SW-MOV-110A %W/lNIT 1 RECIRC AIR COOLIE C0!L ll115-FM-078A4/43/04 58 265' - R - CLOSED CLD5ED 10 N/A WA 150L ; 5202 1 OBA 1-SWEV-1108 SW/ UNIT I RECIRC Alt C00 Lim Coll ll715-FM-078A4/43A)4 58 265' - R - CLOSED CLO5ED 10 N/A N/A I 150L 5232 1 08A 1-SW-lOV-Il3A SW/CCW FIEL PIT COOLERS 150L 11715-FM478A4/43/87 AUX 244' 8.3/F R - CLOSED CLOSED 10 N/A N/A 5234 1 08A 1-5W-lOV-113B SW/ECW FUEL PIT COOLERS ISOL ll715-FM-078A4/43/85 AUX - 244' 8.7/F R - CLOSED CLOSED NO N/A N/A 5203 1 OBA 1-5W-MOV-Il4A SW/ UNIT I RECIRC Alt COOLING Colt 11715-FM-078A4/43/D4 58 265' - R - CLOSED CLOSED NO N/A N/A ISOL , 5204 1 08A 1-SW-MOV-1148 SWAMIT 1 REClRC AIR COOLIE COIL ll715-FM-078A4/43/D4 SG 265* -- R - CLOSED C'0 SED 10 N/A N/A ISOL r 5171 1 08A 1-SW-lOV-Il5A SW/ AUX SW PLPF 150L II715-FM-078A1/36/E6 SWPH 254' 8.5/C R 11 CLOSED CLOSED NO N/A N/A 5358 1 08A 1-5W-MDV-121A SW/SW TO ARRAYS . Il715-FN-078H/DC/C5 SWVH 326' - R - OPEN OPEN ND II/A N/A 5355 1 08A 1-SU-MOV-1218 SW/SW TO ARRAYS 11715-FM-078H/04/C7 SWVM 326' -- R - OPEN OPEN NO N/A N/A [ 5359 1 08A 1-SW-MOV-122A SW/SW TO ARRAYS 11715-FM-078H/04/05 SWVH 326' - R - OPEN OPEN 10 N/A N/A 5356 1 08A 1-5W40V-1228 SW/SW TO ARRAYS Il715-FM-078H/04/C6 SWVH 326' - R - OPEN OPEN 10 N/A N/A 5348 1 08A 1-SW-MOV-123A SW/SW RESERV0lt !$0L 11715-FM-078H/04/E4 SWVH 326' - R - OPEN OPEN _ 10 N/A N/A l 5350 1 08A 1-SW40V-1238 SW/SW RESERV0lt ISOL ll715-FM-078H/04/E8 SWVil 326' - R - OPEN OPEN 10 N/A N/A ; 5211 1 08A 2-SW40V-201A SW/ UNIT 2 RECIRC SPRAY HX 150L ll715-FM-078A4/43/E7 QSPN 256' Q5PN SR - CLOSED GPEN YES N/A 2-EP-IC-19 I I v
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Gl %d { Page No.13 NORTH Apatii UNIT 1 Report Date/ Time: 05-19-97 / 15:31:15 SAFE SHUT 00WN EQUIPMENT LIST (SSEL) CapFOSITE $$fL * (Sorted by Equipment Class and Mark 06mber) l LINE EQUIP SYSTEM / EQUIPMENT e EQUIPMENT LOCATION ----> <- OP. ST. -> POWER StPPORTIE SYS. REQ *D INTERCOMECTION5 REG. W. TRAIN CLASS MARK W. DESCRIPfl0N Dwg. No./Rev./ Zone Building Fir.E lv. Rs. or Row / Col. SORT poTES Normal Desired REQD? DE. NO./REV. & STPORTIE C0pFONENTS ISSUE ' (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) . (14) (15) (16) (17) , p 5212 2 08A 2-SW M-2018 SW/ UNIT 2 RECIRC SPRAY HX ISOL ll715-FM478A4/4347 QSPH ' 256' QSPH SR -- CLOSED OPEN YES N/A 2-EP-MC-21. 5213 1 08A 2-SW MOV-201C SW' UNIT 2 RECIRC SPRAY NX 150L ll715-FM-078A4/43/E7 QSPM 256' QSPH 'S R -- CLOSED GPEN VES N/A 2-EP-8C-19 f 5214 2 08A 2-SW 50V-2010 SWMIT 2 RECIRC SPRAY HI ISOL 11715-FM478A4/43A7 QSPN 256' QSPN SR - CLOSED OPEN YES N/A 2-EP-MC-21 5214A 2 08A 2-SWM-203A SW/RECIRC SPRAY COOLER A IEET ll715-FM-07883/21A7 QSPN 265' - 4 -- OPEN OPEN NO N/A N/A ISOL 52148 2 08A 2-SW50V-2038 SW/RECIRC SPRAY COOLER 8 INLET ll715-FM-07883/2]A6 QSPN 265' -- E - OPEN OPEN NO N/A N/A ISOL j 5214C 2 GBA 2-SWM-203C SW/RECIRC $ PRAY COOLER C INLET ll715-FM-07883/21/E5 QSPH 265' - II - OPEN OPEN NO N/A N/A
- ISOL j 52140 2 08A 2-SW MOV-203D SW/RECIRC SPRAY COOLER D IEET 11715-FM-07883/21A3 QSPH 265' - II --
