ML20137T671
| ML20137T671 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/05/1985 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20137T655 | List: |
| References | |
| NUDOCS 8512090082 | |
| Download: ML20137T671 (559) | |
Text
{{#Wiki_filter:- - _ ENVIRONNENTAL 90ALIFICATION SUMNARY REPORT FOR HOPE CREEK GENERATING STATION PUBLIC SERVIEL ELECTRIC & GAS r rm N) REY DATE PREPARED , REVIEWED APPROVED
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g] g ENVINDINIENTAL 00ALIFICATICII SUINIARY REPORT FOR BOPE CREEK GENERATING STATION SECTION TITLE I Purpose II Program Synopsis III Procedures IV Regulatory Compliance V Quality Assurance Provisions VI Environmental Conditions - VII System / Component Identification ( VIII Qualification Testing / Analysis
,, IX Follow On Program X Equipment Environmental Summary Sheets XI Program Status O
[ 1 PREFACE
'\,_./
- d This report summarizes $Ne status of the environmental qualification program.for safety related electrical and mechanical components installed at HCGS. This program is an ongoing effort with completion scheduled ~ prior to initial core loads this document reflects the work done to date. The scheduling and status.information is? included as Section XI.
of this report. Major EQ related items currently being reviewed for resolution.are identified.in Section XI. Note that this revision *(Revisioh 3) includes work completed since 3/28/85 and also addresses items discussed during the NRC EQ audit in July of 1985. 4 i O h \ tj
I. PURPOSE The purpose of this HCGS Summary Report is to explain the approach taken to identify and to ensure the operability, under any postulated environmental conditions (normal /ab-normal / accident), of the safety related electrical and mechanical components required to bring the plant to, and maintain it in, a safe shutdown condition any time during its anticipated forty year life. In accordance with Item (b) of 10CFR50.49, this report ad-dresses qualification oft (1) safety related electrical equipment, (2) non-safety related electrical equipment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety func-tions, and (3) post accident monitoring equipment located in a harsh environment as delineated in HCGS FSAR Section-1.8.1.97 and FSAR Table 3.11-5. As HCGS is qualifying each of these types of equipment equally in this EQ program, the words " safety related" as applied to electrical components and when used in this report only, are synonymous with the three categories noted. HCGS compliance with 10CFR50.49 is 7, summarized in the attached FSAR Table 3.11-3 (pages I-3
) thru I-6).
Additionally, in accordance with Section 4.4.1 of IEEE STD-627-1980, this report addresses the qualification of safety related mechanical components whicht (1) are located in a harsh environment, (2) contain materials with "significant aging mechanisms", and (3) are required to function during and/or aft 1r a Design Basis Accident (DBA). This Summary Report includes a synopsis of (1) The identification of the various parties,(PSE&G, GE, Bechtel, etc.), responsible for the ongoing technical re-view as well as the establishment and periodic updating of
.the EQ file and EQ Summary Report (Section III).
(2) The listing of applicable EQ Program related design criteria including Regulatory Guides, IEEE Standards, NUREG's, IE Bulletins / Notices, etc. (Section IV). (3) The Quality Assurance programs utilized to assure ad-herence of the EQ program to the requirements of 10CF50, Appendix D (Section V). - (4) The analysis methods used to determine the environmen-
'n tal design envelopea (radiation, pressure, temperature, i humidity) for normal as well as abnormal and Design Basis Accident (DBA) operating conditions (Section VI).
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T (5)- The identification process used to determine: (a) the systems required to mitigate and follow the course of any V e). postulated DBA as well as achieve and maintain safe shut-down following a DBA, and; (b) the selection process used to identify the individual electrical and mechanical components within each of these systems required to function to ensure required system operation (Section VII). (6) The review process methods used to ensure the com-pleteness of EQ reports for each of the identified safety related system components to verify compliance with appli-cable EQ design criteria including HCGS Licensing commit-ments to IEEE Standards, Regulatory Guides, NUREG, IE aulletins/ Notices, and Code of Federal Regulations. (Section VIII). (7) The description and implementation process for a main-tenance and surveillance program to document the proper monitoring, and performance of maintenance related repairs and/or replacement of EQ related electrical and mechanical components to ensure operability under any anticipated en-vironmental conditions during the forty year life of the plant (Section IX). (8) The development method used for the compilation of Equipment Evaluation Summary Sheets (EESS) by system which summarizes the EQ data on a component by component basis f (Section X). In addition to the EQ data contained in this Summary Re-port, the following sections of the HCGS FSAR contain EQ support documentations (1) Section 1.8 Conformance to NRC Guidelines (2) Section 1.10 TMI-2 Related Requirements for New Op-erating Licenses. (3) Section 1.11 Differences from Standard Review Plan. (4) Section 1.12 Unresolved Generic Safety Issues. (5) -Section 3.1 Conformanc2 with NRC General Design Cri-teria. (6) Section 3.2 Classification of Structures, Compon-ents, and Systems. (7) Section 3.9 Mechanical Systems and Components. (8) Section 3.10 Seismic Qualification of Seismic Cate-gory 1 Instrumentation and Electrical Equipment. (9) Section 3.11 Environmental Design of Mechanical and Electrical Equipment. (10) Chapter 6 Engineered Safety Features. (11) Chspter 7 Instrumentation and Controls. (12) Section 8.3 On-site Power Systems. (13) Chapter 15 Accident Analysis.
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Various EQ applicable sections of the FSAR are summarized
) in this EQ Summary Report. These sections of the PSAR were
{Q utilized and referenced to determine the environmental de-sign criteria, to identify the systems / components required to achieve and maintain plant shutdown, and to verify the licensing criteria (NUREGS, Regulatory Guides, IE Bulletins / Notices, etc.) to which the HCGS EQ Program is committed. 9 D f l' Z-3
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e l l 4 I I l i i i I i 4 i 4 j 1 f f FSAR TABLE 3.11-3 !9 l l l I t I l t t i i } t l l i h } t f i l h f a i
\* HCGS FSAR 1/85 l O
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TABLE 3.11-3 Page 1 of 4
SUMMARY
OF HCGS COMPLIANCE WITH 10 CFR 50.49 i This table represents a summary of Hope Creek Generating Station compliance with 10 CFR 50.49. ! Paragraph (a) . Requirement incorporated. A program has
. been established for qualification of electric equipment in a harsh environment that is safety-related.. The present !
program will be discussed in detail by an E0 summary report as referenced in Section 3.11. Paragraph (b) - Requirements incorporated. Safety-related (1) electrical equipment, needed to mitigate. design basis events, has been identified, designed and will be qualified to function properly in the environmental conditions during normal, abnormal and design bacis O events. Paragraph (b) - Requirement incorporated. The criteria l (2) used to identify non-safety electric equ'pment whose f ailure could affect operation of safety-related equipment will be included in the summary EQ report. (To date no non-safety-related equipment in this category has been identified.) Paragraph (b) - Requirement incorporated. The parameters l (3) required to be measured by Regulatory Guide 1.97 are included to the extent noted in Section 1.8.1.97. Equipment required by Regulatory Guide 1.97 to be environmentally qualified has been included in the equipment qualification program. Paragraph (c) - No requirement. This section details items i (mild environment, seismic qualification, etc.) that are not included within the scope of this rule. l l Amendment 9 l l 1
; HCGS FSAR 1/85 l
() TABLE 3.11-3 (Con't) Page 2 of 4 Paragraph (d) - Requirement incorporated. Table 3.11-5 has been developed to identify safety-related r
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electric equipment located in a harsh environment. This table is included in : Section 3.11 and will be included in the EQ l summary report. Paragraph (d) - Requirement incorporated. The equipment l (1) evaluation summary (EES) sheets in the EQ summary report will provide this information. Paragraph (d) - Requirement incorporated. Equipment test l (2) reports will provide this information. Paragraph (d) - Requirement incorporated. The EES sheets l (3) in the EQ summary report will provide this information. ; Requirement incorporated. Section 3.11 Paragraph (e) - l (1) discusses the design basis including : temperature and pressure. A plant specific 0 - profile for temperature and pressure vs. time for equipment qualification will be included in the EQ summary report. Temperature and pressure limits are included on the EES's and in Table 3.11-1. t Paragraph (e) - Requirement incorporated. Humidity has l (2) been considered where it is applicable and is included on the EES's and in Table 3.11-1. ] Paragraph (e) - Requirement incorporated. Chemical l l (3) effects are not applicable since : domineralized water is used. Effects on ! demineralized spray are encompassed by ; testing at 100% relative humidity. Equipment subjected to direct spray impingement will be evaluated to determine ' if testing under spray conditions in addition to 100% relative humidity , conditions is required. l l O Amendment 9 l
l l HCGS FSAR 1/85 l () TABLE 3.11-3 (Con't) Page 3 of 4 Paragraph (e) - Requirement incorporated. Radiation l (4) effects on safety-related electrical
- equipment-have been taken into account, where applicable, including radiation resulting from recirculating fluids.
Radiation levels are included on the EES's and in Table 3.11-1. Paragraph (e) - Requirement incorporated. Aging is l (5) included as part of equipment qualification except where equipment is not considered to be age sensitive. Qualified life is included on the EES's. Paragraph (e) - Requirement incorporated. Equipment that l (6) could be submerged has been identified and demonstrated to be qualified by test for the duration required. Paragraph (e) - Requirement incorporated. Synergisti,c l (7) effects have been considered in the accelerated aging programs. An engineering Os evaluation will be performed to identify known synergistic effects for materials that'are included in the equipment qualified. Any identified synergistic effects are accounted for in the qualification programs. Section 3.11.2.7.4 discusses the design basis for synergistic effects. Paragraph (e) - Requirement incorporated. The equipment l
-(8) technical specification includes the margin in the environmental conditions of the plant and the margin to be applied to service conditions. Section 3.11.2.7.1 discusses margins as part of the design basis.
Paragraph (f) - Requirement incorporated. Section 3.11.6.1 l (1-4) discusses performance of environmental qualification by testing and' analysis. O Amendment 9 l
HCGS FSAR 1/85 l TABLE 3.11-3 (Con't) Page 4 of 4 Paragraph (g) - N/A. Pertains to plants receiving operating licenses prior to February 22,
. 1983.
Paragraph (h) - N/A. Pertains to plants receiving , operating licenses prior to February 22, 1983. Paragraph (i) - N/A. Pertains to plants receiving operating licenses prior to November 30, 1985. Paragraph (j) - Requirement incorporated. Section 3.11.3 states that environmental qualification documentation for safety-related electrical equipment will be available for NRC audit. Paragraph (k) - No requirement. This section permits applicants for, and holders of, operating licenses exemption from this rule if the , I Commission previously required qualification of equipment in accordance with DOR guidelines or NUREG-0588. [ Paragraph (1) - Requirement incorporated. Replacement equipment will be qualified in accordance with 10CFR-50.49. I O Amendment 9 l
;II.-LPROGRAN' SYNOPSIS
- The objective-of the'EQ program is to ensure that the.elec-trical and mechanical. components required to safely shut 1
down the station under,any-postulated DBA will successfully Lperform their' safety related function. -This.DBA could t occur atrany! time. during the anticipated forty year plant
' life. -.This objective is met by:
- (1) _ Identifying the systems and the components within each. system required to safely shut down the
' station.-
(2) Determining the normal environmental operating condi-tions that the components will be functioning under.
'(3) Determining the worst case environmental condi-tions-the' components will be subject to 'under nor-
' mal, abnormal, and DBA occurrences.
(4) Ensuring that the EQ test / analysis data for each component verifies component operability under both these normal and worst' case DBA environmen-tal conditions. O kl An additional, unique EQ related ef fort which was performed for 'HCGS but is not included in this EQ Summary Report,, is the qualification review'of the components required to miti-gate the ~ consequences .of . an Anticipated Transient Without Scram (ATWS) event. In summary, a qualification program.was performed .by General Electric (GE) and verified by PSE&G whi& ensures that the various components. required for ATWS
, were qualified to operate- in the ATWS environment for the length of time required to perform their defined functions.
- .: 1(1) Identification of the Components Reauired to Safely Shut Down'the Station These were defined as those system components required to detect, follow and mitigate ' an accident condition and to niaintain the
~ station in a. safe shutdown condition following,the accident. Each accident scenario was ' reviewed and the components required to perform' detection, monitoring and/or mitigating functions were identified on a~ system-by-system basis.
' These systems and their related components were defined and
. separated into the following categories:
(a) Protection Systems - those systems which ini-tiate safety actions to mitigate the conse-quences of a DBA. II-1
_ _ . _ . , _ . _ _ _ . _ .. _ ..__ _ _ _ . _ _ ~_. y w d7 _ f ;(b) Engineered Safety Feature Systems .those systems.which provide.. cooling,. core protec-EA m . tion and isolation of the reactor plant dur- ' dj . ing a DBA. Safe Shutdown' Control Systems - those control
~(c)' ~ systems-used to achieve and. maintain.the sta-
-tion in a safe shutdown condition following a DBA.
4 N '(d) ' S'afety - Related Display Instrumentation - the
. display . instrumentation = available to the N
. operator to indicate-proper, functioning of safety'related systems including indication of required = operator . manual initiation and Tcontrol-of safety. systems / components..
.(2) LDetermination of Normal Environmental Conditions .
lOnce'the components required for safe shutdown were identified, itheir. physical locations within the station were determined. The
< architect / engineer ( A/E)~ for HCGS (Bechtel). then calculated the conditions; that ' exist during . routine ' station ' operation including .
'startup,_ shutdown,~ power operation, refueling and maintenance.
This ; data was T u' sed as- the baseline ' data in determining normal environmental; ef fects on components - required to safely operate
~^
indfshut down the station. (3) Determination of Worst Case Environmental' Conditions-
\ - The A/B then analyzed the ef fects that abnormal operating condi-
'tions would have-on the environment of each. identified safety re--
. la ted '. component. This analysis' included such conditions as loss
~
o f foffsite power 'and ' loss .of. ventilation as well as Design-' Basis LAccidents (DBA) such as LOCA,- feedwater line break, etc. 'The resultant worst case environmental conditions postulated were ,~
' chosen-for each plant area. From this analysis,:two categories
.of environmental states were defined:
s> (a) Harsh' Environment- Components located in these areas would-be subjected to worst case DBA. anticipated temperatures', pres-sure, humidity, and/or radiation extremes well above the normal operating environ-mental conditions. Harsh environmental areas'are those'in which the~ abnormal or DBALvalues,of temperature or radiation exceed 120 F'or 1- X 103 RADS respec-tively. (b)' Mild Environment- Components located in
. these areas would at no time (including under worst case DBA) be subjected to en-
-vironmental conditions significantly more severe than those experienced under nor-
-g : mal plant operating conditions.
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(4) Verification of Component Operability Under Defined Environ-mental Conditions . The test / analysis- data for each component was then reviewed to [- ensure- that the component would perform its required safety re-V lated function under normal, abnormal and applicable DBA environ-mental conditions. This was accomplished by comparing the det-ailed manufacturer or component supplier EQ reports for each identified safety related component to the environmental en-velopes calculated for the normal, abnormal and DBA operaring states under which that component'would be required to operate. e O 4 O II-3
7., II
I. PROCEDURE
S The responsibility for the development and ongoing tech-nical review of the HCGS.EQ program, including the creation and updating of the EQ central file, has been undertaken by the' Controls and Electrical Division of the PSE&G Engineer-ing and Construction Department. As such, it is respon-sible for the coordination and monitoring of the efforts of the various participants involved in the EQ program includ-
-ing the A/E (Bechtel), NSSS supplier (GE), and other PSE&G division personnel as well as associated independent con-sultants, component suppliers, and testing labs.
The EQ program supervision.is under the direction of a PSE&G Principal Engineer and includes a functional engi-neering staff which is supported by Bechtel, GE, and a con-sultant. The work activities are applicable to; (1) the NSSS EQ program and- (2) the Balance-of-Plant (BOP) EQ pro-gram and include the following:
- Direct the efforts of the architect-engineer (A/E) requiring interface with GE and other vendors.
/7 - Verify that all equipment requiring qualification C is identified.
- Review specified environmental conditions and qualification plan compliance.
- Review / approve all EQ documents submitted by the vendor including test plans, analyses, and re--
ports. Prepare qualification documentation in the form of NRC auditable packages.
- Assure that necessary checklists and equipment evaluation-work sheets are prepared and approved.
Review / approve work done by consultants, GE, or the architect-engineer.
- Participate as a member .of Technical Review Com-mittee (TRC) in the NSSS EQ Program. g
- Resolve comments generated on plans and reports and provide recommended resolutions of equipment qualification issues.
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-- 14oriitor open' issues. ; f-m. -- Establish a program to provide documentation for the . development of a plant maintenance, surveil-lance, and replacement program for EQ related com-ponents.
Review of USNRC IE Bulletins / Notices to determine any impact on the EQ program and resolution of any recultant' discrepancies. In additicn, PSE&G's engineering personnel involved in EQ are responsible for-preparation and updating of_ this EQ Summary Report. This includes review and resolution of USNRC licensing concerns as they pertain to the EQ pro-gram. The completion, and continuation, of the Hope Creek Envi-ronmental Qualification effort has been re-assigned to site engineering personnel who will eventually become part of the PSE&G Nuclear Department. This transition of respon-sibility is in-process as of the date of this amendment and is expected to be complete prior to fuel load. All EQ work required during plant operation will be performed by the Nuclear Department. J
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IV. . REGULATORY COMPLIANCE-The.HCGS EQ effort for safety related electrical equipment (m .l located in-a harsh environment is required to comply.with
. Category;II of NUREG-0588, " Interim' Staff Position on En-vironmental Qualification of. Safety.Related Electrical Components"~ dated Decemb~er 1979 and.IEEE-323-1971 "IEEE Standa'rd for Qualifying Class 1E Equipment for Nuclear Power. Generating Stations". However,' the EQ program is at-tempting to meet, wherever possible, and qualify equipment to the Category I requirements of NUREG-0588 and IDEE-323-1974. In addition, the EQ program will conform to the r criteria of 10CFR50.49_ for safety related electrical equipment located in both harsh and mild environments.
For safety related mechanical equipment located in a harsh environment, the EQ Program establishes, via analysis, the
. qualified life of the components including proper required functionability before, during, and after.a DBA. This analysis is performed by identifying significant aging mechanisms within each_ mechanical component in accordance with-IEEE-627-1980, " Design Qualification of Safety' Sys-tems Equipment Used in Nuclear Power Generating Stations",
Section 4.4.1. This EQ program is designed to supplement, and, as such, neither replaces nor modifies compliance with other appli-cable; codes and standards prepared by ASME, AI'SC, ACI or Q. V. any other governing organization. Additionally, the safety
~
related mechanical components meet the sequential testing, seismic mounting configuration verification, functional assurance criteria, identification of aging mechanism's process, maintenance / surveillance interface requirements and other applicable criteria delineated in the ' Seismic' Qualification Review Team (SQRT) and the Pump and Valve Operability Review Team (PVORT) documentation. This overall EQ program effort includes, but is not limi- # ted to, conformance with the following as described in the PSAR: (a) ASME Section III, Class 2 Criteria.
-(b) IEEE Standard 344-1975 - " Recommended Prac-tices for Seismic Qualification of Class 1E Equipment" (c) IEEE Trial Use Standard 323-1971 - " General Guide for Qualifying Class 1E Electric Equip-ment for Nuclear Power Generating Stations" (d) IEEE Standard 383-1974 -
" Type Test of Class 1E Electric Cables, Field Splices, and Connec-tions for Nuclear Power Generating Stations" b'
v IV-1 " ~
(e) IEEE S tandard ' 382-1980 - " Type Test of Class 1E Electric Valve Operators"
~
(f)'IEEE 627-19 80 " Design Qualification of Saf-
'T ety Systems Equipment Used in Nuclear Power
) Generating Stations" (g) ANSI Standard N-278 "Self Operated and Power Operated Safety Related Valves Func-tional Specification Standard" (h) Regulatory Guide 1.148 " Functional Specifi-cation for Active Valve Assemblies -in Systems Important to Safety" (i) ~ NUREG.0800 " Standard Review Plan for the Re-view of Safety Analysis Reports for Nuclear
. Power Plants" 4
As is noted in- FSAR Section 3.11, the EQ program is also designed to be in conformance with the following 10CFR Ap-pendix A General Design Criteria and Regulatory Guides: O .[ The extent of compliance with these guide-lines / criteria is delineated in.the paren-thesized FSAR Chapters / Sections]. (a) General Design Criterion 1: Quality Standards and Records (Chapter 17)
/
) (b) General Design Criterion 4:
\_f Environmental and Missile Design Basis (Sections 3.5, 3.11).
(c) General Design Criterion 23: Protection System Failure Modes (Chapter 7) (d) General Design Criterion 50 Containment Design Rasis (Chapter 6) (e) Regulatory Guide 1.30 Quality Assurance Requirements for Instrumentation and Electrical Equipment (Chapter 7) (f) Regulatory Guide 1.33 Quality Assurance Program Requirements (Sections 1.8, 3.11) (g)' Regulatory Guide 1.63 Electrical Penetration Assemblies inContainment Structures for Light Water Cooled Nuclear Power Plants (Sections 1.8, 8.1.4.12) (h) Regulatory Guide 1.73 Qual i ficationTes ts_of Electr ical Valve Opera tors r^ Installed Inside the Containment of Nuclear Power (f); Plants (Sections 1.8, 3.11) IV-2
(i) R gulct ry Guida 1.89 Qualification of Clcss 1E Equipmsnt for Nuclear Power Plants (Sections 1.8, 3.11) (j) Regulatory Guide 1.97
- n. "
) Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Condi-tions During and Following an Accident (Section 1.8).
Additionally, concern about continued compliance with USNRC ini-tiated Bulletins, Circulars and Information Notices has resulted in the establishment of the following review process designed to analyze, identify and address the potential impact of these docu-ments as they pertain to the ongoing EQ program: PSE&G receives and tabulates the various USNRC Bulletins, Circu-lars and Information Notices and assigns Bechtel the task of per-forming a detailed review and analysis to determine potential HCGS impact. Bechtel-in turn maintains a historical tabulation of these docu-ments (commencing circa 1977) which pertain generically to USNRC BWR plant concerns. This computerized tabulation is continually updated to reflect the relevance of the particular document to HCGS. Bechtel perforns its initial analysis to determine applica-bility to HCGS. If it is determined that the specifics of a par-ticular document are not pertinent to HCGS, Bechtel prepares a draft response to the USNRC for PSE&G review stating the
. _ reason (s) why the Bulletin / Circular is not relevant. Upon PSE&G
( } concurrence, this response is transmitted to the USNRC and the j computerized table is updated to reflect the non applicability. For Notices where no formal USNRC response is required, the app-roved PSE&G reply is filed in the HCGS documentation for future reference. Again, the computerized tabulation is updated to re-flect the reply file location. For USNRC documents which require USNRC written response (Bulletins / Circulars) and which are determined to apply to HCGS, Bechtel performs its detailed analysis to determine the impact on ongoing HCGS licensing efforts. This analysis, along with any determined modification / changes required to comply with the concerns outlined in the Bulletins / Circulars, is then sent to PSE&G Engineering for additional detailed analysis, review, comment and ultimate concurrence. The final accepted response which addresses the course of action which will be taken at HCGS to meet the intent of the concerns outlined in the Bulletin / Circular is then transmitted to the USNRC for review. Upon final acceptance by the USNRC, which may include additional support documentation and/or meetings, the proposed modifications will be implemented at HCGS. The correspon-dence flow and the final resolution is again documente.1 on the computerized tabulation for future reference. N,.# IV-3
For USNRC '_ Notices which 'do ;not requiro - formal response to the-USNRC but aro ' determined to be . applicable to HCGS, this review
. path. is ' ident'ical to that outlined above except that no formal USNRC correspondence is transmitted. Therefore, the detailed .[ '
N analysis.and propo' sed modifications, if. required, are. performed "and the documentation flow path and resolution ( c) are' noted on
'the computerized tabulation.
In this_way, the ongoing EQ program is continually updated to re-flect the. response to EQ concerns contained in USNRC Bulle-tins / Circulars / Notices as they. pertain to HCGS. s u li IV-4
7 :- s V. QUALITY ASSURANCE PROVISIONS i V _Per the licensing requirements of 10CFR50, Appendix B, the
-Quality Assurance (QA) programs of both PSE&G and the archi-tect/eng ineering . firm, (Bechtel Power Corporation) for HCGS have been implemented _ in the establishment as well as the ongoing efforts of the EQ program. PSE&G's QA' commitments are described in detail in both Chapter 16 of the HCGS PSAR and in PSE&G's QA Manual. The applicable EQ sections of Bechtel's QA program are delineated in an appendix to its Engineering Procedure. Manual.
The purpose of the QA program is to ensure that the documen-tation required _to validate EQ safety related equipment's
~
proper performance over its qualified life is complete, ac-curate, traceable and auditable. This QA program effort in-cludes: Audit of the overall EQ program including the documented selection process for safety related classification. QA ensures that this documenta-tion is traceable, auditable and independently re-viewed and approved. Audit of the environmental design and accident analysis to ensure that the correct conditions and f( calculations were utilized and independently veri-(
) fled for correctness.
Review and approval of vendors to verify that they are qualified to supply the specified safety re-lated equipment. This. vendor approval may include vendor subcontractors and may involve vendor /sub-contractor site visits to review the in-house QA/QC program and evaluate the objective evidence of the vendor's ability to meet his QA/QC commit- ,- ments. Review and approval of testing laboratories used to perform EQ analysis and/or testing. Site visits to review in-house QA/QC programs, test f acili-ties, test instrumentation calibration documenta-tion, test setups, . data collection, analysis and storage, etc., are also performed. Ver .fication of proper procedures and practices for the shipment, storage and mounting of safety related equipment including proper signof fs of equipment receipt inspection, and proper signoff of pre-installation / operation tests. Level of storage in accordance with vendor and EQ require-g meets is verified. b V-1
r [. i' I Audit of the EQ file to verify that the required I, support documentation is available for review. [' ; This includes auditir.g of the vendor supplied de-- [ tailed operating, test, an'd m'aintenance manuals, noting particularly the highlighting of any EQ re-lated requirements, as well as verification of document control for any equipment replacement or modification. Audits to ensure proper review and signoff of ven-dor' qualification plans, test procedures and ana-lysis documentation. Witnessing of tests and sign-offs at prescheduled hold points is performed. Audits of plant . surveillance and maintenance pro-gram procedures to ensure compliance with vendor's recommendations and in-plant experience. Equip-ment repair and replacenent activities must be .. verified to be in strict accord with EQ require- 'l ments.over the qualified life of each piece of equipment. These EQ related programs are audited to verify periodic update based on IE Bulletins, vendor feedback, industry data and the plant's own experience with the equipment. Verification of a program to procure qualified spare parts and/or replacement equipment from ap-
./ ; proved vendors.
j Establishment of a documented process for QA iden-tified deficiency resolution. L g f h
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<, -VI. ENVIRONMENTAL CONDITIONS
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The development of .the abnormal / Design Basis Accident (DBA) environmental envelopes established for each harsh environ-mental area of the plant in which safety related electrical and mechanical equipment is located was based on accident scenarios described and analyzed in FSAR Chapter 15. In selecting an environmental envelope for any particular com-ponent, the'DBA which results in the worst case environ-
. mental extremes .( temperature, pressure, humidity, radia-tion). under which the component was required to perform its defined s'afety function was chosen. The analysis to deter-mine the environmental envelopes for the DBA's was perfor-med by Bechtel Power Corporation, the Architect / Engineer for HCGS.
The DBA's identified as causing worst case harsh environment conditions were: (1) Loss of Coolant Accident (LOCA) Inside Primary Containment (Drywell). (2) Main Steam Line Break Outside Primary Containment. (3) Instrument Line Break Outside Primary (~') . Containment. (_/- (4) Feedwater Line Break Outside Primary Con-tainment. (5) Control Rod Drop Accident. (6) Fuel Handling Accident Based on these analyses, the environmental conditions for the following plant areas were determined and the resultant parameter excursions. listed in Table 3.11-1 of the FSAR: (1) -Reactor Building (2) Turbine Duilding (3) Auxiliary Building (4) Intake structure (5) lInside Drywell (6) Inside Suppression Chamber Each table prcvides the following information: (1) Area description and elevation. (2) Normal operating environmental condi-tions (temperature, presssure, humidity, n ;- radiation). ('-') (3) Abnormal operating environmental condi-tions. VI-I n
(4) DBA environmental conditions (worst case). i The plant environmental conditions contained on these tables
,O have-been based on the following:
(1) Norsaal Cor.ditions - Plant design criteria or calculations for the heating, ventilat-ing, and radiation shielding design for HCGS. (2) Abnormal Conditions - Plant design criteria or calculations per-formed to bound the environment caused by such an event. Abnor-mal condition calcula-tions were performed for areas containing or affecting safety related equipment. (3) DBA Conditions - Plant design criteria or calculations of bounding environment for the DBA's identi-r] fied above. The safety related components are generally qualified.to these environmental envelopes with emphasis upon the DBA extremes. This. environmental envelope approach is conserva-tive in that it ensures that each safety related component located in a harsh environment which is required to perform c safety related function will perform its required safety function under each anticipated DBA condition. Exceptions are identified in FSAR Table 3.11-6 (included.in Section VII of this report). In addition to determining worst case environmental condi-tions, margin is normally added to each component's cualifi-cation program to both the qualification parameters and the analyzed time duration, to increase confidence in the compon-ents ability to perform its defined safety function and is in accordance with IEEE-323, IEEE-627, and NUREG 0588. For the duration of the DBA environmental conditions, two different time periods are used. For temperatures, press-ures and humidit-los, a conservative duration of 100 days was used with ambient conditions reached thereafter. For the post-accident integrated radiation exposures, a period of
'180 days was used. The systems and components required to
,, mitigate the consequences of the DBA are designed and tested
.e i
)
s. VI-2
;a
~ 1 Lto verify functional operability .und'er the DBA environmen-tal conditi'ons. For.some' specific components, the tempera- l 7'. :ture, pressure and/or. humidity conditions are reduced to- :
\ - > c l lcoversjust: their~ required functional . operation period ,fol-lowing the.DBA (case-by-case basis). Based upon the compon-
~
ent's functional requirement, the EQ. Program insures that , . inone of these-components will fail during the 100 day oeriod
- in_'a manner which would jeopardize a safety function.
Th'e:DBA radiation total integrated doses (TID) and dose rates were established in accordance with NUREG 0588. TID o, _levelsninside containment for the 180_ day period were based-
- - on release to containment of 100% of core noble gas inven-tory,:50% of core halogen inventory and 1% of core . solid c sfission inventory. Enveloping TID conditions outide contain-
~ " ment ' but '.inside the reactor building, based again on NUREG
- 0588, were assumed to be from two sources:
4 (1) After a DBA, 50% of core halogen inventory and.1% of; core' solid fission product inventory were in-troduced to the emergency core cooling system
, water.
o .i
- ( 2 )' After a DBA,' the airborne _ cloud has been released to, the reactor building from the primary contain- -
ment. The' TID inside'the reactor building', like that inside con-l L\ /n . tainment, was assumed for a 180 day period with saturation assumed thereafter. Dose rates were determined based on normally' anticipated radiation levels preceding, during and following the DBA. e Environmental Maps l ~ The , locations given on the component summary sheets for the & various defined' harsh environmental areas correspond to the. J .variousJareas of the plant shown in the attached harsh en- * ~
.vironment zone' maps (Figures 1 thru 9) and corresponding
'" Enveloping - Plant Environmental Conditions - Reactor Build-
.'ing",' Table 3.11-1a (9-'pages). The conditions listed are-
~those that would. exist in a specific area during normal,.ab-
' normal, and the most severe DBA conditions, y
'e L.
r.. VI-3 i
l i FSAR TABLE 3.11-la AND ENVIRONMENTAL ZONE MAPS l i l l l l 1
- f i
i l l I f r
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/
NOTES
- 1. ENVIRONMENTAL CONDITIONS FOR PUBLIC SERVICE ELECTRIC & GAS COMPANY ROOMS 4102 THRU 4118 SHOWN HOPE CREEK GENERATING STATION ABOVE APPEAR ON FSAR TABLE -
- 3. ll-la. (FIG. la)
[] 2. ROOM 4101 DOES NOT HAVE HARSH "
- EQUIPMENT QUALIFICATION V' ENVIRONMENT ESTABLISHED FOR HARSH ENVIRONMENT ENVIRONMENTAL QUALIFICATION IN ACCORDANCE WITH FSAR TABLE [ REACTOR BLDG. EL. 54' JOB NO. DRMNG NWBER 3EV
- 3. ll-la. (FIC. la)
FIG. 1 L
I d i i t i KIIB Feas i Meta 3.ll-le afv51DFIsai PLANT EBv' . " 03 38750 5 - Reacios settesse pues 4 of 9 l 1
, enraal escrettee Come&tions Ahmores! Cumf8ttame em Cemettlems prese Stup, 4 set nam Snee latees e aan prese, temp t set amm 5AER adCA 8etess .
1 area aseestystem a ans/ste, *r humidity este, ames, press Demy sueletty pelg er ammidity amme amte, ames, emma ammber me Smet/ Mas.'aee/let e amm/Inta ame/h med (t) pele *r ama/h&a (33 (3) ame/h ($,78 ame 44,78 I anestar aut148es, el M' , Omrs apter 1/-e.35 tie /78/6e/4e M/3e e.09 3.9s3 ama 813 ses/34 3-M min les See 1.33S est
- pagpsamme (33 elm , ell 6, j 4908, ette C- u...M 1.veufu 9.ne 3.3 9.133 m ile io./M 3-M a M.-M l 9. = = l j ream 4159 -
(33 (43 mm per 1/=0.3S 15t/04/73/4e M/38 10.0 3.Ss4 aca lla 100/38 3-30 mia les les S.989 3e8 reams 4114, 4107 (3) a
- het pump a a t/-e.3S 111/79/69/44 90/2e 10.0 3.S84 ag e 113 196/34 5-30 sia 346-M esa 100 9.08S See samme else, ell 3 (3) (4) f aClc m f/-8.3S 194/79/69/64 M/38 4.S 9.183 ata 113 500/30 3-30 sta M6-M maa See e.884 Me
! assus elle 485 443 i 3 Elast. eestemmat l/-e.3S =/194/73/48 90/2e 0.003S 0.053 ata les les/as 3-30 sta 148 See 7.09-9 30 i como ella, eles (3) Ols/em pump t/-e.35 =/05/74/40 90/2e 0.31 7.484 ata 114 900/30 >M ela let See 4.88S 4e0 e team ette tal segue estes 1/-4.31 -/193/104/44 90/38 0.01S S.3Ss3 maa 143 100/3e 3-M ela les 100 S.9a3 24 Sttaa veettbute 1/-8.35 =/104/-/48 90/20 0.0035 0.0s3 = = = 3-30 sta 148 l 41:3, ell? ES) l Dague emmeewtammt 1/-4.35 -/08/77/48 90/3e 0.108 3.See men les les/36 3-M maa MS-M m&a les 9.21 483 ) 4883 (3) tel i Ome/ses penny t/-e.3S -/95/74/4e De/3e e.31 7.4e4 men 114 tes/M 3-M ela les les 3.985 M7 ' ream ells (35 i les 3.688 Ml l 1 l i i ric. la l i Tie 03739W-a3 l N 3, le/05
N n ,
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& , N. T No7ar conmot CENTER ARGA W
~
h . ./- .
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14207{ M_ rrrro N, ' T i. .-
. . , \ . .; ,. .> .. ., ... ,, .
LVESTIBULE l+2:2.1 PASSAGE [+2t3] l , NOTES
- 1. ENVIRONMENTAL CONDITIONS FOR ROOMS PUBLICSERVICEELECTRIC&GASCOMPAE 4201 THRU 4219 SHOWN ABOVE APPEAR HOPE CREEK GENERATING STATION ON FSAR TABLE 3.11-la. (FIG. 2a) -
- 2. ROOMS 4220 AND 4221 HAVE HARSH I g\ ENVIRONMENTS ESTABLISHED FOR THE- *
(
- EQUIPMENT QUALIFICATION l
\ DRY WELL AND APPEAR IN FSAR TABLE HARSH ENVIRONMENT
^"
3.11-lf. REACTOR BUILDING EL. 77' JOB NO. ORAWING NUMBER REV FIG. 2
- s i
I
I i . HOW PpAS Theta 3.tl-te ! pese 3 of 9 eNWB8aPRIIG PEAIIT SUVI ADMat. CMEtim - MAC10D Wa&S350 ? l ahnerest come1etens ahm Come44$mme norme1 eperettan come4tsene j gens sees lategr 4 ami erese, M t est amm 8 6 BAEa toteer prese 3mmy, t een seen, i ' or mem848ty amte, tese, Prose temp mentatty potg er mentatty ames mate, man / tela, 2 area esosttytlen a mese summes Ise smet/ team /aee/ tate mas /tain med/h and (Il pale *r sama/Into (33 (39 and/h 45,75 med te,78 I anester settelee, . j et ??' 90/M e.0835 0.053 ata 134 100/34 3- M mis See aaCe pump t/-a.35 -/93/03/40 (38 See 1.359 M3
- remum 430s, SS/M e.0035 0.083 ata 534 les/20 S-M mia 344 j ants a l/-4.3S =/93/03/40 (3) 100 9.21 23
- tamm east 10.0 3.Se4 ata 113 100/24 'S-30 mia MS-Se sta IME m t/-0.3S 181/79/69/40 98/38 443 100 9.teS see 839 j
temmo 430s, 4314 90/2e 8.003S 0.883 ate stS 19e/20 3-30 mie 14e j esteemete test 9/-4.33 -/03/77/40 (3) See 1.20 asa j samme 4390, eats 90/20 0.0035 8.383 ate see 100/3e 3-30 mia 14e acuter emetral t/-0.35 -/17/M/40 83: les 1.358 M3 t j eenter 4355 i tee /3e 3- M m8e see 4 Inster emetrel t/-4.3S -/07/79/40 M/30 0.003S 8.esa ata tle see 3.389 M3 ' i lll j eenter 4Mt et M m i 3-se sta 14e : 4 9e/24 e.e835 a.es3 ata 1e7 tes/se ,389 j eenter sentret 1/-4.35 -/76/67/4e (3) toe t tes l t eenter 4310 90/M e.8839 0.e53 ata IN 100/3e 3-M mia see Cm pg 1/-4.35 =/97/se/44 (33 See 3.388 M3 ream 4303 et M h
- J 0.0035 0.883 ata Sto 100/3e 3-M m&m les Omtrider 4303 t/-4.3S -/03/77/4e 94/38 838 lee 3.184 est S.383 - - - 3- M als Me-33 mia insetitute 4304 1/-4.35 =/110/-/43 90/28 e.etS 438 tel see 3.ese MS >
e.esa - 3-M sin fee Possese 4307, I/-o.35 -/184/-/44 to/3e e. seat - - See 3.e50 Est (3) esetS S.383 - - - S-3e sta 340-30 sta westthole 4306, t/-4.25 -/115/-/44 90/30 (33 tel tee 3. ewe MS
* /
e.esa ata 19e 188/36 3-30 mia lee Instar sentret 9/-e.35 -/77/70/44 Se/M 8.0435 tes 3.491 est (38 1 0.0835 0.083 ata lle les/3e 3-30 mia lee Corr 8 der 4316 t/-4.35 =/03/77/48 90/3e (38 tes 3.tm Mt S.M3 - - - 3-Se =ta See- M =*= 1 s/-e. ts -/i44/-/4e to/3e e.e:S see 3.tse - 3mi
. tie.te 43i? tu eel ,
l FIG. 2a l ,,,,,,, , ,, ,,,,,
O o TABLE 3.1l-1h EHWELDPI3E3 RADIAT1000 COIIDETIORIS Il8&IDE Pales &RY CCIITAlthasas? Radiation operating Does Design Basie Event Integrated Domesa,as g nrnat'8 Twee matesa3 2Xas DOES.ggiaca_aa naarmal ggg,,, t Dryeell, imoide Gaema 2.3 y 10* IACA 8.1 x le* hiological shield Neutron 8.8 m lyn (e8 3.1 x 10' (*a g meta (*a --- outside biological shield some 1 Gamma 52.3 x 10* IDCA $8.I z 10* 58.8 x 108 (e8 53.1 x lee (*3 g j Above core tenutrea - - - - Beta (*8 Gamma 54.8 IACA 1.9 x 10' ) Some 2 ges 4.3 x les top g
- Core region 12 t.eostron eta <*8 Gamma 52.3 x 10* IOCA 58.1 x 10*
Some 3 (en 53.1 x 10* (*8 ! under vessel seenstrom 54.8 x 10s g ! Beta c*a -- 50.0 IDCA 1.4 x to' Bone 4 Gamma (88 4.3 x 10* (*8 I ! temas recircesisties seestron ' 512 --- i Beta (*8 50.0 IaCA 1.4 x 10* some 5 Gamma (s8 4.3 x 108 (*8 l I > 15 feet from recir- Neastrom 512 culation meta (** l Gamma 50 LOCA 5.1 x 10* at 48 h 1.8 x 10' 6. 3 x 10* l Rome & 4.3 m 104
- Seappressica chasJaar Monstrom 512
(*3 1.5 x 10* at 48 h 3. 5 x 108 l Beta t a a The enit of does rate la Rade/hr, The unit of does is made ca3 asotaal integrated does is calculated for 40 years ga s Das does rate is the dose rate immediately follaerlag the DBE, unless otherwise specified. (** The beta does is not significant compared to othere during normal operation. t i
- asa Gamma 1.9 x la' (airbornel i
1.9 x 10e (plateout at 1 14 Beta 3.1 x 108 (airborne) 1.1 x 107 (plateout at I hl 468 Gemma 2.6 x 10' (aa rtorme) g teta 3.4 x 10* 9.S x 108 gplateouti (41rterne) f t G u RE 2b 6.7 x 108 (plateout) (F8 See Fagure 3.11-1 f or areas ameace prtaasy contaanmant. g
luo33~ut.5, Rev. U
/
e. Table 5 () Environmental, Conditions Inside Primary Containment for the Design Basis Event Drywell Temperature Pressure Humidity Time (Decrees F) (psio) (%) l 0 - 20 sec 340 0 - 62 100 l 20 see - 5 min' 340 62 100 5 min - 3 hr 340 - 40 100 3 - 6 hr 320 40 100 6 - 24 hr 250' 25 100 - , 1 - 4 days 200 25 1'00 4 4- days 200 10 100 l 10 0 O i . FIG. 2c h e e. e
1 I (RPT BREAKER RM1 5 N L41LJ
-m ELEV MACH RM AIRLOCK l93341
[43 t31
/
[ CORRIDOR CRO MASTER control g CORRIDOR y l43og] MCI VE ST. _- _, . L43t l I ,_ MoToK CONT STEAM s 7e*wfg"gg CTR AREA- -
% '.'PERS.4 _l- f TUMNEL \
- k SS + I43:(>l ,
l3, NA 8 DRY WELT. I4338 l--.
- w -
' -RCic PIPE CHASE [43 q ]
ACCESS WASM *; o6w M -'
/-l , ,
ARE A f, - I433o1 g. ARE%33g a p eto pro PtPE CHASEW [4329) cRD f,/f-
.[ , d '
g*
, 1 '
L No$T p- .
& ~f ' .t NeNcpk ASE i, ., o ToRAsf f
~
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=
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. ih. '
h REMcMAt- AjgtocK'l4324l . EcutP (~] ( REPAip - AlRLoCK ,,;'g , V AREA 'ac i k- [43g3] 1 I+3 trol t
,, [lh #M i
S AC S 14E AT 4 SACS HEAT EXCHAMCmER S d l k EXCH AN C2ER S k PUMPS R M , PUMPS RM I. = [43091 f;, I4307_) y* 1 _. i NOTE PUBLIC SERVICE ELECTRIC & GAS COMPANY HOPE CREEK CENERATING STATION
- 1. ENVIRONMENTAL CONDITIONS FOR ROOMS ,,
4301, 4303 TRRU 4305, 4307, 4309 (3 THRU 4311, 4313, 4315 THRU 4324 AND 4326 THRU 4334 SHOWN ABOVE APPEAR
,,, EQUIPMENT QUALIFICATION ON FSAR TABLE 3.ll-la (FIG 3a & 3b). ,,,, HARSH ENVIRONMENT
,,y REACTOR BUILDING EL. 102' JOB NO. DRAWING NUMBER REV FIG. 3
% g
/
1 - V e e I meus reas Tasta 3.18-le WrvtIDPING PEAirr asFIpolemptAL CGet?Ious - meACTom BellatuG pese 3 of 9 esorme1 cyeratine Coneitsome abnotme! Comeattone ogs Good 1ttone reees hay, t Son nos Does lategt t met press, Tuey 4 met sees RACA SACA 3atoes Area Demeription 6 pase/esta, *F hidity mate, Sees, Frees trop mism L48 t y pole *F Deatetty Base hete, Sese, ennen seienhet up het/stsa/ Ave /pla seos/tein med/h med 113 pole *f gese/tain tal (23 med/h (5,73 and E6.78 toector Bel 14 tag, el 103' etsam tiemmet 1/-0.35 -/97/se/46 9e/2e 18.e 3.3s6 ata 129 100/2e 10-30 min 34&30 min See gamune 5.9s? 3m? 4314 (33 141 bote 3.18e let ! north pipe chase 1/-a.3S -/103/94/4e 90/28 0.715 3. Sal Ata 129 100/20 b34 sta 34h 30 sta . See 8.18S ese 4329 (31 tel seeth pipe chose 1/-0.3S -/91/01/40 90/20 1.0 1.3s6 Ata 119 Ste/20 3-30 sta 349-Se ela 100 1.135 436 4331 (31 tel apCI pipe chose l/-0.25 -/71/52/40 90/20 3.5 9.153 Ata 104 100/20 S-30 ala 340-30 ala See 1.754 ese 4331 63) (4) 34 h l acIC pipe chase 1/-0.35 -/71/62/40 90/20 1.5 6.SE3 Ata 105 100/20 3-30 sia 340-30 sie 100 3.5s4 ese 4319 (3) tel 34 h i peroommet 6 ogstp- 1/-e.35 -/92/02/48 90/20 ' 0.002S 0.052 Ata 115 100/20 Flo sta t4e lec 1.381 est meet accese esse (3) 4333, 4331 mostren amantestag 1/-a.35 -/99/90/44 90/20 250.0 1.134 Ata 118 198/20 3-30 min 140 100 1.3s3 3s3 ersten 4318 (33 CBD hydreolic 1/-0.25 -/92/02/40 90/20 0.0025 8.es2 Ata IIS 100/30 3-30 min 140 100 0.4s3 ese 4333 (3) et 36 h Cum mester contgel 1/-0.2S =/92/02/40 90/20 0.0025 0.832 Ata IIS 100/3s 3-30 ala les 100 9.630 483 ease 6 corriest 4317, 4355 ' asehdemie aree 1/-0.25 =/92/02/40 90/20 0.0825 8.002 Ata 115 190/2e F 3e ein tot its 3.235 esp 4333 (3) Beastpoemt ett lect 1/-0.25 =/194/-/40 90/20 0.002S 8.083 - - - 3-30 als les 100 1.5s 3 MI 4304, 4305, 4313 831 Isotar seatsel 1/-0.25 -/91/71/40 90/20 0.0025 0.083 Ata 133 100/3e b3e ela 140 100 1.Se See seater elle 138 Inster sentret 1/-a.25 -/05/74/4e 90/20 0.0e25 a.esa Ata 11S 194/28 3-30 sta 140 10e 4.S32 ans center 4343 (3) 90/20 0.002S 3.052 95 - 194/20 3-30 min les See 3.7m1 332 SACS piamp a sE 1/-a.25 -/94/07/40 Ata rems 4347, 4309 tal I
~
l FIG. 3a l
s .
. v 4
I 1 aces rena . Theta 3.tl-le . DeuB4artuG PLANT BfFlecuumpr48. CDIDITI4But = BanC70s 3s383385 Does 4 et e
, earmen oporetian Omndittems abnormal comenttema ens cameitlese prese %, e met stam seen Inteer a met Mees, temp 4 set Amm 8 m 54:4 Setegs ease sames8ptlam & Ilms/ tale. *F Sme&4 tty Rete, Dese, Prose Samp M ity pelg eF Sum 64&t3' Does Rote, Game,
- seem member see Seet/ team /heeAlta atmeMlla Ras /h And (t) petg *f Olan/ttia 331 (3) Rae/h (S,1) Ama te,7) !
a Cap sanovel & 1/-a.35 ./194/-/40 se/20 0.0035 8.083 . . . 3-M sia See repels 43M g33 900 e.ast 4s3 I Cze etersee 4333 t/-4.3S =/304/-/40 M/20 0.10 3.Ss4 . . . 3-M mia 144 (3) See S. Set 4s3 weetthole a eles I/=0.3S =/804/=/44 M/3e 8.0035 e.083 . . . 3-34 mia 14e sembles team east, (33 See 1.Sa3 Mt 43M Dryuell amasse t/-0.35 ./804/-/40 N/34 3.S e.esS . . . 3-M ata les team 43M (31 See samme I.es? 3s? ' heta 3.tes see art breaker ream 1/=0.35 =/01/17/40 N/20 0.0435 e.esa ata 133 100/20 3-M mia tes 4Mt (33 See 9.58-3 Mt spelpment ett 1/-4.35 -/04/14/44 M/3e e.0035 0.083 Ata 187 100/30 3-M sin les Root,4333 (33 tee e.sas ens stolpment ett 1/-0.35 ./984/-/4e M/20 0.003S 0.083 . . . 3-M ata fee best, 4334 (35 les e.sae 4s3 Cup byerem18e 9/-4.3S =/03/03/44 M/20 0.83 1.083 Ata st$ 100/34 43M t.nel 4.s . l FIC. 3b etra tisw.e e n m . .e ce
INSTR G AS COMPRESSOR NH EM I44121 I_T (j I CENTRAL ALARM INSTR G AS COMPUTER STATION l++ GI coM P R E SS O R,, I+4181 ~ RM 144t31 "" g7
~
+ c . y.~ .7.. .;., ,
CoMPuTERg I44t91 [Iq4
.., ( w=)
q"I j ; p Mo w ir.ein c,.
~
i 1 N L n g' /g, (cosmontcGi AREA W4151-
// }.pk.l\P ';
[ EQUIP AREg l IMOII ht i ,\ g [ pgys UNtT REclRC ARE A t'.- #, __ @ \\V. M R4 1] 0 M __PtPE CH ASE O 144o21 P A {""IPn'
' -=
~
I=r DNREAcToR
-- n WTR
.- ?
t .. - 7 _-
+
c.u. RE Ct RC. s m . PUMP RM
? FRVS UNtTS AREA REclRC\p':'..
.f / N
, - 144031
.. . ? q DCoRRIDOR
~" 14 41o1 M. l' 144oM NI i
t/ d- .J REACTOR WTR
' C.U. RECtRC PMP RM 144os 1 l
[V f e
-RE Acto R
\ . WTR C.U.
BAC KWASH TRANSFER j-COMPRESSOR 8 ELECTRtc At. EQUIf .N REACTOR. p STEAM VEENT, , AREA [44cgl WTR C.U. . L 14409]
- BACKWASH
{ M# RECEtVIN 4 TANK & f INSTR RACK 1440-)I NOTES
- 1. ENVIRONMENTAL CONDITIONS FOR ROOMS PUBLIC SERVICE ELECTRIC & GAS COMPANY 4401 THRU 4413, 4415,4416, 4418 & 4419 HOPE CREEK GENERATING STATION SHOWN'ABOVE APPEAR ON FSAR. TABLE .
3.11-la. (FIC. 4a) CT " V EQUIPMENT QUALIFICATION
,, HARSH ENVIRONMENT
- o. . REACTOR BUILDING EL. 132' JOB NO. DRAWING NUMBER REV FIG. 4
n f%
) I
,1 . / %]
MCCS FSAR TAht2 3.13-13
/
ENVEIDFIha P!Aarr ENVinOt#W3sTAL COMOITIOles - REACTOR DUItattfC Page 5 of 9 anormal Operating Conditione Abnormal Condit$ona OsE Conditione Press hop, % Re1 Mas tese Integg 8 Re1 Press, Asse Description 6 seas / Min, hop 9 Re1 Mas IACA I4CA Integt OF Numidity Rate, Done, Pr esa Temp snos number seg het/ Mas / Ave / Min Humidity pelg 0F Rumidity Doce Rate, Dose, seem/ Min Rad /h Rad (1) peig Of Mas / Min (2) (2) Red /h (5.7) Red (6,76 - Beactot Building, wt 112* amCU rectre pep t/-0. 5 -/104/=/40 90/20 9J.0 1.1E6 ' - - - 6-30 min 250-30 min sous 4403. 4405 (3) (4) 100 3.51-2 2tl susQs backweek pep 1/-0.25 -/104/-/40 90/20 55.0 1.1E6 - - - 6-30 min 256-30 men some 4406 (3) (4) 100 1.55-2 2El BasCU bacteach I/-0.25 */104/-/40 90/20 1.19E2 4.2E7 sec6ss tant 4407
- 6-30 min 250-30 min (3) (4) 100 1.55-2 2EI south pipe chase 1/-0.25 -/91/79/40 90/20 09.0 2.0E6 Ata 119 100/20 6-30 min 4402 340-30 min (3) (4) 100 S.4E2 GE4 FWV3 rectrc 4418, 1/-0.25 */B0/69/40 at 36 h 90/20 0.0025 S.9E2 Ate 110 100/20 0 14 0 4498 100 2.tE3 256 squipmost area 1/-0.25 -/76/65/40 et le days 90/20 0.0025 0.8E2 Ata 105 100/20 3-30 min tot 4408 (3) 100 9.55-2 2El Cossadot 4464 t/-0.25 -/964/-/40 90/20 0.0025 8.8E2 Ate 105 100/20 3-30 min 148 (3) 100 1.5E-2 251 l Conoseeast a elect 1/-0.25 -/104/-40 90/20 0.0025 8.eE2 ogtap sata 4400 Ate 105 100/20 3-30 min 148 (3) 100 4.7E-2 7El Instrument gas at 10 days f I/-0.25 -80/67/40 90/20 0.0025 0.8E2 Ata llo 100/20 3-30 min 140 compestaot scom 4412, 4413 (3) 100 2.0E0 3E3 at 10 days entsancs to 1/-0.25 -/88/75/40 90/20 0.0025 0.0E2 ttsam tent 4409 Ato 100 100/20 3-30 min 340-30 min (3) (4) 100 2.0E; 653 Caxtral Elare .25/-0.25 -/104/-/40 90/20 0.0005 2E2 - -
Etttlon 4416 sumstosing and ccie- .25/-0.23 -/104/-/40 90/20 0.0005 2E2 - - munication area 4415 Computer Room .25/-0.25y404/-/40 90/20 0.0005 2E2 - - - 4418, 4419 l Fig.4a l Tl00J729V-a
, AstEsststEBr? 2,10/83
DOCUIM ENT ' STORAGE RM 1451GI
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\ STEAM 70MME' L HVAC EQUIP. RM 14 518]
..~ ,
g A\RLoCKI45101 CONFERENCE . , _. j 8
,I ,7 ELEc Equip GENERAL '
C//' h e
'= a AKEA I45ol WoRtc AREA' "~
hg$ok gg I45341 .y I45i 31 g} Q},i V ( g s
- J .REACTom WTR
,' FRYS VENT . C.U. ElLTER
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UN LT" RM #- l45111 I : 1
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' F] DEMIN Hot.OlMG PUMP- RM 4
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. L 5- i+5os 1
- FRVS UHtT RM VENTj: . . _
k un. LN_**?
- 1._.
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-REACT oR, WT R c.u. FIGER l+ss 21 "'*" i ! N ***'N'H***
T /j . ,p g PMP RM l45o2.1
. i
/[ (t 'PASSAGiEWAY 14sosi p- \ '.
q( N -PIPE CHASE I; I 145o5]
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C o R RIDO R (.Qg 145061 'REACTog vlTg
\
i t C.U. HEAT
, maw EXCR RM l
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g PIPE CHASE I45o61 145091 , i
! - _ . . . . . _ ppo e _. . _ . . . . . . _ . . . _ .
NOTE PUBLIC SERVICE ELECTRIC & GAS COMPANY
- 1. ENVIRONMENTAL CONDITIONS FOR ROOMS HOPE CREEK CENERATING STATION 4501 THRU 4506 AND 4508 THRU 4513, 4515, 4516 AND 4518 SHOWN ABOVE
, O APPEAR ON FSAR TABLE 3.ll-la.
(FIG. 5a) m am EQUIP M QUALIFICATION HARSH ENVIRONMENT l casa REACTOR BUILDING EL. 145'
)j JOB NO. DRAWING NUMBER REV FIG. 5 I
['N /D %
.e BL48 PSAR TAata 3.ts-le 3svst4PIIIC PIAspf EfWI A0usertAL anettIONS - BSAC10h DOItatuG tese 6 e4 9 aosman 00erettae canditione abnesman Conditione ces condittene Psees her, e Amt Igen sees Intogs e me! M oos, Tony e Sol Itas 8dE4 laCA !stees Asee Demogiptiae 6 lens /Itin, *P h idity hete, Does, Press temp Ehmidity pelg *F . Bieele t ty Snee Sete, tems, amen sheter use Smet/saae/ hee /ttle enan/tsin had/h and (Il pele *f seam /tain (33 123 ame/h (S,75 med 44.73 anecter mistletas, el 14S'
-,24 5., 2 .ta 148 . .,30 . 3,- . ... 304-34 ... 4. 0. 3 4 m .506 t,-e.3S -,8,0, ,.4 (3) tel et M t 1
*/98/19/44 90/30 3.004 194/28 8 34 ele 350-34 eln 800 e.4e3 ese Seath pipe othese 9/*4.2$ 55.8 Ata lit l
eSel (31 lei et Mb Cleomesp f!!tes 6 1/-G e25 -/94/03/44 94/20 e.M25 e.es2 ata 126 100/24 6-30 min 3SS-38 els 800 8.Sa-3 act hetow W ream (St tel 4S42, 4S43 Cett& der 4500 t/-4.25 -/94/03/40 90/24 8.H25 0.052 Ata 124 194/20 0 148 100 4.75-3 751 le st le days meet pipe steme 1/-a.35 -/94/03/44 90/20 4.015 S.SE3 htm 124 800/2e e lee les e.esa ese 4549 et M b Cloctsical op tp- 1/-0.2S =/94/83/40 90/20 4.H 21 e.es2 Ata 136 let/3e e 148 - les 5.38-3 758 meat etee elet et le dare
- f.1steet elle 1/-0.25 -/104/98/44 90/20 0.0025 0.083 4ta 123 100/24 0 140 See t.SS-3 act e let see 1.484 983 FWwe esat team 1/~e.25 -/lEJ/98/44 90/20 0.0425 e.es2 Ata las lH/34 et le days 3
4589. 4592 0.0435 0.053 122 1M/34 e 140 IH semple etetlen l/-4.35 =/184/98/48 90/20 Ata seem ella . 844/3e e let les Generet seek t/-6.35 -/70/73/68 90/24 e.0425 0.3s3 Ata let stee elle 4.082 95 198/3e 0 144 See conference seen 4 SIS 1/-4.25 -/78/73/68 90/28 e.Hal Ata See - =
-/78/73/60 4.ee25 0.082 Ata 99 194/3e e les F_ t storece 1/-0.35 90/20 ream 4516 0.303 104/20 0 140 See -
ettiseelt ell? t/-4.31 -/78/73/68 90/20 0.0425 Ata 195 tsee elle svaC duct este 1/-e.2$ -/.44/94/68 94/24 0.0025 8,es2 Ata 149 194/28 e toe tee space e lee See 0.4e2 ee4 Cossides 4Se4 I/-0.3% -/94/03/4e 90/28 0.0425 8.883 Ata *136 194/2e et 34 h 758427299-3 asenempt 3. 58/03 4 FIG. Sa
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RE actor, WTR c.u. ! FILTER.4DEMINERALIZ.ER 1 ARE A l46Eol l+62 Il s .: i
)
=
Y._.fy .. l l K SPENT FUELI, FRVS RM Pool l4sitj\ FRVS RM l+6151 1 GAMMA SCWg [46141 j. -NCC AREA DETEcTot ' - p N 146oll ARE A 1461314 CASK t.oADlHS -> p ,coNTAlHMENT
. -cN . w.-:s . ,-
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1 % IlI -'.' PRE- PORG E
,, .. : . l . : s:. .. . CLEAMuP RM
' ._ 7 VAULT 146tolyN ;- -
.g 1ee 4 /' I 4 031 FUEL Pool- N Co o t.. PuM f' h
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- -RECoMBINER l ' Alt,EA WE?N$ l,, ' ~ -l'f g ' # ' *'
146091 &" N.h. k EqutP AREA *
)L -REcoMBiblER hs)
-' FOEL Poot , (Mec) AREA l46041 coot. PUMP .
146o51 146261 /** E"'D Il E l a
*- STANDBY FUEL Po e t. ,
HEAT EXcH ' 'I i Liquio f,%- T- . CONT ft OL I46171 AREA g FUEL Pool
; w .my WATER. Sothe 14606l FOEL Pool / ARE.A [46071 HE AT EXCH l 14628] 1 l
. I i 1 i i i
NOTE PUBLIC SERVICE ELECTRIC & GAS COMPANY
- 1. ENVIRONMENTAL CONDITIONS FOR HOPE CREEK GENERATING STATION ROOMS 4601 THRU 4615, 4620, 4621 AND 4625 THRU 4628 SHOWN (f.)
-V ABOVE APPEAR ON FSAR TABLE 3.11-la. (FIG. 6a & 6b) [ EQUIPMENT QUAI,IFICATION a,en HARSH ENVIRONMENT oars REACTOR BUILDING EL. 162' JOB NO. DRAWING NUMBER REV FIG. 6
. . _ . . n . > , -. .
~ ,, _
/ N.
v ). SICGs FSaa TastA 3.11-te 6 ElfvstDPleG PLAast 38WImoisuirrhL ConDITIout - MACEOR sultalme page ? et g I moree& oyeaetine Ouedatione asmermeI conditione car Come4 atone { press Temp, t nel sans Does latees 4 Del prose. Tem 7 4 son men taCA taCA 8etess Asee Deess8pties 6 Ihms/Inte, ey , geogggty Rete, Does, 'Pr ese temp munnetty pelg *r Bear.te t t y tumee hete. lees.
. ames alumber 1sy Seat /thes/ Ave /bsta sens/Islo had/h had (Il pole 4 , 8f pens /ttin 13) ' (23 med/h it.1l Ame 44.I) -
meester Soldies. >
'p el 143' 6 170' Game seem 1/-e.3S -/tM/93/40 N/3e e.eet 3.553 Ata 199 100/20 - e 14e See 1.5s-3 3mt detes.- ~ , , ,
4413
/
Cast leedlee 1/-e.35 -/tH/-/4e M/30 0.04 3.See - - - 8 j 144 See t.Sa-3 apt 4 at le doye eroe 44tt r e Castelement pre- 1/-e.35 -/194/91/48 M/30 0.te 3.?se = = - .O e les 1M 4.est Ts3 purge steamey se t / 4ee3 M/3e e.M35 0.e83 Ata 134 100/36 e 140 let 3.338 ase inster emntrol 1/-G.3S -/101/09/40 conter 4404 et le dare , ee.1 v-..a -/iun4/4. Sene S.Ma 8.en - ist iM/a e. iM i.e . . .n M. l i Bacal 4463,4404 et Mh M/34 0.002S e.esa ata les tee /36 e 14e see 3.ts3 amt Pues unite 4415, 1/-e.25 -/03/13/40 , 4437 i, i ,t q
'/ at n dare
'i . S.Sa-t oss Corriest 440s 1/-e.25 */tM/93/46 M/20 0.e435 O.tal #Ata 199 100/30 e 144 ( tes
. / < et 34 h seu rest vault 1/-e.35 =/te4/98/46 90/3e e.te 3.534 -
;- - e let see 5.Ss-3 3s9 use '
^ j j >
8.58-3
<0 14e lee 381 Ceek leedles etee 1/-0.25 =/104/95/40 N/3e S.te 3.584 = = - . '
4419
-/ tee /93/40 3.001 3.583 Ata 199 100/3e e les toe 8.55-3 3mt Gamme scan 1/ 0.3S N/3e o ectrentee se ,
,/
4468 /.
%l ass spent teet poet s/~e.35 -/tesiSt/4e 9e/3e ; e.se35 s.ea7 5 - - -
4:. ee see toe t.Ss-3 esta ; j ,. amates et opent tuon pee! 4413 s/-o.35 -/213/935/6e see ~3.et 4 e 9.este - - d [. e tee see t.Sm.3 aus
)
e see See t.Ss-3 'MI spent tool punt 9/-o.35 . =/313/935/40 See 3.0734 1.787 - - -
# +
gate 4613
- , e t.e1 t/-.. n -/iei/91/.. Not . .. n e..n .t. 134 #
i 1M/3e .. , 10 IM ..-3 et Mh M4 i I j centes. detS ! tim 3 3w-s .. FIG. 6a' Asummamer 3. te/H
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. K seem $ses 3/-0.35 -/tes/st/se ge/3e e.M35 e.eg3 ag, g38 888/38 lee 8 les e.98-3 m setCW F/s to 9/-a.3S -/lH /98/44 9e/38 7.383 3.sas Ata 133 les/3e s.7-30 sta 233-M esa feae, esal see t.Se-3 amt (3) - 143
} Fuel post emellas 1/-6.39 -/989/93/48 M/30 e.85. 5.384 Ata 819 tes/M e . 140 see ymmy team 4.Sm.3 at esas, M M .. j ,., e m. .t. v-e.3S -/ieu,vM M/M e. Mas .. 3 Ma i33 tee /M e its i.e . pmot 4833 i.S 3 Mt t setten of Styos 9/-4.3S -/885/-/4e See le 3.335 Me 19.3 ses/M e les les 1.5s.3 at espaseter poet hetpoet M t/-4.35 */IN/93/4e ge/3. e.S 8. 85 Ata les IN/3e 3 358-M mie IM l.5e-3 at seen esaf, Mae gg, , sestatten estee s/-8.35 -/198/9e/40 90/3e 8.0035 ..esa Ata 133 ses/3e e toe we e,yg.3 gg I
'= "3* ;
= 1. de,e FWUS tectre s/-8.3S */IN/98/4e M/3e e.es35 ..e33 Ata See e see les/M tes 3.553 38 utte seen sets, 43*e et te days l
Fuel past mates 1/-e.35 -/lN/95/4e M/3. 4.444 S.3804 Ata 133 104/34 e les im 3.5e-3 at mostlin aree Ges? l ,
- Weam Ma e. . ..e.3 ,,,,, ,,e 1
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! FIG. 6b 1 q eenest, m e 3* M/88
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N I FRVS RM I"'7 I FFNS RM ! 14 6161 Y~ i sbv
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\
SPENT 1 l FUEL Po ot . . _ . ..
/ EPA tor f4
- sa SToR PoOt. '~
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1%2.3] _,
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]* ELECTRIC AL ACCESS ARE A i"j I4618] g
*pPF- [ I%i91
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1 l . F I NOTE PUBLIC SERVICE ELECTRIC & GAS COMPANY HOPE CREEK GENERATING STATION
- 1. ENVIRONMENTAL CONDITIONS FOR ROOMS 4616 THRU 4619,
,O-(,) ~
AND 4623 SHOWN ABOVE APPEAR ON FSAR TABLE 3.ll-la. *
- EQUIPMENT QUALIFICATION ,
(FIG. 7a & 7b) HARSH ENVIRONMENT
'[] REACTOR BUILDING EL.178'-6" JOS NO. DRAWING NUMBER REV FIC. 7 ,
1 P% :&
.l ' s
( 'V' j . . NCCe FEAR Thele 3.ll-le
. aufwstarteG PEANF BetIMAL CouBITHese - REAC9am egItaisus p.g. y ,g ,
earmet Operaties Onnettleae Ahnesee! Ceeditiene Det Coasttlene psees 1eep, 4 set sees Deee integt 4 Bel psees. Temp t set men nach Asee Deactlptiae e sees /sein. *r Dwete tt y Rete. Dese. Press Deep Nuoldity Delg #F Buel44ty Sees hete. taca intege Sees. m tsunbeg me Test / tees / nee / tela seas / tete had/h Red (13 pelg - *f gems /Isla (23 (3) med/h 41 ?)' Red 44.18 meector tendtag, at 863* 6 17e' Camme scan 1/=0.39 -/196/93/4e Se/3e 8.001 3.333 Ata sit 100/2e e les les 8.St-3 3st detector esse 4443 Coat needing 1/-e.35 -/194/-/48 98/3e e.te 3.534 - - - 0 140 tee 1.30 3 3g3 ease 44tt et le days Contalasment pre- t/-a.35 -/184/99/40 90/3e 0.te 3.S34 - - - e- les les 3.333 933 posgo cleaney se 4603 . sester sentset 1/-e.35 -/101/09/4e 90/2e e.043$ e.es3 Ata 134 tee /3e e les see 3.3st 3t4 contes 46el at le days ase m iner Ipeet t/-0.3S =/194/74/4e 94/20 0.003S 8.033 Ata let 100/3e e les see 0.4g3 ese , facAl see3.46e4 et Hh i = Fees matte estS. t/-0.35 -/83/73/4e 9e/3e e.ee25 8.es3 Ata see les/3e e les See 3.ts 3es l 4437 et to dayo j corrides 4000 t/-e.35 -/100/13/4e 90/30 0.003S e.es2 ate $19 tee /38 e les les S.Se-t 4el j et 3e b
- .e. , met esen. i/-..n -/t.4/9i/4. 9./n e. . 3.u. - - - e i.e t 4.u 3 al Cast leeting stee 1/-9.35 -/104/91/4e 90/20 e.te 3.Ss4 - - - 0 149 les t.Sc.3 3st 4415 I
i Geese aces t/-e.3S -/tH/93/4e 90/20 e.003 3.533 Ate 119 les/3e e les See 1.53-3 3e1
- slectsenice to j ues I spent feet poel 1/-e.3S -/194/91/40 9e/20 0.eG3S 0.es3 - = = 0 14e les I.Sc.3 389 44 3 I
settaa of opent s/-a.35 -/313/135/se 100 3.07 4 9.este - - - e see see S.Sc.3 3el f feel pool 4413 speet toen poet s/-a.35 -/312/93S/6e les 3.0734 9.731 - - - e 14e lee t.Sc.3 3ct gets 4613 e.te, ca.t.es i/... n ./ 9/91/4. 9./n . . .. n ..=3 .te su te./n . 34. lee 0.4 3 See i
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.~~- W CASK l i W ASHOOW M l AREA 147071 l
l
- 1. ENVIRONMENTAL CONDITIONS FOR ROOMS PUBLIC SERVICE ELECTRIC & GAS COMPANY l I
4624, AND 4703 TilRU 4710 SHOWN HOPE CREEK GENERATING STATION ABOVE APPEAR ON FSAR TABLE'3.11-la. l (FIC. 8a) rm
"", EQUIPMENT QUALIFICATION
.,,a HARSH ENVIRONMENT o.ra REACTOR BUILDING EL. 201' JOB NO. DRAWING NUMBER REV FIG. 8 ;
k 1 8 s g o , 9 t l _ 1 9 ne l 8 t t t t l 9 l e ie6s , s 8 s t s s s - E. t e k 1 , 2 2
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- 1. ENVIRONMENTAL CONDITIONS FOR HOPE CREEK CENERATING STATION ROOMS 4701 AND 4702 SHOWN ABOVE APPEAR ON PSAR TABLE 3.11-la.
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') EQUIPMENT QUALIFICATION k 5"*
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VII. SYSTEN/CONPONENT IDENTIFICATION p,') The systems determined to be required to operate during and-
.following a DBA to mitigate the consequences of and follow .- - the' course of the DBA, as well as to maintain the plant in a safe ' shutdown condition,- were those safety related systems de. fined in Section 7, " Instrumentation and Controls", hnd Section 8, " Electric Power", of the!HCGS FSAR.
Specifically, these systems were defined and separated into
.. the following. categories and are inclusive of the electrical
~ ! .- power systems _that supply them: *
~ Protection Systems - the protection systems initiate safety actions to mitigate ' the con-sequences of a DBA and include the Reactor Protection-' System (RPS) and the initlation functions of the Engineered . Safety Features
.(ESF).
Engineered: Safety Features - the ESF includes both the operational and control elements which ensure ~ proper cooling of the reactor plant as well as core protection and isola-tion of- the reactor plant during and follow-ing a DBA.
^
Safe Shutdown Systems - the safe shutdown systems are those operational'and control systems .used to achieve and ' maintain the plant in a safe shutdown condition following a DBA and include ~ core cooling, remote shut-down capability and required support sys-tems. Safety Related Display Instrumentatien -this
' display. instrumentation provides the operator with information critical in' determining the status and proper functioning of safety re-lated systems to. enable the operator to ini-tiate manual action to mitigate operation'al transients and/or anomalies. This display in-cludes the status of bypassed or inoperable systems important to safety as well as Post Accident Monitoring Instrumentation as delin-eated in HCGS FSAR Section 1.8.1.97.
As is noted in FSAR Sections 7 and 8, these safety systems are designed to meet the criteria for design, fabrication, construction, testing and performance as' delineated in the HCGS applicable CFR'.s, Reg. Guides, NUREG, IEEE Standards, BTP's, SRP's, etc. Included in these criteria are the EQ g requirements for these safety related systems.
,, VII-1 Q:E '
.Tho' HCGS'_EQ progrca is deoigncd to ensure that the Gyotsms and related components listed in the applicable aforemen-tioned FSAR' sections"are qualified to. correctly perform f :their defined-safety-functions in their anticipated environ-4 mental conditions during and following a DBA.