OPEN OPEN NO N/A N/A ISOL ! 5215 1 C8A 2-SW40V-205A SW/LkIT 2 RECIRC SNAY HX ISOL ll715-FM-07844/4157 QSPN 256' -- I? A CLOSED CLOSED NO N/A N/A 5216 2 OBA 2-SW-MOV-2058 SW/ UNIT 2 REClic SPRAY HX ISOL ll715-FM-078A4/43A7 QSPN 25s' - 1 A CLOSED CLOSED NO N/A N/A 5217 1 08A 2-SW40V-205C SW/tMIT 2 RECIRC $ PRAY HX ISOL ll715-FM-078A4/43/E7 QSPfl 255' - R A CLOSED CLOSED 10 N/A N/A 5218 2 DBA 2-SW40V-20SD SW/lNIT 2 RECIRE SPRAY HX ISOL ll715-FM-078A4/434/ QSPN 256' - R A CLOSED CLOSED NO N/A N/A 5365 1 GBA 2-SW-EV-208A SW/CC RX INLET ISOL II715-Fit-078C1/32/A4 AUX 244' 9.3/F R - OPEN OPEN 10 N/A WA 5366 1 08A 2-SW-MOV-2088 SW/CC HX INLET ISOL ll715-FM-078C1/32/A4 SWVH - - R - OPEN OPEN NO N/A N/A 5219 1 08A 2-SWM-210A SW/ UNIT 2 RECIRC Alt C00 Lim Coll Il715-FM-078A4/43/F8 QSPH - - R - CLOSED CLOSED NO N/A N/A ISOL 5220 1 08A 2-SW40V-2108 SW/tmIT 2 RECIRC Alt COOLIE Colt Il715-FM-c78A4/43/F8 QSPN -' - R - CLOSED CLOSED 10 N/A N/A ISOL 5233 1 08A 2-SW40V-2134 SW/tCW FUEL PIT COOLERS ISOL ll715-FM-078A4/43/87 AUX - -- R - CLOSED CLOSED 10 N/A N/A 5235 1 08A 2-SW-MOV-2138 SW/CCW FUEL PIT COOLERS ISOL ll715-FM-078A4/43/85 AUX 244' 9.5/F R - CLOSED CLOSED NO N/A N/A 5221 1 08A 2-SUM-214A SW/ UNIT 2 RECIRC AIR COOLIE COIL ll715-FM-078A4/43/F8 QSPN .- - R - CLOSED CLOSED NO II/A N/A ISOL 5222 1 OBA 2-$W40V-2148 SW/ UNIT 2 RECl%C AIR COOLING Coll Il715-FM478A4/43/F8 QSPN - - R - CLOSED CLOSED NO N/A N/A ISOL 5172 1 08A 2-SW MOV-215A SW/ AUX SW Pt99 ISOL 11715-FM-078Al/3647 SWPN 254' 8.5/C R 11 CLOSED CLOSED NO N/A N/A 5230 1 08A 2-SW-MOV-220A SW/ RADIATION MONITORIE Ptp@ ll715-FM-078A4/43/F3 TS 254' - R - CLOSED CLOSED NO N/A N/A OUTLET ISOL 5231 1 OBA 2-SW-MOV-2208 SW/ RADIATION MONITORINC Pl#F 11715-FM-078A4/43/F3 T8 254' - R - CLOSED CLOSED NO N/A N/A I OUTLET ISCL
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Page No.14 NORTH AMA LMIT I Report Date/ Time: 05-19-97 / 15:31:15 SAFE $ NUT 00WN EQUIPMENT LIST JCi CopFOSITE SSEL (Sorted by Equipment Class and Mark tember) LIM EQUIP SYSTEM / EQUIPMENT < EQUIPMENT LOCATION ----> <- CP. ST. --> POWER SLPPORTING SY5. REQ'D INTERComECTIONS REG. ND TRAIN CLASS MARK NO. DESCRIPTION Img. NodRev./20ne Building F tr.E lv, Re. or RouKol. SORT NOTES Normal Desired RE007 DWG. NO./REV. & StPPORTING CGPOENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5353 1 08A 2-SWM-221A SW/SW 10 ARRAYS ll715-FM-078H/04/08 SM 326' -- R - OPEN OPEN NO N/A N/A 5360 1 GBA 2-SW-MOV-2218 5W/SW TO ARRAYS 11715 FM-078H/04/04 SM 326' -- R -- OPEN OPEN NO N/A N/A 5354 1 08A 2-SW-MDV-222A SW/SW TO ARRAYS ll115-FM-078H/04/C7 SWVH 326' -- R - OPEN OPEN NO N/A N/A 5361 1 08A 2-SW-MOV-2228 SW/SW TO ARRAYS ll115-FM-078H/04/04 SM 326' - R -- 0 FEN OPEN NO N/A N/A 5351 1 08A 2-SW-MOV-223A SW/SW RESERV0lt ISOL 11715-FM-078H/04/D8 SM 326' -- R - OPEN OPEN NO N/A N/A 5349 1 08A 2-SW-MOV-2238 SW/SW RESERVOIR ISOL ll715-FM-078H/04/D4 SWVH 326' - R - OPEN OPEN W N/A N/A 5093 1 088 1-CC-50V-103A CC/RHR HX OUTLET CONTMT ISOL PILOT ll715-FM-07981/21/87 AUX - 252' 7/L R A,27 AIR AIR YES Il715-CC-0Bl/4 N/A 5101 1 088 1-CC-50V-1038 CC/RHR XX OUTLET CONTMT ISOL PILOT 11715-FM-07981/21/07 AUX 252' 7/L R A,27 AIR Alt YES 11715-CC-082/4 N/A 1171 2 088 1-CH-50V-Ill3Al CH/8AST TO VCT CONTROL PILOT ll715-CH-017/11 AUX 278' 8.5/J R A AIR AIR YES 11715-CH-017/Il 1-EP-C8-26A 1172 2 088 1-CH-50V-Ill3A2 CH/ BAST TO VCT CONTROL PILOT 11715-0H-017/11 AUX 278' 8.5/J R A AIR AIR YES ll715-CH-017/ll 1-EP-C8-26A 1198 2 088 1-CH-50V-1201 CH/ EXCESS LETDOWN HX ISOL PILOT ll715-CH-079/3 CONTMT 236' 6 R - WNT VENT N0 ll715-FK-001D N/A 1108 1, 2 088 1-CH-50V-1303A CH/ SEAL WATER LEAKOFF PILOT ll715-CH-065/3 CONTMT 218' 18.5 R 21.36 VENT WNT ND ll715-FK-001E l-CH-NEV-1303A 1109 1, 2 088 1-CH-50V-13038 CH/ SEAL WATER LEAK 0FF PILDT ll715-CH-066/3 CONTMT 219' 11.5 R 21,36 WNT VENT N0 ll715-FK-0010 1-CH-HCV-13038 1110 1, 2 088 1-CH-50V-1303C CH/ SEAL WATER LEAKOFF PILOT ll715-CH-067/3 CONTMT 219' 7 R 21,36 VENT VENT ND ll715-FK-0010 1-CH-HCV-1303C 1118 2 088 1-CH-50V-1307 CH/ SEAL BVPASS OUTLET ISOL PILDT ll715-CH-074/4 CONTMT 255' A 8.5 R 36 VENT VENT N3 Il715-FK-001D l-CH-NCV-1307 1085 1 088 1-CH-50V-1310 CH/ CHARGING ISOL PILOT ll715-CH-069/3 CONTMT 222' 11.5 R - VENT VENT m 11715-FK-001D N/A 2007 1, 2 088 1-CH-50V-1311 CH/ AUX SFRAY ISOL PILOT 117154H-003/4 . CONTMT 220' 11 R 28 VENT VENT NO 11715-FK-001D N/A . 1207 2 088 1-CH-50V-1389 CH4XCESS LETDOWN FLOW DIRECTING 11715-CH-075/3 CONTMT 234' 6 R - VENT VENT ND ll715-FK-01D/11 N/A PILOT 5543 1 088 1-EG-50V-600HA . EG/ AIR START SOLENDID VALVE Il715-FM-107Al/09/I6 58 270' DG SR 36 0FF ON YES N/A EOG-lH 5544 2 088 1-EG-SOV-600H8 EG/ AIR START S0LENDID VALVE 11715-FM-107A2/09/E6 SB 270' DG $R 36 0FF ON YES N/A EDG-lit $545 1 088 14-$0V-600JA EG/ AIR START SOLENDID VALVE 11715-FM-107A3/10/E6 58 270' DG SR 36 0FF ON YES N/A EDG-lJ 5546 2 088 1-EG-50V-600J8 EG/ AIR START SOLEEID VALVE 11715-FM-107A4/10/E6 58 270' DG SR 36 0FF ON YES N/A EOG-1J j 4210Al 0R8 1-FV-50V-1478-1 50LENDID OPERATED VALVE 58 294* . 4/D, MERIl 5R , 4210A2 088 1-FW-50V-1478-2 SOLEWID OPERATED VALVE $8 294' 4/D, MRi! 5R 4211A1 088 1-FV-50V-1479-1 SOLENDID OPERATED VALVE 58 294' 3/D, MElli SR 4211A2 088 1-FW-50V-1479-2 SOLENDID OPERATED VALVE $8 294' 3/D ERi1 SR I
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l 4 N )) & Q) Page h- 15 ERTH AMIA LMIT I Report DateTTime: 05-19-97 / 15:31:15 SAFE SHUTLON EQUIPMENT LIST (SSEL) COMPOSITE SSEL (Sorted by Equipment Class and Mark Number) Lim EQUIP SYSTEMAQUIPMENT < -- EQUIPMENT LOCATION ---> <-- OP. ST. -> POWER SWPORilE SYS. REQ'O INTERComiECT10N5 REG. W. TRAlld CLASS MAM NO. DESCRIPTION [bg. No./Rev./ Zone Building F ir.E lv. Rs. or Row / Col. SORT NOTES Normal Desired REQD? DdG. NO /REV. & SFFORTIE CO@0NEN15 ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 421081 088 1-FW-50V-1488-1 SOLENDID OPERATED VALVE 58 294' 4/D 5R 421082 088 1-FW-50V-1488-2 50LEN010 OPERATED VALVE 58 294' 4/D 5R 421181 088 1-FW-50V-1489-1 50LENDID WERATED VALVE 58 294* 3/D SR 421182 088 1-FW-50V-1489-2 50 LEE 10 OPERATED VALVE $8 294' 3/D 5R 421001 088 1-FW-SOV-1498-1 SOLEN 0ID OPERATED VALVE 58 294' 4/D, MERil 5R 421002 088 1-FW-50V-1498-2 SOLENDID OPERATED VALVE 58 294' 4/D, HERil 5R 4211C1 088 1-FW-50V-1499-1 SOLENDID OPERATED VALVE $8 294' 3,1 5R 421102 088 1-FW-50V-1499-2 SOLENDID OPERATED VALVE 58 294' 3/D 5R 1241 1, 2 088 1-HRS-50V-1623 HRS /RC C0li IEG 5AWLE COOLER ISOL ll715-FM-089Dl/16/D5 AUX 259' 7.6/K $R 24 VENT AIR YE5 Il715-HRS-014/3 INST AIR PILDT 1227 1, 2 088 141RS-50V-1625 HRS / HOT LEG SATLE COOLEk INLET 11715-FM-08901/16/E6 AUX 259' 7.6/K $R 24 VENT AIR YES Il715-HRS-016/3 INST AIR 150L PILOT 4269 1, 2 088 1-HRS-50V-1627 HRS /SAWLIE SYSTEM ISOL PILOT ll715-FM-08901/16/F4 AUX 259' 7.6/K 5R 24 VENT AIR YES N/A INST AIR 4267 1, 2 088 1-HRS-50V-1628 $$/5AMPLING SYSTEM ISOL 11715-FM-108Al/03A5 AUX 259' - R -- VENT VENT NO N/A N/A 5425R I 088 1-HV-50V-1200A HV/CND WTR PtN SEAL FLOW CONTROL 11715-FB-04(X)l/15 SB 256' CHILLER RM 5R - P9/ CL OPEN YES N/A N/A 54255 1 088 1-HV-50V-12008 HV/CE WTA Ptw SEAL FLOW CONTROL ll715-FB-04001/15 58 256' CHILLER RM SR -- OP/CL OPEN YES N/A N/A 5425T 2 088 1-HV-50V-12000 HV/CE WTR PlNP SEAL FLOW CONTROL 11715-FB-040Dl/15 58 256' CHILLER RM 5R -- OP/CL OPEN YE5 N/A N/A 4018 1, 2 088 IM-50V-101A1 MS/5G A MSIV PILOT VALVE Il715-FM-07081/19A4 QSPH 272' 4.5/C8 SR - AIR VENT YES N/A N/A 4019 1, 2 088 IE-50V-101A2 MS/5G A M51V PILOT VALVE Il715-FM-07081/19/E4 QSPN 272* 4.5/G8 5R -- AIR YENT YES N/A N/A 4020 1, 2 088 1-MS-50V-101A6 MS/5G A MSIV PILDT VALVE Il715-FM-070Bl/19/F4 CSPH 272' 4.5/G8 $R - AIR VENT YES N/A N/A C321 1, 2 088 IM-50V-101A7 MS/5G A MSIV PILOT VALVE Il715-FM-07081/19/D3 QSPM 272' 4.5/GB $R - AIR YENT YES N/A N/A 4044 1, 2 088 1-MS-50V-10181 MS/5G B M51V PILOT VALVE 11715-FM-07082/19A4 QSPH 272* 4.5/G8 5R -- AIR VENT YES 11715M-111/9 N/A 4045 1, 2 088 IM-50V-10182 MS/SG B MSIV PILOT VALVE Il715-FM-07082/19A4 QSPH 272' 4.5/GB 5R - AIR VENT YES 11715M-111/9 N/A 4046 1, 2 088 1-MS-50V-10186 MS/5G B M51V PILOT VALVE IIT15-FM-07082/19/E4 QSPH 272' 4.5/G8 SR - AIR VENT YES ll715M-111/9 N/A C047 1, 2 08B 1-MS-50V-10187 M5/5C 8 MSIV PILOT VALVE Il715-FM-07082/19/F4 QSPH 272' 4.5/G8 5R - AIR VENT YES Il715-MS-111/9 N/A 4070 1, 2 088 1-MS-50V-10101 MS/SG C M51V PILOT VALVE Il715-FM-07083/23/D4 QsPM 272' 4.5/G8 $R - AIR VENT YES 11715~ D/9 N/A 4071 1, 2 085 14-50V-101C2 MS/5G C MSIV PIL0T VALVE Il715-fM-07083/23/04 QSPN 272' 4.5/G8 $R - AIR YENT YES 11715- ; '1 N/A 4072 1, 2 088 1-MS-50V-101C4 MS/5G C M51V PILOT VALVE Il715-FM 07083/23/D4 QSPN 272' 4.5/G8 5R - AIR VENT YES Il715-M5 ' , N/A
4 O J % . . Page Ib.16 . NORTH AlelA LMIT 1 Raort Date/ Time: 05-19-97 / 15:31:15 SAFE SHUTOOWN EQUIPM[NT LIST (55EL) COPPOSITE 55EL (Sorted by Equipnent Class and Mark Number) LINE EQUIP SYSTEM / EQUIPMENT < EQUIPMENT LOCATION --- <- OP ST. --> POWER SlFPORTIIR; SYS. REQ'D INTERC010ECTIG15 REG. NO. TRAIN CLASS MAPK m. DESCRIPil0N Dwg. No./Rev./ Zone Building F ir.Elv. Re. or Row / Col. SORT ETES Normal Desired REQ 07 OWG. W./ REY. & SLPPORTING CapFONENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 4073 1, 2 088 1-MS-50V-101C5 MS/5G C M51V PILOT VALVE Il715-FM-07083/23/D4 05PM 272' 4.5/GB 5E -- AIR YENT YES Il715-MS-Il2/9 N/A e C74 1, 2 088 1-MS-50V-101C6 MS/5G C MSIV PIL0T VALVE Il715-FM-07083/23/D4 Q5PN 272' 4.5/G8 5R -- AIR VENT YES 11715M-112/9 N/A C75 1, 2 088 IM-50V-101C7 MS/5G C M51V PILOT VALVE Il715-FM-07083/23/D4 05PH 272' 4.5/GB ' 5R - AIR VENT YE5 11715-M5-112/9 N/A C4 1 088 1-MS-50V-Illa MS/TDAFW STEAM ADMISSION PILOT ll715-FM-07043/26A5 MSVH 252' 5.5 5R - AIR VENT YES 11715-MS-Il5/8 N/A 4086 2 088 MS-50V-Ill8 MS/TDAFW STEAM AINISSION PIL0T llT15-FM-070A3/26/E4 M5VH 252' 5.5 5R - AIR VENT YES 11715-MS-Il6/10 N/A , 51198 1 088 1-NS-50V-101 NS/ NEUTRON SHIELD SURGE Tale: 11715-FM-07985/21/D3 CONTMT 262' 14 R 34 VENT VENT NO 11715-NS-001 N/A OUTLET 150L PlLOT 3001 1 088 1-RC-50V-101A-1 RC/RV VENT VALVE 11715-FM-093A3/22/A5 CONTMT 262' TOP 0F RV HEAD R -- CLOSED CLOSED NO N/A N/A 3002 2 088 1-RC-50V-101A-2 RC/RV VENT VALVE 11715-FM-09343/22/A5 CONTMT 262' TOP OF RV HEAD R - CLOSED CLOSED W N/A N/A 3003 1 088 1-RC-50V-1018-1 RC/RV VENT VALVE 11715-%093A3/22/A5 CONTMT 262' TOP OF RV HEAD R - CLOSED CLOSED NO N/A N/A + 3004 2 088 1-RC-SCV-1018-2 RC/RY VENT VALVE ll715-FM-093A3/22/A5 CONTMT 262* TOP OF RV HEAD R -- CLOSED CLOSED NO N/A N/A 3013 1 088 1-RC-50V-102Al RC/PZR VENT VALVE 11715-FM-09381/22/03 CONTMT 291' PC 9 R -- CLOSED CLOSED 2 N/A N/A 4 3014 2 088 1-RC-50V-102A2 RC/PZR VENT VALVE 11715-FM 05381/22/03 CONTMT 2918 PC 9 R - CLOSED CLOSED NO N/A N/A 3015 1 088 1-RC-50V-10281 RC/PZR VENT VALVE 11715-FM-0931/22/03 CONTMT 291' PC 9 R -- CLOSED CLOSED m N/A N/A 3016 2 088 1-RC-50V-10282 RC/PZR VENT VALVE 11715- % 09381/22/03 CONiMT 291' PC 9 R - CLOSED CLOSED NO N/A N/A 2021 2 088 1-RC-50V-14550-1 GN'PZR PORY PILOT 11715-%105Al/20/F5 CONTMT 308' 9.5 5R 33 VENT AIR YE5 11715-RC-111/12 N/A