A. . System List j The'HCGS project "Q" list (maintained throughout the
~~
. project life) was established in-accordance with the requirements of Appendix B to 10CFR50 as the controll-ing document identifying the safety-related struc-tures, systems, and components required to assure: ,
s Integrity of the reactor coolant boundary. Capability to achieve and-maintain a safe shutdown. Capability to prevent ~or mitigate the conse-quences of an accident which could result in potential of f-site exposure comparable to the guidelines of 10CFR Part'100. Retaining ' of fuel temperature within design limits by maintaining fuel coolant inventory , and temperature within design limits. Control the concentration of combustible gases O' in the containment system within established limits. All structures,-systems and components are evaluated by PSEEG and Bechtel< Power Corporation to determine those which are required to achieve the atove safety functions in accor-dance with the criteria listed in 10CFR50, Appendix A.- The Q-list is updated as required to reflect design changes and
'is thoroughly reviewed by both' engineering organizations to
, ensure that structures,~ systems and components have been correctly classified. _;
The following is a listing of the safety related systems de-termined to be required to operate during and/or after a DBA as a result of the analyses. This listing includes the sys-tem designators (in parenthesis) .
- 1. PROTECTION SYSTEMS 1.1 Reactor Protection System (PPS).
1.2 Engineered Safety Feature System (ESF)-Initiation. i VII-2 1
- 2. ENGI"EERED SAFETY FEATURE SYSTEMS (ESP)
'2.1 Emergency Core Cooling System (ECCS).
% 2.1.1 High Pressure Coolant Injection Sys-tem (HPCI). ,
~ 2.1.2 Automatic Depressurization System (ADS).
2.1.3 Core Spray System (CS). 2.1.4 Residual Heat Removal System (RHR)
; Low Pressure Coolant Injection (LPCI) Mode.
2.2 Primary Containment 'and Reactor Vessel Isola-tion Control System (PCRVICS). 2.3 Residual Heat Removal (RHR) -Containment Spray Cooling Mode (CSCM). 2.4 Residual Heat Removal (RHR) - Suppression Pool Cooling Mode (SPCM). 2.5 Primary Containment Isolation System (PCIS). 2.6 Containment Atmosphere Control System (CACS). 2.6.1 Containment Hydrogen Recombination System (CHRS). 2.6.2 Vacuum Relief Valve System (VRVS). ('- 2.7 Main control Room Habitability _ and Isolation System (MCRHIS). 2.8 Main Steam Isolation Valve Sealing System-(MSIVSS). 2.9 Filtration, Recirculation, and Ventilation System (FRVS). 2.10 Reactor Building Ventilation Isolation System ( RBVIS ) . 2.11 Essential Auxiliary Supporting Systems (EASS). 2.11.1 Station Service Water System (SSWS). 2.11.2 Saf ety Auxiliaries cooling System (SACS). 2.11.3 Class 1E Power Systems. 2.11.4 Primary Containment Instrument Gas System (PCIGS). 2.11.5 Engineered Safety Feature- Equip-ment Area Cooling System (ESF-EACS). 2.11.6 Control Area Chilled Water Sys-tem (CACWS). dI VII-3
- 3. SAFE SHUTDONN SYSTEMS 3.1 Reactor Core Isolation Cooling System (RCIC).
3.2 Standby Liquid Control System (SLC). 3.3 Residual Heat Removal - Reactor Shutdown Cooling Mode (RHR-RSCM).
~ 3.4 Remote Shutdown Facility (RSF).
3.5 Essential Auxiliary Supporting Systems 4
-Safe Shutdown;(EASS-SS).
3.5.1 S tation Service Water System (SSWS). 3.5.2 Safety Auniliary Cooling System (SACS). s.5.3 Class IE Power. Systems.
*3.5.4 Safe Shutdown Equipment Ventilation Systems (SSVS).
- 4. SAFETY-RELATED DISPLAY INSTRUMENTATION 4.1 Control Rod Position Indication System (CRPIS).
4.2 Bypassed and Inoperable Status Indication Sys-
;p) tem (BISIS).
v 4.3 Control Room Integrated Display System (CRIDS). 4.3.1 Plant Operating Displays. 4.3.2 Safety Parameter Display System (SPDS). 4.3.3 Emergency Response Facilities Dis-play System (ERFDS). 4.3.3.1 Technical Support Center Display System (TSC). 4.3.3.2 Emergency Operation Fac-ilities Displays (EOF). 4.4 Post Accident Monitoring Instrumentation (PAMI).
- 5. OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 5.1 Process Radiation Monitoring System (PRMS).
5.2 High Pressure / Low Pressure System Interlocks (HPLPSI).
'~h (G
VII-4
vs v 5.3 LSEk Datcction Systsm (LDS). s j 5.4 Neutron Monitoring-System (NMS). s ~5.5 Recirculation Pump Trip (RPT) Controls and In-struments.
- 5.6 M'ain Steam Safety / Relief Valves (SRV) -Relief Function.
i _y 5.7 Redundant ~ Reactivity. Control SystemI(RRCS). 5.8, sSafety System /Non Safety ~ System Isolation-1 (SSNSSI). , Plant structures," systems, and components, including their foundations and supports, designed to remain functional in the event of a safe shutdown earthquake
--(SSE) 'are designed as Seismic Category I, as indicated-in HCGS FSAR Table 3.2-1.
+
;Those portions of~ structures', syste:ns, or components
>whose continued function is-not required but whose
' f ailure could reduce the' functic,ning .of any Seismic
. Category I plant feature to'an unacceptable safety level are verified so that an SSE would not cause such a-failure. These' items are classified as Seismic Cate-gory II/I, as indicated in- FSAR Table 3.2-1.
E All systems listed in FSAR Table 3.2-1 which are not J(- . included in FSAR Tables 3.11-5 or 3.11-6 are contained
'in'the attached FSAR Table-3.11-8. Table 3.11-8 in-cludes a descrlption of the system,-its reference to Table 3.2-1 and the reason as to why it is not included in Table 3.11-5 or 3.11-6.
B. Functional System Reviews HCGS.has' established a comprehensive, systematic program identifying electrical equipment required to be environmentally.-qualified. Safety-related eg'uipment has been identified according to the safety function objectives of 10CFR50.49(b)(1), and placed.on the HCGS project Q-list.
' For .non-safety-related electrical equipment whose . failure could prevent achieving these safety ob-jectives (paragraph'(b)(2) of 10CFR50.49), a re-view of. systems interactions had been performed-to--
ascertain which components fall into this cate-gory. This systems interactions review took into account the following studles and analyses: O VII-5
- 1. 3cp0 ration R3vicw Progrc r A separation review analysis and corresponding
!rf,i plant walkdown has been conducted on a room-V- by-room basis in the auxiliary and reactor buildings. The review identified the safety related systems and components required to meet the separation criteria provided in 10CFR100. The review /walkdown was conducted by engineering personnel familiar with areas and systems under review. Conflicts in separ-ation criteria will be reviewed and resolved. The separation review considered the following internally generated hazards:
- a. Pipe break effects (high or moder-ate energy) including pipe whip, jet impingement, steam / water flood-ing, subcompartment pressurization and water spray.
- b. Internally generated missiles resulting from explosions or pressurized compon-ents with single retaining devices.
- c. Fires including electrical, installed combustibles or transient combustibles (in accordance with 10CPR50, Appendix R).
s
d. Seismic II/I (two over one) effects on equipment, piping, or structures.
- 2. Common Sensor Failure Study.
- 3. Control Systems Failure Study.
- 4. Reactor Vessel Water Level Instrumentation Study.
- 5. Nuclear Safety Operational Analysis
- 6. Control Room Design Review
- 7. Ef fect of High Energy Line Breaks on Control Systems.
Any components identified by these studies whose fail-ure could prevent attainment of the safety function objective have been included on the project 0-list.
~ fD u
VII-6
~
Afeeparate HCGS program to verify that all safety-y related equipment for both the NSS and BOP systems.and
- l components have been properly classified was completed.
This classification program involved a re-review of-the following documents: ,
- FSAR.
- P& ids,-Elementaries
--Systems-Descriptions and Operating Manuals LLogic/ Loop Diagrams
' Instrument, Equipment and Valve Indices .
- Electrical Drawings The'P&ID is the basic lead design document and was developed by the use of - the system descriptions, 'which are based on multi-discipline design standards, the logic / loop diagrams identifying the process control /in-dication-required and in some' systems, a process flow diagram was developed. From the PEID, PSAR and later, -
, FSAR, commitments are made, the Q-list updated, all
' ' inputs .to the indices are made, and all required com- ,
ponents are purchased for the design depicted.- Later receipt of the. supplier drawings and components com-
.pletes that portion of the design furnished by the- .
supplier. All'the'information developed was entered
'into .'the Master Equipment List (MEL) for maintenance, surveillance and spare parts accountability..
'The postulated event analyses in Chapter 15 of the FSAR O - were reviewed to identify systems which have a . safety-related function or support-in any manner a safety--
The Q' list was updated to reflect related function.
~
any systems and components identified in the Chapter 15 analysis. The.following information describes the interface activities between Bechtel and PSE&G which were performed to assure-that all components requiring qualification were identified. (1) Bechtel furnished, for PSE&G' review and comment,
,. a ~ listing .of both safety and non-safety ' related components used at HCGS. The' safety related com-ponents were further subdivided into those that
. require actuation during o r. following the DBA , (" active") as'well as those~not requiring actua- ' r tion to' mitigate or follow.a DBA (" passive").
.\
(2) This list was used to develop a safety related
~
components list for both active and passive com- ! ponents. Included in this listing by Bechtel was the; physical' location on a component-by-com-ponent basis which was' determined from review of HCGS arrangement drawings, instrument location drawings and HVAC location drawings. VII-7
,~ . . - ~ - -- . _ _ - . . . . . - - - . - -. . - .-.. ... - - - - . .-
if 4
. (3) .Bochtel roviGwOd the environmontal effects of.
the worst' case postulated DBA and determined which . locations at HCGS would be subjected to a : A harsh environment. Areas found not to be affec-() ted were designated as . mild environment loca-tions. l , (4) Comparison of the areas identified as being sub-jected to a harsh environment to the list of. i
.- ~
-safety related components developed in Item #2 resulted in the determination of which active i
. safety related components required qualifica-tion-for harsh environment. Safety related mech- , anical components which could be shown to have , no age related failure mechanisms that could im- ;
- pair - the components ability to perform its de-fined safety function were considered exempt from EQ requirements. Their qualified life was assumed to be equal to the stated service life.
Passive safety related components were not in-cluded as- they were assumed. to fail "as is" and were determined not to require actuation to per- , form either short or long term monitoring or i control functions.- 8 \
.(5) During the course of identifying the equipment :
which requires qualification, safety related i equipment was identified which is both subject
~
to a harsh environment and for which exception O - is taken with respect to qualification to that harsh environment. equipment meets one or more of the following In these instances the conditions:
- Equipment is required to perform its safety function to mitigate the effects of a speci-fic DDA, but is not subjected to a harsh environment as a result of that DBA.-
1
- Equipment performs itsafunction before its F exposure to the harsh environment, and the
, adequacy of the time margin provided is justified; subsequent failure of the equip-1 ment as a result of thts harsh environment will not degrade other safety functions or mislead the. operator.
'- Equipment is exposed to environmental condi-tions during a DBA which do not require the equipment to operate and for which the eq-uipment'is not qualified to operate. In some cases, the equipment is protected by redundant,' qualified isolation devices which .
are not subject to the same DBA environment. ' This design does not affect the concepts of 1 4 I VII-8 4 _----..,,.----....._,_..._...-.,-...-~-,_,._...._,_.-,.-,m,~_m_-_m,,-._-- -,_____,m ,
redundancy and divsrsity sinco the icoleted equipment in these cases is permitted to f ail with no resultant effect on the safety O function. A list of the equipment which h meets this EQ exemption criteria is attached as FSAR Table 3.11-6.
- The. safety function can be accomplished by some other designated equipment that has been adequately qualified and satisfies the single-failure criterion.
' Appropriate justification for the determination of one of the above categories is provided on an equipment-specific basis.
(6) All safety related devices which were determined to be required to operate during and/or follow-ing a DBA but which were located in a mild en-vironmental area, were also determined. (7) The above activities resulted in FSAR Tables 3.11-4 (mechanical) and 3.11-5 (electrical) which include all NSSS and non-NSSS components requiring qualification for a harsh environment. Table 3.11-5 is also inclusive of components required for post accident monitoring per Reg. Guide 1.97, Revision 2 (HCGS FSAR Section , 7,m - 1.8.1.97) and post TMI-2 action items. In ac-cordance with the guidance contained in Appendix V) E of NUREG 0588, PSE&G performed a further ana-lysis to determine the safety related function of- each component listed on Table 3.11-5. This categorization included: (a) Equipment that will experience the environmental conditions of design basis accidents for which it must func-tion to mitigate said accidents, and that will be qualified to demonstrate operability in the accident environment for the time required for accident mitigation with safety margin to fail-ure. (b) Equipment that will experience environ-mental conditions of design basis acci-dents through which it need not func-tion for mitigation of said accidents, but through which it must not fail in a manner detrimental to plant safety or i accident mitigation, and that will be qualified to demonstrate the capability to withstand any accident environment for the time during which it must not b]
/
. fail with safety margin to failure. VII-9
l (c):Equipasnt that will expsrienco environ-mental ~ conditions ' of design basis acci-dently.but whose sole purposa is to n . supply' supplemental information tc the I J
- control room operator to monitor sys- l tem / equipment operation.
i- . , The results of this review are included in the EQ summary sheets..
- (8) Additional verification that a particular com-ponent listed in Tables 3.11-4 E.5 existed and that it was correctly. identified as being safety related-was performed by again re-reviewing -
relevant documentation such 'as the . instrument index, P&ID's, loop diagrams, electrical draw-ings, FSAR sections, Systems Descriptions, the electrical device list, ' and other design docu-ments. C. Preventative Features
.1 . ENVIR0tulENTAL SEALING OP QUALIFIED DEVICES The ' design of wiring . terminations at the environ-mentally-qualified devices is based on the quali-I' . fication program, test configurations, the speci-j fic manufacturer instructions, and the environmen-
-tal conditions of the area where the devices are O located. The guidelines for the design are sum-
- C. marized below
! a. Devices Located Inside the Containment 4 (i) Devices-that are qualified without sealing fittings are installed in accordance with-the manufacturer's > instructions without any sealing fitt-ings. , (ii) Suitable Conax sealing connectors are provided on devices that are qualified with sealing fittings and are in ac-1- cordance with the manufacturer's in-structions. (iii) Suitable Conax sealing connectors are !1 provided on devices that are qualified without exposing the-internal parts to the DBE environmental conditions. . (iv) No sealing fittings will be used on terminal boxes with qualified cable j splices (Raychem splices). , VII-10
(v) Limitorquo valva oparators cro instal-led with breather T-drain plugs and are in accordance with the manufac-v turer's instructions.
- ( 3;
- b. Devices Located in the Reactor Building And Steam Tunnel (i) Devices that are qualified without
_ sealing fittings are' installed in accordance with the manufacturer's instructions without any sealing fitt-ings. (ii) Qualified Conax sealing fittings are provided on devices that are qualified with sealing fittings and are in ac-cordance with the manufacturer's in-structions. (iii)~In HELB areas and in the steam tunnel areas, the qualified Conax sealing fittings are prcvided on devices that are qualified without exposing the internal parts to the DBE environmen-tal conditions. (iv) Conax type PG sealing fittings are provided on devices located in the
,O Reactor Building pump room areas, b except those that are in the HELB areas covered 'under I tera (b)(iii) above.
(v) Terminal boxes with low voltage /small signal (such as 4-48vdc/4-20ma) wire terminations are sealed with qualified Conax sealing fittings. No sealing fittings are used on terminal boxes with qualified cable terminations of 120V and above or on those with quali-fled splices. (vi) Limitorque valve operators are instal-F- led with breather T-drain plugs and are in accordance with the manufa'c-turer's instructions.
- 2. WATER SPRAY / JET IMPINGEMENT / SUBMERGENCE
- a. Class 1E components that are susceptible to
' water spray / submergence are identified and protected or electrically isolated from the Class 1E power supply, or qualified ucing a r3 system evaluation for safe ahutdown. U VII-11
I 1
- b. A hnzerds walkdown is to bs performtd in accor- ;
dance with guidelines to identify Class 1E components that may-be subjected to jet im-
?~i pingement. 'The component a that may be suscep-dj ,
tible to jet impingement are to be identified and protected or relocated, except for compon-ents that are not needed to mitigate the event and can be rendered inoperative without de-grading any other safety related systems that _ may be required to mitigate the accident.- , D. . System Component Listing The listing of safety related components in the harsh environment requiring environmental qualifi-cation are shown in the attached tables: Table 3.11-4 Mechanical Components Table 3.11-5 Electrical Components The listing of safety related components in the harsh environment for which environmental qualifi-cation is taken exception to is included in at-tached Table 3.11-6. A (j-f l VII-12
4___ . _.m .a _ . _ _ _. -..- A w- an.w.. - E ___.m. _ O 4 .t i i I FSAR TABLE 3.11-14 O d 4
m - fy . j% HCGS FSA3 TABLE 3.11-4 NECHANICAL BQUIPNENT SELECTED FOR HARSH ENVIRONNENT OUALIFICATION
- REV. 2 PAGE l' OF 96 P.O. 8 N001 Component: Safety Relief Valves (B21-F013) SHEET 1 of 1
- ~
Nanufacturers Target Rock Corp. Functional Description Location I .D. No. Model No. (Typical for all Valves on this Sheet) Reactor Bldg. ISM PSV F013A 7567F Gen'l. Config. Dual function safety and relief valves self actuating EL 121' (7567F-010-10) at the spring safety set pressure (safety mode) and per-mit remote manual or automatic relief opening at pres- Reactor Bldg. ISM PSV F0138 7567F Gen'l. Config. sure below the set point with the electro-pneumatic EL 121' (7567F-010-10) actuator. Reactor Bldg. 153 PSV F013C 7567F Gen'l. Config. Safety Functions: EL 121' (7567F-010-10) To open to its ASNE rated capacity position, as a mini- Reactor Bldg. ISH PSV F013D 7567F Gen'l. Config. mum, and permit depressurization of the reactor pressure EL 121' (7567F-010-10) vessel to provides Reactor Bldg. ISM PSV F013E 7567F Gen'l. Config. 1. Operation of the valve at a vessel pressure at or EL 121' (7567F-010-10) above the valve's (inlet pressure) spring safety set point (safety mode) to provide overpressure Reactor Bldg. lA3 PSV F013F 7567F Gen'l. Config. protection. EL 121' (7567F-010-10)
- 2. A manual means of relieving steam generated by core Reactor Bldg.
IA3 PSV F013G 7567F Gen'l. Coinfig. ' decay heat to the suppression pool in the event that EL 121' (7567F-010-10) the main condenser is not available as a heat sink after reactor shutdown and until the RHR steam con- Reactor Bldg. lA3 PSV F013H 7567F Gen'l. Config. densing mode of operation is initiated trollef EL 121' (7567F-010-10) mode). Reactor Bldg. IA3 PSV F013J 7567F Gen'l. Config. 3. Automatic depressurization (ADS) of the reactor EL 121' (7567F-010-10) pressure vessel under an assumed loss-of-coolant condition (relief model. Reactor Bldg. IA3 PSV F013K 7567F Gen'l. Config. EL 121' (7567F-010-10) 4. An alternate means to cool and shutdown the reactor by passing water from the reactor to the suppression Reactor Bldg. IA2 PSV F013L 7567F Gen'l. Config. pool in the unlikely event that the RHR shutdown EL 121' (7567F-010-10) suction line is not available to transmit water from the reactor to the RHR heat exchanger while the Reactor Bldg. lA3 PSV F013N 7567F Gen'l. Config. RHR/LPCI pumps are injecting water into the reactor EL 121' (7667F-010-10) (relief mode). Reactor Bldg. IAB PSV F013F 7567F Gen'l. Config. EL 121' (7567F-010-10) Reactor Bldg. IA3 PSV F013R 7567F Gen'l. Config.
~
EL 121' (7567F-010-10) n P85 8/04 1-cag
~3 _
Q () (_ HCGS FSAR TAeLE 3.11-4
-MECHANICAL EOUIPMENT SELECTED FOR HARSH ENVIRONMENT OUALIFICATION REV. 2 PAGE- 2 ' OF 96 P.O. 8 M001 Component: Main Steam Isolation valves Manufacturer: Atwood & Morrill Co. SHEET ~1 of 1'~
(821-F022/F025) I e. No. Model No. Functional Description Location IAB HV F022A 21362H , _' Inboard . To remain open throughout the normal plant' Reactor Bldg. (Typicall operation. In' case of small line break EL 102' (of 4) accident, the operator may keep the MSIV's IAB HV F0228 21362H open to ut111:e the main condenser. In case Reactor Bldg. of a DBE, the MSIV's will t,e closed within EL 102' the first hour of the accident and maintained 1AB HV F022C 21362H in the closed position throughout the post- Reactor Bldg. accident period. The MSIV's are to limit the EL 102' leakage through the valve seat. The MSIV's IA3 HV F022D 21362H + are equipped with limit switches to provide Reactor Bldg. safety signals to the reactor protection EL 102'
. system.
IAS HV F028A 21362H Outboard: To remain open throughout the normal plant Reactor Bldg. (Typical) operation. In case of small line break EL 102' (of 4) accident, the operator may keep the MSIV's IAB HV F0288 21362H open to utilize the main condenser. In case Reactor Bldg. of a D8E, the MSIV's will be closed within EL 102' the first hour of the accident and maintained 1A3 HV F028C 21362H in the closed position throughout t5e post-- Reactor Bldg. accident period. The MSIV's are to limit the EL 102 leakage through the valve seat. The MSIV's IA3 HV F028D 21362H are equipped with limit switches to provide Reactor Bldg. safety signals to the reactor protection EL 102' system, k 4 1 k i I C3 PSS 8/04 2-cag 1 i
O G
^
,Y%
--kj .
NCGS FSAR TABLE 3.11-4 NECHANICAL BOUIPMENT SELECTED FOR HARSit 4 ENVIROINGENT OUALIFICATION dEv. 2- ! PAGE 3 OF 96 i P.O. 8 N001 Component Recirculation Pumps (531-C001) SMBET I of 1-
- ~
a Manufacturer: Syron Jackson Pump Co. i I .D. No. Model No. Functional Description Location 1st AP 201 28X28X35EvsS . To provide flow to the jet pump which provides forced ~ Reactor aldg. coolant flow through the Reactor Core.- EL 077'
-(Drywell)
IBS BP 201 28X28X35Evss Reactor aldg. 1 EL 077' (Drywell) 1 4 I i h } i l 1 i i 1 j N P85 8/04 3-cag i l 1 ~
e
% /\.
O% d V
.NCGS FSAR TABLE 3.11-4
. NECliANICAL EQUIPstENT SELECTED FOR MARSH ENVIROsletENT QUALIFICATION REV. 2 PAGE 4 OF 96~
SWEET T of l
~ ~
P.O. 4 N001 - Component: Recirculation System Valves Manufacturers Lunkenheimer (331-F023/F031 I P. No. Model No. Functional Description Location ISS HV F023A D-12925. Suction:
- Reactor Bldg.
EL 077' 188 HV F023B D-12925 Suction *
' Reactor Bldg.
EL 077' las r.V F031A D-12926 Discharges
- Reactor Bldg.
EL 100' 103 HV F0318 D-12926 Discharges-
- Reactor Bldg.
EL 100'
'The recirculation block valves stay opened throughout the normal plant operation. They are closed only for recirculation pump maintenance. After a confirmed ATNS, !
it is desiratle that one of the block valves stay oper-able. The valve will be closed to route the shutdown , cooling water to the jet pump inlet, but this is not a safety function. These valves have no active safety function they shall maintain pressure integrity of the reactor coolant boundary. C3 PS5 8/04 4-ceg i
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HCCS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH ENVIRONMENT OUALIFICATION REV. 2' PAGE 5 or 96 SMEET 1 of 1~
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P.O. 8 N001 Component: CRD Hydraulic Control Units. Manufacturers General _ Electric Co. C11-Dect I e. M 3. Model No. Functional Description Location IBF 00 202 761E500G007 Modular assembly of Control Rod Drive directional Reactor aldg. (Typical for 1851 -Control valve, Scram Valve, and accumulator. .EL 102' (Unito.- 3 (Bach HCU is identifled by the . appropriate control i ' rod, which has been
, ccoigned a coordinate 1 Eumber that detines the location of the rod withirt the core.
All coordinate numbers 1 consist of four , digits: Two for i row and two for column. Rows are ] cecit ned odd . numbers and columns acoigned even numbars) a s i i i 1 I I ) G P85 8/04 5-cag i 4
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' TABLE 3.11-4 MECMANICAL EQUIPMENT SELECTED FOR MARSH ENVIRONMENT QUALIFICATION REV. 2 PAGE 6 OF 96-
~
P.O. 9 N001 Component CRD Vent italves and Drain Valves SMEET T of 1~ Manufacturers Hasunel Dehl - ~ Cll-F010/FIGO/F0ll/F/181 I I.m. No. Model No. Functional Description Location 1 BF W F010 522FAR62HA29 Inboard
- Reactor Bldg.
EL 102' 1 BF W F180 522FRR62HA29 Outboard
- Reactor Bldg.
EL 102' 1 BF W F011 522J RR62HA29 Inboard
- Reactor Bldg.
EL 102' 1 BF W F181 522J RR62HA29 Outboard -
- Reactor Bldg.
EL 077'
- Air operated globe valves ut!!! sed to facilitate proper venting and draining of the SW header, except during scram when the valves are closed to conserve reactor
, water.
i The valves are required to operate and isolate the SW > vent and drain lines within 12 hours after a small break accident (SSA) occurs and remain closed for the post accident duration. After a LOCA, the valves may be delayed up to 40 seconds prior to required operation. M P85 8/04 6-caq l t i
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NCGS FSAR-TABLE 3.11-4 NECMAs3ICAL EQUIPMENT. SELECTED FOR HARSM ENVIRONMENT QUALIFICATION REV. 2
, PAGE 7 OF 96
'SMEET T of 1-
~ ~
P.O. 8 N001 Ccaponent: Standby Liquid control Puunos Manufacturers Union Pump Co. (C41-C001 I.M. No. Model No. Functional Description Location. 1 SM AP 208 2X3,TD-60 Triplex To pump a neutron absorber solution .(sodiusa pentaborate) Reactor Bldg.~ from the system storage tank into the reactor-vessel. EL 162'
. Provides all inde;endent backup capability to shutdown 1 BM BP 208 2X3,TD-60 Triplex the reactor and keep it suberitical as it cools, peactor Bldg.
' EL 162' L
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HCG 3 FSAR 4 '~ TABLE 3.11 +
, NECNAMICAL EQUIPMENT SELECTED FOR HARSP. -- l>
ENVIRONMENT QUALIFICATION REV. 2 - PAGE 8 OF 96 /.. P.O. t. n001 Component RHR Heat Exchancer (El1-9001) Manufacturer: Delta Southern Co. .SNEET T of 1,~ I.D. No. Model No. Functional Description Location. 1 BC At 205 &EU - The functions of the RHR Heat Exchanger, depending on Reactor. Bldg. operating mode are: ..EL 054'
- 1 SC BE 205 @ 1. Provide's containment cooling during containment '.eactor Bldg. '
j spray. EL 054' i-
- 2. Fuel Pool cooling.
3 Suppression pool cooling. 4.. Condensation of reactor vessel steam produced by reactor decay heat while the reactor is on hot standby.
- 5. Reactor water cooling during reactor shutdown.
Safety Functions l a containment cooling during containment spray and pool l cooling operations. 1 i l } 3 i i ) l 4 E3 PSS 8/04 8-cag i 1 i
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.O HCCS FSAR-J u TABLE 3.11-4 MECHANICAL EQUIPNENT SELECTED FOR HARSH ENVIRONNENT QUALIFICATION RW. 2 P.O. 0 'N001 Component: RHR Pumps (Ell-C002 A, B,'C, D) PACE 9 OF 96 Manufacturer: Inoersoll Rand SHECT T of [
I.D. No. Nodel No. Functiona1 Description Locatlo'n 1 BC AP 202 34APKD Provide emergency' cooling to the reactor core. ' Reactor, Bldg. EL 054' 1 BC BP 202. 34APKD Provide emergency cooling to the reactor core. Reactor Bldg. EL 054' 1 BC CP 202 34APKD Provide emergency cooling to the reactor coce. Reactor Bldg. 1 BC DP 202. EL 054' 34APKD Provide emergency cooling to the reactor-core. Reactor Bldg. EL 054'
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-TABLE 3.11-4 MECHANICAL BOUIPNENT SELECTED FOR HARSH ENVIRONNENT QUALIFICATION
) REV. 2 PAGE 10 OF 96 P.O. 9 N001 Components RHR (LPCI) Check Valves (Testable) Manu facturers - Atwood & Norrill Co. -SHEET 1 of l' (Ell-F041/F050 Functional Description I.D. No. Model No. (Typical for All Components on this Sheet) Location 1 BC HV F050A (14053-01-H)* To prevent backflow of . reactor water in event of a pipe . Reactor-Bldg. rupture. upstream of valve. The solenoid-controlled air EL 100' cylinder is used as a positive means of opening the. 1.DC HV F0508 (14053-01-H)* valve at zero pressure differential,.but is not capable Reactor Bldg.
' uf closing the valve or holding the valve open against EL 100' reverse flow. The actuator and related linkages and l'BC HV PO41A (14053-01-H)* components are designed to preclude anf damage as a Reactor Bldg.
result of applying maximum pneumatic pressure to the EL 100'
- actuator in the opening or closing direction while the 1 BC HV F0418 (14053-01-H)* valve disc is positioned by system fluid forces. Reactor Bldg.
EL 100' 1 BC HV F041C (14053-01-H)* Reactor Bldg.' I EL 100' 1 BC HV F041D (14051-01-H)* Reactor Bldg. EL 100'
- Drawing No.
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HCGS FSAR TABLE 3.11-4 . MECHANICAL EQUIPMENT SELECTED FOR HARSH ENVIRONMENT QUALIFICATION REV. 2-PAGE 11 OF 96' P.O. 8 M001 Cossponents LPCS Check Valves (Testable) (E21-FOO6) Manufacter Atwood & Morrill Co. SHEET T of [
'I-D. No, Model No. -Functional Description Location 1 53 HV F006A (Drawing 14053-01-H) To prevent backflow of reactor water'in event of pipe Reactor Bldg.
I 88 NV F0068 (Drawing 14053-01-H) rupture upstream of valve. The solenoid-controlled air EL 100' cylinder is used as a positive means of opening the valve at zero pressure differential, but is not capable of closing the valve or holding the valve open against, reverse flow. The actuator and related linkages and components are designed to preclude any damage as a result of applying maximum pneumatic pressure to the actuator in the opening or closing direction while the - valve disc is positioned by system fluid forces. 1 M P85 8/04 11-cag
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'HCGS FSAR TABLE 3.11-4
- MECHANICAL EQUIPMENT SELECTED FOR HARSH ENVIRONMENT QUALIFICATION REV. 2.
PAGE 12 OF 96 i - P.O. O N001 Component: LPCS Core Spray Pumps (E21-C001) Manufacturers. Incersoll Rand I SHEET T ot [ Functional Description I D. No. Model No. Typical for all components on this Sheet) Location i 1 EE AP 206 25APKD Provide emergency cooling flow to the reactor core. Reactor Bldg.
- Provide makeup water in the event of a loss of reactor EL 054' coolant in order to prevent fuel damage should the core
- 1.EE EP 206 25APKD become uncovered. The pumps operate only when the ' Reactor Bldg.
reactor is depressurized. EL 054' 1 BE CP 206 25APKD Reactor Bldg. EL 054' 1 EE DP 206 25APKD Reactor Bldg. EL 054' i 4 1 k b M PBS 8/04 12-cag i 1 1 4
s (- s - HCGS FSAR TABLE 3.11-4 MECHANICAL BOUIPMENT SELECTED FOR HARSH ENVIRONMENT OUALIFICATION L REV. 2 PAGE- 13 OF 96 I P.O. 4 M001 Component: HPCI Pump Assembly (E41-C001) Manufacturer Byron Jackson Co_. SHEET T of f I.D, No. Model No. Functional Description Location-1 BJ OP 217 12X14X23DVS Booster Pumps
- Reactor Bldg.
EL 054' 1 BT OP 204 10x12X15DVS, 2STG MVMX Main Pumps '*
-Reactor Bldg.
EL 054'
*To supply domineralized make-up from the condensate storage tank or suppression pool water to the reactor vessel, to provide that adequate core cooling takes place to avoid overheating of the reactor f uel, in the event of, a loss-of-coolant accident (LOCA), an Antici-pated Transient Nithout Scram ( ATWS), or reactor isola-
, tion and failure of the Reactor Core Isolation Cooling (RCIC) system.
i 4 I 1 i 9 i
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N ' *** L) LJ HCGS FSA2 i-TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HAPSH , ENVIRONNENT OUALIFICATION REV. 2 PAGE 14 OF 96 lP.O. 8 N001 Component: RCIC Pump (E51-C00ll Manufacturers' Binohan Willamatte Pump Co.
' SHEET T of f I.D. No. Model No. Fuy tional Description Location I 1 ED OP203 ' '6X6X10-1/2CP The RCIC pump is directly connected to the RCIC turbine . Reactor Bldg.
driver ard supplies water to the reactor vessel during EL 054 1 solation conditions accomplished with the los:a of l normal feedwater. 1
. 4 i
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MECHANICAL 80UIPMENT SELECTED FOR HARSH ENVIRONMENT QUALIFICATION. REV. 2 PAGE- 15 OF 96' P.O. 9 M001 Components TIP Valve, Guide' Tube' Assembly 'Manuf acturers Consolidation Controls Corp. SHEET]T~of I[~ (C$1-J004) I.D. No. Model No. Functional Description Location 1 CE XV J004B1 .136B1302G002 A squibb fired isolation valve for the tube containing Reactor Bldg. the in-core monitoring calibration detector. EL 102' 1 SE XV J004B2 13681302G002 A squibb fired isolation valve for the. tube containing Reactor Bldg. the in-core monitoring calibration detector. 'EL 102' , 1 SE XV J00483 136B1302G002 A squibb fired isolation valve for the tube containing Reactor Bldg. the in-core monitoring calibration detector. EL 102' 1 SE XV J00484 136B1302G002 A squibb fired isolation valve for the tube containing Reactor Bldg. the in-core monitoring calibration detector. EL 102' 1 SE XV J004BS 136B1302G002 A squibb fired isolation valve for the tube containing Reactor Bldg. the in-core monitoring calibration detector.. EL 102' 4 M P85 8/04 15-cag
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HCG 1 PSAR TABLE 3.11-4 MECHANICAL BOUIPMENT SELECTED FOR HARSH ENVIRONMENT QUALI?ICATION RE\'. 2-PAGR 16 OF 96
' P.O. 9 N001 Component: ' Reactor Core Isolation Coolina ' ~ Manufacturer Terry Corporation snEET -J, of J,.
Turbine Assembly E51-C002 I,D, No. Model No. Functional Description' Location ,
~
.I'FC 05212 GS-2 Provides the motive power for driving the RCIC pump. Reactor Bldg.'
EL 054' 4
\ l l
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j [ J kf HCGS FSAR TABLE 3.11-4 NECHANICAL EQUIPMENT SELECTED FOR HARSH - R EV'. - 25 i ENVIRONNENT QUALIFICATION PAGE M of 96 P.O. 0. N070(O) Component: Pumps, SACS ' Manuf acturer Ingersoll Rand SHERT 1 of 1,; I.D.'No. Model No. Functional Description Location . 1.EG AP 210 147.23S (volute) To provide flow for sapety auxiliaries cooling'.(closed Reactor Bldg. . ; i- loep) system.' EL 102' I 1 EG BP 210 14X23S (volute). To provide. flow for safety. auxiliaries cooting (closed Reactor Bldg.
- loop)' system. EL 102' 1 EG CP 210 14X23S (volute) To provide flow for safety auxiliaries cooling (closed Reactor Bldg.
q loop). system. EL 102' , 1 EG DP 210 14X23S (volute)
- To provide flow for safety auxiliaries cooling (closed Reactor. Bldg.-
+
loop) system. EL.102' i 1. t I 1 d 1 N P85 8/04 17-cag i i
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- TABLtl 3.11-4 ~ .
MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2' ENVIRONMENT QUALIFICATION Pact 18. cr 96
; P,0. 8 N082(O) Components Horizontal Centrifugal Pumps' Manufacturers Hayward Tyler . SHEET 1 of 1 I.D. No. Model No. Functional Description Location 1
4 1 BC AP 211 4X6X10'NHSH- Fuel Pool Cooling Pump Reactor Bldg. I-EL.162 1 EC BP 211 4X6X10 NHSH- Fuel Pool Cooling Pump ' Reactor Bldg. EL 162' t 9 4 3 1 i 1 1 J e l M PBS 8/04 18-cag f 1
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- MECMANICAL EQUIPMENT SELECTED FOR HARSH . REV. 2 ENVIRONMENT OUALIFICATION PAGE 19 of 96--
P.O. 9 M141(0) Component Nuclear Relief Valves ' Manufacturers Crosby Valve & Gaos Company ' SHEET 1 of 9 i I.D.'No. Model No. Functional De script ion Location
- 1 AB PSV F037A- Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg.
EL 102' 1 A3 PSV F0378 Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. j EL 102' 1 A3 PSV F037C Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' i 1 AS PSV F037D Style: VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. - a EL 102' 1 A3 PSV F037E Styles VR Vacuum Relief - Discharge Line vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' $ 1 AD PSV F037F Style: VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1
-1 AB PSV F037G Style: VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg.
EL 102' 1 A3 PSV F037H Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 4 1 A3 PSV F037J Ctyles VR Vacuum Relief - Discharge Line vacuum Breaker Drywell Torus, Reactor Bldg. j EL 102' , 1 AB PSV F037K Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. , j EL 102' 1 AS PSV F037L Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 1 AB PSV F037M Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 AB PSV F037P Styles VR Vacuum' Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. j EL 102' 1 AB PSV F037R Styles Vk Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' l M P85 8/04 19-cag 1 4 1
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/ G Y HCGS FSAR TABLE 3.11-4 MECHANICAL BOUIPMEKT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 20 OF 96 P.O. 8 M141(O) Component: Nuclear Relief Valves Manufacturer: Crosby Valve & Gage Company SHEET 2 of 9
! I D. No. Model No. Functional Description Location 1 AS PSV 4500A Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 A3 PSV 45008 Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 A3 PSV 4500C Style VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 AB PSV 4500D Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' , 1 A3 PSV 4500s Style: VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 AB PSV 4500F Style: VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 A3 PSV 4500G Style VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. l EL 102' l 1 A3 PSV 4500H Style: VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 AB PSV 4500J Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 AB PSV 4500K Style: VR Vacuum Relief - Discharge Lire Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 A3 PSV 4500L Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 AB PSV 4500M Style: VR Vacuum Relief - Discharge Line vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 A3 PSV 4500P Styles VR Vacuum Reliof - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' 1 A3 PSV 4500R Styles VR Vacuum Relief - Discharge Line Vacuum Breaker Drywell Torus, Reactor Bldg. EL 102' ' M P85 8/04 20-cag
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- TABLE 3 11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 l ENVIRONMENT OUALIFICATION PAGE 21 OF 96 '
P.O. 9 M141(O) Component: Nuclear Relief Valves Manufacturers Crosby Valve & Gage Company . SHEET 3 of.9 I e. No. Model No. Functional Description Location a 1 FD PSV F076- Style: 'VR HPCI Vacuum Breaker Line Reactor Bldg. EL 077' 1 FD PSV F077 Styles VR HPCI Vacuum Breaker Line Reactor Bldg. EL 077' 1 FC PSV F063 Stylds VR RICCI Turbine Exhaust Valve Raactor Bldg. EL 077' 1 FC PSV F064 Styles VR RICCI Turbine Exhaust Valve Reactor Bldg. EL 077' 1 BC PSV F151A Styles VR Siphon Breaker - HX A to Torus Reactor Bldg. EL 054' 1 BC PSV F151B Styles VR Siphon Breaker - HX B to Torus Reactor Bldg. ' EL C54' 1 BC PSV F152A style: VR ' Siphon Breaker _- HX A to Torus Reactor Bldg. EL 054' 1 BC PSV F152B Style: VR Siphon Breaker - HX B to Torus Reactor hldg. EL 054' 1 BC PSV F055A Style: JB-56-TD RHR Heat Exchanger A Inlet Reactor Bldg. EL 077' 1 BC PSV F0558 Style JB-56-TD RHR Heat Exchanger B Inlet Reactor Bldg. EL 077' 1 BF PSV 4003 Style: VR Disch. Vol. Vent'n (Vac. Skr.) Reactor Bldg. El. 102' 1 KP PSV 5832A Style: JMBU MSIV Inboard Seal Gas Supply Reactor Bldg. EL 102' 1 KP PSV 5832B Style: JMBU MSIV Outboard Seal Gas Supply Reactor Bldg. EL 102' M P85 8/04 21-cag i
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J V HCGS FSAR-TABLE 3.11-4 MECHANICAL SQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 22 OF 96 P.O. 9 M141(O) Component: Nuclear Relief Valves Manufacturert. Crosby Valve & Gage Company SHEET 4_ of 9 I.D. No. Model No. Functional Description ~ Location , 1 A3 PSV 45G4A JO-25-SPL + SRV PSV F013A Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 AS PSV 45048 JO-25-SPL + SEV PSV F013B Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 A3 PSV 4504C JO-25-SPL + SRV PSV P013C Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 A3 PSV 4504D JO-25-SPL
- SRV PSV F013D Acc. Relief Valve Drywell Torus, Reactor Bldg.
El. 121' 1 AD PSV 4504E JO-25-SPL + SRV PSV F013E Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 A3 PSV 4504F JO-25-SPL + SRV PSV F013F Acc. Relief Valve Drywell Torus, Reactor Bldg. Bl. 1218 1 A3 PSV 4504G JO-25-SPL + SRV PSV F013G Acc. Relief Valve Drywell Torus, Reactor Oldg. El. 121' 1 AB PSV 4504H JO-25-SPL + .SRV PSV F013H Acc. Relief Valve Drywell Torus. Reactor Bldg. El. 121' 1 A3 PSV 4504J Jo-25-SPL + SRV PSV F013J Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 A3 PSV 4504K JO-25-SPL
- SRV PSV F013K Acc. Relief Valve Drywell Torus, Reactor bldg.
El. 121' 1 A3 PSV 4504L JO-25-SPL *- SRV PSV F013L Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 A3 PSV 4504M JO-25-SPL + SRV PSV F013M Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 121' 1 A3 PSV 4504P JO-25-SPL + SRV PSV F013P Acc. Relief Valve Drywell Torus, Reactor Blog. El. 121' + Model No. shown is generic identifier only. The unique valve data sheet should be checked for supplemental parameters and characteristics. M P85 8/04 22-cag
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-ENVIRONMENT OUALIFICATION PAGE- 23-OF.96-P.O. 8- M141(O) Component Nuclear Relief Valves Manufacturers Crosby Valve & Gage Company SHEET 5,of 9,-
'I.D. No. Model No. Functional Description Location 1.A3 PSV 4504R ,
JO-25-SPL + SRV PSV F013R Acc. Relief Valve. Drywell Torus, Reactor Bldg. El. 121'
- 1 AD PSV 4505A J O-2 5-S P L + ' MSIV HV-F022A Acc. Relief Valve Drywell Torus, Reactor Bldg.
El. 102' 1 A3 PSV 45058 Jo-25-SPL + MSIV HV-F022B Acc. Relief Valve Drywell Torus, Reactor Bldg. El. 102' I AD PSV 4505C JO-25-SPL + MSIV HV-F022C Acc. Relief Valve Drywell Torus, Reactor. Bldg. , El. 102' 1 A3 PSV 4505D' JO-25-SPL + MSIV HV-F022D Acc. Relief Valve Drywell Torus, Heactor Bldg. El. 102' 1 A3 PSV 4506A JO-2 5-SPL + MSIV HV-F028A Acc. Relief Valve Reactor Bldg. , El. 102' 1 A3 PSV 4506B JO-25-SPL +. MSIV HV-F028B Acc. Relief Valve Reactor Dldg. El. 102' j 1 A3 PSV 4506C JO-25-SPL + MSIV HV-F028C Acc. Relief Valve Reactor Bldg. I El. 102' 1 A3 PSV 4506D JO-25-SPL + MSIV HV-F028D Acc. Relief Valve Reactor Bldg. El. 102' 1 EG PSV 6220A JO-35-SPL + RHh HX AE205 Outlet Reactor Bldg. El. 054' 1 EG PSV 6220B JO-35-SPL
- RHR HX BE205 Outlet Reactor Bldg.
El. 054' 1 GS PSV 4986Al JO-25-SPL + H2/02 Analyzer Bottles Reactor Bldg. El. 162' l + Model No. shown is generic identifier only. Th2 unique valve data sheet should be checked for supplemental parameters and characteristics. , M P85 8/04 23-cag _m - -- - - _ - _ - - _ _ _ _ _ _ _ u +
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MECHANICAL EQUIPMENT SELECTED POR HARSH- REV. 2 ENVIRONMENT OUALIFICATION PAGE M OP 96 P.O. 9.'M141(O) Component: Nuclear Relief Valves Manuf acturers Crosby Valve & Gace Company . SHEET 6,of 9, I D. No. Model No. Functional Description Location ,. 1 G3 PSV 4986A2 Jo-25-SPL + 1004 Oxygen Relief Valve. Reactor Bldg.
- 81. 162' 1 G3 PSV 4986A3 JO-25-SPL + 5% Oxygen Relief Valve Reactor Bldg.
El. 162' 1 CS P!;V 4986B1 JO-25-SPL + 54 Oxygen Relief Valve Reactor Bldg. El. 162' 1 GS PSV 4986B2 JO-25-SPL + H 2 /02 Analyzer Bottles Reactor Bldg. El. 162' 1 GS PSV 4986B3 JO-25-SPL + 5% Oxygen Relief Valve Reactor Bldg. Bl. 162' 1 CS PZV 5745Al JO-25-SPL + 1004 Hydrogen Relief. Valve Reactor Bldg. E1. 132' 1 CS PSV 574581 JO-25-SPL*+ 1004 Hydrogen Relief Valve Reactor Bldg. El 132' 1 GS PSV 6292A JO-25-SPL + Contn'm' t Atm. Vlv. Opr. Acuum. A Reactor Bldg. El. 077' 1 GS PSV 6292B JO-25-SPL + Contn'm't Atm. Vlv. Opr. Acuum. S Reacator Bldg. El. 077' 1 BH PSV F029A D2-JO-55-9-WR-S-SP SLC Pump A Disch. Reactor Bldg. El. 162' 1 BH PSV F0298 D2-JO-55-9-WR-S-SP SLC Pump B Disch. Reactor Bldg. El. 162' 1 ED PSV F017 JMB-WR-TYPE B RCIC Pump Suction Hdr. Reactor Bldg. El. 054'
+ Mod 31 No. shown is generic identifier only.
Th2 unique valve data sheet should be checked for cupplemental parameters and characteristics. M P85 8/04 24-cag
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q ,) l HCGS FSAR- .. TABLE 3.I1-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 25 OF 96 . P.O. 8 M141(Ol Component: Nuclear Relief Valves Manufacturers Crosby Valve &' Cage Company SHEET 7 of 9_- I.D. No. Model No. Functional Description Location 1 FC'PSV F018 -JMB-WR-TYPE B RCIC .Clg Water Supply Hdr Reactor Bldg. El. 054' 1 BC PSV_F030A JMB-WR-TYPE B RHR Pump A Suppr Pool Suctiois . Reactor Bldg. El. 054' i ! BC PSV F030B JMB-WR-TYPE B RHR Pump B Suppr Pool Suction ' Reactor Bldg. El. 054' 1 BC PSV F030C JMB-WR-TYPE B RIIR Pump C Suppr Pool Suction Reactor Bldg. El. 054' 1 BC PSV F0300 .JMB-WR-TYPE B RHR Pump D Suppr Pool Suction Reactor Bldg. El. 054' 1 BC PSV F029 JMB-WR-TYPE B RHR Pump Suction Shutdn C1g Reactor Bldg. Bl. 054' 1 BC PSV F025A JMB-WR-TYPE B LPCI Injection Line A Reactor Bldg. El. 077' 1 BC PSV F025B JMB-WR-TYPE B RHR LPCI Injection Line B Reactor Bldg. El. 077' 1 BC PSV F025C JMB-WR-TYPE B LPCI Injection Line C Reactor Bldg. El. 077' 1 BC PSV F025D JMB-WR-TYPE B RHR LPCI Injection Line D Reactor Eldg. El. 077' 1 BE PSV F032A JMB-WR-TYPE B CS Pmp AP206 Suction Relief Reactor Bldg. El. 054' j 1 BE PSV F032B JMB-WR-TYPE B CS Pmp BP206 Suction Relief Reactor Bldg. ] E1. 0 54: M P85 8/04 25-cag
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TABLE 3.11-4 ( PECHANICAL EOUIPMENT. SELECTED FOR HARSH 'REV.'2 ENVIllONMENT QUALIFICATION. -PAGE 26 Or 96 P.O . 9 'M141(O) Component:~ Nuclear Relief valves Manuf a.c tu rer s Crosby Valve s Gaoe Company SHEET 8_.cf 9 I.D. No. M W 1 No. Functional Description Location 1 BE PSV F032C JMB-WR-TYPE B CS Pup CP206 Suction Relief . Reactor Bldg. El. 054' 1 CE PSV F032D JMB-WR-TYPE B CS Pop DP206 Suction Relief Rat.ctor Bldg. El. 054' 1 BE PSV F012A F2-JO-35-WR Core Spray Loop A'Rclief Wolve Reactor Bldg. El. 054' 1 BE PSV F012B F2-JO-35-WR Core Spray Loop E Ralter valv:: Reactor Bldg. l' El. 054' l BJ PSV F020 JMB-WR-TYPP B 'HPCI Pump Suction 8tdr Relief Reactor Bldg. El. 054' 1 FD PSV F050 'JMB-WR-TYPE B HPCI Clg. Water Supply Hdr. Reactor Bldg. El, 054' 1 BD PSV F097 4P-6JO-25-3-WR-SPL RHR Loops to RCIC Reactor Bldg. El. 054' 1 PSV 2526A JMB-WR-TYPE B Spare 1 PSV 2526B JMB-WR-TYPE B Spare 1 EG PSV 2530A JMB-WR-TYPE E Fuel Pool HX AE202 Reactor Bldg. El . 16 2 ' 1 M PSV 2530B JMB-WR-TYPE B Fuel Pool HX BE202 Reactor Bldg. El. 162* 1 EC PSV 4674A JMB-WR-TYPE B Fuel Pool HX AE202 Reactor Bldg.
- 1. 16 2 '
M P85 8/04 26-cas
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M () ~f d U- U HCGS FSA2 4 TABLE 1.11-4 MECHANICAL' EQUIPMENT SELECTED FOR HARSH REV. 2
' ENVIRONMENT-OUALIFICATION PAGE 27 OF 96 4
~~
P.O. 8 M141(O) Component: Nuclear' Relief Valves Manufacturers -Crosby Valve & Gage Ccepany SHEET 9 of 9L I.D. No. Model No. Functional Description Location 1 EC PSV 46748 JMB-WR-TYPE B Puel Pool HX 8E202 Reactor Bldg. t El. 162' 1 BG PSV F036 3 K 4-J O-2 5-WR RWCU Disch to Equip Drain Reactor Bldg. El. 071' 1 BC PSV 4425 JMB-TYPE B 8teact Recirc to RHR Sys Reactor Bldg. El. 102' 1 G3 PSV 9522A JRAK-BS Ch Wtr. Loop A Supply Drywell Torus, Reactor Bldg. El. 102' 1 G3 PSV 9522B J RAK-BS Ch Wtr Loop B Supply Drywell Torus, Reactor Bldg. f El. 102' ! I CD PSV 9523A JRAK-BS Ch Wtr Loop A Rtn Drywell Ttsrus, Reactor Bldg. j El. 102'
- I G3 PSV 9523B JRAK-BS Ch Wtr Loop B Rtn Drywell Torus, Reactor Bldg.
El. 102' , 1 FD PSV F018 G2-1/2-JO-25-WR Glnd Seal Cond Relief Reactor Bldg. El. 054' 1 FC PSV F033 G2-1/2-J0-25-WR RCIC Gland Seal Cond Vac Tank Reactor Bldg. El. 054' M P85 8/04 27-cag
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HCGS FSAR TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH-- REV. 2 ENVIRONMENT OUALIPiCATION PAGE 28 OP 96 P.O. 8 MISO (O)* Component: Vacuum Relief Valves Manufacturer: GPE Controls (Div. Vapor Corp.) SHEET i of 1 I.D. No. Model No. Functional Description Location I GS PSV 4946A* LD240-447 Rev.'B Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' ! I CS PSV 49468*- LD240-447 Rev. B Suppressiori Chamber Vacuum Breaker Reactor Bldg. EL 054' 1 CS PSV 4946C* LD240-447 Rev. B Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' 1 GS PSV 4946D* LD240-447 Rev. 8 Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' 1 GS PSV 4946E* LD240-447 Rev. B Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' I GS PSV 4946P* LD240-447 Rev. B Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' 1 GS PSV 4946G* LD240-447 Rev.-R Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' 1 CS PSV 4946H* 'LD240-447 Rev. B Suppression Chamber Vacuum Breaker Reactor Bldg. EL 054' 1 GS PSV 5030 LD240-383 Reactor Bldg. Vacaum Reactor Bldg. EL 077' 1 GS PSV 5032 LD240-383 Reactor Bldg. Vacuum Reactor Bldg. EL 077' 1 I
- NOTE: These valves, purchased under P.O. No. 150(O), were modified by vendor under P.O. No. 150A(0).
, M P85 8/04 28-cag
f' (- 2- - i. HCGS FSAR' TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 - ENVIRONMENT QUALIFICATION PAGE 29 OF 96-P.O. 8 ~M713(O) Component: Fans, Centrifuaal- Manufacturer Buffalo Forae Company SHEET 1 of 2_ I -D. No. peoovi mo. Functional Description Location 1 GU AV 206 840 BL Filtration, Recirculation & Vent Fan Reactor Bldg. EL 145' ! 1 GU BV 206 840 BL Filtration, Recirculation & Vent Fan . Reactor Bldg. EL 145' . I GU AV 213 805 BL FRVS, Recirculation Fan Reactor Bldg. EL 132' j 1 Go BV 213 805 BL PRVS, Recirculation Fan Reactor Bldg. 4 r EL 178' , 1 GU CV 213 805 BL PRVS, Recirculation Fan Reactor Bldg.
' EL 132' 1 CU DV 213 805 BL PRVS, Recirculation Fan Reactor Bldg.
1 EL 162' l i i l i 0 1 a W % I I
! M P85 8/04 29-cag i
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O HCGS FSA2 TABLE 3.11-4 1 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. ' 2 ENVIRONMENT.OUALIFICATION PAGE. 30 OF 96
'P.O. 8 M713(O) Component: Fans, Centrifugal Manufacturers Buffalo Force Company SHEET 2,of 2, l I,M. No. Model No. Functional Description Location.
t j .1 GU EV 213 805 BL FRVS, Recirculation Fan Reactor Bldg. EL.162' 1 GU FV 213 805 BL FRVS, Recirculation Fan Reactor Bldg. i EL 178' j. l i i 1 l l i
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HCGS FSA2 . TABLE 3.11-4 MECHANICAL BOUIPMENT SELECTED FOR HARSH REV 2 ENVIRONMENT QUALIFICATION 'PAGE. 31 OF 96 P.O. 9 J601(Q) Components control Valves Manufacturer: 'Masonellon Div.'(McGraw Edison) SHEET 1 of 1 1.D. No. Model No. Functional Description- Location , 1 BC LV F053A 38 20721 RHR HX A To RCIC Reactor Bldg.
, EL 054*^
1 BC LV F053B 38 20721 RHR HK B Disch. to Sup PL/RCIC Reactor Bldg. EL 054' 1 CC Lv 4660 38 20771 Skimmer Surge TK B Make-Up SPL Reactor Bldg. EL 162' i 1 FC LV F005 38 20771 RCIC Vacuum TK To Clean Rad. Waste Reactor Bldg. EL 054' f i 1 FD LV F025 38 20771 Vac TK Cond. PMP Disch to CRW Reactor Bldg. EL 054' 1 BC PV F051A 38 40512 HPCI STM Press Reducing Reactor Bldg. EL 077' 1 BC PV F0518 38 40512 HPCI to RHR Heat Exch D Reactor Bldg. 1 EL 077'- i i r j I i 4 Q P85 8/04 31-cag
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) U HCGS FSA3 TABLE 3.11-4 MECHANICAL EQUIPMENT SCLECTED FOR HARSH REV 2 -
ENVIRONMENT QUALIFICATION PAGE -32 or 96- t P.O. 9 J605(O) Component Control Valves Manufacturers Fisher Controls Corp. (Controls Ass.) SHEET 1 of 1- , I.D. No. Model No. Functional Description Location-1 EG V804 7670- SACS Heat Exchanger Butterfly Valve Reactor Bldg.
'EL 103' 1 EG V805 7670' SACS Heat Exchanger Butterfly Valve Reactor. Bldg.
} EL 113' i ! 1 EG V806 -7670 SACS, Heat Exchanger Butterfly Valve Reactor Bldg. EL 103' i 1 EG V807 7670 SACS Heat Exchanger Butterfly Valve Reactor Bldg.
- EL 113' i ! BC HV F048A 7620 RHR Butterfly Control Valve Reactor Bldg.
EL 077' 1 CC HV F0488 7620 RHR Butterfly Control Valve Reactor Bldg. , EL 077' 1 EG TV 2517A 7620 SACS Heat Exchanger Butterfly Bypass Valve Reactor Bldg. I EL 102' 1 1 1 EG TV 25178 7620 SACS Heat Exchanger Butterfly Bypass Valve Reactor Bldg. I i EL 102' 1 { i 1 4 i I l j M P85 8/04 32-as l I i
_ . - ._. _ _ __ . . _ m __ s~ 'f HCGS FSAR TABLE 3.11 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV 2 ENVIRONMENT OUALIFICATION PAGE 33 OF 96 P.0, 8 J703(O) Component: ' Excess Flow Check Valves Manufacturer: Dragon valve Inc. SHEET 1,of 15 I.D. No. Model FO. Functional Description Location 1ABFO 3666A 12696-7L MS Line A Instrument Line Drywell Torus, Reactor Bldg. EL 112' ' 1AIFO 36668 12696-7L MS Line B Instrument Line Drywell Torus, Reactor Bldg. EL 100' l l 1AIFO 3666C 12696-7L MS Line C Instrument Line Drywell Torus, Reactor Bldg. t EL 100' 1A1FO 3666D 12696-7L MS Line D Instrument Line Drywell Torus, Reactor Bldg. EL 112' d 1A*FO 3667A 12696-7L MS Line A Instrument Line Drywell Torus, Reactor Bldg. EL 112' 1ATFO 36678 12696-7L MS Line a Instrument Line Drywell Torus, Reactor Bldg. i EL 100' i IAIFO 3667C 12696-7L MS Line C Instrument Line Drywell Torus, Reactor Bldg. EL 100' 1ABFO 3667D 12696-7L MS Line D Instrument Line Drywell 7orus, Reactor Bldg. EL 100' 1AIFO 3668A 12696-7L *
- MS Line A Instrument Line Drywell Torus, Reactor Bldg.
EL 112' 1AIFO 36688 12696-7L MS Line B Instrument Line Drywell Torus, Reactor Bldg. EL 112' l lASFO 3668C 12696-7L MS Line C Instrument Line Drywell Torus, Reactor Bldg. 4 l EL 100* 1AIFO 3668D 12696-7L MS Line D Instrument Line Drywell Torus, Reactor Bldg. i EL 100' 1AIFO 3669A 12696-7L MS Line A Instrument Line Drywell Torus, Reactor Bldg. EL 112' 1AIFO 3669B 12696-7L MS Line B Instrument Line Drywell Torus, Reactor Bldg. f
' EL 112' M P85 8/04 33-az 1
+ 1'
Q/ %d HCGS FSAR TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV 2 ENVIRONMENT QUALIFICATIOM PAGE 34 OF 96-P.0, 8 J703(O) Component: Excess Flow Check Valves Manuf acturer: Dragon Valve Inc. SHEET 2 of 15 I .D. No, Model No. Functional Description Location IABFO 3669C 12696-7L MS Line C Instrument Line Drywell Torus, Reactor Bldg. EL 100' IAIFO 3669D 12696-7L MS Line D Instrument Line Drywell Torus, Reactor Bldg. 4 EL 112' 1 ABXV 3666A 12504-4 Main Eteam Line A Excess Flow Reactor Bldg. EL 077' 1ABXV 3666B 12504-4 Main Steam Line B Excess Flow Reactor Bldg. EL 077' 1ABXV 3666C 12504-4 Main Steam Line C Excess Flow Reactor Bldg. EL 077' 1ABXV 3666D 12504-4 Main Steam Line D Excess Flow Reactor Bldg. - EL 077' 1ABXV 3667A 12504-4 Main Steam Line A Excess Flow Reactor Bldg. EL 077' IABXV 3667B 12504-4 Main Steam Line B Ewcess Flow Reactor Bldg. EL 0778 1ABXV 3667C 12504-4 Main Steam Line C Excess Flow Reactor Bldg. EL 077' 1ABXV 3667D 12504-4 Main Steam Line D Excess Flow Reactor Bldg. EL 077' 1ABXV 3668A 12504-4 Main Steam Line A Excess Flow Reactor Bldg. EL 077' IABXV 3668B 12504-4 Main Steam Line B Excess Flow Reactor Bldg. EL 077' i 1ABXV 3668C 12504-4 Main Steam Line C Excess Flow Reactor Bldg. EL 077'. lABXV 3668L 12504-4 Main Steam Line D Excess Flow Reactor Bldg. EL 077' M P85 8/04 34-az
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( U V' HCCS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SRI,R(7ED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 35 OF 96 P.O. 8 J703(O) Component: Excess Flow Check Valves Manufacturer Eragon Valve Inc. SHEET 3 of 15 I.D. No. Model No. Functional Description Location IABXV 3669A 12504-4 Main Steam Line A Excess Flow Reactor Bldg. EL 077'. 4 1 ABXV 3669B 12504-4 Main Steam Line B Excess Flow Reactor Bldg. EL 077' 1ABXV 3669C 12504-4 Main Steam Line C Excess Flow Reactor Bldg.
, EL 077' i IAbXV 3669D 12504-4 Main Steam Line D Excess Flow Reactor Bldg.
EL 077' IEIFO 3621 12696-7L IBB-LT-36228-Instrument Line (Spare) Drywell Torus, Reactor Bldg. EL 145' IEIFO 3649 12696-7L Reac. Head Seal Leakage Det Drywell Torus, Reactor Bldg. EL 162' IEIFO 3725 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 121' IEIFO 3726A 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 162' 11BFO 3726B 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 162' 121FO 3727A 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 162' IEIFO 37278 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 162' IE!FO 3728A 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 145' i 11;FO 3728B 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 145' , 1ECFO 1729A 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. EL 145' M P85 8/04 35-az s i
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' TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REv. 2 ENVIRONMENT QUALIFICATION; PAGE 36 OF 96 P.O. 9 J703(O) Component: Excess Flow Check valves Manuf acture r: Draeon valve Inc.
SHEET 4 of M
'I.D."No.
Model No. Functiona1 Description Location i } 10BFO 37298 12696-7L Reactor vessel Instrument Line- Drywell Torus, Reactor Bldg. :
~
EL 145'- ISBFO 3730A 12696-7L Reactor Vessel Ir strument Line Drywell Torus, Reactor Bldg.
, EL 145'
. !!CFO 37308 12696-7L Reactor Vessel Instrument Line Drywell Torus, Reactor Bldg. . EL 132' IGZFO 3731A 12696-7L Reactor Vessel Instrument Line ' Drywell Torus, . Reactor Bldg. EL 145' j IEIFO 37318 12696-7L Reactor Vessel Instrument Line " Drywell Torus, Reactor Bldg. EL 132' IIIFO 3732A' 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' , 10100 37328 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' . IE1FO 3732C 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldo. 1 EL 121 1 IEBFO 3732D 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. ] EL-ll2' f IEIFO 37328 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. j EL 121' ISIFO 3732F 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' IEZFO 3732C 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. 1 4 EL 121' IEBFO 3732H 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. l EL 112'- i IETFO 3732J 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' ! M P85 8/04 36-as 3 i
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. TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR. HARSH REV. 2-ENVIRONMENT OUALIFICATION PAGE 37 OF 96 P.O. 8 .J703(O) Component: Excess Flow Check Valves Manufacturer: Dragon Valve Inc. SHEET 5 of 15 I.D. No. Poodel No. Functional Description Location IEIPO 3732K '12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg.
EL 112' IBIFO 3732L 12696-7L. Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' IEIFO 3732M 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' IEIFO 3732N 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' IEZFO 3732P 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' lEBFO 3732R 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' IEBFO 3732S 12696-7L Jet Pump Instrument Line Reactor Bldg. EL 077' IBIFO 3732T 12696-7L Jet Pump Instrument Line Reactor Bldg. EL 077' IEXPO 37320 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' IBBFO 3732V 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' IBBFO 3732W 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' lt:FO 3734A 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' ISBFO 3734B 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' IEIFO 3734C 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 121' M P85 8/04 37-az
s , N k. , '\ HCGS PSAR TABLE 3.11-4
' NECHANICAL EQUIPMENT SELECTED FOR HARSH REV. ' 2 _
ENVIRONMENT QUALIFICATION PAGE. 38 OF 96-
.P.O.'8 J703(O) Component: Excess Flow Check Valves Manufacturer: Dragon Valve Inc.
SHEET 6 of M I.D. No.. Model No. . Functional Description Location I $ IMFO 3734D '12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. EL 112' IQ~FO 3737A '12696-7L IBB-PDT-NO32-B21. Instrument Line .Drywell Torus, Reactor Bldg.
'EL 100' IETFO 3737B 12696-7L Control Rod Drive Instrument Line Drywell Torus, Reactor Bldg. .
EL 100' IE1FO 3738A 12696-7L Jet Pump Instrument Line 'Drywell Torus, Reactor Bldg. EL 100' a IIIFO 3738B 12696-7L Jet Pump Instrument Line Drywell Torus, Reactor Bldg. ! EL 100' IBIFO 3783 12696-7L Recirc. Pump A Seal Instrument-Line Reactor Bldg. EL 102' i IC1FO 3785 12696-7L Recirc. Pump A Seal Purge Instr. Reactor Bldg. EL 102' 1 l IBBFO 3787 12696-7L Recirc. Pump B Seal Instrument Line Reactor Bldg. EL 102' IBIFO 3789 12696-7L Recirc. Pump Seal B Purge Instr. Reactor Bldg. EL 102' 1BIFO 3801A 12696-7L Recirc. Line A Instrument Line Reactor Bldg. EL 102' 11BFO 3801C 12696-7L Recirc. Line A Instrument Line- Reactor Bldg. [ EL 102' 4 IBBFO 3802A 12696-7L , Recirc. Line A Instrument Line Reactor Bldg. EL 102' 131FO 3802C 12696-7L .Recirc. Line A Instrument Line Reactor Bldg. , EL 102' 12696-7L 1BBFO 38038 Recirc. Line B Instrument Line Reactor Bldg. i EL 102' 4 N P85 8/04 38-az i
HCGS FSA*t 1 TABLE 3.11-4 . MECHANICAL EQUIPMENT SELECTED FOR HARSH. -REV.. 2 ENVIRONMENT OUALIFICATION PAGE 39 OF 96 P.O. 8 J703(O) Component: Excess Flow Check Valves Manufacturers- Dragon Valve Inc. SHEET 7 of 15 I.D. No. Model No. Functional Description ' Location IF4FO 3803d' 12696-7L Recirc. Line B Instrument Line Reactor Bldg. EL 102' , 15AFO 3804B 12696-7L Recirc. Line B Instrument.Line Reactor Bldg. EL 102' INFO-3804D 12696-7L Recirc. Line B Instrument Line Reactor Bldg. EL 102' . ICZFO 3820 12696-7L Recirc. Pump A Discharge Instrument Line Reactor Bldg.
.EL 102'
,- IMFO 3821 12696-7L Recirc. Pump A Suction Instrument Line Reactor Bldg. EL 102' ISIFO 3826 12696-7L Recirc. Pump B Suction Instrument Line Reactor Bldg. EL 102' IBBFO 3827 12696-7L Recirc. Pump B Discharge Instrument Line Reactor Bldg. EL 102' 1BBXV 3621 12504-2 IBB-LT-3622B Instrument Line Reactor Bldg. EL 145' ISBXV 3649 12504-4 Reactor Head Seal Leakage Det Drywell Torus, Reactor Bldg. EL 14 5' IBBXV 3688 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IBBXV 3691A 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IBBXV 36918 12504-4 Excess Flow Check Valve Reactor Bldg.
-EL 077' IBBXV 3725 12504-4 Excess Flow Check Valve Reactor Bldg.
EL 145' IEBXV 3726A 12504-2 Excess Flow Check Valve Reactor Bldg. EL 102' M PBS 8/04 39-az '
+
- s. s tq)' . x w ) (J-HCGS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 40 DF 96 P.O. 9 J703(O) Component: Excess Flow Check Valves Manufacturect Dragon Valve Inc.
SHEET 8 of M I.D. No. Model No. Functional Description Location 11BXV 3726B 12504-2 Escess Plow Check Valve Reactor Bldg. EL 102' IBBXV 3727A 12504-2 Excess Plow Check Valve Reactor Bldg. EL 102' IEBXV 3727B 12504-2 Excess Flow Check Valve Reactor Bldg. EL 102' IEBXV 3728A 12504-2 Excess Plow Check Valve Reactor Bldg. EL 102' IBBXV 37288 12504-2 Excess Flow Check Valve Reactor Bldg. EL 102' IE.BXV 3729A 12504-4 Excess Plow Check Valve Reactor Bldg. EL 102' IIBXV 37298 12504-4 Excess Plow Check Valve Reactor Bldg. EL 102' IEBXV 3730A 12504-2 Excess Flow Check Valve Reactor Bldg. , EL 102' IBBXV 3730B 12504-2 Excess Flow Check Valve Reactor Bldg. EL 102' IEBXV 3731A 12504-2 Excess Plow Check Valve Reactor Bldg. EL 102' IBBXV 3731B 12504-2 Excess Plow Check Valve Reactor Bldg. EL 102' 11BXV 3732A 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IBBXV 37328 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732C 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' M P85 8/04 40-az
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Nj V ]. HCGS FSA7 TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 41 OF 96 P.O. 8 J703(O) Component: Excess Flow Check Valves Manufacturer: Dragon Valve Inc. SHEET 9 of 15 I D. No. Model No. Functional Description' Location IEBXV 3732D 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732E 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' 11BXV 3732F 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732G 12504-4 1 mess Flow Check Valve Reactor Bldg. EL 077' 11BXV 3732H 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732J 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' lZBXV 3732K 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' ! IBBXV 3732L 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' j 11BXV 3732M 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732N 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' 11BXV 3732P 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732R 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3732S 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077'. IIBXV 3732T 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' M P85 8/04 41-az
p .-g-C):' HCGS PSAR-TABLE 3.11-4 ' MECHANICAL EQUIPMENT SELECTED POR HARSH REV.'2 ENVIRONMENT QUALIFICATION PAGE 42 OP 96 P.O. 9 J703(0) Component:' Excess Plow Check Valves Manufacturer: Dragon Valve Inc. SHEET 10 of 15 I D. No. Model No. Functional Description Location IEBXV 37320 12504-4 Excess Plow Check valve Reactor Bldg. EL 077' IEBXV 3732V 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IECXV 3732W 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' 11BXV 3734A 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3734B 12504-4 Excess Plow Check Valve Reactor Bldg. EL 077' 1BBXV 3734C 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077'~ IBBXV 3734D 12504-4 Excess Plow Check Valve Reactor Bldg. EL 077* IEBXV 3737A 12504-4 Excess Plow Check Valve Reactor Bldg. EL 077' IBBXV 3737B 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3738A 12504-2 Excess Flow Check Valve Reactor Bldg. EL 077' ID:XV 3738B 12504-2 Excess Flow Check Valve Reactor Bldg. EL 077' 11BXV 3783 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3785 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' IEBXV 3787 12504-4 Excess Flow Check valve Reactor Bldg. EL 077' ' M P85 8/04 42-az i
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& 'J %J HCGS PSAR TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 43 OP 96 P.O. 9 J703(O) Component Excess Plow Check Valves Manufacturer: Dragon Valve Inc.
SHEET M of M j I.D. No. Model No. Functional Description Location ICBXV 3789 12504-4 Excess Flow Check Valve Purge Reactor Bldg. EL 077' 1 BXV 3801A 12504-4 Excess Plow Check Valve
. Drywell Torus, Reactor Bldg.
EL 086' IEBXV 3801B 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. EL 077' 11BXV 3801C 12504-4 Excess Plow Check Valve Drywell. Torus, Reactor Bldg. j EL 077' IEBXV 3801D 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. EL 077' 1 BXV 3802A 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. EL 077' 1;BXV 3802B '12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. EL 077' t IIBXV 3802C 12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. EL 077' .) i 11BXV 3802D 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. EL 077' IEBXV 3803A 12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. ? EL 0778 IEBXV 3803B 12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. EL 077' IEBXV 3803C 12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. EL 077' IEBXV 3803D 12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. EL 077' 11BXV 3804A 12504-4 Excess Plow Check Valve Drywell Torus, Reactor Bldg. EL 077' M P85 8/04 43-az
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TABLE.3.11-4 NECHANICAL EQUIPNENT SELECTED FOR HARSH REV. 2 ENVIRONNENT OUALIFICATION PAGE 44 OF.96 P.O. 8 J703(O) Component: Excess Flow Check Valves Nanufacturer: Dragon Valve Inc. SHEET 12 of 15 I.D. No. Nodel No. Functional Description Location
.IIBXV 38048 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. , EL 0.77' ) IEBXV 3804C 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg.