;11715-FK-0010 2022 2 088 1-RC-50V-1455C-2 GN/PZR PORY PILOT 11715-%105Al/20/F5 CONTMT 308' 9.5 5R 33 VENT AIR YES 11715-RC-Ill/12 N/A sil715-FK-001D 2023 2 088 1-RC-50V-1455C-3 GN/PZR PORV PILCT ll715-%105Al/20/F5 CONTNT 308' 9.5 5R 33 AIR VENT YES Il715-RC-Ill/12 N/A 2026 2 088 1-RC-50V-1456-1 CN/PZR PORY PILOT ll715-%105A1/20/F6 CONTMT 308' 9.5 5R 33 VENT AIR YES Il715-RC-109/II N/A sll715-FK-001D ,
2027 2 088 1-RC-50V-1456-2 GN/PZR PORY Pitol 11715-FM-105A1/20/F6 CONTNT 308' 9.5 5R 33 VENT AIR YES Il715-RC-109/II N/A , illT15-FK-001D 2028 2 088 1-RC-50V-1456 3 GN/PZR PORY PILOT 11715-%105Al/20/I6 CONTNT 308' 9.5 5R 33 AIR VENT YE5 11715-RC-109/11 N/A 1192 2 088 1-RC-50V-1557A RC/RC 15 LETDOWN !$0L PILOT ll715-RC-051/4 CONTNT 245' 11 A R -- VENT VENT ND VIMS 27749-27750 N/A Il715-FK-001E 1194 2 088 1-RC-50V-15578 RC/RC 15 LETDOWN 150L PILOT ll715-RC-052/4 CONTMT 243' 13 $ R - VENT VENT E VIMS 28208-28211 N/A Il715-FK-0010 11 % 2 088 1-RC-50V-1557C RC/RC 15 LETDOWN 150L PILOT ll715-RC-053/4 CONTMT 243' 7.5 C R - VENT VENT W VIM 528616-28218 N/A 11715-FK-001D i
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J J Page No.17 WRTH A8MA LNii ! Report Date/ Time: 05-19-97 / 15:31:15 5AFE SHUTDOWN EQUIPMENT tl5T (SSEL) CIM'051TE SSEL (5orted by Equipment Class and Mark Number) LIJE EQUIP SYSTEM /EQUIPMCNT < EQUIPMENT LOCATION ---> <-- OP. ST. -> POWER SLFPORTING SYS, REQ'D INTERC018 ECT10Ni REG. NO TRAIN CLAS5 MARK NO. DESCRIPTION Dwg. NeJRev./ Zone Building F tr.E lv. Rs. or Row / Col. 50RT NOTE 5 Normal Desired REQD? DE. NO./REV. & StFPORTING CMONENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 2047 ' 1, 2 088 1-51-50V-18508 SI/ACCLM TEST ISOL PIL0T 11715-51-022/3 CONTMT 221' l.5 R 21,36, VENT VENT ND ll715-FK-00!E l-51-HCV-18508
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4274- 1, 2 088 1-51-50V-18500 SI/ACCtM TEST ISOL PILOT 11715-51-024/2 CONTMT 221' 13 R 22,36 (ENT YENT W ll715-FK-0CID l-51-HCV-1850D 4277 1, 2 088 1-51-50V-1850F - SI/ACCtM TEST 150L Plt 01 11715-51-026/3 CONTNT 221' 7.5 R 22 VENT VENT NO ll715-FK-001D;I N/A 1715-FK-001D 1236 , 1, 2 088 1-55-TV-102A 55/ COLD LEG SNLE NEADER 150L 117154 089D1/16/D6 CONiMT 241' 8.5 5R A,40 CLO5ED GP/CL YES 11715-15-005/5; N/A 11715-FK-001D 1237 1, 2 088 1-55-TV-1028 55/RC COLD LEG SWLE 150L 11715-FM4901/16/06 AUX 245' 7/K $R A,40 CLOSED CP/C1 YES 11715-55-036/3 N/A 4264 1, 2 088 1-55-TV-103A 55/5MLING SYSTEM ISOL ll715-FM 08901/16/F7 CONTMT 241' 7.5 5R A,40 CLO5ED C#/CL YES 11715-55-013/3; R/A 11715-55-008 4265 1, 2 088 1-55-TV-1038 55/5WilNG SYSTEM 150L 11715-408901/16/F5 AUX 245' 5R A,40 Closed OP/CL YES N/A N/A 1224 1, 2 088 1-55-TV-106A SS/HDT LEG SWLE HEADER 150L ll715-F108901/16/E6 CONTMT 241' 8.5 5R A,40 CLOSED OP/CL YES 11715-55-C11/6; N/A Il715-FK-[01D 1225 1, 2 088 1-55-TV-1068 55/ HOT LEG SAMPLE 150L 11715-FM-08901/16/E6 AUX 245* 7/K 5R A,40 CLOSED OP/CL YES 11715-55-012/3 N/A 4262 1, 2 'A8 1-55-TV-107A 55/RHR HX OUTLET TO SAPPLIE 11715-%08901/16/F8 CONTMT 216' 7 5R -- CLO5ED OPEN YES 11715-55-013/3 N/A SYSTEM . Il715-FK-0010 VIM 530448-30450 [ 4263 1, 2 088 1-55-TV-1078 55/RHR HX OUTLET 10 SNLING 11715-%08901/16/F8 CONTMi 241' 4 5R - CLOSED OPEN YES 11715-55-014/3 N/A SYSTEM VIM 527348,27370 1223 1, 2 088 I-55-TV-108D SS/ HOT LEG SWLE ISOL 11715-FM-08901/16/D8 CONTMT 241' 13 8 5R - CLO5ED GPEN YE5 11715-55-018/4 N/A VIMS 28479, 28416, 28436 1231 1, 2 088 1-55-TV-109A SS/ COLD LEG SWLE ISOL 11715-%08901/16/D8 CONTMT 243' CA 1.5 A 5R - CLOSED GPEN NO 11715-55-019/3 N/A VIMS 27864 i 11715-FK-001E 5206 2 088 1-5W-50V-101A-1 SW/ UNIT I RECIRC AIR COOLING COIL ll715-FM-078A4/43/D4 58 265' - 5.5/GA R - WNT WNT N0 ll715-5W-037R N/A 150L PILDT 5207 2 0F* 1-5W-50V-101A-2 SW/tMIT 1 RECIRC P' COOLIE COIL 11715-%C78A4/43/D4 58 265' 5.5/GA R - VENT VENT W ll715-5W-037/7 N/A 150L PILOT 5209 2 088 1-5W-50V-1018-1 SW/ UNIT 1 RECIRC AIR COOLING COIL ll715-FM-078A4/43/D4 58 255' 5.5/GA R - VENT VENT W 11715-5W-038/7 N/A 150L PILOT 5210 2 088 1-5W-50V-1018-2 SW/lMIT 1 RECIRC AIR COOLIE Colt 11715-FM-078A4/43/D4 58 265* ii.5/GA R - VENT VENT W 11715-5W-03Bn M/A 150L PILOT 5547 1 088 2-EG-50V-700HA EG/ AIR START SOLENDID VALVE 12050-FM-107Al 58 270' OG $R 36 0FF ON YE5 N/A EDG-2N 5548 2 088 2-EG-50V-700H8 EG/ AIR START SOLENDID VALVE 12050-FM-107A2 58 270' DG 5R 36 0FF ON YE5 N/A EDG-2H j i i _.._____m_ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-v_ __ ~__._.,m_ -_o w
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Page No.18 10RTH AWA tali i Report Date/ Time: 05-19-97 / 15:31:15 5AFE il41TDOWN EQUIPMENT LIST (55EL) COWOSITE SSEL (Sorted by Equipment Class and Mark Number) , LIG EQUIP SYSTEM / EQUIPMENT < EQUIPMENT LOCAil0N ----> <-- OP. ST. -> POWER SlFPORTIE SYS. REQ'D INTERComECTIONS REG. 10 TRAIN CLASS MARK 00 DESCRIPTION Dwg. No /Rev./ Zone Building F tr.E lv. Ra or Row / Col. SORT fcTES Normal Desired REOD? OWG, NO./REV. & SLFPORTING COWONENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5549 1 088 2-EG-50V-700JA EG/ AIR START 50LEN0!D VALVE 15050-FM-107A3 58 270' DG 5R 36 0FF ON YES N/A EDG-2J 5550 2 0B8 2-EG-50Y-700J5 EG/ Alt START 50LEN010 VALVE 120504M-107A4 58 270' DG SR 36 0FF ON YES N/A EDG-2J 5432 1 11 1-HV-E-4A HV/ CHILLER UNIT 11715-FB-040Dl/15/E5 58 254' AC RM 4/C 5R - ON ON YES Il715-F8-040A1/ 14P-E-10 13 5433 1 11 1-HY4-48 HV/ CHILLER UNIT 11715 4 8-04001/15/85 58 254' AC RM 4/C 5R -- ON ON YES 11715-FB-040Al/ l-EP-MC-Il 13 5434 2 11 1-HV4-4C HV/ CHILLER UNIT ll715-F8-04001/15/05 58 254' AC RM 4/D 5R -- ON ON YES 1171548-040Al/ 14P-E-41 13 6057 1 14 1-8P-5W-1 BP/8Y-PA55 SWITCH I (MAttlAL) Il715-FE-00lVl/02/J2 58 277' 9/C 5 INVERT INVERT YES 117154E-IIE/051-V8-1-01 6058 1 14 1-8P-5W-2 BP/BY-Pass SWITCH 2 (MANLfAL) Il715-FE-00lVl/02/J4 58 277' 9/C 5 INVERT INVERT YES Il715-FE-11E/051-V8-1-02 6059 2 14 1-8P-5W-3 8P/8Y-PA55 5 WITCH 3 (MAMJAL) 11715-FE-00lVl/02/J5 58 277' 8/C $ INVERT INVEPT YES 117154E-IIE/051-VB-I-C3 6060 2 14 1-8P-5W-4 BP/BY-PASS SWITCH 4 (bNtRL) Il7154E-00lVl/02/J7 58 277' 8/D $ INVERT INVERT YES 11715-FE-11E/051-VB-I-04 6065 1 14 1-EP-CB-002 EP/120 AC UNIT 1 APP-R DIST. PNL ll7154E-001AEl/13/A $8 254' 10/C 5R -- N/A N/A YES N/A 1-VB-I-01 (RED) 7 6061 1 14 14P-C8-04A EP/120V VITAL AC 1-1 BUS (RED & 11715-FE-001Vl/02/0158 277' 9/C 5R - N/A N/A YE5 N/A 1-8P-5W-01 ORANGE) 