EL 077' IIBXV 3804D 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. EL 086' 11BXV 3820 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg. EL 077' IIBXV 3821 12504-4 Excess Flow Check Valve Reactor Bldg. EL 077' J 1EBXV 3826 12504-4 Excess Flow Check Valve Drywell Torus, Reactor aldg. EL 077' 11.BXV 3827 12504-4 Excess Flow Check Valve Drywell Torus, Reactor Bldg.
, EL 077' IBCFO 4411A 12696-7L Excess Flow Check For PDT-N060A Drywell Torus, Reactor Bldg.
j EL 077' IBCFO 44118 12696-7L LPCI Inject Press Drywell Torus, Reactor Bldg. EL 100' t IBCFO 4411C 12696-7L Excess Flow Check For PDT-N060A Drywell Torus, Reactor Bldg. EL 100'
, IBCFO 4411D 12696-7L LPCI Inject Line Press Drywell Torus, Reactor Bldg.
EL 077'
- IECFO 4429A 12696-7L Excess Flow ' Check For PDT-N058A Drywell Torus, Reactor Bldg.
EL 077' IBCFO 44298 12696-7L HV-F017B Ell DP LN Flow Check Drywell Torus, Reactor Bldg. EL 102' IBCFO 4429C 12696-7L Excess Flow Check For PDT-N058C Reactor Bldg. EL 077' M P85 8/04 44-az l l P e
f' T\ [ \ (v k) v .h HCGS FSAR TABLE 3.11-4 NECHANICAL EOUIPNENT SELECTED FOR HARSH REV. 2 ENVIRONNENT QUALIFICATION PAGE 45 OF 96 P.O. 8 J703(O) Component Excess Flow Check Valves Manufacturer: Dragon Valve Inc. SHEET 13 of 15 I.D. No. Model No. Functional Description Location 1BCFO 4429D 12696-7L' HV-F017D Ell DP LN Flow Check Drywell Torus, Reactor Bldg. EL 102' IBCXV 4411A 12504-4' Excess Flow Check For PDT-N060A Reactor Bldg. EL 077' IECXV 4411B 12504-4 Excess Flow Check For PDT-N060B Reactor Bldg. EL 077' 11CXV 4411C 12504-4 Excess Flow Check For PDT-N060A Reactor Bldg. EL 077' IBCXV 4411D 12504-4 Excess Flow Check For PDT-N060A Reactor Bldg. EL 077' 1BCXV 4429A 12504-4 Excess Flow Check For PDT-N058A Reactor Bldg. EL 077' 1BCXV 4429B 12504-4 HV-F017B Ell DP LN Flow Check Reactor Bldg. EL 077' 1BCXV 4429C 12504-4 Excess Flow Check For PDT-N058C Reactor Bldg. EL 077' 11CXV 4429D 12504-4 HV-F017D Ell DP LN Flow Check Reactor Bldg. EL 077' IBEFO 4575A 12696-7L Core Spray Loop B To PDT-N056 Drywell Torus, Reactor Bldg. EL 102' IBEFO 4575B 12696-7L Core Spray Loop A To PDT-N056 Drywell Torus, Reactor Bldg. EL 102' IBEXV FOl8A E21 12504-4 Excess Flow Check Valvo PDT N056 Drywell Torus, Reactor Bldg. EL 077' IIEXV FOl8B E21 12504-4 . Excess Flow Check Valve PDT N056 Drywell Torus, Reactor Bldg. EL 077' IBGPO 3882 12696-7L RV Drain Ex Flow Drywell Torus, Reactor Bldg. EL 102' N P85 8/04 45-az i
- HCCL4 FSA3 TABLE 3.11-4 '
4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REY. 2
! ENVIRONMENT QUALIFICATION PAGE 46 Or 96-P.O. 8 J703(O) Components ~ Excess Flow Check Valves Manufacturers- Dragon Valve Inc. SHEET 14 of 15 1.3 No. Model No. Functional Description l Location i t
IBGFO 3884A 12696-7L RtfCU Inlet Flow Ex F1 Drywell Torus, Reactor Bldg. EL 121' j IBGFO 38848 12696-7L .RNCU. Inlet Flow Ex F1 ~ Reactor Bldg. EL 150'-
- j. IBCFO 3884C 12696-7L RtfCU Inlet Flow Ex P1 Reactor Bldg.
EL 150' ] IBGFO 3884D 12696-7L RNCU Inlet Flow Ex F1 Reactor Bldg. EL 150' j IBGXV 3882 12504-2 RV Drain Excess Flow Check Valve- Reactor Bldg. i ! EL 077' s IBGXV 3884A 12504-4 RtfCU Inlet Flow Ex F1 Check Valve Reactor Bldg. EL 077' i j IBCXV 38848 12504-4 RefCU Inlet Flow Ex F1 Check Valve Reactor Bldg. i EL 077' t 1 IEGXV 3884C 12504-4 RtfCU Inlet Flow Ex F1 Check Valve Reactor Bldg. EL 077' j IBCXV 3884D 12504-4 RtfCU Inlet Flow Ex F1 Check Valve Reactor Bldg. 4 l EL 077' l IFCFO 4150A 12696-7L RCIC Turbine Steam Instr Line Reacter Bldg. EL 087'
, IPCFO 4150B 12696-7L^ RCIC Turbine Steam Instr Line Reactor Bldg.
EL 087' IFCFO 4150C 12696-7L RCIC Turbine Steam Instr Line
' Reactor Bldg.
i EL 087' j- IFCFO 4150D 12696-7L RCIC Turbine Steam Instr Line Reactor Bldg. EL 087' ! IFCXV 4150A 12504-4 RCIC Turbine Steam Ex F1 Check Valve Reactor Bldg. l M PSS 8/04 46-az i I 1
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q .Q) V. HCGS FSAR TABLE 3.11-4 ~ NECHANICAL EQUIPMENT SELECTFD FOR HARSH REV. 2 ENVIRONNENT QUALIFICATION PAGE. 47 OF 96 P.O. 9 J703(O) Components Excess Flow Check Valves Manufacturer: Dracon Valve Inc. SHEET M of M I.D. No. Model No. Functional Description Location IFCXV 41508 12504-4 RCIC Turbine Steam Excess Flow Check Valve Beacto Bldg. EL 077 IFCXV 4150C 125C4-4 RCIC Turbine Steam Excess Flow Check Valve Reactor Bldg.
.EL 077' IFCXV 4150D 12504-4 RCIC Turbine Steam Excess Flow Check Valve Reactor Bldg.
EL 077' IFDFO 4800A 12696-7L HPCI Steam Supply Instr. Line Drywell Torus, Reactor Bldg. EL 077' IFDFO 48008 12696-7L HPCI Steam Supply Instr. Line Drywell Torus, Heactor Bldg. EL 077' IFDFO 4800C- 12696-7L HPCI Steam Supply Instr. Line Drywell Torus, Reactor Bldg. EL 102' IFDFO 4800D 12696-7L HPCI Steam Supply Instr. Line Drywell Torus, Reactor Bldg. EL 102' IFDXV 4800A 12504-4 HPCI Steam Supply Instr. Line Reactor Bldg. EL 077' IFDEV 48008 12504-4 HPCI Steam Supply Instr. Line Reactor Bldg. EL 077' IFDXV 4800C 12504-4 HPCI Steam Supply Instr. Line Reactor Bldg.
- EL 077' IPDXV 4800D 12504-4 HPCI Steam Supply Instr. Line Reactor Bldg.
EL 077' Cl P85 8/04 47-az
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C D k HCGS FSAR TABLE 3.11-4 MECMANICAL EQUIPMErr SELECTED FOR HARSH REV. 2 ENVIRO MENT OUALIFICATION FACE 48 OF 96 P.O. 9 J70s(Q) Component: Nuclear Instrument Valve Manufacturers Dragon Valves ' SHEET 1 of 3 I .D. No. Model No. ' Functional Description Location IAP XV 2043 14833 Spare Reactor Bldg. (Condensate Storage Tank Excess Flow' Check Valve) (EL 077.') IEG XV 2518Al 14833 RHR Pump Bearing Cooler check valve . Reactor Bldg. EL 054' IEG XV 2518A2 14833 RHR Pump Bearing Cooler Check Valve Reactor. Bldg. EL 054' IEG XV 251881 14833 RHR Pump Bearing Cooler Check Valve Reactor Bldg. EL 054' IEG XV 251882 14833 RHR Pump Bearing Cooler Check Valve Reactor Bldg. EL 054' IEG XV 2518C1 14833 RHR Pump Bearing Cooler Check Valve Reactor Bldg. E L 0 54 ' IEC XV 2518C2 14833 RHR Pump Bearing Cooler Check valve Re ac to r Bldg . EL 054 IEG XV 2518D1 14833 RHR Pump Bearing Cooler Check Valve Reactor Bldg. EL 054' IEC XV 2518D2 14833 RHR Pump Bearing Cooler Check Valve "teactor Bldg. EL 054' IEG XV 2533Al 14833 RHR Pump Bearing Cooler Check valve Reactor Bldg. EL 054' M PSS 8/04 48-az
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sq . ( ' b ~ l TABLE 3.11-4 ' ' '
'Nt.CNANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 2 i
ENVIRONMENT QUALIFICATION PAGE 49 OF 96 N; P.O. 9 J705(O) Components nuclear Instrument Valve Manufacturer: Draaon Valves
- SHEET 2 of 3 '
I-D. no. mode 1 No. Funetiona1 Deocrietion Location 7 1 G XV 2533A2 14833 RHR Pump Seal Cooler Check Valve Reactor Bldg. EL 054' i j 'IEG XV 253381 14833 RHR Pump Seal Cooler Check Valve Reactor Bldg. - j EL 054' ]' IEC XV 253382 14833 RHR Pump Seal Cooler. Check . Valve Reactor Bldg.' EL 054' j IEC XV 2533Cl 14833 RHR Pump Seal Cooler Check Valve Reactor Bldg. 1, EL 054' j IEG XV 2533C2 14833 RHR Pump Seal Cooler Check Valve Reactor Bldg. 3 EL 054' I
; IEC XV 253301 14833 RHR Pump Seal Cooler Check Valve Reactor Bldg.
EL'054 4 ., IEG XV 2%33D2 14833 RHR Pump Seal Cooler Check Valve Reactor Bldg. EL 054' 1 i i 1 1 i i i t l 4 ), t I ! i M P95 S/04 49-az ' 3 l
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_,- f~s p),. 1 b) HCGS FSA*2 b TABLE 3.11-4' MECHANICAL EQUIPMENT. SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE -50 OF 96-P.O. 8 J105(O) Component: Nuclear Instrument valve Manufacturer: Dragon Valves SHEET 3,of 3, * ] I.D. No. Model No. Fur ctional Description ~ Location e IEC XV 4660 14833 Spare - Reactor Bldg. ( Fuel Pool Cooling and Torus water Cleanup Skimmer (EL 162') Surge Tank Limiting Flow Check Valve) ' j IEC XV 4662A 14833 Fuel Pool Cooling Pumps, Suction Side Limiting . Re ac to r Bl dg . l Flow Check Valve 'EL 162' k j IEC XV 46628 14833 Fuel Pool Cooling Pumps, Suction Side Limitirg _ Reactor Bldg. Drywell 1 Flow Check Valve EL 162' I IEC XV 4673A 14833 Fuel Pool Cooling Pumps, Discharge Side Beactor Bldg. Drywell Limiting Flow Check Valve EL 162' I j IEC XV 4673B 14833 Fuel Pool Cooling Pumps, Discharge Side Reactor Bldg. Drywell Limiting Flow Check Valve EL 162' j ICC XV 4682A 14833 Fuel Pool Cooling System Limiting Reactor Bldg. Drywell
! Flow Check Valve EL 162' t
i 1EC XV 4682B 14833 Fuel Pool-Cooling System Limiting Reactor Bldg. Drywell l Flow Check valve EL 162' t 1 105 XV 2077A 14833 Standby Liquid Control Reactor Bldg. Drywell EL 077' = 1
! IBM XV 2077B 14933 Standby Liquid Control
- Reactor Bldg. Drywell EL 077' [
5M15SIDN2 Mot Applicable 5 Valve Manifold w/ threaded connection various tocations
, EL Various i 2M15SIDN2 Not Applicable 2 Valve Manifold w/ threaded connection Various Locations j EL Various i
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f% , TABLE 3.11-4 NECHANICAL EOUIPMENT SELECTED FOR HARSH R EV . 2 ENVIRONMENT QUALIFICATION .PAGE ~ _51 OF 9 6-P.O. 0 . J715(O) Component: Nuclear Instrument valves Manufacturers . Dragon valves SHEET 1,of 1_- I .D. No.* Model No. Functional Description Location i i Ca15S1PN2 13770N-7 Instrimment Calibration Isolation valves and High Approx. Se of these 1500 Point Vent Valves valves are used in the Diesel Gen. Bldg. and the
- Balance of Plant. Asma i n-ing 954. in Reactor Bldg.
Ca1521EN2 13770N-6S E7 Instrtament Calibration Isolation Valves and High 550 valves purchased for Point Vent Valves various applications in q the Reactor Bldg. C815S2HN2 13769N-6S E Instrnament Calibration Isolation Valves and High 220 valves purchased for. Point vent valves various applications in the Reactor Bldg.
*These valves will not receive unique tag nasaberst valvos classification nisaber is shown here.
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HCGS FSAR TABLE 3.11-4 MECHANICAL SQUIPMENT SELECTED FOR NARSH REV. 2 ENVIBONNSNT OUALIFICATION PAGE_ 52 OF 96' P.C. 8 P301(O) Component: Laroe valves Manufacturer: Anchor Darlina Valve Co. SHEET 1,of-13 IM. No. Model No. Functional Description Location 04PNV 2072 Not Applicable RB Isolation Valve -Reactor Bldg. EL 'O R4 ' OAPNV 2073 Not Applicable RB Isolation Valve Reactor Bldg. EL 054' ODNNY 2069 Not Applicable RB Isolation Valve Reactor B'Idg. EL 054' 1 AIM 6V 2600 Not Applicable Domin. Mater to Reactor Ble.g. Reactor Bldg. EL 054' IBCMV F003A Ell Not Applicable RHR HX A Shell Outlet Reactor Bldg. EL 054' IBCMV F0038 Ell Not Applicable RHR HTK B Shell Outlet Reactor Bldg. EL 054' lbCMV F004A Ell Not Applicable RHR Pump A Suppr. Pool Suct. Reactor Bldg. ** EL 054' IBCNV F0048 Ell Not Applicable RHR Pump B Suppr. Pool Suct. Reactor Bldg. EL 054' 1BCMV F004C Ell Not Applicable RHR Pump C Suppr. Pool Suct. Reactor Bldg. EL 054' s ! IBCMV F004D Ell Not Applicable RNR Pump D Suppr. Pool Suct. Reactor Bldg. EL 054' IBCMV F006A Ell Not Applicable RHR Pump A Shtdwn Clg Suct Valve Reactor Bldg. EL 054' IBCMV F0069 Ell Not Applicable RHR Pump B Shtdwn Clg Suct Reactor' Bldg. EL 054' IBCMV F307A Ell Not Applicable RHR Pump A Min Flow Bypass Reactor Bldg. EL 054' IBCNV F0078 ell Not Applicable RHR Pump B Nin Flow Bypass Reactor Bldg. EL 054' O PG5 8/04 52-az
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, NECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE -53 Or 96-P.O. O P301(O) Component: Large valves Manufacturer: Anchor Darlina valve Co. SHEET 2 of 13 I D. No. Model No. Functional Description Location IDCMV FOO7C Ell Not Applicaole RHR Pump C Min Flow Bypass Reactor Bldg.
a EL 054' 18CMV F007D Ell Not Applicable RHR Pump D Min Flow Bypass Reactor Bldg. EL 054' , 19CMV F010A Ell Not Applicable RHR Pump C Test Return Reactor Bldg. EL 054' IBCMV F010B Ell Mot Applicable RHR Pump D Test Return Reactor Bldg. EL 054' 19CMV F011A E11 Not Applicable RHR HK A To Suppr Pool Reactor Bldg. ! EL 054' i IBCMV F0118 Ell Not Applicable RHR HK B Test Return Reactor Bldg. EL 054' ISCMV F016A Ell Not Applicable RHR Cont Spray Outbd Reactor Bldg. EL 102' l 19CMV F016B Ell Not Applicable RHR Cntat Spray B Outbd Reactor Bldg. EL 132' j 19CMV F021A Ell Not Applicable RHR Cntant Spray Inbd Reactor Bldg. EL 102' 19CMV F0218 Ell Not Applicable RHR Cont Spray B Inbd Reactor Bldg. EL 132' l IRCMV F024A Ell Not Applicable RHR Pump A Test Return Reactor Bldg. EL 054' I 1 19CNV F0248 Ell Not Applicable RHR Pump B Test Return Reactor Bldg. EL 054' 18CNV F026A Ell Not Applicable RHR HX A To Reic Reactor Bldg. j EL 054' i 13CMV FC268 Ell Not Applicable RHR HK B To Reic Reactor Bldg. EL 054' l D re5 S/04 53-az 1 ( l 4 w-- - w
p % /m. '- ( MCCS FSAR J b , l TABLE 3.11-4 [ MECHANICAL EQUIPMENT SELECTED FOR MARSN REV. 2 ENVIRONMENT OUALIFICATION PAGE 54 OF 96 P.C. 8 P301(O) Component: Laroe Valves -Manufacturer: Anchor Darline Valve Co. SNEET 3 of 13 E.P. ano. Model No. Functional Description Location IBCMV F027A E!! Not Applicable RHR Pump A Suppr Pool Spray Reactor Bldg. EL 077' 13CMV F027B E!! Not Applicable RHR Pump B Suppr Pool Spray Reactor Bldg. EL 077' 19CMV F940 E11 Not Applicable RHR Disch To Rdust Isin Outbd Reactor Bldg. ( EL 077' 19CMV F047A Ell Not Applicable RNR NK A Shell Side Inlet Reactor Bldg. i EL 077 13CNV F0475 E11 Mot Applicable RNR HK B Shell Side Inlet Reactor Bldg. EL 077' ' d IBCMV F049 E11 Not Applicable- RNR Flush to adust IsIn Inbd Reactor Bldg. EL 077' IDCMV F075 El1 Not Applicable RNR Svce Ntr Cross Tie Reactor Bldg. I EL 077' 19CMV 4426A Ell Not Applicable RHR HK A Vac RLF Isin Reactor Bldg. I EL 077' ' InCMV 4420s Ell Not Applicable RHR HK B Vac RLF Isin Reactor Bldg. EL 077' IBCMV 4421 Ell Not Applicable RHR HK B Vac RLF To Torus Reactor Bldg. EL 077' 19CMV C439 Ell Mot Applicable RK Bldg Isin/RNR S To Liq RN Reactor Bldg. EL 077' Itoelv F013 E51 Not Applicable RCIC Pump Suction From CS Tank Reactor Bldg. EL 054' 150erv F031 E51 Not Applicable RCIC Pump Suction From Sup Pool Reactor Bldg. ; EL 054' 15ENV F901A E21 Not Applicable Core Spray Pump AP206 Suction Reactor Bldg. EL 054' Q PSS 8/04 54-az I B
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NCGS FSAR TABLE 3.11-4 NECMANICAL BOUIPMENT St.LECTED FOR MARSN REV. 2 .. ENVIBONNENT OUALIFICATION PAGE 55 OF 96-P.C. O P381(O) Component Laree Valves Manufacturer: Anchor Berline Valve Co.' 'sNEET 4 of 13, I.n No. @ l No. Functional Descristion Locationi IDENW F90lt E21 mot Applicable Core Spray Pump BP206 Suction Reactor Bldg. EL 054' 18ENV F941C E21 Mot i n ..< ble Core Spray Pump CP206 Suction Reactor Bldg.
-EL 054' IDENW F9010 E21 Not Appi. wale Core Spray Pump DF206 Suction Reactor Bldg.
EL 054' 18ENV F9154 E21 Not Applicable CS Loop A Test Return Valve Reactor Bldg. EL 077' IBENV F9154 E23 Not Applicable CS Loop B Test Return valve Reactor Bldg. EL 077' l IDENV Fella E21 .Not Applicable Core Spray Loop A Nin Flow Bypass Peactor Bldg.. EL 054' , t IDENV F9318 E21 Not Applicable core Spray toop B Min Flow Bypass Reactor aldg. l EL 054' 1BFNV 4005 Not Applicable CRD Pump Suction RK Bldg Isla Reactor Oldg. EL 054' 1 INNV F984 541 Not. Applicable NPCI Pump Suctton From CST Reactor Bldg. EL 054' l INNV F942 E41 Mot Applicable NPCI Pump Suct From Supp Pool Reactor Bldg. EL 054' IECNV 4676A Not Applicable F1tr Domin Inlet Outhd Isin Reactor Bldg. EL 077' IECMV 46765 Not Applicable F1tr Domin Inlet Inbd Is1n Reactor Bldg. , EL 077' t i 1ECNW 4678 W2t Applicable F1tr Domin Outlet Isin Reactor Bldg. ' EL 077' IECMV 4689A Not Applicable Fuel Pool F1tr Domin Bypass Reactor Bldg. EL 162* t a Pe5 C/04 55-as t i
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Q y/ w/ l HCGS FSAR t TABLE 3.Il-4 [ NECHANICAL BOUIPNSNT SELECTED FOR HARSM REV. 2 ENVIRONNENT QUALIFICATION PAGE. -56 OF 96-P.C. O P30lf0) Components Large valves Manufacturer: Anchor Darlino Valve Co. SHEET 5 of 13 I.n. No. Model No. Functional Description Location I l IECMV 46898 Not Applicable Fuel Pool F1tr Domin Bypass Reactor Bldg. EL 162' - l IEDNV 2553 Not Applicable React Recirc Pump Cooling Isin Reactor Bldg. EL 102' l IEDNV 2554 Not Applicable React Rectre Pump Cooling IsIn Drywell Torus, Reactor Bldg. EL 100' IEDNV 2555 Not Applicable React Recire Pump Cooling IsIn Reactor Bldg.
. EL 102' IEDuv 2556 Not Applicable React Recirc Pump Cooling Isin Drywell Torus, Reactor Bldg.
l EL 100' l l IEENV 4652 Not Applicable Torus Wtr Clnup Supr P1 Isin Reactor Bldg. l EL 054' l l IEENV 4655 Not Applicable Torus wtr Clnup RX Bldg Isin Reactor Bldg. l EL 054' 1 ICENV 4656 Not Applicable Torus Wtr Clnup RX Bldg Isin Reactor Bldg. EL 054' i lEENV 4663 Not Applicable Torus Wtr Clnup RX Bldg IsIn Reactor Bldg. l EL 077' IEENV 4679 Not Applicable Torus Ntr Clnup RX Bldg Istn Reactor Bldg. EL 054' I IEENV 4680 Not Applicable Torus Wtr C1nup Suppr P1 IsIn Reactor Bldg. EL 054' IEENV 4651 Mot Applicable Torus Wtr Clnup Suppr P1 Isin Reactor Bldg. L l EL 054' i lECMV 2290A Not Applicable RNR Pump RN Unit Cooler AVH210 Reactor Bldg. j EL 054' IBGNV 22908 Not Applicable RHR Pump RN Unit Cooler BVH210 Reactor Bldg. EL 054' l 0 PS5 8/04 56-az l f l 1
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p {N f'] h WCGS FSAR C) - V ThaLE 3.11-4 NECNAMICAL EQUIPIIserr ssLECTEo rom NAasts REV. 2 EIfVIROINIEleT QuALIFICATICII PAGE - E OF 96 P.C. 8 PMl(O) Component: Laree valves IIanufacturer: Anchor Darlina valve'Co. 'sIIta? 6,of 13 I #. no. Ilodel Iso. Functional Description Location IBGIIV 2294C Ilot Applicable RIIR Pump met Unit Cooler CVN210 Reactor Bldg. EL 054' IEGIIV 2296D Not Applicable RNR Pump RIt Unit Cooler DVN210 Reactor Bldg. FL 054' leGeeV 2290E not Applicable RIIR Pump IWI Unit Coolers EVN210 Reactor Bldg. EL 077' IBcasv 2290r Isot Applicable ReIR Pump RII Unit coolers FVN210 Reactor 81dg. EL 077' IEGIIV 2290C mot Applicable IIIIR Pump RIt Unit Coolers CVN210 Reactor Bldg. EL 054' IBGetV 229001 Not Applicable RIIR Pump RIE Unit Coolers MVN210 Reactor Bldg. EL 054' IECarW 2292A mot Applicable NPCI Pump RII Unit Cooler AVN209 Reactor Bldg. EL 054' IBGlev 22923 Not Applicable NPCI Pump RIS Unit Cooler BVil209 Reactor aldg. EL 054' IEGesV 2M2A Isot Applicable FRVS Cooling Coil AVN213 Reactor Bldg. EL 132' loca:V 23423 slot Applicable FRVS Cooling coil SVN213 Reactor Bldg. EL 170' IEGIIV 2M2C Isot Applicable FItVS Cooling coil CVII213 Reactor aldg. EL 132' IBGEII 2342D Isot Applicable FRVS Cooling coil DUN 213 Reactor Bldg. EL 162' IBGifV 2382E Not Applicable FRVS Cooling Coll EVit213 Reactor aldg. EL 162' leGIIV 2382F ISot Applicable FRVS Cooling coil FVII213 Reactor Bldg. EL 170' , O P95 8/04 57-as
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I O t L (G HCGS FSAR TAaLE 3.11-4 NECMANICAL ROUIPetsgrf SELSCTED FOR NARSM - REV. 2 ENVImma*WT QUALIFICATIOII , PAGE M OF 96 P.O. O P3ellOf Components Large Valves Nanufacturer: Anchor Darlina Valve Co. SutET 7 of 13 I.n. No. Itodel No. Functional Description Location IBGEV 2325A Not Applicable Core Spray Pump Ret Unt Cls AVH211 Reactor Sldg. EL 054' IEGNV 23259 Not Applicable Core Spray Pump Rm Unt Cls BVH211 Eeactor Ridg. EL 054' IECHV 2325C Not Applicable Core Spray Pump Ret Unt Cls CVH211 Reactor Bldg.. EL 054' leQIV 2325D Not Applicable - Core Spray Pump RN Unt Cls DVH211 Reactor Bldg. EL 054' IEQsv 2325E Not Applicable Core Spray Pump met Unt Cls EVH211 Reactor Bldg. EL 054' - IEGaIV 2325F Not Applicable' Core Spray Pump Ret Unt C1s FVH211 Reactor Bldg. EL 054' IEQeV 2325G seot Applicable Core Spray Pump Ret Unt Cls GvH211 Reactor Bldg. EL 054' IFCMV F059 E51 Not Applicable RCIC Stm Esh Is1n valve Reactor Bldg. EL 077' IFCatV F962 151 Mot Applicable RCIC Vaccum Breaker Isla Valve Reactor Bldg. EL 077' IFCIIV F084 E51 Not Applicable RCIC Vacuum Breaker Isin valve Reactor Bldg. I EL 077' IFDetV F071 E41 Not Applicable NPCI Sta Enhaust Isin Valve Reactor Bldg. EL 077' IFDetV F075 E41 Not Applicable NPCI Turb Enh Vac Brkr Isin Reactor Bldg. EL 077* IFDIIV F079 E41 Not Applicable NPCI Turb Exh Vac Brke Isin Reactor Bldg. ' EL 077' IGaetV 9531A1 Ilot Applicable CH Ntr Loop A Sply CT9tT Istn Reactor Bldg. EL 102' j O PG5 8/04 58-az
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, U NCGS FSAR L; et TAaLE 3.11-4 NECHANICAL BOUIPettetT SELECTED FOR NARSM REY. 2 ENVIansamenT QUALI"ICATION PAGE_ 59 OF 96 (P.O. 8 F341(Q) Compomea.ts Large Valves Naaufacturer: Anchor Darline Valve Co. SMEET S,of 13 I.O. No. Model ho. Functional Description Location IGBWV 9531A2 Not Applicable CH Ntr Loop A RTM Ctat Isln Reactor Bldg. EL 102' I IGaNV 9531A3 Not Applicable CH wtr Loop B Sply Ctat Isla. Reactor Bldg. l EL 102' ICaWV 9531A4 Not Applicable CH wtr Loop B RTN Ctat Isin . Reactor Ridg. EL 102'- l IGaNV 953181 Not Applicable CH Ntr Loop A Sply Ctat IsIn Drywell Torus, Reactor Bldg. EL 100' IGaNV 953182 Mot Applicable CH Mtr Loop A RTM Ctat IsIn Drywell Torus, Reactor Bldg. ' EL 100'
- IGaNV 953183 Not Applicable Ch Wtr Loop B Sply Ctat Isin Drywell Torus, Reactor Bldg.
I EL 100' IGaNV 953184 Not Applicable CH Ntr Loop B RTN Ctat IsIn Drywell Torus, Reactor Bld(. EL 077' IGResy 9532-1 Not Applicable CH Ntr R'ai m Reactor Bldg Is1n Reactor Bldg. EL 162' 1GaNV 9532-2 Not Applicable CH Ntr Sply Reactor Bldg Istn Reactor Bldg. EL 162' IGSNV 50504 Not Applicable Drywell To H2 Recomb AS205 Drywell Tcrus, Reactor Bldg. EL I45' IGSNV 50508 seot Applicable Drywell To H2 Recomb BS205 Reactor Bldg. l EL 102' 1GSNV 5052A Not Applicable Drywell To N2 Recomb AS205 Reactor Bldg. , EL 145' ! IGSHV 58528 h Applicable Drywell To H2 Recomb BS205 Reactor Bldg. j EL 102' l l 1GSNV 5053A Not Applicable H2 Recomb AS205 Suppr. Pool Reactor Bldg. EL 077' O PSS S/04 59-az . 5 {
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-TASLE 3.11 NECMANICAL 80utresENT SELECTEo rom NAaSN REv. 2-
.ENVIRONNEBIT QUALIFICATION PAGE : R OF 96,-
P.O. 8 PMl(Q) e-- . r ; t s Laree valves . Manufacturer: Anchor Darline Valve Co. _SNEET 9 of M I n. No. 'Nodel No. Functione1 Deseristion Locattoni 1GSWF.54538 Not Applicable N2 Re' comb BS205 To Suppe Pool meactor 31dg. EL 077' ICSWW 5054A Not Applicable N2 Recomb AS205 To Suppe Pool .meactor aldg. EL 077' ICSNW 54548 seot Applicable -N2 Decemb BS205 To Suppe Pool neactor aldg. EL 077' IMONW F983 C14 teot Applicable Isla closure' Signal valve Drywell Torus, Reactor Bldg.r EL 077' INSWW F064 G14 teot Applicable Isa.e Closure Signal Valve Beactor Bldg. EL 077'
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INSWW 7919 c14 Not Applicable Drywell Equip Drain Sump Pump Drywell Torus, Reactor Bldg. EL 077' INSWW F029 C14 Ilot Applicable Drywell Equip Drain Sump Pump Reactor Bldg. EL 077' 1NeWw 5262 Mot Applicable as/Drywell Dr To Dr Call Tk Reactor Bldg. EL 077' Iment 5275 Not Applicable 9s/Drywell Dr to waste Coll Tk neactor aldg. EL 077' IIICNW 5551 Not Applicable Beactor Bldg IsIn valve Unit 1 seactor aldg. EL 132' 1:Aart 7626 slot Applicable meactor aldg Isolation Reactor aldg. EL 077' IEBMW 7629 Not Applicable Reactor Bldg Isolation Reactor. Bldg. RL 077' IESWF 7634 seot Applicable Spare Unassigned 1CNW 34488 Isot Applicable Sys IPD3-IPD11 Isin valve IV049 neactor 31dg. EL 077' C3 705 s/04 60-az
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.NCC3 FSAR TABLE 3.11-4 NECHANICAL EQUIPMENT SELECTED FOR NASSN ~REV. 2 EW IRONNENT QUALIFICATION 1 .PAGE R OF 96 P.O. 9 P301(O) Component:' Large Valves Manufacturers Anchor Darling Valve Co. SNEET g of M I.D. No. Model No. Functional Description (Nisc. Data) Location IECNV 3404N Not Applicable Spare Unassigned 12CMV 34000 Not Applicable Spare Unassigned 1 GNV 7401 Not Applicable areathing Air Valve Reactor Bldg.
EL 054' 1 C3 NV 5035 Not Applicable RB Nitrogen Sply Valve Reactor Bldg. EL 077' 1 SG W 2325N Not Applicable Core Spray Pump Rn Unit Cls Reactor Bldg. EL 054' 1 CC MV 3474 Not Applicable Spare Valve Unassigned 1 CC NV 3408P Not Applicable Spare Valve Unassigned - 1 EC NV 3400R Not Applicable Spare valve Unassigned 1 CEV 007 Not Applicable Check Valve (6*-HCC-CE) Reactor Bldg. IP&ID 53-1, N.R. No. 15.5) El. 054' 1 ECV 015 Not Applicable Check Valve (8*-NCC-CE) Reactor Bldg. (P6ID 53.1, M.R. No. 15.7) El. 054' 1 BCV 038 Not Applicable Testable Check Valve (6*-CBB-TCK) Reactor Bldg. IPEID 51-1, N.R. No. 3.91 El. 054 I aCV 002 Not Applicable Check Valve (IS*-CSS-CE) Reactor Bldg. IP6ID 51-1, M.R. No. 3.7) El. 054' 1 BCV 000 kot Applicable Check Valve (IS*-G8B-CE) Reactor Bldg. IP61D 51-1, N.R. No. 3.71 El. 054' 1 BCV 099 hot Applicable Check Valve (IS*-GSB-CE) Reactor Bldg. IPEID 51-1, N.R. No. 3.7) El. 054' 1 BCV 105 Not Applicable Check Valve (IS*-GSS-CE) Reactor Bldg. IP6ID 51-1, N.R. No. 3.7) El. 054' El PO5 8/04 61-az
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NCGS FSAR TABLE 3.11-4 MECMANICAL EQUIPREerr SELECTED FOR NARSN REV. 2 ENVImoesIEIrr OUALIFICATION PAGE'. g or 96 P.C. O P301(Q) Components Large Valves Manufacturer Anchor Darline Valve Co. SNEET 11, 1 of M-I .D. Iso. Model No. Functional Description (Misc. Detal Location l 1 DEV c13 Not Applicable Check Valve (12*-CBS-CK) Reactor Bldg. ! IP&ID 52-1, M.R. No. 3.51 E1. 054' j 1 SEV 014 Not Applicable Check Valve (12*-Cas-CK) Reactor aldg. [P61D 52-1, M.R. No. 3.51 E1. 0 54 ' 1 SEV 015 Not Applicable Check Valve (12*-Cas-CE) Reactor aldg. IP61D 52-1, M.R. No. 3.51 El. 054' 1 BEV 016 peot Applicable Check valve (12*-Gas-CK) Reactor Bldg. 1 (P6ID 52-1. M.R. No. 3.51 El. 054' l 1 AFV 042 Not Applicable Testable Check valve (4*-GSS-TCK) lleactor Bldg. [PEID 51-1, M.R. No. 3.31 E1 102' 1 AFV 043 100t Applicable Testable Check valve (4*-Ca8-TCK) Reactor Bldg. IP6ID 51-1, M.R. No. 3.31 . El. 102' 1 APV 045 seot Applicable Testable Check Valve (4*-Gas-TCK) Reactor 81dg. IPEID 51-1, M.R. No. 3.31 El. 102' 1 APV 046 Blot Applicable Testable Check Valve (4*-GSS-TCK) Reactor Bldg. I IP61D 51-1, M.R. No. 3.31 El. 102' 1 APV 054 tsot Applicable testable Check valve (4*-Cas-TCK) Reactor aldg. (P61D 51-1, M.R. No. 3.31 El. 102' 1 AFV 055 seot Applicable Testable Check valve (4*-GSS-TCK) Reactor Bldg. [P&ID 51-1, M.R. No. 3 31 E1 102' 1 AFV 057 Not Applicable Testable Check valve (4*-G88-TCK) Reactor Bldg. IP&ID 51-1, M.R. No. 3.31 E1. 102' 1 APW 058 stot Applicable Testable Check valve (4*-Ges-TCK) Reactor aldg. IP6ID 51-1, M.R. No. 3.31 E1. 102' O PSS 8/04 62-az i
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4 , k ( NCGs rSA3 TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED POR NARSH REV. 2 ENVIROISIENT QUALIFICATION PAGE M OP 96 P.O. 5 P301(O) Component: Large valves Manufacturer: Anchor Darling Valve Co. SNEET M of M I .D. No. Model No. Punctional Description (Misc. Detal Location 1 BCV 024 Not Applicable Testable Check valve (4*-CBB-TCK) Beactor Bldg. IP&ID 51-1, M.R. No. 3.31 El. 054' 1 BCV 030 I&st Applicable Testable Check Valve (4*-GSB-TCK) Reactor Bldg. IPEID 51-1, M.R. No. 3.31 El . 0 54 ' 1 BCV 033 Not Applicable Testable Check Valve (4*-GSB-TCK) Reactor Bldg. IPEID 51-1, M.R. No. 3.31 El. 054' 1 BCV 127 Not Applicable Testable Check Valve (4*-CBB-TCK) Reactor Bldg. IPEID 51-1, M.R. No. 3.31 El. 054' 1 BCV 130 Not Applicable Testable Check valve (4*-CBB-TCK) Reactor aldg. IP&ID 51-1, M.R. No. 3.31 El. 102' 1 BCV 163 Not Applicable ~ Testable Check Valve (4 *-CBS-TCK) Reactor Bldg. IP&ID 51-1, M.R. No. 3.31 . El. 102' 1 APV 039 Not Applicable Testable Check valve (3*-GBB-TCK) Reactor Bldg. IP&ID 52-1, M.R. No. 3.1) El. 102' 1 APV 040 Not Applicable Testable Check Valve (3*-CBS-TCK) Reactor Bldg. (P&ID 52-1, M.R. No. 3.1) El. 102' 1 Arv 060 Not Applicable Testable Check valve (3*-CBS-TCK) Reactor Bldg. IP&ID 52-1, M.R. No. 3 11 El. 102' 1 APV 061 Not Applicable Testable Check Valve (3*-GBB-TCK) Reactor Bldg. IP& ID 52-1, M.R. No. 3.11 El. 102' 1 BEV 028 Not Applicable Testable Check valve (3*-GBB-TCK) Reactor Bldg. IP&ID 52-1 M.R. No. 3.11 El. 054' 1 BEV 030 Not Applicable Testable Check Valve (3*-GBB-TCK) Reactor Bldg. IP&ID 52-1, M.R. No. 3.1) El. 054' 1 BEV 032 Not Applicable Testable Check Valve (3*-CBB-TCK) Reactor Bldg. IP&ID 52-1, M.R. No. 3.11 El. 054' 1 NEV 034 Not Applicable Testable Check Valve (3*-CBS-TCK) Reactor Bldg. IP&ID 52-1 M.R. No. 3.1] El. 054' O P85 8/04 63-az
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NCGS PSAR TABLE 3.11-4 . MECHANICAL BOUIPMENT SELECTED POR NARSH REY.' 2 . ENVIROWNENT OUALIFICATION --PAGE -64 OP 96-P.O. 9 P301(O) Component: Large Valves Manufacturer: Anchor Darlina Valve Co. SNEET 13 of 13 3.D. No. stodel No. Functional Description (Misc. Datal Location t 1 BDV 001 Not Applicable Testable Check Valve (6*-H88-TCK) Reactor Bldg. IPEID 49-1, M.R. No. 7.5) El. 054' i l 1 SDW 004 Not Applicable Testable-Check Valve (6*-HB8-TCK) Reactor Bldg. I , IPEID 49-1, M.R. No. 7.5) El. 054' i 1 FCV 003 Not Applicable Testable Check Valve (10*-HB8-TCK) Reactor Bldg. 1 IP&ID 49-1, M.R. No. 7.7) El. 054' 1 EJV 006 Not Applicable Testable Check Valve (16*-HRB-TCK) Reactor Bldg. IP&ID 55-1, M.R. No. 7.9) El. 054' 1 E3V 008 Not Applicable Testable Check Valve (16*-HBB-TCK) Reactor Bldg. IP&ID 55-1, M.R. No. 7.9) El. 054' 1 PDV 004 Not Applicable Testable Check Valve (20*-HBB-TCK) Reactor Bldg. (PEID 55-1, M.R. No. 7.111 El. 054' l l l l l 53 P85 8/04 64-az l
HCGS FSA*t TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 65 OF 96 P.O. 8 P302(O) Components Nuclear Valves Manufacturer Anchor Darling Valve Company SHEET l_ of 7
'I.D. No. Model No. Functional Description Location l 1ABHV F016 .821 Not Applicable Steam Line Drain Inbd Isin Drywell Torus, Reactor Bldg.
EL 100' 1ABHV F019 B21 Not Applicable Steam Line Drain Outbd Isln Reactor Bldg. EL 102' IABHV F020 B21 Not Applicable Main Steam Line Equalizer Valve Reactor Bldg. EL 132' 1ABHV F021 B21 Not Applicable Steam Line Start-up Drain Valve Reactor Bldg. EL 102' 1ABhv 3631A Not Applicable Main Steam Line A Stop Valve Reactor Bldg. EL 132' 1ABHV 3631B Not Applicable Main Steam Line B Stop Valve Reactor Bldg. EL 132' 1AiHV 3631C
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Not Applicable Main Steam Line C Stop Valve s Reactor Bldg. EL 132' IATHV 3631D Not Applicable Main Steam Line D Stop Valve Reactor Bldg. EL 132' IAEHV F0llA B21 Not Applicable Feedwater Inlet A Shutoff Drywell Torus, Reactor Bldg. EL 121' 1AEHV F0lls B21 Not Applicable Feedwater Inlet B Shutof f Drywell Torus, Reactor Bldg. EL 121' 1AEHV F032A B21 Not Applicable Fdw Line A Inlet Check Valve Reactor Bldg. EL 132' 1AEHV F0328 B21 Not Applicable Fdw Line B Inlet Check Valve Reactor Bldg. EL 132' 1AEHV F039 G33 Not Applicable RWCU Disch To Feedwater Reactor Bldg. EL 102'. lAEHV F074A B21 Not Applicable Fdw Line A Inlet Check Valve Peactor Bldg. EL 102' M P85 8/04 65-az
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HCCS PSA2 TABLE 3.11-4 NECHANICAL EOUIPNENT SELECTED FOR HARSH REV. 2 ENVIRONNENT OUALIFICATION PAGC 66 OF 96 P.O. O P302(O) Component: Nuclear Valves Nanufacturer Anchor Darlina Valve Company SHEET 2 of 7 I.D. No. Nodel No. Functional Description Location IAEHV F074B B21 Not Applicable Fdw Line B Inlet Check Valve Reactor Bldg. EL 102' 1APHV F0ll. E41 Not Applicable HPCI Disch Isin To Cst Sht off Reactor Bldg. EL 077' IECHV F008 E!! Not Applicable RHR Outboard Shtdn Clg Isin Reactor Bldg. EL 102' IBCHV F009 Ell Not Applicable RHR Inbd Shtdn Clg Isin Drywell Torus, Reactor Bldg. EL 100' IBCHV F015A Ell Not' Applicable RHR Shtdn Clg Inject Outbd Reactor Bldg.
. EL 102' IBCHV F015B Ell Not Applicable RHR Shtdn Clg Inject Outbd Reactor Bldg.
EL 102' IBCHV F017A Ell Not Applicable RHR/LPCI Line A Reactor Bldg. EL 102' IBCHV F017B Ell Not Applicable LPCI Injection Line B Reactor Bldg. EL 102' 1RCHV F017C Ell Not Applicable RHR/LPCI Line C Reactor Bldg. EL 102' IBCHV F017D Ell Not Applicable LPCI Injection Line D Reactor Bldg. EL 102' IBCHV F022 Ell Not Applicable RHR RPV Head Spray Isin Inbd Drywell Torus, Reactor Bldg. EL 145' IBCHV F023 Ell Not Applicable RHR RPV Head Spray Isin Outbd Reactor Bldg. EL 145' IECHV F052A Ell Not Applicable HPCI To RHR HX A Reactor Bldg. EL 077' 1BCHV F052B Ell Not Applicable RHR HX B Inlet Stop From HPCI Reactor Bldg. EL 077' N P85 8/04 66-az
,D D /3 HCCS FSAR TABLE 3.11-4 NECHANICAL EOUIPNENT SELECTED FOR HARSH REV. 2 ENVIRONNENT QUALIFICATION PAGE 67 OF 96 P.O. O P302(O) Component Nuclear Valves Nanufacturer: Anchor Darlina Valve Company SHEET 3 of 7 I.D. No. Nodel No. Functional Description Location IEDHV F012 E51 Not Applicable RCIC Pump Discharge Valve Reactor Bldg.
EL 054' IEDHV F013 PS1 .Not Applic.nble RCIC Feedwater Isin Valve Reactor Bldg. EL 102' 12DHV F022 E51 Not Applicable RCIC Test Loop Isin Valve Reactor Bldg. EL 077' lZEHV F004A E21 Not Applicable Core Spray Loop A Isin Valve Reactor Bldg. EL 102' ICEHV F004B E21 Not Applicable Core Spray Loop B Isin Valve Reactor Bldg. EL 102' IBEHV F005A E21 Not Applicable CS Loop A Containment Isin Reactor Bldg. EL 102' IBEHV F005B E21 Not Applicable CS Loop B Containment Isin Peactor Bldg. EL 102' IBGHV F001 G33 Not Applicable RWCU Inbd Isin Valve Drywell Torus, Reactor Bldg. ' EL 145' IBGHV F004 G13 Not Applicable RWCU Outbd-Isin Valve Reactor Bldg. EL 145' IBGHV F031 G33 Not Applicable RWCU Blowdown Orifice Bypass Reactor Bldg. , EL 132' ! IBGHV F034 G33 Not Applicable RWCU Disch to Condenser Reactor Bldg. EL 077' IBGHV F035 G33 Not Applicable RWCU Disch To Equip Drain Reactor Bldg. EL 077' , 1BCHV F100 G33 Not Applicable Suction From Recirc Loop A Drywell Torus, Reactor Bldg. EL 077' ! N P85 8/04 67-az
e {g p s. b U V HCGS FSAR TABLE 3.Il-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 68 OF 96 , P.O. 6 P302(O) Component: Nuclear Valves Manufacturer . Anchor Darling Valve Company SHEET 4 of 7 I .D. No. Model No. Functional Description Location IBCHV F101 G33 Not Applicable Suction From RPV Bdt Drn Drywell Torus, Reactor Bldg. EL 100' IBGHV F102 G33 Not Applicable Suction From Recirc Inside Cont Drywell Torus, Reactor Bldg. EL 100' IBGHV F106 G33 Not Applicable Suction From Recire Loop B Drywell Torus, Reactor Bldg. EL 077' 1BJHV F006 E41 Not Applicable HPCI/ Pump Discharge Valve Reactor Bldg. 3 EL 102' IBJHV F007 E41 Not Applicable HPCI Pump Discharge Valve Reactor Bldg. EL 054' IBJHV F008 E41 Not Applicable HPCI Test Bypass To CST Reactor Bldg. EL 077' i IBJHV F012 E41 Not Applicable Min Flow Bypass Valve Flow Reactor Bldg. EL 054' IBJHV 8278 Not Applicable HPCI Pump Dsch To Fdwtr Line Reactor Bldg. EL 124' IFCHV F007 E51 Not Applicable. Steam Supply Isin Valve Drywell Torus, Reactor Bldg. EL 100' IFCHV F008 E51 Not Applicable Steam Supply Isle Valve Reactor Bldg. l EL 102' IFCHV F045 E51 Not Applicable Recic Turb Steam Stop Reactor Bldg. EL 054' 5 1FDHV F001 E41 Not Applicable Turb Steam Supply Valve Reactor Bldg. EL 054' IFDHV FC32 E41 Not Applicable HPCI Pump Turb Stm Isin Valve Drywell Torus, Reactor Bldg, EL 100' IFDHV F003 E41 Not Applicable HPCI Pump Turb S'_m IsIn Valve Reactor Bldg. EL 102' M PBS 8/04 68-az
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.MCGS.FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH . REV. 2' ENVIROISIENT QUALIFICATION' PAGE . 49 OF 9 6 -
-P,0. O P302(O) Caponent: Nuclear Valves Manufacturer Anchor Darling Valve Company SHEET 5 of 7 I D. No. Model No. Functional Description. Location 1 ECV 074 Not Applicable RHR HX to Recirc System Valve ~ Drywel Torus, Reactor Bldg.
EL 100'. 1 ECV 183 Not Applicable RHR HX to'recirc. System Valve 'Drywell Torus, Reactor Bldg. EL 106' . 1 BG HV F044 G33- Not Applicable. RNCU Filter.domin bypass Reactor Bldg. EL 146' 1 BG HV F042 G33 Not Applicable Regen HK Rtn Isin Valve Reactor Bldg. EL 145' M P85 8/04 69-az i i
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HCGS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED POR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 70 Or 96 P.O. O P302(O) Co:monent: Nuclear Valves . Manufacturers -Anchor Darlina Valve Company SHEET 6_ of 7 I.D. No. Model No. Functional Description (Misc. Data] I.ocation
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I BG HV F104 G33 Not Applicable RNCU HX Bypass Valve Reactor Bldg. Bl. 132' 1 ECV 263 Not Applicable Check Valve (6"-DBA-CK) Drywell, Torus, Reactor Hldg. (PEID 51-1, M.R. No. 4.5] El. 162 1 BJV 003 Not Applicable Check Valve (14"-DBB-CK) Reactor Bldg. (P&ID 55-1, M.R. No. 7.3) El. 054' 1 EDV 010 Not Applicable Check Valve (6"-DBB-CK) Reactor Bldg. E1.054' [P&ID 49-1, M.R..No. 7.111 El. 054* 1 BGV 005 Not Applicable Check valve (3"-DBC-CK) Reactor Bldg. (P&ID 44-1, M.R. No. 10.1) El. 132' 1 BCV 009 Not Applicabl'e Check Valve (3"-DBC-CK) Reactor Bldg. IPEID 44-1, M.R. No. 10.1] El. 132' 1 AEV 003 Not Applicable Check Valve (24"-DLA-CK) s Drywell Torus, Reactor Bldg. [PEID 41-1, M.R. No. 16.31 El. 112' 1 AEV 007 Not Applicable Check Valve (24"-DLA-CK) Drywell Torus, Reactor Bldg. IPEID 41-1, M.R. No. 16.3]. E1. 112' T M P85 8/04 70-az
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HCGS FSAR'
. TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 71 OF 96 P.O. 0' P302(Q) Components Nuclear Valves Manufacturer Anchor Darling Valve Company SWEET 7 of 7
!.D. No. Model No. Functional Description [ Misc. Datal Location.
1 1 BJV 015 Not Applicable Testable Check Valve (4"-DBB-TCK) Reactor Bldg. [PsID 55-1, M.R. No. 7.7] El. 054' 1 APV 003 Not Applicable Testable Check Valve (10"-DBB-TCK) Reactor Bldg. iP&lD 55-1, M.R. No. 7.13) El. 077' 1 AEV 127 Not Applicable Testable Check Valve (4"-DBB-TCK) Reactor Bldg. [P51D 44-1, M.R. No. 7.9] El. 102' 1 AEV 128 Not Applicable Testable Check Valve (4"-DBB-TCK) Reactor Bldg. IP&ID 44-1, M.R. No. 7.9] El. 102' , 1 APV 005 Not Applicable Testable Check Valve (4"-DBB-TCK) Reactor Bldg. [P&ID 49-1, M.R. No. 7.9] El. 077' 1 APV 036 Not Applicable Testable Check Valve (3"-DBB-TCK) Reactor Bldg. IP&ID 55-1, M.R. No. 7.15) El. 102' 1 APV 037 Not Applicable Testable Check Valve ( 3 "- DBB-TCK ) Reactor Bldg. IP6ID 55-1, M.R. No. 7.15] El. 102' 1 APV 050 Not Applicable Testable Check Valve (3"-DBB-TCK) Reactor Bldg. [P&ID 49-1, M.R. No. 7.15] El. 102' 1 APV 051 Not Applicable Testable Check Valve (3"-DBB-TCK) Reactor Bldg. [PEID 49-1, H.R. No. 7.15] El. 102' M P85 8/04 71-az I
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( \ N.) HCGS FSA*1 I V) TABLE 3.11-4 4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE' 72 OF 96 P.O. SP303A(0) Components. Small Valves' Manufacturer: 'Rockwell International SHEET 1 of 17 I.D. No. Model No. Functional Description Location
.IABHV F067A B21 3624-MT MS Line A Outbd Drain Valve Reactor' Bldg.
EL 102' 1ABHV F0678 B21 3624-MT MS Line B Outbd Drain Valve Reactor Bldg. EL 102' i I ABHV F067C B21 3624-MT MS Line C Outbd Drain Valve Reactor Bldg. EL 102' 1AIHV F067D B21 3624-MT MS Line D Outbd Drain Valve Reactor Bldg. EL 102* 1ADHV F070A B21 3624-MT MS Line Downstream Drain Valve Reactor Bldg. EL 102' 1A!HV F070B B21 3624-MT MS Line B Downstream Drain Valve Reactor Bldg. EL 102' I A":HV F070C B21 3624-MT Mil Line C Downstream Drain Valve Reactor Bldg. EL 102' 1ABHV F070D B21 3624-MT MS Line D Downstream Drain Valve Reactor Bldg. EL 102' ! 1ABHV F071 B21 3624-MT ST Hdr Downstream Drain IsIn Valve Reactor Bldg. i EL 102' lEBHV F001 B21 3624-MT RV Head Vent To Drw Inbd Isin Drywell Torus, Reactor Bldg. EL 162' IBBHV F002 B21 3624-MT RV Head Vent To Drw Outbd Isin Drywell Torus, Reactor Bldg. EL 162' IBBHV F005 B21 3624-MT RV Head Vent To Steam Line A Drywell Torus, Reactor Bldg. EL 162' IBCHV F103A Ell 3624-MT HX A Vent Valve Outbd Reactor Bldg. EL 077' IBCHV F103B Ell 3624-MT RHR Heat Exchr B Vent Reactor Bldg. EL 077' M P85 8/04 72-az l
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[T V w V} HCCS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 73 OF 96 P.O. 8 P303A(Q) Component: Small Valves Manufacturer: Rockwell International SHEET 2 of 17 I.D. No. Model No. Functional Description Location 1BCHV F104A Ell 3624-MT HX A Vent Valve Inbd Reactor Bldg. - EL 077' IBCHV F104B Ell 3624-MT RHR Heat Exchr B Vent Reactor Bldg. i EL 077' IBCHV F122A Ell 36124MMRTl RHR HV-F050A Ell Bypass Drywell Torus, Reactor Bldg. i EL 100' { IBCHV F122B Ell 36124MMRTI
- RHR HV-F0508-E11 Bypass Drywell Torus, Reactor Bldg.
EL 100' IBCHV F146A Ell 36124MMRTl RHR HV-F041A Ell Bypass Reactor Bldg. EL 100' IBCHV F1468 Ell 36124MMRTl RHR HV-F041B Ell Bypass Drywell Torus, Reactor Bldg. EL 100' IBCHV P146C Ell 36124M;1RTl RHR HV-F041C Ell Bypass Drywell Torus, Reactor Bldg. EL 100'
, IBCHP F146D Ell 36124MMRT1 RHR IBC HV-F041D Ell Bypass Drywell Torus, Reactor Bldg.
EL 100' IBCHV 4428 3684-MT Steam Line Warmup Valve Reactor Bldg. EL 077' IBDHV F046 E51 3624-MT RCIC Turb Clg Wtr Supply Reactor Bldg. EL 054' , IBEHV F039A E21 36124MMRTl HV-F006A Bypass Test Valve Drywell Torus, Reactor Bldg. EL 100' lbEHV F039B E21 36124MMRTl HV-F006B Bypass Test Valve Drywell Torus, Reactor Bldg. { EL 100' IBFHV 3800A 36224-F316LMT Recirc Pump A Supply Reactor Bldg.
, EL 077' I
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v HCCS FSAR TABLE 3.11-4 MECHAMICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 3 OF 9_6 P.O. O P303A(0) Components. Small valves ' Manufacturer Rockwell International SHEET 3,of 17-j I.D. No. Model No. Functional Description Location i
- 11FHV 38008 36224-F316LMT Rectre Pop B Sply Reactor Bldg.
j EL 077' i
- IBGHV 3980 3624-MT React Bldg. Isin Valve To Cwt Reactor Bldg. .
EL 132' ! 11.HHV F006A C41 3624F316-LMT Slc Outbd Isin Stop Chk A Drywell Torus, Reactor Bldg. EL 145' IIHHV F0068 C41 3624F316-LMT Sic Outbd Isin Stop Ckh B Drywell. Torus, Reactor Bldg. EL 145' IBJHV F059 E41 3624-MT HPCI L.O. Cooling Water Valve Reactor Bldg.
- EL 054'
) IBJHV 4803 3624-MT Suppr Pool Lvl Instr-LP IsIn Reactor Bldg. EL 077' 1 IBJHV 4804 3624-MT Suppe Pool Lvl Instr-Hp Tap Reactor Bldg. 9 EL 054' i ] IBJHV 4865 3624-MT Suppr Pool Level Instr-Lp Tap Reactor Ridg. EL 054' i IBJHV 4866 3624-MT Suppr Pool Level Instr-Hp Tap , Reactor Bldg. EL 054' IECHV 4647 36224-F16LMT Fuel Pool Makeup'SSWS Loop A Reactor Bldg. EL 162' IECHV 4648 36224-F16LMT LP B Emerg Makeup To Fuel Pool Reactor Bldg. EL 162' IEGHV 2293A 36124MMRTl Reic Pop RM Unit Cooler AVH208 Reactor Bldg.
!EL 054' IECHV 22938 36124MMRTl Reic Pmp RM Unit Cooler AVH208 Reactor Bldg.
EL 054' { IEGHV 2320A 3624-MT Containst Instr Gas Comp Clr Reactor Bldg.
; EL 132' M P85 8/04 74-az l
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g ] ~[^\ a a HCGS FSAR u TABLE 3.11-4' MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONeggNT QUALIFICATION PAGE 75 OF 96 P.O. 8 P303A(Q) Component: Small Valves Manufacturers -Rockwell International SHEET-4,of E I.D. No. Model No. Functional Description Location IEGHV 23208 3624-MT Containst Instr Gas Comp Clr. Reactor Bldg. EL 132' IECHV 2321A 3624-MT Containst Instr Gas Comp Clr Reactor Bldg. EL 132' IEGHV 23218 3624-MT Containst Instr Gas Comp Clr Reactor Bldg. EL 132' IECHV 2446 3624-MT Emerg Clg Wtr M/U To SACS LP A Reactor. Bldg. EL 102' IEGHV 2447 3624-MT Emerg Clg Wtr M/U To SACS LP B Reactor Bldg. EL 102' IECHV 2452A 3624-MT Containst Instr Gas Comp Clr A Reactor Bldg. EL 132' IEGHV 2452B 3624-MT Containst Instr Gas Comp Clr e Reacter Bldg. N EL 132' IECHV 2453A 3624-MT ~ Con _tainst Instr Gas Comp Clr Reactor Bldg. EL 132' IEGHV 24538 3624-MT Containst Instr Gas Comp Clr Reactor Bldg. EL 13 2 ' IECHV 2480A 36224P316LMT Sacs Expan. Tnk Make Up Reactor Bldg. EL 201' IECHV 24808 36224F316LMT Sacs Expansion Tnk Make Up Reactor Bldg. EL 162' IECHV 2520A 36124 MMRTl RHR Cooler Pop AP202 Reactor Bldg. EL 054' . IEGHV 2520s 36124 MMRTl RHR Cooler Pop BP202 Reactor Bldg. EL 054' IECHV 2520C 36124 MMRTl RHR Cooler Pop CP202 Reactor Bldg. EL 054' M P85 8/04 75-az e w-
NCGS FSAR ~ TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH. REV. 2-ENVIRONMENT QUALIFICATION PAGE 76 OF 96 P.O'.'S P303A(0) Component: Small valves _ Manufacturers Rockwell International SHEhr 5,of Q I.D. No. Model No. Functional DescriDtion Location 1 i IEGHV 2520D 36124 MMRTl 9HR Cooler Pop DP202 . Reactor Bldg. . . j EL.054' IFCHV F004 ESI 16124 MMRTl Reic Vac Tnk Cond Pop Drain Reactor Bldg. EL 054' IFCHV F025 E51 36124 MMRTl Rcic Steam Trap Isin valve Reactor Bldg.
! EL 054' IFCHV F026 E51 36124 MMRTl Rcic Steam Trap Isin Valve Reactor Bldg.
EL 054' i IFCHV F060 E51 3624-MT Rcic Vacuum Pump Discharge valve Reactor Bldg. EL 077' i IFCHV F076' E51 3624-MT Reic Isolation valve Bypass. Drywell Torus, Reactor Bldg. EL 100' IFDHV F026 E41 36124 MMRTl Vac Tk Cond Pop Disch To Crw Reactor Bldg.- EL 054' i IFDHV F028 E41 36124 MMRTl HPCI Stm Trap Isin valve Reactor Bldg. } EL 054' 4 IFDHV F029 E41 36124 MMRTI HPCI Sta Trap Isln Valve Reactor Bldg. .; EL 054' IFDHV F100 E41 3624-MT HPCI Narmup Line IsIn Valve Drywell Torus, Reactor _ Bldg. EL 100' ! IFDHv4922 3624-MT Containment Purge Valve Bypass Reactor Bldg. I (Re-tagged by field, was previously EL 149'
- IGSHV4951 and before that IKPHV6056) t l
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TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT OUALIFICATION PAGE 77 OF 96-P.O. O P303A(Q) Component: Small Valves Manufacturers Rockwell Intwrnational SHEET 6 of 17 I.D. No. Model No. Functional Description Location IGSHV 4955A 3684-F16LMT Drywell ATM Sample Isin Reactor Bldg. EL 132' ICSHV 49558 3684- F16 LMT Drywell ATM Sample Isin Reactor Bldg. EL 162' ICSHV 4959A 3684-F16LMT Supp Chabr ATM Sample Isin Reactor Bldg. EL 077' IGSHV 49598 3684-F16LMT Supp Chabr ATM Sample Isin Reactor Bldg. EL 077' ICSHV 4963 3624-MT Supp Chabr Purge Exhaust (Spare) Reactor Bldg. EL 077' IGSHV 4965A- 3624-F16LMT Supp Chabr ATM Sample Isin Reactor Bldg. EL 077' IGSHV 4965B 3624-F16LMT Supp Chmbr ATM Sample Isin Reactor Bldg. EL 077' IGSHV 4966A 3624-F16LMT Supp Chabr ATM Samp RTN Isin Reactor Bldg. EL 077' IGSHV 4966B 3624-F16LMT Supp Chabr ATM Samp RTN Isin Reactor Bldg. EL 102' IGSHV 4974 3624-MT Nitrogen Makeup Istn Reactor Bldg. EL 102' IGSHV 4983A 3624-F16LMT Drywell Sample Isin Reactor Bldg.
)
EL 132' IGSHV 49838 3624- F16 tJIT Drywell Sample IsIn Reactor Bldg. EL 162' ICSHV 4984A 3624-F16LMT Drywell Sample Isin Reactor Bldg. EL 162' ICSHV 4984B 3624-FIELMT Drywell Sample Is1n Reactor Bldg. EL 162' A P85 8/04 77-az
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%J' TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 78 OF 96 P.O. 9 P303A(0) Corsponent Small Valves Manuf acturer: Rockwell International SHEET 7 of M I.D. No. ,Model No. Functional Description Location IGSHV 5019A 3624-F16LMT Drywell ATM Sample Isln Reactor Bldg.
EL 162' ICSHV 5019B 3624-F16LMT Drywell ATM Sample Isin Reactor Bldg. EL 162' l ICSHV 5022A 3624-F16LMT Chabr AT.4 Samp RTN Isin . Reactor Bldg. I EL 077' ICSHV 5022B 3624-F16 LMT Chmbr ATM Samp RTN Isin Reactor Bldg. EL 102' 1GSHV 5741A 36224-F316LMT R2/02 Analyzer A H2 Supply Reactor Bldg. EL 132'
- IGSHV 5741B 36224-F316 LMT H2/02 Analyzer B H2 Supply Reactor Ridg.
EL 132' IKLHV 5124A 36224-F316LMT Supply HDR A Shutoff Valve Drywell Torus, Reactor Bldg. EL 100' IKLHV 51248 36224-F316LMT Supply HDR B Shutoff Valve Drywell Torus, Reactor Bldg. EL 121' i IKLHV 5126A 3624-MT Instr Gas HDR A Outbd Isin Reactor Bldg. EL 102' IKLHV 5126B 3624-MT Instr Gas HDR B Outbd Isin Reactor Bldg. EL 102' IKLHV 5147 3624-MT Instr Gas Cprar A Suct Isin Drywell Torus, Reactor Bldg. EL 132' , IKLHV 5148 3624-MT Instr Gas Cprsrs Suct Isin Drywell Torus, Reactor Bldg. l EL 145' IKLHV 5152A 3624-MT Instr Gas Hdr A Inbd Isin Drywell Torus, Reactor Bldg. EL 100' M PB5 8/04 78-az
'A N U J MCCS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 BNVIRONMENT OUALIFICATION PAGE 79 OF 96 -
P.0, f P303A(0) Component: Small valves Manufacturer: Rockwell International SHEET of I.D. No. Model No. Functional Description Location IKLHV 51528 3624-MT Instr Gas HDR S Inbd Isin Drywell Torus, Reactor Bldg.' EL 112' IFLHV 5154 36124MMRT1 Instr Gas To Vac RV Outbd Isin Reactor Bldg. EL 077' IKLHV 5155 36124MMRTI Instr Gas To Vac RV Inbd Isin Reactor Bldg. EL 077' IKLHV 5156A 36124MMRTl Instr Gas Sply HDR A Xconn Reactor Bldg. EL 102' IKLHV 5156B 36124MMRTl Instr Gas Sply HDR B Xconn Reactor Bldg. EL 102' IKLHV 5160A 3624-MT Instr Gas CPRSR A LOCA Suct Reactor Bldg. EL 132' IKLHV 51608 3624-MT Instr Gas CPRSR R IDCA Suct ' Reactor Bldg. i EL 132' 1KLHV 5162 3624-MT Instr Gas CPRSRS Suct Isin Reactor Bldg. EL 132' IKLHV 5172A 3624-MT ' Instr Gas To Vac Brkr Acc A Reactor Bldg. t EL 102' 1 IKLHV 51728 3624-MT Instr Gas To vac Brkr Acc B Reactor Bldg. 1 EL 102'
- IKLHV 6057 36124MMRTl Seal Gas Test Line Isin Reactor Bldg.
EL 077' j IKPHV 5829A 3624-MT MSIV Inbd Seal Gas Sply Sov 1 Reactor aldg. EL.102' i lEPHV 58298 3624-MT MSIV Outbd Seal Gas Sply Sov il Reactor Bldg. z EL 102' i IKPHV 5834A 3624-MT MSL A MSIV Inbd Seal Gas Sply 4 Reactor Bldg. EL 102' M P85 8/04 79-az i 1
g , 4 3 y } , \v! HCGS FSAR TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 ' ENVIRONMENT OUALIFICATION PAGE 80,OF 96 P.O. 8 P303A(0) Components Small Valves Manufacturers Rockwell International SHEET 9,of 17 I.D. No. Model No. Functional Description . Location i IKPHV 58348 3624-MT MSL B MSIV Outbd Seal Gas Sply Reactor Bldg. EL 102' IKPHV 5835A 3624-MT MSL B MSIV Inbd Seal Gas Sply Reactor Bldg. EL 102' IKPHV 58358 3624-MT MSL B MSIV Outbd Seal Gas Sply Reactor Bldg. EL 102' IKPHV 5836A 3624-MT MSL C MSIV Inbd Seal Gas Sply Reactor Bldg. EL 102' IKPHV 58368 3624-MT MSL C MSIV Outbd Seal Gas Sply Reactor Bldg. EL 102' IKPHV 5837A 3624-MT MSL 0 MSIV Inbd Seal Gas Sply Reactor Bldg. EL 102' IKPHV 5837B 3624-MT MSL D MSIV Outhd Seal Gas Sply s Reactor Bldg. EL 102' IKPHV 6055A 36124MMRTl Inbd Seal Gas Test Line Isln Reactor Bldg. EL 102' IKPHV 6055B 36124MMRTl Outbd Seal Gas Test Line Isin Reactor Bldg. EL 102' ISEHV 5161 36124MMRTl Tip Purge Containment Isin Reactor Bldg. EL 100' ISKHV 4953 36224-F16LMT Drywell Gas Sample Isolation Reactor Bldg. EL 162' ISKHV 4957 36224-F16LMT Drywell Sample Return Isolation Drywell Torus, Reactor Bldg. EL 145' ISKHV 4981 36224-F16LMT Drywell Sample Return Isolation Drywell Torus, Reactor Bldg. EL 145' ISKHV 5018 36224-F16LMT Drywell Gas Sample Isolation Reactor Bldg. EL 162' M P85 8/04 80-az
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Q \ G HCGS FSAR TABLE 3.11-4 MECHANICAL BOUIPMENT SELECTED PDR HARSH REV. 2 ENVIRONMENT QUALIFICATION- PAGE E OF 6 P.O. 8 P303A(Q) Components Small Valves Manuf acturer Rockwell International SHEET 10 of 17 I.D. No. Model No. Functional Description (Misc. Data) Location 1 Bev 043 36274F316LTl Check Valve (3/4"-CCA-CK) Drywell Torus, Reactor Bldg.- IP&ID 43-1, M.R. Item No. 6.3] El. 094' 1 CBV 047 36274F316LTl Check Valve (3/4"-CCA-CK) Drywell Torus, Reactor Bldg. 4 IP&ID 43-1, M.R. Item No. 6.3) El. 094' 1 BHV 004 36274F316LT1 Check Valve (1-1/2"-CCA-CK) Reactor Bldg. [P&ID 48-1, M.R. Item No. 6.5) El. 168' 1 BHV 005 36274F116LT1 Check Valve (1-1/2"-CCA-CK) Peactor Bldg. IPEID 48-1, M.R. Item No. 6.5) El. 168' I BHV 029 36274F316LT1 Check Valve (1-1/2*-CCA-CK) Drywell Torus, Reactor Bldg. IP&ID 48-1, M.R. Item No. 6.5] El. 148' 1 BCV 195 838YTl Check Valve (l"-EBA-CK) Reactor Bldg. [PEID 51-1, M.R. Item No. 9.1] El. 056' ! 1 BCV 206 838YT1 Check Valve (l"-EBA-CK) Reactor Bldg. IP&ID 51-1, M.R. Item No. 9.1) El. 065' i 1 ECV 207 838YTl Check valve (l"-EBA-CK) Reactor Bldg. ! (P&ID 51-1, M.R. Item No. 9.1) El 057' 1 BCV 208 838YTl Check Valve (l"-EBA-CK) Reactor Bldg. IP&ID 51-1, M.R. Iten No. 9.1] El. 057' 1 ECW 210 838YT) Check Valve (l"-5BA-CK, Reactor Bldg. (P&ID 51-1, M.R. Item No. 9.1] El. 057' 1 BCV 211 838YT1 Check Valve (l"-EBA-CK) Reactor Bldg. 1 (P&ID 51-1, M.R. Item No. 9.1) El. 057' i M P85 8/04 81-as 1
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,' TABLE 3.11-4 MECHAMICAL EQUIPMElfr SELECTED FOR HARSH REV. 2-F4VIROISIENT QUALIFICATICBI PAGE M OF 96 P.O. O P303A(Q) Components ~ Small Valves Manufacturers -Rockwell international SNEET 11,of M I .D. No. Model No. Functional Description IMisc. Detal Location 1 BCV 260 838YTl Check valve (l"-EBA-CK) Reactor Bldg.