6062 1 14 14P-08-048 EP/120V VITAL AC 1-11805 (WITE) ll7154E-00lVl/02/D2 58 277' 9/C $R - N/A N/A YES N/A 1-8P-5d-02 6063 2 14 14P-CB-04C EP/120V VITAL AC 1-111 BUS (BLUE & Il7154E-001Vl/02/D4 58 277' 9/C 5R -- N/A N/A YES N/A 1-8P-5W-03 PtRPLE) 6064 2 14 14P-CB-04D EP/120V VITAL AC 1-IV BUS (YELLOW) Il7154E-001Vl/02/05 58 277' 9/C 5R - N/A N/A YES N/A 1-BP-5W-04 6045 1 14 1-EP-CB-12A EP/125V VITAL DC BUS (1-l) Il7154E-001El/18/E7 58 254' 9/C 5R - N/A N/A YES N/A 1-BY-C-02,-03,-04;l-8Y-8-01 6046 1 14 1-EP-C8-128 EP/125V VITAL 0C BUS (1-11) Il715-FE-001El/18/D7 58 254' 9/C $R -- N/A WA YES N/A 1-8Y-C-02.-03,-04;l-8Y-B-02 6047 2 14 14P-C8-12C EP/125V VITAL DC BUS (1-III) Il7154E-001E2/17/E7 58 259' 8/C 5R - N/A N/A YES N/A 1-8Y-C-05,-06,-07;l-8Y-8 03 6048 2 14 1-EP-C8-120 EP/125V VITAL 00 805 (1-IV) ll715-FE-001E2/17/07 58 254' 8/C $R - N/A WA YES N/A 1-8Y-C-05,-06,-07;1-8Y-B-04 6035 1 14 1-EP-08-16A EP/120V SEMI-VITAL AC 1A BUS 117154E-00lW1/16/El 58 277' 8/D 5R - N/A N/A YES N/A TRANS-70 6037 2 14 14P-C8-168 EP/120V SEMI-VITAL AC 18 BUS 117154E-00lWl/16/E3 58 277' 8/D 5R -- N/A N/A YE5 WA TRANS-71 5571 1 14 14P-C8-41AN EPNEAT TRACE DISTRIBUTION CABINET ll715-FE-10/27 AFPH 271' l.1/LA 5R -- ON ON YES N/A N/A 5583 2 14 1-EP-CB-41AR EP/ HEAT TRACE DISTRIBUTION CABINET ll715-FE-63 SERIES AFPH 271' 1.1/LA 5R 30 ON ON YES N/A N/A
Page No,19 NORTH AfetA UNIT I Report Date/ Time: 05-19-97 / 15:31:15 - SAFE SHUTDOWN EQUIPENT LIST (SSEL) Cuff 05tTE SSEL (Sorted by Equipment Class and Mark Number) LIA EQUIP SYSTEN/EQUIPNENT < EQUIPENT LOCATION ----> < -- OP ST. -> POWER St.PPORIllC SYS. REQ'O INTERC018ECT10N5 REG. > C. TRAIN CLASS NARK E. DESCRIPTION Dug. No./Rev./ Zone Buildin9 F tr.Elv. Re. or Row / Col. SORT ETES Normal Desired REQC? DWG. ND / REY. 8 StPPORTING CG90NENTS !$5UE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5572 1 14 1-EP-08-418N EP/ HEAT TRACE DISTRIBUTION CABINET ll715-FE-10/27 AFPH 271' l.1/LA 5R -- ON ON YES N/A N/A 5584 2 14 1-EP-C8-4182 EP/ HEAT TRACE 0157RIBUTION CA8INET ll715-FI-63 SERIES AFPH 271' l.1/LA 5R 30 ON ON YES N/A N/A 6049 1 15 1-BY-8-01 8Y/125V 8ATTERY l-1 Il7154E-001E1/18/D7 58 294' 9/C 5 - N/A N/A YES N/A N/A 6050 1 15 1-8Y-8-02 BY/125V BATTERY l-11 11715-FE-001El/18/87 58 252' 9/C 5 -- N/A N/A YES N/A N/A 6051 2 15 1-8Y-8-03 BY/125V 8ATTERY l-111 11715-FE-001E2/17/E7 58 294' 8/DB 5 - N 'A N/A YES N/A N/A 6052 2 15 1-8Y-8-04 BY/125V BATTERY l-IV ll715-FE-001E2/17/07 58 252' 8/D 5 - N/A N/A YES N/A N/A 6066 1 15 14G-8-01A AP/EDG 8ATTERIES A9 RACKS 11715-1.30-212C 58 272' EDGIN 5 -- N/A N/A NO N/A N/A f 6067 2 15 1-EG-8-03C AP/EDG 8ATTERIES AS RACKS 11715-1.30-712C 58 272' CiX;1J $ -- N/A N/A ft) N/A N/A , 6040 1 16 1-8Y-C-02 8Y/ BATTERY CHARGER 1-1 117154E-001El/18/07 58 254' EER $WGR 5R -- WA N/A YES N/A 1-EPM-10
- 6039 1 16 1-8Y-C-03 BV/ BATTERY CHARGER IC-1 Il715-FE-001El/18/08 $8 254' EER SWGR 5R -- N/A N/A YE5 N/A 14P-NC-10
- 6041 1 16 1-BY-C-04 BY/8ATTERY CHARGER l-11 Il7154E-001El/18/C7 58 254' EER $WGR 5R -- N/A N/A YE5 N/A 14P-NC-10 6043 2 16 1-8Y-C-05 8Y/ BATTERY CHARGER l-III Il7154E-01081/19/A9 58 254' ENER SWGR 5R - N/A N/A YES N/A 1-EP-pC-11 6042 2 16 1-BY-C-06 8Y/8ATTERY CHARGER 1C-11 Il715-FE-010Bl/19/09 58 254' EER SWGR 5R - N/A N/A YES N/A 1-EP-NC-Il 6044 2 16 1-8Y-C-07 BY/8ATTERY CHARGER 1-IV ll715-FE-01081/19/F6 58 254' EER SWGR 5R -- N/A N/A YES N/A 1-EP-NC-11 !