[P6ID 51-1, M.R. Item No. 9.11 El. 065' 1 CSV 081 838YTl Check Valve (l"-EBA-CK) Reactor Bldg. [P6ID 57-1, M.R. Item No. 9.1] El. 096' 1 GSV 093 838YTl Check valve (l"-EBA-CK) Reactor Bldg. [PEID 57-1, M.R. Item No. 9.11 ' El . 0 96 ' 1 CSV 138 838YTl Check valve (l"-EBA-CK) Reactor Bldg. IP6ID 57-1, M.R. Item No. 9 1] El. 096' 1 CSV 139 838YTl check Valve (l"-EBA-CK) Reactor Bldg. IP6ID 57-1, M.R. Item No. 9.1) El . 0 96 ' 1 KLV 005 838YT1 Check Valve il"-EBA-CK) Reactor Bldg. [P6 ID 59-1, M.R. Item No. 9.1) El. 133' 1 KLV 006 838YT1 Check Valve (l"-EBA-CK) Reactor Sldg. IP61D 59-1, M.R. Item No. 9.1] El. 133' M P85 8/04 82-az
NCGS FOAR TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 83 OF 9J P.O. O P303A(0) Component: Small valves Manufacturers Rockwell International SHEET 12 of M I.D. No. Model No. Functional Description (Misc. Datal Location 1 BCV 089 838YTl check Valve (l*-EBA-CK) Reactor Bldg. IP6ID 51-1, M.R.-No. 9.11 El. 057' 1 BCV 090 8387T1 Check valve (1*-EBA-CK) Reactor Eldg. IFsID 51-1, M.R.-No. 9.11 El. 057' 1 BCV 194 83Sf71 Check Valve (!"-EBA-CK) Reactor Bldg. [PE ID 51-1, H.R.-No. 9.11 El. 056' IEG-HV 2542A 36124 MMRTl - (System Spare) Reactor Bldg. Unassigned IEG-HV 25428 36124 MMRTI (System Spare) Reactor Bldg. Unassigned IEG-HV 2543A 36124 MMRTI (System Spare) Reactor Bldg. Unassigned IEG-HV 2543B 36124 MMRTl (System Spare) Reactor Bldg. Unassigned ICS HV 4963 36124 MMRTl (System Spare) Reactor Bldg. Re-tagged by field, was previously IKLHV 5175 Unassigned IAB-HV F073 B21 36124 MMRTl (System Spare) Reactor Bldg. Unassigned IBC Hy 5055A 3624-MT Valve from RHR HX to Hydrogen Recombiner Rector Bldg. EL 058' IBC HV 50558 3624-MT Valve from RHR HX to Hydrogen Recombiner Reactor Bldg. EL 090' IGS HV 5057A 3624-MT Valve from RHR HX to Hydrogen Recombiner Reactor Bldg. EL 058' IGS HV 50578 3624-MT Valve from RHR HX to Hydrogen Recombiner " Reactor Bldg. EL 090'. M PSS 8/04 83-as
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( t s C/ (V ' HCGS FSAR TABLE 3.11-4 MECHANICAL BOUIPMENT SELECTED POR MARSH REV. 2 ENVIROINSENT QUALIFICATION PAGE 84 OF 96 P.O. 8 P303A(0) Components small Valves Manufacturer: Ro: kwell Internattocol SNEET 13 of E I.D. No. Model No. Functional Description (Misc. Datal Location 1 BCV 308 838YT1 Check Valve (2"-EBA-CK) Reactor Bldg. (P&ID 52-1, M.R. Item No. 9.5) El. 056' 1 CCV 3C9 838YTl Check Valve (2"-EBA-CK) Reactor Bldg. IPEID 52-1, M.R. Item No. 9.5) El. 056'
! BCV 312 838YT! Check Valv1 (2"-EBA-CK) Reactor Bldg.
IP&ID 52-1, M.R. Item No. 9.5) El. 056' 1 CCV 313 838YT1 Check Valve (2*-EBA-CK) Reactor- Bldg. IPEID 52-1, M.R. Item No. 9.5] El. 056' 1 BCV 423 838YT1 Check Valve (2"-EBA-CK) Reactor Bldg. IP&ID 10-1, M.R. Item No. 9.5) E1. 108' 1 ECV 023 838YTl Check Valve (2"-EBA-CK) Reactor Bldg. IPEID 50-1, M.R. Item No. 9.5) El. 061' 1 BJV 027 838YTl Check Valve (2"-EBA-CK) Reactor Bldg. [P&ID 56-1, M.R. Item No. 9.51 El. 061' 1 EAV 557 838YT1 Check Valve (2"-EBA-CK) Reactor Bldg. IPEID 10-1, M.R. Item No. 9.5) E1. 103' 1 ECV 704 838YTl Check Valve (2"-EBA-CK) Reactor Bldg. IP&ID 11-1, M.R. Item No. 9.5) El. 056' 1 EGV 705 838YT1 Check Valve (2"-EBA-CK) Reactor Bldge. IP&ID 11-1, M.R. Item No. 9.51 El. 056' 1 EGV 706 838YT! Check Valve (2"-EBA-CK)
- Reactor Ridg.
[P&ID 11-1, M.R. Item No. 9.5) El. 057' 1 EGV 707 838YT1 Check Valve (2*-EBA-CK) Reactor Bldg. IP&ID 11.1, M.R. Item No. 9.5) E1. 058' 1 FCV 010 838YT1 Check Valve (2*-EBA-CK) Reactor Bldg. IP&ID 49-1, M.R. Item No. 9.5) El. 061'. M P85 8/04 84-as
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NCGS FSAR TABLE 3.11-4 MECHANICAL EQ'JIPMENT SELECTED FOR HARSH ' REV. 2 ENVIRONMENT QUALIFICATION PAGE 85 or 96 - P.O. 8 P303A(0) Components Small valves Manufacturer: Rockwell International SHEET H of E I.D. No. - 'Model No. Functional Description [ Misc. Data] Location 1 FDV 032 838YT1 Check valve (2"-EBA-CK) Reactor Bldg. (P&ID 56-1 M.R. Item No. 9.5] El. 061' 1 FDV 038 838YT1 Check Valve (2*-EBA-CK) Reactor Bldg. [P&ID 56-1, M.R. Item No. 9.5] E1. 061' 1 GUV 032 838YT1 Check Valve (2"-EBA-CK) Reactor Bldg. [P&ID 84-1, N.R. Item No. 9.5l E1. 085'
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_ _ . - __ - _ _. - . - - . _ , . . _ . . . .~ ._ ._. . . ' _ S FSA. TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSM REV. 2 ENVIRONMENT 00ALIFICATION PAGE . 86 OF 96
- P.O. 8 P303A(0) Component
- Small Valves Manufacturers. acekwell International SHEET 15 of 17
!.D. No. Model No. Functional Description _ Location IAew F033 821 ~36124MMRTI steam Line Inboard Drain Valve peactor islc,.
EL 102 j I ASW F068 821 3624-MT MS Outbd Drain HDR Startup Valve Reactor B1dg. j EL 102' IELW 5125 36124MMRT1 Instr. Air Backup Sply peactor Bldg. EL 132' IEDW F019-E51 3624MT RCIC Pump min. flow bypass (Spare) Reactor Bldg. 1 EL 078' IBGW F101 3624MT System Spare peactor Bldg. i (Re-tagged by field, was previously 1EGHV 2313A)- Unassigned IECHV 23138 3624MT System' Spare Reactor Bldg. j- Unassigned-1 1 IELHV 5189A 36224-F316LMT Spare unassigned i lELHV 51898 36224-F316LMT Spare Unassigned l l i 1 ! t ] I r '. k i
! M P85 8/04 86-as t
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e (" . _' HCGS FSAR TABLE 3.11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 E*lVIltONMENT QUALIFICATION PAGE 87 OF 96 P.O. 8 P303A(Q) Component Small Valves Manufacturers Rockwell International SHEET 16 of 17 1.D. No. Model No. Functional Description [ Misc. Data] Location I 1 KLV 023 938TT1 wheck Valve (2" EBA-CK) Reactor Bldg. (P&ID 59-1, M.R. No. 9.5) El. 116' 3 I KLV 024 838YTl . Check Valve (2" ERA-CK) Reactor Bldg. IP&ID 59-1, M.R. No. 9.5] El. 116' i i 1 BDV 020 '.6174T1 Check Valve (l" CBA-CK) Reactor Bldg. IP&ID 49-1, M.R. No. 3.3] El. 060' l 1 BDV 029 36174T1 Check Valve (l" CBA-CK) Reactor Bldg. [P&ID 49-1, M.R. No. 3.31 El. 060' i 1 BJV 014 36174T1 Check Valve (l" CBA-CK) Reactor Bldg. [PEID 49-1, M.R. No. 3.31 El. 062' 1 BJV 023 36174T1 Check Valve (l" CBA-CK) Reactor Bldg. [P&ID 49-1, M.R. No. 3.31 El 062'
! CDV 006 3617471 Check Valve (2"-CBA-CK) Reactor Bldg.
! (P&ID 72-1, M.R. No. 3.7) El. 064' 1 KPV 011 36174T1 Check Valve (2"-CDA-CK) Reactor Bldg. [P&ID 72-1, M.R. No. 3.7) El. 116' 1 KPV 017 36174T1 Check Valve (2"-CBA-CK) Reactor Bldg. [P&ID 72-1, M.R. No. 3.71 El. 109' 1 KPV 018 36174T1 Check Valve (2*-CBA-CK) Reactor Bldg. [PEID 72-1, M.R. No. 3.7] El. 109' i i
! M P85 8/04 87-as l
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NCGS PSAR TABLE 3.11-4 NECHANICAL EOUIPNENT SELECTED POR HARSH REV. 2 ENVIRONNENT OUALIFICATION PAGE- 88 OP 96 P.O. 8 P303A(Q) Component: Small valves Manuf acturers Rockwell International SHEET. E of 1,7, I.D. No. Nodel No. Functional Description (Nisc. Datal Location I KPV 019 36174TI Check Valve (2"-CBA-CK) Reactor Bldg. [PEID 72-1, N.R. No. 3.71 El. 109' 1 KPV 070 36174T1 Check Valve (2*-CBA-CK) Reactor Bldg.. IPEID 72-1, N.R. No. 3.7) El. 109' 1 KPV 021 36174T1 Check valve (2"-CBA-CK) Reactor Bldg. IPsID 72-1, N.R. No. 3.7) El. 116' I CDV 022 36174T1 Check valve (2"-CBA-CK) Reactor Bldg. [PEID 72-1, N.R. No. 3.7) El. 116' I EDV 023 36174T1 Check Valve (2"-CBA-CK) Reactor Bldg. IPEID 72-1, N.R. No. 3.7) El. 116' l 53 P85 8/04 88-as ! 1
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HCGS FSAR TABLE 3.11-4 MECHANICAL BOUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 89 OF 96 P.O. O P305(O) Component Butterfly Valves Manufacturer B.I.F/ Unit of General Sianal SHEET 1,of 4, I.D. No. Model No. Functional Description Location IEAHV F073 Not Applicable Emerg Clg Ntr M/U Loop B Reactor Bldg. l EL 077' ! IEAMV 2203 Not Applicable SSWS Loop A To RACS HK Reactor Bldg. EL 102' IEAHV 2204 Not Applicable RACS HTX Clg Wtr From Loop B Reactor Bldg. EL 102' IEAHV 2207 Not Applicable RACS HX Cooling Wtr Inlet Reactor' Bldg. EL 102' IEAHV 2234 Not Applicable Emerg Clg Wtr M/U Loop A Reactor Bldg. EL 077' IEAHV 2236 Not Applicable Emerg Wtr M/U Loop A IsIn Reactor Bdig. EL 077' IEAHV 2238 Not Applicable Emerg Wtr M/U Loop B Isin Reactor Bldg. EL 077' , IEAHV 2346 . Not Applicable RACS HTX Clg Wtr Disch Isin V. Reactor Bldg. EL 077' IEAHV 2355A Not Applicable SACS HTX A2E201 Outlet Reactor Bldg. EL 102' IEAHV 2355B Not applicable SACS HTX B2E201 Outlet Peactor Bldg. EL 102' IEAHV 2356A Not Applicable SACS LP A To Yard Dump Reactor Bldg. J EL 102' IEAHV 2356B Not Applicable SACS LP B To Yard Dump Reactor Bldg. EL 102' IEAHV 2357A Not Applicable SACS LP A To C1g Tower Reactor Bldg. 4 EL 077' IEAHV 23578 Not Applicable SACS LP B To Clg Tower Reactor Bldg. EL 077' M PBS 8/04 89-az ' l s I
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) j- d-NCCS FSAR TABLE 3.11-4 NECHANICAL BOUIPMENT SELECTED FOR NARSM REV. 2-ENVI N T OUALIFICATION PAGE _90 OF _96-P.O. O P305(O) Coeponents Butterfly Valves Manufacturers B.I.F/ Unit Of General Signal SHEET 2 of 4 ..
I.D. No. Model No. Functional Description Location t IEANV 2371A Not Applicable SACS HTX AIE201 Outlet Reactor. Bldg. EL 102'. IEANV 23718 Not Applicable SACS HTX BIE201 Outlet Reactor' Bldg. EL 102' IEDNV 2598 Not Applicable Reac/ Aux Bldg Isin Reactor Bldg. EL 054' IEDHV 2599 Not Applicable Reac/ Aux Bldg Isin Reactor Bldg. EL 054' ' I IEGNV 2314A Not Applicable Fuel Pool HX AE202 Reactor Bldg. EL 162' IEGNV 23148 Not Applicable Fuel Pool HX BE202 Reactor Bldg. EL 162' ' j IEGHV 2317A Not Applicable Fuel Pool HX AE202 ' s Reactor Bldg. ! EL 162' IECHV 2317B Not Applicable Fuel Fool HX BE202 Reactor Bldg. EL 162' i IEGHV 2457A Not Applicable SACS Heat Each Loop A Bypass Reactor Bldg. EL 102' IECHV 24578 Not Applicable SACS Heat Exch Loop B Bypass j Reactor Bldg. , EL 102' I IEGHV 2491A Not Applicable SACS HX AIE201 Inlet. i Reactor Bldg.
- EL 102' l IEGNV 24918 Not Applicable SACS MX B18201 Inlet 1
1 Reactor Bldg. l ' . EL 102' , l IECHV 2494A Not Applicable SACS HK A2E201 Inlet Reactor Bldg. EL 102' IEGHV 24948 Not Applicable SACS HK B25201 Inlet ] Reactor Bldg. EL 102' j Q POS 8/04 90-as , f t
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I NCGS PSAR i TABLE 3.Il-4 NECHANICAL EQUIPMENT SELECTED POR HARSN REV. 2-ENVIROINGENT QUALIFICATION PAGE 91 Or 96 P.O. 8 P305(O) Components Butterfly Valves Manufacturers. B.I.F/ Unit Of General Signal l SHEET 3 of 4 f.D. No. peodel No. Functional Description Location IEGNV 24964 Not Applicable SACS Loop A Return Valve Reactor Bldg. EL 102' IEGNV 24968 Not applicable SACS Loop B Return Valve Reactor Bldg. EL 102' IEGNV 2496C No*c Applicable SACS Loop A Metura Valve Reactor Bldg. EL 102' IEGHV 2496D Not Applicable SACS Loop B Return Valve Reactor Bldg. EL 102' lEGNV 2512A Not Applicable RHR HK AE205 Disch Reactor Bldg. EL 077' IEGNV 25128 Not Applicable RHR HX BE205 Disch Reactor Bldg. EL 077 IEGNV 2522A Not Applicable SACS To TACS Loop A Supply Reactor Bldg. EL 102' IEGHV 25228 Not Applicable SACS To TACS Loop B Supply Reactor Bldg. EL 102' IEGHV 2522C Not Applicable SACS To TACS Loop A Supply Reactor Bldg. EL 102' IEGHV 2522D Not Applicable SACS To TACS Loop B Supply Reactor Bldg. EL 102' IEGHV 7921A Not Applicable Fuel Pool Heat Exchanger Reactor Bldg. EL 162' IEGHV 79218 Not Applicable Fuel Pool HZ BE202 Reactor Bldg. EL 162' N PSS 8/04 91-az
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HCGS PSAR , TABLE 3.11-4 i NECHANICAL BOUIPMENT. SELECTED F02 HARSH REV. 2
..?
ENVIROWNENT QUALIFICATION PAGE -92 OF 96-P.O. O P305(O) Co:ponent: Butterfly valves . Nanuf actu rers B.I.r/ Unit of General Slanal SHEET 4 of 4 I.D. No. Model No. Functional Description Location IEGNV 7922A Not Applicable Fuel Pool HK AE202 Reactor Bldg. EL 162' IECHV 79228 Not Applicable Fuel Pool HX BE202 Reactor Bldg. EL 162' IGHHV 5543 .Not Appllcable Aln Up Rcvg TK IOT217 Vent PW Reactor Bldg. EL 077' IGSHV 4950 Not Applicable Drywell Purge Exhaust. Reactor Bldg. EL 145' IGSHV 4952 Mot Applicable Drywell Purge Exhaust Reactor Bldg. EL 145' ICSHV 4956- Not Applicable Drywell Purge Inlet Valve Isin Reactor Bldg. EL 102' j IGSHV 4958 Not Appilcable Suppe Chabr Purge Inlet Reactor Bldg. EL 077' IGSHV 4962 Not Applicable Supp Chabr Purge Exhaust Reactor Bldg. EL 0778
; ICSHV 4964 Not Applicable Supp Chabr Purge Exhaust Reactor Bldg.
EL 077' I ICSHV 4978 Not Applicable Nitrogen Purge IsIn Reactor Bldg. 7 EL 102' j 1GSHV 4979 Not Applicable Drywell Prepurge C/U Inl Line Reactor Bldg. t 1 EL 102' I IGSHV 4980 Not Applicable Drywell Prepurge C/U In1 Line Reactor Bldg. EL 077' j ICSHV 5029 Not Applicable Reactor Bldg ATM Control Reactor Bldg. EL 077' ICSHV 5031 Not Applicable Reactor Bldg ATM Control Reactor Rldg. EL 077' 1 N P85 8/04 92-az i 1 l i
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HCGS FSAR TABLE 3 11-4 MECHANICAL EOUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 9 3 OF 96 P.O. 9 P366(O) Component: Resilient Seated Check Valves Manuf acturers Circle Seal Controls (Brunswick Corp.) SHEET 1 of 1~
~
(Technetics Div.) I .D. No. Model No. -Functional Description Location-1ABV 051 Not Applicable Inboard MSIV Instrtamentation Check Valve Reactor Bldg. EL 102' 1ABV 052 Not Applicable Inboard MSIV Instrtamentation Check Valve . Reactor Bldg. EL 102' 1ABV 053 Not Applicable Inboard MSIV Instrtamentation Check. Valve Reactor Bldg. EL 102' 1ABV 054 Not Applicable Inboard MSIV Instrisnentation Check Valve Rector Bldg. , EL 102'
- 1ABV 055 Not Applicable Outboard MSIV Instrtamentation Check Valve Reactor Bldg.
EL 102'
- lABV 056 Not Applicable Outboard MW. Instrtsnentation Check Valve Reactor Bldg.
4 's EL 102' 1ABV 057 Not Applicable Outboard 4TIV 1*'strtamentation Check valve Reactor Bldg. EL 102' 1ABV 058 Not Applicable Outboard MSIV Instrtsnentation Check Valve Reactor Bldg. EL 102'
*The balance of the 1-AB valves (14) have not yet been assigned.
1 I r M P85 8/04 93-az i i______________ _ _ _ _ _ _ _ _ _ _
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HCGS FSAR TABLE 3.11-4 MECHANICAL EQUIPMENT SELECTED FOR HARSH- REV. 2 ENV?RONMENT QUALIFICATION PAGE <94 OF _96 P.O. 8. P401D Component: Hydraulic Snubbers Manufacturers ; E-Systems, Inc. , Montest Division' SHEET 1 of 3 l I.D. No. Model No. (Rating) Functional Description Location i 1-AB-030-H02 152007 70 Kip Pipe Support / Restraint Device Re9ctor Bldg. , EL 121' l-A%030-H03 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg. , EL 121' 1-AB-030-H04 152007 70 Kip Pipe Support / Restraint Device ' Reactor Bldg., EL 121' ,
?
l-AB-030-H05 152007 70 Kip . Pipe Support / Restraint Device Reactor Bldg. , EL 121' l-A2-031-H02 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg. , EL 121'
! l-AB-031-H03 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121'~
. 1-AB-031-H05 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' l-A3-031-H04 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' 152005 l l-AB-031-H07 50 Kip Pipe Support / Restraint. Device Reactor Bldg., EL 121' l-AB-032-H04 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121'
. 1-A3-032-H07 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' l-AB-032-H02 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' l-AB-032-H05 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' 1
3 1-A3-033-H02 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' j 1-AB-033-H03 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' j 1-AB-033-H04 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 121' l-AB-033-H05 152007 70 Kip Pipe Support / Restraint. Device Reactor Bldg. , EL 121' 1 1-83-Oll-H02 152005 50 Kip Pipe Support / Restraint Device . Reactor Bldg., EL 086' l-E3-011-H03 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' l-E3-Oll-H07 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' 1-B3-011-H08 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' ! M P85 8/04 94-az ] l
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,d . .
TABLE 3.11-4
. MECHANICAL EQUIPMENT SELECTED FOR HARSH REV. 2 ENVIRONMENT QUALIFICATION PAGE 95 OF 96 ,
P.O. O P401D Component: Hydraulic Snubbers Manuf actu re r s E-Systems, Inc., Montek Division SHEET 2_ of 3 I.D. No. Model No. (Rating) Functional Description Location ] l-CD-Oll-Hll 152010 100 Kip Pipe Support / Restraint Device . Reactor Bldg., EL 100' , 1-BB-011-H12 152010 100 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' l-BB-011-H13 152010 100 Kip Pipe Support / Restraint Device Reactor. Bldg., EL 086' 1-BB-011-H14 152010 100 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' l-20-012-H02 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086 1-C3-012-H03 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' 1-C3-012-H07 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' ) 1-ES-012-H08 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100'
; l-BB-012-H09 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100*
1-E3-012-H10 152005 50 Kip Pipe Support / Restraint Device g Reactor Bldg., EL 100' i 1-BB-012-H11 152010 100 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' l-BB-012-H12 152010 100 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' l-Es-012-H13 152010 100 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' l-BB-012-H14 152010 100 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' 1-83-013-H02 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' ! 1-B3-013-H01 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' l-t:-013-H04 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 086' l-E3-013-H06 152003 30 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' l-BB-013-H07 152003 30 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' , 1-EG-013-H08 152003 30 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' 1-03-013-H09 152003 30 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' , M P85 8/04 95-az l t (
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, TABLE 3.11-4 NECHANICAL EQUIPMENT SELECTED FOR HARSH REV.-2
-ENVIRONNENT OUALIFICATION 'PAGE 96 OF 96 P.O. O P401D Component Hydraulic Snubbers ' Manufacturers E-Systems, Inc.. Montek Division
. SHEET 3_of 3 1.D. No. Model No. (Rating) Functional Description ' Location P
I l-ZI-014-H02' 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' 1- D-014-H01 152005 -50 Kip- Pipe Support / Restraint Device Reactor Bldg., EL 100'
, 1-E2-014-H04 152005 50 Kip Pipe Support / Restraint Device ~ Reactor Bldg., EL 086' l
1-c3-014-H06 152003 30. Kip Pipe Support / Restraint Device Reactor Bldg.,-EL 100' 1-E2-014-H07 152003 30 Kip Pipe SupW4t/ Restraint Device Reactor Bldg., EL 100' l-li3-014-H08 152003 30 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' l-E3-014-H09 152003 30 Kip Pipe Support / Restraint Device Reactor Bldg., EL 100' f 1-AD-032-H03 152007 70 Kip Pipe Support / Restraint Device Reactor Bldg., EL 124' i ) 1-33-Oll-H09 152005 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 104' 1-B3-Oll-H10 152035 50 Kip Pipe Support / Restraint Device Reactor Bldg., EL 107' j s i i l I. M P85 8/04 96-az f 4 1
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TARLE 3.11 EQUI PMENT SEI.ECTED FOR MARSM ENVIDONNENT QUALI FICATION . . P61 D ' N-01 -l '. SYSTEN . MAIN STK4M AN . . ID NO. PAN: IMI ACTION ' P.O. . LOCATION. EOUIP. PLAN EQUIP. Not e (5) NPL NO. COM PONENT BLDC. ELEV. N001 1 - S t*- PS-N0 0 5A C71 Press. Switch geoTE (1) sviris ( 2) EESS REF. NO. M001 Turbine 123 No No- 1 65 1-SH-PS-N005M C71 Press. Switch Turbine '123 M021 1 -SH-PS-N005C '
' No No : '.161 C71. Press. Switch Turbine 123 No M001 3-SH-PS-N00$D . No 1 61 C78 Press. Swit ch '. Turbine 123 No No 161 Matt I-Sn-25-N006A C7L Position Switch 7t.(bine 102 No MGil 1-5B-25-M006s C71 No 119 Position 541tch Turbine 102 No- No .;
M011 1-SM-2S-N006C C78 119 Moil Position Switch- . Turbine .102 No - No 119 1 -SM-Z S-N006 D C71 Position S*6 tch Mool 1 -SM - 2 5-N0 06E Turbine 102 :No: No 119
- C78 Positinn Switch Turhine. 77 No MOSI 'l-SB-ZS-N006F No 119 C71 Position Switch turbine 77 No MOSI l-SB-2%-N006G C71 No 'll9~
Position Switch Turbine 77 No No ,119 N004 1-SB-25-N006H C71 Position Switch Turbine 77 No No: 119 4 M P24 89 01 1/2-as Whnt 13 Revision 3
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k : N..,..' ' S 4 NCGS FSAR TABLE 3.11-5 Page 2 of 120 - .
"i EQUI PMENT SELECTED FOR HARSH ENVIRONNENT QUALIFICATION P6tD.
N-08-0' EVSTENs CONDENSATE 6 REFUELING #ATEd STORAGE & TRANStER AP ID NO. PAN .- , TNI ACTION
'P.O. LOCATION - EQUIP. . PLAN equip.
Note (5) NPl. NO. CorPONENT PLOG. E l.Ev. NOTE (l) NOTE 12) 'EESS REF. ha. J4830 1-ap-LS-#935A E51 level Switch J483Q 1-BD-LS-N035E peactor 77 .No Yes E51 level Switch ~42 N001 1-M -LT-N06IA E41 Reactor ?? No Yes 42 Level Trans peactor.' . 77 Noel I-N-LT-N06tB E48 Level Trans Deactor ?? No No 155 P)SIQ 0-DN-NV-2069 No No ' 155 Contr. Valve Meactor' 54 - No P3010 0-mm-IS-2069 Limit Switch No 127 P30lO 0-AP-HV-207 2 Reactor 54 No No 127 Contr. Valve- Beactor 54 No P3110 0-AP-IS-2072 Limit Switch - No 127 P3010 0-AP-NV-2073 .meactor 54 No NO 127 Cont r.. Valve Reactor 54 P30lO 0-A P-IS-207 3 No No 127 Limat Switch . Reactor' 54 . No No 127 5 PO4 89 021/2-as Amendment 13 Nevision 3 Q
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TABLE 3.!!-5 l EOutigeENT SELECTED FOR NARSH ENVIRONNENT OuaLt ert CAftUN P6tD SYSTEso s SERVICE edATE.R N-IO-l EA 10 NO. PAN TN! ACTICN4 P.O. tente (51 NPL 000. IBCATION Coul P.' CopePONENT ett_ DG , EIEV. PLAN EQulP. NOTE (I l NOTE (2) EESS REF. No. P3050 1-EA-HV-F073 Control Valve P 3050 4-EA-IS-P073 peactor 77 No . No 144 Limit Switch peactor 77 J6030 1-SC-SV-F074 Solenoid Valve No No I44-P 3050 1-EA-NV-2203 feeactor 77 . No No Control valve peactor 46 P 3050 1-EA-2S-2203 102 No No '144 Lamit Switch peactor. 102 P3050 1 -EA-teV-2204 Control Valve
,No No 144 P3050 1-EA-25-2204 Reactor 102 No No 144 Limit Switch peactor 102 No P3050 1 -EA-teV-2207 Control valve No 144 peactor. 102 P3050 1-EA-2S-2207 Limit Switch peactor No No' 144 P3050 1-EA-tev-2234 102 No No 144 Control valve peactor 77 P30$O l-EA-IS-2234 Limit Switch No No 144 J A'30 peactor 77. No 1-EA-SV-2235 Solenoid valve No
' 144 '
P3050 1-E A-seV-22 36 seeactor -77 No No - 47 Control Valve Beactor 77 No P3450 1-EA-2S-2236 Limit Switch No 144 J ',8 30 1-EA-SV-2217 Reactor 77 No No Solensid Valve .heactor 77 444 P3050 1-EA-HV-2238 No No 46' Control Valve Reactor 77 No P3050 1-ES-25-2238 Limit Switch No 144 J6030 1-EA-SV-2239 peactor 77 No No Solenoid Valve . Reactor 77 l's ! P3050 1-EA-HV-2346 No No 47 Control Valve Reactor 77 P3050 1 -EA-2 S-2 34 6 Limit Switch . 94 0 No 144. J 30lO l-EA-PDT-2354A Beactor. 77 No No 144 Press. Diff. Trans. Beactor 102 No No 29 ~ Cl Pe 4 u9 03 1/2-a r Amendment 13
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.NCGS FSAR TABLE 3.11-5 Page 4 ot.120:..
EOUIPMENT SELECTED FOR MANSH ENVIRONMENT QUALIFICATION Pkt O - S2STEA: SERVICE MATER N-10-1 EA
. I D NO. PAN TNI ACTION '
P.O. asute (5) NPL NO. LOCATION EQUIP. . PLAN EOutP. 1' CONetNsEst? SIE . FIEV. NOTE (1 ) NOTE (2) EESS REP. NO.