6053 1 16 1-V8-1-01 V8/ INVERTER TO VITAL I-I BUS 117154E-011E/05/88 58 252' 9/C 5R - N/A N/A YES N/A 1-EP-08-12A
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6054 1 16 1-V8-I-02 V8/ INVERTER TO VITAL I-11 BUS 11715-FE-OllE/05/E8 58 252' 9/C 5R - N/A N/A YES N/A 1-EP-CS-128 6055 2 16 1-V8-1-03 VB/ INVERTER TO VITAL I-Ill 8U5 Il715-FE-OllE/05/HB 58 252' 8/C 5R - N/A N/A YE5 N/A 14P-C8-12C 6056 2 16 1-V8-1-04 V8/ INVERTER TO VITAL I-IV BUS Il715-FE-OllE/05/L8 58 252' 8/C 5R - N/A N/A YE5 N/A 1-EP-C8-120 , 6001 1 17 EDG-lH* AP/EERGDEY DIESEL GEERATOR IX ll7154E-001A1/21/83 58 272' 14/D 5R - 0FF ON YES N/A 1-BY-8-01 -02 6002 2 17 EDG-lJ* AP/EERGENCY DIESEL GEERATER IJ ll715-FE-001A1/21/8158 272' 16/D 5R -- 0FF ON YES N/A 1-8Y-8-03,-04 5003 1 18 1-CC-FT-1004 CC/CCW HX OUTLET FLOW ll7154N-07941/17/E4 AUX 259' 8.5/F 5R - ON ON YES 11715-CC-063/3 M/A 5007 1 18 1-CC-FT-1008 CC/CCW HX OI,TLET FLOW ll715-FWO7M1/17/D4 AUX 259' 8.5/F 5R - ON ON YES 11715-CC-063/3 N/A 5088 1 18 1-CC-FT-132A CC/CC XX FLOW TO RHR HX II7154M-07981/21/F6 CONTNT 216' 7 5R - DN . CN YES Il715-CC-110/5 M/A 5096 1 18 1-CC4T-1328 CC/CC HX FLOW TO RHR HX ll715-FWO7981/21/F5 CONTNT 216' 4.5 5R - ON ON YES 11715-CC-111/6; (/A i Il7154K-18 5049 1, 2 18 1-CC-LT-101 CC/CC $ URGE TA8K LEVEL 11715-FN-07941/17/07 AUX 298' 9/F 5R - ON ON YES ll715-CC-057/8 1/A 5311 1 18 1-CC4T-100 CC/CCW HX OUTLET PRESSURE 117154N-07%1/17/D3 AUX 245' 8.5/G $R - ON ON YES Il715-CC-059/6 N/A .____ --__-_____-______ - ____- _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ ~_. . - -~ ..- .__-_ . _ . _ _ _ - _ _ _ - - _ _ . _ _- . _ _ _ _ _ _ _ . _ _ _ - - _ _ _ _ _ _ _ _ .
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O O O Page No. 20 . NORTH AfstA tmli 1 Roert Date/ Time: 05-19-97 / 15:31:15 5AFE SHUTDOWN EQUIPMENT LIST (55EL) CGF051TE SSEL (Sorted by Equipment Class and Mark thmber) 11 3 EQUIP SY5 TEM /EQUIPMGT < EQUIP!(NT LOCATION ---> <-- (F. ST. -> POWER SLPPORTilt; SYS. REQ'O INTERCOISECTIONS REG. NO. TRAIN CLASS MARK mi CESCRIPTION Dwg. NedRev./ Zone Building F ir_ Elv. Rs. or Row / Col, SORT ETES Normal Desired REQ 07 DE. E./ REY. & SUPPORTING CMNTS ISSUE
. (1) (2) (3) (4) (5) (6) (7) (8)- (9) (10) (11) (12) (13) (14) (15) (16) (17) i 1076 1 18 1-CH-E/P-II22 CH/ CHARGING FLOW TO REGrN HI Il7154H-001/7 AUX 245' 12/H R -
ON ON YES N/A WA 1092 1 18 1-CH-E/P-ll86 CH/CCP TO RCP SEAL INE. St !!715-CH-068/1 AUX 245' 8.5/L R -- ON ON YES N/A N/A 1201 2 18 1-CH-E/P-NCV-1137 CH/EXCES5 LET00WN HX 150L E/P 11715-CH-077/3 CONTMT 217' 5.5 R - ON ON YES 11715-FK-01A/14 RACK 1-100}}