- P3050 1-EA-NV-2356A Control Valve P 3050 1-EA-25-23564 Reactor. 102 : No 'No 144 Limit Switch Reactor 802 No J3010 1-EA-PT-2 356Al Press Trans. 1No 144 J3SIO 1-EA-PT-2356A2 Reactor. 17 No No 29 '
J 3010 t-EA-PT-2356A3 Press Trans. Reactor -17 No No Press Trana. 29 P3050 1-EA-NV-23565 Reactor 77 No No 29 P3050 Control Valve peactor 102 ' No No 1-EA-IS-2356a Limit Switch 144 J MIO 1-EA-PT-2356s1 meactor 102 . No No 144 J3440 Press Trans.~ meactor 77 No 1 -EA-PT-235642 Press Trans. No 29 J)010 1-EA-PT-235683 Reactor 77 No No 29 PM50 Press Trans.. Reactor 77 No No 1-EA-NV-2357A Control valve 29 P3050 1-EA-2S-2357A
,peactor 77 No No 144 Limit Switch Reactor 77 No No P3050 1-EA-HV-23578 Control valve beactor 17
.344 P3450 1-EA-IS-2357s No No 144 Limit Switch peactor 77 No No 144 gb Pe4 89 0 3 1/2-as Anenoment 13 kewision 3 l
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J NCGS FSAR TAsLE 3.11-5 Page h of 'I 20
- EOut s9st.NT SELECTED POR HARSH ENVI RONMENT (MJALI FICATION ' P6 t D -
SYSTENs - SERVICE tlATER N-RO-! EA 10 000. PAR TNI ACTI(Ni P.O. geote (5) LOCATION -EOulP. ' PLAN EOu!P. sePL 300. ColePOISENT BLDC. ELFV. NOTE (I l NOTE (2) EESS M:P. 10 0 P3050 1 -EA-23-2 M 04 Position Switch peactor 102 No-P3050 1 -EA-IS-2 M 0s No 146, Position Switch heactor '102 peo ' No P3050 1 -EA-Is-2 M 3A Position Switch peactor 146 1 -E A-2 S-2 M 3s 102 No No 146 P3050 Poettion Switch meactor 102 sto too 146
. J 20lO l-EA-esS-2M74 asand Switch .meactor 102 No J6030 1-EA-SV-2 M 7A m) 25 Solenoid Valve .heactor 102 m) No J 20lO l-EA-MS- 2 M 78 Itand Switch 47 J60 30 1 -EA-SV-2 M 78 Beactor 102 No No 25 Solenoid Valve Beactor 102 seo geo J 20lO l-E A-MS-2 M7C leend Switch 47 J6430 1 -E A-SV-2 M 7C
- Aeactor- 102' No No 25 Solenoid valve peactor 17 No J20lO l-EA-MS-2 M 7D isand Switch
' No 47 iteactor 102- seo No 25 J50 30 1 -E A-SV-2 M 70 - . Solenoid Valve peactor 102 No P3050 1 -EA-HV-2 37 5 A mm 47 Control Valve leedctor 802 No No P3050 3-EA-IS-23784 Limit Switch Deactor 102 >>
144' P3050 1-EA-seV-2371s le. 344 control Vanwe .meactor 102 No No P3050 1-EA-IS-23718 Limit Switch 144 l-EA-Ptyr- 2 37 3A. anactor 102 No No 144 J 30lO Press Diff. Trans. Deactor 102 ma J 30lO l-EA-POT-23738 leo 29 P303AO 1-EG-NV-2446 Press Dif f. Trans. Reactor ~ 102 . m2 Em 29 Control Valve leeactor .102 96 0 No P303AO 1 -EG- 2S-24 46 Limit Switch 3 19 peactor .102 No . No " 1 39 P303AO 1-EG-Ilv-24 47 Control Valve peactor.. 102 ., No P 30 3AO l-EG-2S-2447^ No 1 39 - Limit Switch Beactor' 102- No m) P30 3AO l-EC-MW-4647 Control Valve 1 39 4-EC-IS-4647 heactor 162 No No 1 19 ; P 30 3AO Limit Switch 1 . Reactor 162 mm eso 1 39 P30 3AO l-EC-00V-4648 Control Valve Reactor 162 l-EC-2S-4648 , No No I 19 P30 3AO Limit Switch meactor 162 mi eso 1 39 IS PG4 89 03 3/4-as Amendment 13 Revision 3 O
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l { + l NCGS FSAR TABLE 3.11-5 Page 6 of 120 EOul PseENT SELECTED FOR MARS 33 ENVi kONMENT OUALIFICATION P6 t D SYSTEse SAPETY AUE COOL SYSTEN N-!!=1 EG I D 360.' PAN TN! ACTI(NG P.O. soote (5) LOCATION EQUIP. PLAN EQUIP. NPL seO. CasspUNEss? hlDG. ELEV. NOTE (1) NOTE ( 2) EESS REF. 80 0 . J 2010 IA-C-201 SACS Control Panet A heactor 102 J20lO IB-C-201 No No 26,27 SACS Control Panel 3 asactor 102 No No J 20lO IC-C-201 SACS Control Pane! C 26,27 J 20!O ID-C-201 Deactor 102 No No 26,27 SACS Control Pane! D Deactor 102 No G112m0 IA-P-280 SACS Pump sootor Imeactor No 26,27 Ell 2AO la-P-210 102 No No I SACS Pump stator Reactor 102 No Ell 2AO IC-P-210 SACS Pump peutor peactor No I (fil 2AQ I D- P-210 102 No No I SACS Pump stotor peactor 102 No P30lO l-EG-SV-22904 No I Solenoid valve .Deactor 54 seo No P 30lO l -EG-2S-229 04 Position Switch 1 24 P 30lO l-EG-Sv-2 290s teactor 54 No No 125 Solenoid valve peactor 54 No No P30lO l-EG-2 5-229 08 Position Switch 1 24 P30lO l-EG-SV-2290C Beactor 54 No No 825 Solenoid Valve Beactor 54 No No P30l O l-EG-25-2290C Position Switch peactor ~ 124 P 30lO 54 No No 525 [ 1 -EG-Sv-2290D Solenoid valve peactor 54 P30!O l-EG-IS-2290D No No 1 24 Position Switch Deactor 54 No No P3010 1 -EG-SV-2290E Soleeid Valve 325 P30lO l-EG-IS-229 0E Reactor 77 No No 1 24 Position Switch Reactor 77 No No P30lO l-EG-SV-2290P Position Switch 77 125 P 30lO l-EG-SS-2290P Reactor sto No 1 24 Position Switch meactor 77 No No P30lO l-EG-Sv-2290G Solenoid valve peactor 54 125 P3080 1 -EG-25-2290G No No 1 24 Position Switch peactor 54 No No 125 Amendment 13 Rwvasion 3 o
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a NCGS PSAR TAaLE 3.11-5 p,q, h o f I 24 l EQUIPetENT SELECTED POR MARSH ENVIRONNENT QUALE PICATION P6I D -
.ETSTER: SAFETY Aux Cool SysTEN N-II-I '
EG IO NO. PAN
- TNI ACTION
. P. O. teote ( 5) LOCATlON .. EOUI P.,
PLAN EQUIP. NFL 000 CONDONESIT - SLDC. EI.EV. NOTE (ll teOTE (25 EESS REF. NO.- P30!O l-EG-2S-229808 Position Switch
- PMIO l-EG-SV-229 2A .Deactor . 54 No No '
Solenoid Wa!we neactor 54 No I25' P3elO l-EG-2S-229 24 Position Switch No 124 P3410 1 -EG-SV-229 28 heactor 54 No No 125 PMIO Solenoid Valve -Beactor 54 No I-EG-3S-22928 Position Switch teactor No 124 P 34 3AO l-EG-SV-22334 54 No No 125 Solenoid Valve peactor - 54 . No P M 340 1-EG-2S-229 34 No 140 Position switch teactor 54 No P34340 1 -EG-SV-229 38 Solenoid Valve No I41 peactor 54- No P 34 340 1-EG-IS-2293s Position Switch *>- 140 ' P3410 1-EG-SV-2342A teactor 54 No No I41' Solenoid Valve beactor 132 No P 30lO l-EG-IS-23424 P;sitton Switch No 524 P3410 1-EG-SV-23428 Deactor 1 32 No No 325 Solenoid Valve Deactor 178 No P3elO l-EG-25-236 3 Position Switch meactor 178 No 124 i PMIO l-EG-SV-2342C No No Solern&d Valve peactor 112 No 125' I P 3410 1-EG-IS-2342C Position Switch peactor No 524 ' P3elO l-EG-SV-2M2D i32 No No 1 25 . Solenoid valve peactor 162 No P3010 1-EG-3S-23e2D position Switch No $24 peactor 162 No
. Ple!O l-EG-SV-2 M2E Solenoid Valve Peactor No 125 P3010 l-EG-2S-2342E 162 No. No 124
-Position Switch neactor 162 mm No P3e10 1-EG-SV-2302P Solenoid valve 1 25 - t
! P3410 1-EG-2S-2 M 2P Reactor 178 No No 124 P3050 Position Switch peactor 178 No No [ 1-EG-HV-2314A Coat r. Valve 125 Ple5O l-EG-IS- 2314A Reactor 162 No No I44 Limit Switch peactor > l62 No No 'J 144 [
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NCGS FSAR TAhLE 3.11-5 pan 8 of I 20 EOUI PetENT SELECTED FDP NARSN ENVI AOINoENT QUALIFICATlON . P6I D ' SYSTEso s SAFETY Aux Cook SYSTEse - N-11-1 EG I D 860. PA80 T98 ACTION P.O. esote (5) LOCATIOst EDOI P. PLAN EQUIP. 88P0 sec. CostposeEstr SLDC. ELEV. sofyrE (1)- NOTF ( 2) EESS REF. NO. P3050 1-EG-etV-23tes contr. valve peactor P M50 1-EG-IS-2314e 162 sto 'm> 144 Limit Switch heactor 162 No No P3650 1-EG-HV-2317A Coatr. Velve 344 P3650 1-EG-IS-23174 Deactor 162 .No No ~l44 Limit Suitch meactor 162 m> P M50 1 -EG-Nv-2 317s contr. Yalve . Deactor _ soo .I44-P3050 1-EG-IS-2417e 162 seo No 144 Limit Switch meactor 162 h peo - P3e 3a0 1-EG-Nw-232e4 contr. valve peactor 144 P 383AO l-EG-2S-23284 132 seo - No I 19 Limit Switch Reactor 162 h No PM 3AO l-EG-HV-23245 Contr. valve teactor 132 5 39 P3elag 1-EG-25-2320e No No I 19 Limit Switch teactor 162 leo No P343a0 1 -EG-Nv-2321 A Coatr, valwe meactor 1 39 1 32 h No 1 19 P 34 340 l-EG-IS-2321A Limit Switch Ple3a0 1-EG-HV-232ta meactor 1 12 No Iso 1 39 contr. valve Deactor 1 32 Iso P30340 1-EG-IS-232 a Limit Switch anactor 132 sto 1 39 sen seo P30!O l-EG-SV-23254 Solenoid Valve ,beactor 54 1 39 P3elo 4-EG-IS-23254 sto No 1 24
' P3elg Position Switch anactor 54 sea 1-EG-SV-2325e Solenoid valve peactor se.a 125 54 00 0 No 124 P3440 1-EG-2S-2325e Positson SwiLch . Deactor 54 P34tg 1-EG-Sv-2325C No No i25 Solenoid valve me.ctor 54 . sso No F)et O l-EG-IS-2325C -Position Switch 1 24 P3410 1-EG-Sv-23250 teactor 54 *> No n25 Solenoid valve beactor 54 00 0 peo 124 Amendment 13
, Revision 3 9
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-TANLE 3.11-5 Page 9 of 120 :
l i* EOUIPMENT SELECTED FOR HANSH ENVIRONMENT OUALI FICATION !~ P6 t D EYSTENs SADETY AUX COOL SYSTEM N-g1-3 EG ! ID 300 PAN TNI ACTION P.O. anot e ( 5) LOCATION EQUI P. PLAN EQUIP. MPt. No. CONFoseENT kl.DG. ELEV. NUTE (Ib DOTE ( 2) EESS EFP. Nt ). P30lO l-EG-IS-2 32% Position Switch 93010 1-EG-SV-2325E Reactor 54 No .No 125 Solenoid valve peactor 54 No P3010 l-EG-2S-2 325E No 124 Position Switch peactor 54 No P3010 1-EG-SV-2325P No 125 Solenoid valve peactor 54 m D3010 l-EG-2S-2325P Position Switch No 124 P308 0 1-EG-SV-2325G peactor. 54 m No 1 25 P30!O Solenoid Valve . Reactor t4 No No l -EG-2S-23 25G Position Switch peactor 124 P30lO l-EG-SV-2325M 54 No mm. 125 Solenoid Valve peactor 54 mm P3010 1-EG-25-2325el No 124 Position Switch peactor 54 No No P303AQ 1-EG-MV-2452A Cont r. valve teactor I32 425 P30 34Q 1-EG-2S-24524 No No 1 39 Limit Switch .meactor 1 32 soo ho-P303AO l-EG-MV-2452s- Coatr. Valve 1 39 P 303a0 1 -Et.- Z S- 2452es .anactor 112 No No 1 39 Limit Switch steactor I 12 No No P)0 34Q 1-EG-NV-2453A Contr. Valve peactor 1 39 1 32 No No P 30 3a0 1-EG-2S-2453A Limit Switch heactor 132 1 39 F303a0 1-EG-NV-2453es No No 1 39 Cont r. Valve heactor 132 No P 34340 3-EG-IS-2453m No .3 39 Limit Switch Re actor 132 mz *> J20lO l-EG-MS-24574 Mand Switch steactor 102 1 39 P)C50 1-EG-SV-2457A No No 25 Solenoid valve peactor 102 m) No P3050 1-EG-2S-2457A Position Switch 145 femactor 102 No No 146 J5560 1-EG-TE-2457A Temp. Element peactor 102 J20!O l-EG-MS-2457s No No 43 Mand Switch meactor 102 No No P 3050 1-EG-SV-2457s Solenoid valve 25 P3050 1-EG-2S-2457m Isaactor 102 No No 145 Position Switch heactor 102 m) _No J 5560 1-EG-TE-2457m . Temp. Element Beactor 146 102 No No 43 Amendment i3 Revision 3 h
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NCCS FSAR TABLE 3.!!-5 Page 10 of ' 120 - EOulI9eENT SELECTED FOR NARSN ENVIRONNL'NT OuALI FICATION P6th CYsTEN: SAFETY AUX CDOL SYSTEN M-ll-1 EG 10 a00. PAN T(el ACTION P.a. IAICATI ems EQUIP. , PLAN EOulP. teote (5) MPL 800 Cope WMwT HLDG. DN ffE (Il E LE V. seOTE ( 2) EP:SS REF. NO. se0 *! 1 -EG-Puf- 248 54 Diff. Press Trans. koactor 102 90001 1-EG-PDT-24858 No No 155A setet Dif f. Press Trans. Reactor 102 No m 155A 1-EG-PDT-2485C Diff. Press Trans. Reactor 102 speel 1-EG-PDT-2485D No No I SSA Diff. Press Trans. Reactor 102 No No J 2GIQ l-EG-MS-24SSA2 esand Switch Deactor 102 8%5A seo No J2eIO 1-EG-esS-24eSe2 leend Switch peactor 102 25 J 20!O No No 25 l-EG-MS-2485C2 esand switch meactor 102 No J 2010 1-EG-NS-244502 No 25 esand Switch heactor 102 No No p)450 1 -EG-eev-249t A contr. valve 25 P)s50 1-EG-IS-2491A peactor 102 eso No 144 Limit Switch Reactor 102 No No 93050 1 -EG-eev-249 t a contr. valve peactor 144 10'2 No No 144 P3450 1-EG-3S-24948 Limit Switch teactor 102 No F)e50 1-EG-WW-24944 No 344 Contr. Valve peactor 302 No No P M50 1-EG-IS-2494A Limit Switch 144 P)450 1-EG-sev-2494e heactor 102 No geo 144 contr. valve neactor 102 No No Ple5O 1-EG-2S-24948 Limit Switch 144 P3050 1 -EG-eev-24964 Reactor 102 No No 144 contr. Valve beactor 102 seo PM50 1 -EG-IS-24964 Lielt Switch peactor veo 144 p)850 1-EG-Nv-2496a 102 No Iso I44. contr. valve meactor 102 too P 3050 1-EG-IS-24968 Limit Switch veo 144 P)S50 1 -EG-Nv-249tc Deactor 102 No No 144 Contr. Valve Reactor 102 No No P)e50 1 -EG-ZS-249 6C Limit Switch 444 p)e50 hactor 102 . No too 1-EG-NV-2496D Contr. Valve Deactor 502 No I44 P)450 1-EG-IS-2496D . No 144 Limit switch peactor 102 No sto J)elO l-EG-LT-2508A Level Trans. 144 Reactor 201 No No 29 J)et0 l-EG-LT-2500m Emwel Trans. Reactor 201 No J1010 1-EG-LT-2MeC No 29 level Trans. meactor 204 eso No 29 J)e40 1-EG-LT-25000 inwel Trans. Ieeactor .201 No No 29 Amendment 13 Revision )
NCGS FSAN TABLE 3.11-5 Page !I of 1 20 EQUS PNENT SELECTED FOR HARSH 6.NVlitCNNt.NT QUALI FICATION Phl O CYSTEn SAFETY AUX COOI. SYSTEN ~ EG 1 D NO. PAN TM1 ACTSOh r'. * . LOCATIuN EQUIP. PLAN EOutP. Note (5) NPL No. C ON PON ENT HLDG. ELEV. M rrF (t) WYTE ( 2) EESS REF. %). J)010 1-EG-FT-2511A Flow Trans. Reactor 77 J3010 1-EG-FT-25t&B Yes No 29 Flow Trans. Reactor 77 Yes No C3050 1-EG-HV-2512A Contr. Valve Reactor 77 29 C3050 1 -EG-2 S-2512A No No 144 Limit Switch peactor 77 No no P)C50 1-EG-NV-2512h Contr. Valve peactor 77 a44 No No 144 G 305Q 1-EG-IS-2512e Limit Suitels peactor 77 J 2010 1-EG-NS-2517A No No 144 Hand Switch Reactor 102 No No J6050 1 -EG-SV-2517A Solenoid valve 25 J6050 1 -EG- ZS- 2517A Reactor 102 No No 48 Position hwitch Re a : tor 102 No J20lO I-EG-NS-2517a Mand Switch Beactor 102 No 4dA J6050 No No 25 1 -EG-SV-2517s Solenoid Valve Reactor J6050 1-EG-ZS-2517a 102 ho No se Position Switch peactor 102 ma ska U101AQ 1-EG-SV-2520A Solenoid Valve Reacter 54 esA 1 -E.G-2 5-25 2 0A E. No 140 P30 3AQ N i t ioes Swatch peactor 54 No No P301AQ 3-EG-SV-252Ga Solenoid Valve 141 peactor 54 No No P303 Q 1-EG-ZS-25208 I%sition Switch peactor 54 140 C30 3AQ 1-EG-SV-2520C No No 141 Solenoid valve Resctor 54 No % C 30 3AQ 1-EG-2S-2520C Position Switch 140 DD ug peactor 54 No ho 141 1-EG-SV-25200 Solenoid Valve Reactor 54 No D30 Q 1-EG-2S-2520D No 140 Position Swatch heactor 54 No N3 P3050 1 -EG-NV- 25 22A Control Valve 841 be ac t or 102 h No 147 P 305's 1-EG-IS-2522A Limit Switch heactor 102 No P3C50 1-EG-NV-25228 No 147 Control Valve beactor 102 No No P1050 1-EG-25-25228 Limit Switch 847 React or 102 No ho 147 J 2013 1-EG-MS-2522is) Nand Switch Reactor 102 No No 25 Amendment iJ Mewasion ) l [
1 s N $ FSAA TABLE 3.45-5 Pa e 12 of I20 EQUI EMEM7 SELECTZD FOR NARSM ENVi ttONMENT *AIALI FICATION PER D CYSTEM: SAFETY AUX COOL SYSTEM M-II-! EG I D NO. PAa TMI ACTION P.+. Note t5) NPL NO. LOCATI ON EQUIP. COMMusENT BLIC, FIEV. PLAN EQUIP. NOTE (ll sk YTE ( 2) C3050 1-EG-eev-2522C 6'ESS 9FF. NO. Control valve 102 P3050 1-6.G-IS-2522C Limit switch anactor m No 147 P3050 1-EG-NV-25220 anactor 102 No P3050 4-EG-2s-2522D Control valve Reactor 102 No No 147 Limit Switch No 147 J2013 1-ECeNS-2522D3 peactor 102 No esand Switch No 147 J 3013 4-EG-PDT-2529A peactor 102 No Press. Dif f. Trans. N 25 J 3013 1 -EG-PDT-25 298 heactor 162 No J5560 1-EG-TE-2535A Press. Diff. Trans. Reactor 162 No ho m 29 Temp. Element 29 J5560 4-EG-TE-2535a Temp. Element Reactor 102 Yes No J 301') peactor 102 43 4-EG-FT-25444 Flow Trans. Yes No 43 J 3J13 1-EG-F?-25449 Reactor 102 No J J'al+) 1-EG-FT-2544C Flow Treas. Reactor 102 No No 29 Flow Trans. No 29 J 3010 1-EG-FT-2544D Reactor 102 No No J 30!D F1ow Trans. Reactor 102 m 29 l-EG-FT-2549Al Flow Tuans. No 29
- J3083 1-EG-FT-254981 Reactor 102 Yes No J 3013 1-EG-FT-254983 Flow Trans. Reactor 102 Yes 29 Flow Trans. No 29 D3050 1-EG-NV-7928A practor 102 No Conta. Valve No 29 03050 1-EG-IS-7921A .mactor 162 No No Limit switch heacto. 16e 144 P3050 1-EG-NY-7921s contr. Valve No No 144 D3050 1-EG-IS-79219 peactor 162 No No Limit Suttch Reactor I44 P3050 1 -EG-HV- 79 2 2A 162 No No P 3050 1-EG-Is-7922A Contr. Valve Reactor 162 No No 144 Limit s. itch meactor 162 144 03050 1-EG-NV-79223 Contr. Walve No No 144 03050 1-EG-Is-7922s Limit switch Re ac t or 162 m m I44 peactor 162 No No 144 Amen =1 ment 13 kevaston 3 e
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HCGS FSAR TABLE 1.!!-5 Pa e 13 of 120 EOut sveENT SELECTED FOR NARSH ENVI R(JhMENT Ob ALI PS CATlON Phi b
- EYSTEN: REACTOR AUXILI ARIES COOtlerC N-4 3-1 ED 1 D NO. FAN Tnt ACTION P.". Not
- 155 N PL NO. LOCATEON equip. PLAN Egul P.
C000 Pops E NT Hl tr., gggy, g80TF 1Il NOTE I 25 FESS RFF. M. D30lO 1-E NNV-2553 contr. Valve P 30l *) 1 -C D-25-255 3 Reactor 102 No O 127 Limit Switch Reactor 102 C3013 1-E>NV-2554 Contr. Valve Yes No i27 D3013 1 -F D-IS-2554 beactor 802 No No Limit Switch 127 P30!D 1 -ED-HV-2555 Reactor 102 res ha Coatr. Valve Reactor 102 127 P3013 1 -E D-2 S-2555 Limit Switch NO No 1 27 P 3019 l -E D-H V- 2556 heactor 102 Yes eks 127 Contr. Valve Reactor 102 P3010 1-ED-2s-2556 Limit switch No No 127 P3050 1 -E D-HV- 259 8 Reactor 102 Yes No 1 27 Contr. Valve leeactor 54 P3050 1 -E D-2S-259 a Lamit Switch % W 144 P305Q 4 -ED-HV- 259 9 Reactor 54 No No Contr. Valve Reactor 54 144 - P3050 1 -E D 259 9 Lamat Switch h No 144 Reactor 54 No No 144 Amendment 13 Revision 3 l 1 e (
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i -t 1- i i f { #CCS FSAA i TAaLE 3.!!-5 Page 14 of 120 ~ ; l s 80u! PNENT SELECTED FOR NAaSN ENVI ROeueENT QUALIFICATION P6t D [ SYSTSN:- COnPSESSED Al R (INSTR.3 N-15-0 L , . E# l '. I D 800. IJ1CATIuel PAN EQUI P.
- TNf PUIOel !
p.O. moto (5) tePL 800. NMutsas? PLAff E(UI P. I 8tl.DC. ELEV. IeDTE (1). esOTE ( 2) EESS PEF. teo. t P3810 1-EA-tev-7626 - Contr. Valve deactor 17. 3 P30!O l-EA-35-7626 Listt Suiteth No na 1 27 l P3410 1-ES-NV-7629 teactor~ 77 ' peo eso 127 Contr. Valve- heactor- 77 peo
- t. P3eIO 1-58-25-1629 Limit Switctb heactor 77 seo 127
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" DA" TABLE 3.11-5 Page 15 of I 20 EQUI PMLNT SELECTED FOR NAksM EtiVI NureMENT OUALI FICATI(W pgI D SYSTEM: I*MINERALI 2ED NATER M-18-0 AM I D NO. PAM TMI ACTI(W 4
P.O. Note (5) M PL NO. LOCATRON EQUI P. PLAN EQUIP. Con PONENT MIIC. ELEV. MYTE (I) W FTE 12) E t3S 9FF. NO. P 3010 1-Ame-Ny-2600 Contr. Valwe Beactor 54 No P101Q 1-AN-35-2600 Limit Switch No 127 a meactor 54 No No 127 1 1 i ) Ame minen t 13 i Revssion 3 L t i 4 i b l 1 4 3 9 6 1 I
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r s. w MCGS FSAR Page 16- of 8 20 TABLE 3.18-5 EQUI s9eENT SELFCTED FOR NARSes EKVistOhs8ENT OuALIFICATION P65D SY37 ens PLAest LEAK DETECTION N-25-0 SE 1 D eso. PAN TN! ACTIOss
, LOC ATl 000 t; QUI P. PLAN EOutP.
P.C. Isote 15) sePL 800 Cope rnestse? BLDG. ELEV. seOTE I I ) esOTE 12) Es:SS Re:F. NO. 30001 1 -SE-TE-ee009A El 1 Temp. Eleat. Reactor 17
- se001 1-SE-TE-s00098 No N 105' E!! Temp. Elemt. nuactor 17 m .
se001 1-SE-TE-te0104 No 105 D21 Toep. Elset. Reactor 102 lete! 1-SE-TE-te410e 321 soo ms 105 Temp. Eleet. Reactor 1u2 mi seo steet 1-SE-TE-s0010C E21 Temp. Eleet. los see01 1-SE-TE-teet0D ' D21 peactor 102 m me 105 Temp. Elmet. Reactor .102 . No No see$l 1-SE-TE-stell ESI Temp. Eteet. 105 meaetor 54 No No 105 se0Cl 1-SE-TE-teellA B21 Temp. Eleet. Reactor 832 . peo seB *.! l-SE-TE-N011s m2e Temp. Eleet. 36 0 105 se001 1-SE-TE-esO!IC Reactor 132 .W >> 105 S21 Temp. Elmet. - meactor 132 m m2 105 N001 4 -SE-TE-esell D S21 Temp. Eteet. Deactor 132 se001 1-SE-TE-te052A B21 - Toep. Eleet. sto 80 0 105 Reactor 102 seo Mrs 105 se001 4 -SE-TE-N012te B21 Temp. Elost. Reactor 132
- setet 1-SE-TE-teG4 2C B21 soo m> 105 Temp. Eteet. meactor 132 oks No set!! l-SE-TE-stel 2D B21 Toep. Eteet, 505 peactor 132 No No 105 8e001 1 -SE-TE-te0134 B21 Temp. Elemt. Reactor 1 52 No see 1 3-SE-TE-seel3e No 105 B28 Temp. Eleet. Reactor 132 9e0 ms 105 see01 1-SE-TE-seelSC D21 Temp. Elemt. . Deactor 112 No see01 1-SE-TE-N0130 No IOS 821 Temp. Eleet. Reactor 132 No se005 1 -SE-TE-seel e 821 Temp. Et en t ,
96 1 105 steactor 132 sto No 105 see:1 1 -SE-TE-teel 6 h21 Temp. Eleet. Deactor 1 32 h M setel 5-SE-TE-es016A GB3 Temp. Eleet, 105 peactor ! !2 mm sto los peo;4 I-SE-TE-se046AA G33 Temp. Elemt. Deactor 145 eso >> 105 Amendment i3 stevisson 3 4 L I e- ege 9 - - * + = '"* +4--T
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A - ( %j , NCGS FSAR - TAaLE 3.3g.g Pa9e 17 of 12u S LECTED Foa NAasu g"VINENT QUALIFICAT3 Ogg P6t D
.M TENS T LEAE DETECT! m #-25-0 1 D NO. PAM TN1 ACTION P.O. teot e I SI t.OCATI eMe equip. i mPL eso. CostseesENT ALDG. PLAN EQUEP.
FLFV. etECE II) seOTE ( 2) EESS StEF. DIO. E8841 1-5K-T8-a60160 G33 Temp. Eleet.' 18841 1-SE-TE-te016DD G33 Temp. Elemt. meactor 432 sao No 105 seS01 1 -SE-TE-teel 6E G13 Temp. Elset.' Deactor !45 eso No 105 'l IISet 1-SE-TE-teS1640 G33 Deactor 112 No No 50% Te y. Elmet. Reactor 132 teSci 8 -SE-TE-96816J G33 Temp. Eleet. see No 40% SISol 1 -SE-TE-tesl 6es G33 Reactor 145 seo mz toi Temp. Elaet. Deactor 145 seSS1 1 -SE-TE-eeG16es G33 Temp. Elest. No peo .505 48341 1-SE-TE-es0165 G33 Deactor 1 32 eso peo 105 Temp. Eleet. Reactor 145 ses!1 1-SE-TE-stel6T G33 Temp. Eteet, sh No LOS a8041 1-SE-TE-teC16es G33 peactor 145 too No los Temp. Eleet, peactor 132 seSG1 1-SE-TE-teel 7 E21 Te g . Elemt. ski No los teP41 Reactor 102 peo '! 1-SE-TE-seS21s E55 Temp. Eleet, eso 105 sesil 1-58-7E-800210 E51 meactor 54 h No 105 Temp. Eleet. Reactor 54 peo seSol 1~SE-78-500224 G33 peo 10% Temp. Eteet. Reactor 132 east! 1-SE-TE-ses 22AA G33 Temp. Eleme.' too eso 10% teSS1 1-SE-TE-teS22e E51 meactor 145 too No 105 Temp. Eleet. meactor 54 seS!1 1-FC-TE-s0022D E51 Temp. Eteet. No seo los seSet 1-SE-78-88022D G13 .Deector 54 peo No 105 Toep. Eleet, ameactor 132 peo
. ses!1 1-SE-TE-teO22Do Gs3 Temp. Elset, No LOS potel peactor I45 9eo No' 1-SE-TE-te022E G33 -Temp. Elmet, 10%
test 1 1-SE-TE-te022pe G13 asector 112 No soo 1OS Temp. Eleet. Deactor 132 stS41 1 -SE-T E-teS 22 J G33 feo eso 10% Temp. Eleet. Deector 145 feo No 105 Amerkfeent I3 kervision 2
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- f. .x, I-NCGS FSAS TAELE 3.15-5 pag, g g og g' 20 EOut PeeENT SELECTED FOR MAR $es ENVI DOsmeENT OuALI FICATIuh P68 D EWSTEse PLAseT LEAK DETECT 100s N-25-0 SF I D 300 PAN TN! ACTIOss LucATI000 EQUIP. PLAN EOUSP.
P.O. esose (Si sePL seO. Case 90setset BI.DC. EIEV. tWytt (lp esoir ( 2) EEss REr' No, set:1 1 -S5-7E-s60 2200 G33 Temp. Eleet. esse! l-SE-TE-te0 22e6 Deactor 145 No esa 105 G33 Twep. Elemt. Reactor 132 08001 1-SE-TE-es0 22S No eso 105 G33 Temp. Eleet. heactor 132 eso sete! l-SE-TE-teG227 G33 -Toep. Eteet. eso 105 sesel Reactor 4 32 No seo 105 1-SE-TR-se0 2Jef G33 Temp. Elest. asactor 8 12 eso eso 105
. seS03 1 -SE-TL-se02 34 G33 Temp. Elemt. Reactor 8 12 88801 eso eso 105 1 -SE-TE-es0 2 3AA G33 Temp. Eleet. Reactor 145 ska eso 105 seDOI l-SE-TE-se023e ESI Toep. Eteet. Ibractor 54 se0el 1-FC-TE-es0230 No sk3 105 ESS Temp. Eteet. meactor 54 sesel 1-SE-TE-te0230 G33 Temp. Eleet.
eso No 105 senal Reactor 4 32 96 0 peo 105 1 -SE-TE-te0 23DO G33 Temp. Eleet. Deactor 145
.. ses01 seo . No 105 1-SE-TE-es023E G33 Temp. Elmet. hwactor- '132 spell 1 -S E-TE-ee0 2 3es G33 Temp. Eteet.
00 0 ska .305 08901 3 -SE-TE-esO2 3J Deactor 132 No iso 105 G33 . Temp. Eteet. sheactor 145 eso peo seS01 1 -SE-TE-se0 2 De G33 Temp. Eteet, 105 se003 3 -SE-T E-es0 2 3es heactor 145 eso 30 0 105 G33 Teep. Elemt. Reactor 845 No se003 3 -SE-TE-se0 2 3s G33 soo 105 Twep. Eleet, peactor 145 satel I-SE-TE-se0237 G33 Temp. Eteet. eso No 105' see'l peactor 145 sto seo 105 I-SE-TE-se0 2 3ef GB) Temp. Eleet. Deactor 145 semi No No 105 1-SE-TE-N024 E41 Temp. Eteet. Reactor 54 see!! No eso 105 l-SE-TE-es0 25A Bel Temp. Eleet. Reactor 102 satel 1-SE-TE-se0258 E'al Temp. Eleet. sto eso 105 esse! l -SE-TE-se0 25C Reactor 802 No No 105 E45 Temp. Eteet. steactor 102 ma steel 1 -SE-TE-seG 250 ESI Temp. Eleet. seo 105 Reactor 102 ska pha 105 Amendment 13 kevasson 3 0
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EQUI PseENT SELECTED FOR HAkSat ENVIROesMENI OUAL1FICAftisN P61 D SYSTEMS PLANT LEAR DETECTIOes ' SE
- l 1 O NO. PAN TMt ACTION
! P.O. esot e (55 sePL seo. LOCATIuss - Eyes! P. Cole MMsENT HLIC. ElEV. PLAN EQu!P. seOTE II) sk8TE 3 29 EESS BEF. seu. l se001 1-SE-TE-s60 25E Eel Temp. Eteet. peactor 54 setel 1-SE-TE-80025p ESI Toep. Eteet.- soo m 105 seutt 1 -SE-TE-se0 25G E48 heactor 54 mz esa
' Temp. Eleet. Deactor 54 i05 seso! l-SE-TE-se025ss ESI Temp. Eteet, No eso 105 88 0
- 1 1-SE-TE-te0 25J Eel meactor 54 m eso Temp. Eleet. sneactor 54 105 see01 1 -SE-TE-se025 E ESI No Temp. Eleet. Reactor 54 86 0 165 see01 1 -SE-TE-se0 25L eso eso Eel Temp. Eleet. Reactor 54 405 31601 3 -SE-TE-ses 25se ESI Temp. Elemt. No seo 105 880 1 1 -SE-TE-s00 25se E41 Reactor 54 No Temp. Eteet. Reactor 54 sk> 105 se901 1-SE-TE-te025P E51 No No Temp. Eleet. Reactor 54 105 see!! l-SE-TE-te0 25st E4t Temp. Eleet. No seo 105 se001 1-SE-TE-se0255 E51 Reactor 54 No No 105 Temp. Elemt.
l 800Cl 1-SE-TE-se0 28A E41 Temp. Eleet. Reactor 54 m No 105
- se004 1 -SE-T E-teS 28C Deactor 54 No .
tel Temp. Elemt. heactor 54
'Na 105
! le005 1-SE-TE-se0 294 E4t Temp. Eleet. soo No 105. seuel 1 -SE-TE-se0 24A Ell Temp. Elemt. Reactor 54 ski eso 105 see:S 1-SE-TE-ee0 29s Deactor 54 88 0 sto Ell Temp . Et eet , peactor 54 105 l esten 1-bE-TE-se029C E44 Temp. Elmet. No seo 105 l see:1 1-SE-TE-te0104 Eel Reactor 54 No m 105 Temp. Eleet. 1e801 1 -S E-TE-eso l0A Ell Temp. Eleet.
.Deactor 54 m No IG5 se0tl 1-SE-TE-te010e Deactor 17 m eh Ell Temp. Eleet. 105 80001 1 -SE-T E-Is0 30C Eel Temp. Eleet.
Isaactor 77 m 84 o los asactor 77 m eso 105 l Amenoment 11 Revision 3 l (
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'GS N M Page 20 of'420 TAmLE 3.I I -5 EQuligsENT SELECTED FOR MAkS88 t'NVikMENT 068ALIFICATIOtt P61 D SYSTENs PLAle? LEAR DETECTIOst SE I O seo. PAN TNI ACTION P.O. LOCA71 col EUut P. PLAN EOutP.
soote (S) sePL 000 Cost poseENT B L IE. Et EV. eenTE ft) estyTE 62) FESS REF. No. J 4e 30 3 -EG-LSN- 2 35s4 level SJ. nigh J48 30 1 -EG-LSas-2 359a neactor 102 seo sk) 42 level Sw. Iligh heector 102 m) J 49 30 1 -rG-LSN- 2 M 4A Level Sw. Nigen eso 42 J4830 peactor 102 mm No 42 3 -EG-LSN-2 M 4a lawel Sw. Nigh neactor 102 J4830 1 -ED-LS40-2 M 5A No No 42 Imvel Sw. Nigh meactor 77 50 No Joe 30 1 -E D-LSie-2 M 5a Level Sw. Nigh 42 J4430 Steactor 77 ieo ms 42 1 -ED-LSN-2 M 5C Level Sw. esigh . Reactor 77 too mm 42 J48 30 4 LE-4 4 53 -1 level Element aactor 54 J4e 30 DD-LSN-4151-1 sso mm 42 Level Sw. Nigh peactor 54 seo No
'J4830 1 -m D-L E-4158 - 2 Invel Element steactor 54 42 J4330 m3 No 42 1 -DD-LSN-4151-2 Inve! Sw. estuh meactor 54 No No 42 J'430 4 -Isc-LE-4 40 3Al Level Element Desctor 54 ska J4330 4 -DC-LSN-440 3Al Level Sw. Nagh peactar 54 36 3 42 J4430 1-DC-LE-440 342 No m) 42 Imwel Element Reactor 54 No No J483Q E-SC-e.See-4 40 3A2 Level Sw. Nagh 42 teactor 54 seo No 42 J4430 1-SC-L. -440 3al Invel Element Beactor 54 No No 42 J 48 30 1-tC-LS' -4 40 381 Level Sw. Nigh 8teactor 54 No J4530 1 -tC-LE- 440 382 No 42 Emwel Element peactot 54 No J44 30 1-eC-LS4 -4401ss2 ans. 42 J48 30 Level Sw. Niets meactor 54 No Dio 42 1-DC-LE-4 40 3Cl Level Element steactor 54 88 0 ska 42 To be reta.Jged in the field J4430 1-hC-LE-4403C2 I4wel Element meactor 54 No t o I-pf*LE-4134 -2 No 42 To be retapje4 in t!.e field t o I -Ist>-LE-4154 -1 Amendees, t i3 kewision 3 l
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NCGS FSAA TANLE 3.11-5 Page 21 of 120 EQUI PMt NT SFLECTED Fue itAR$tt FNVISONMENT QUALIFICATl04 Phl D SYSTENs PLANT LEAR 1*TECTION N-25-0 SE I D NO. PA89 T841 ACTlth P.O. me e (S) se Pl. NO. LOCATI aA6 EQUIF. CEse MaieE T 1t*10 FIFV. PLAN EQUIP. NOTE Ill m RTE 1 28 FFS$ mEF. NO. J48 30 1-ac-LE-4403D1 lawel Element J4830 1-hC-LSN-4403D1 peactor 54 No Imwel Sw. N!gh No 42 J 48 30 1-BC-LE-4403D2 Reactor 54 No geo J4430 Level Element peactor 54 42 1-BC-LSN-4403D2 Imwe l Sw . High km eso 42 J4830 1-BE-LSN-4581A1 Level Sw. Migh laeactor 54 sao No 42 J4830 1-DE-LSN-458tA2 Beactor 54 No mm Imwel Sw. High Deactor 54 42 J4830 1-8E-LSH-4588BI 14wel Sw. Nigh 90 0 m) 42 J48)Q 1-BE-LSN-458182 aeactor 54 No e Imwel Sw. High 54 42 J 48 30 1-mE-LSN-4581Cl Level Sw. High Beactor m ha 42 J483Q 1-be-LSN-458tC2 Reactor 54 ska m Invel Sw. Nign anacect 54 42 J 48 3Q 3-tE-LSN-4581DI Leven Sw. High No e 42 J4830 1-est-LSN-4 58t D2 Rom tor 54 m2 No Level Sw. Nivlb 42 J 48 30 1-ak3-LE-4807 Level Element Reactor peactor 54 m m 42 J4830 1-RJ-LSN-4807 54 ato e Level Sw. Magh Beactor 54 42 J 48 30 1 -Ik3 -L E- 4 8 0 8 Level Element Reactor No m 42 J48 30 1-aJ-LSN-4808 S4 No No Inwel Sw. High 42 N001 1-SE-LT-4930 Level Trans. Reactor 54 m m 42 se001 1-SE-LT-4931 Drywe!! 77 Yes Yes P30 3AQ 1-hE-HV-495 3 Level Trans. Drywell 77 Yes 155A Control Valve Re act or Yes 155A P30 3AQ 1-SE-IS-4953 145 No m Limit heitch neeactor 145 i 19 P 30 3AQ 1-SE-HV-4957 Control Valve Yes e 1 39 P30 3AQ 1-SE-25-4957 Beactor 145 m 16 o 5 39 Ltait Switch Beactor 145 C)e 3AQ 1 -SE-etV-49 81 Control Vanwe /*s No 1 39 C30 3AQ 3-SE-2S-4981 keactor 145 seu sen 4 39 P 301aq Limit switch Reactor 145 3 95-enV-5088 Control Vanwe Yes see 1 49 P30 3AQ 1-55-25-5018 Reactor 145 seo No I #9 Limat Switch Deactor 145 Ye s No 1 36 Amerw1 ment I3 iswwianon 3 1 i l l
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L NCGS FSAR P y 22 og 133 TAeLE 3.11-5 , EOct rueENT SELECTED Poe NAR$N ENWl"""T OUALIFICATION Pel D I SYSTENs DADtutim;lCAL peONITORING STS M-26-1 l S P _. PAft TUDE ACTIOee
. I D 800. LOCATI One 8001 P. PLAge a001P.
F *- hot
- ESI NPL eso. CasernesENT ELDC. ' ELEV. esOTE ft) teOTE (2) RESS REF. too.
seSta 1-S HSE-90006A Dil mediatton Element Reactor- 102 .No No 1 21
- se001 S P-R E-te00 68 Dll mediation Element Reactor 102 sto m 121 l - fe001 . I-SP-RE-4006C . Oll. Radiation Element peactor 102 ' 30 0 eso 1 25 i 80e01 l-S P-D E-se036D Dil Radiation Element peactor 882 gao geo 121 J 37 30 3 -S P-R E- 4 9 254 Radiation Eleseet Deactor- 145 Tes Yes later J3730 3 -S P-a E-4 8 258 padiation Element Reactor- 145 Ves yes later i J 37 30 1-SP-RE- 4456A ' mediation Element peactor 201 peo seo later
!' J 37 3Q 1 -S P-R E- 44 568 mediatins Element teactor 204 too eso - late r
- J B7 3Q 1-SP-RE-4854C Radiation Element Reactor 201 Iso too 'later J37)O l -S P-R E- 48 57 A hadiation Element heactor '178 Iso Iso later J 37 30 1 -S P- D E- 48578 hadiation Element beactor. 178 Ito too later J3730 1 -S P-R E-4 857C Badiation Element peactor 170 Iso Iso - later J 37 h) . 3904 Rockbestos/Coas Caple CA Deote (31 Tes Yes later Amendment 13 pevision 3 e
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NCGS FSAR TAeLE 3.!!-5 Page 2 3 - of 1 20 EQUI 19 TENT SELECTED FOR NARSN ENVIRONNENT QUALIFICATION P61 D SYST68e a ~ POST ACCIDENT LIQulD s GAS SAMPLissG M-38-0 RC ') I D 800. PAN TMI ACTION P.O. Not e ( 5) LOCATEON -EQUIP. MPL 800 COSBM)stEse? BLDC. PLAN EQUIP. EI.EV. teOTE (l) NOTE ( 2) :j J6030 EESS REF. NO. 1-hC-SV-064 3A Solenoid valve J6430 peactor 77' No 3 -SC-IS-064 3A position Switch Yes 46 J6430 1 -DC-SV-064 38 Solenoid valve Beactor ?? Yes No 46 J6030 I-AC-2S-064 38 peactor 77 peo J 60 30 1-mC-SV-06454 Position Switch - Reactor 77 Yes Yes No 46 J60 30 - 1-RC-IS-0645A Solenoid Valve- heactor 54 seo 46 J6030 1-DC-SV-0645a Position Switch Iteactor 77 No Yes 46 J6030 Solenoid Valve peactor 54 No seo 46' 1-mC-25-0645es Position Switch Yes 46 J6030 1-RC-SV-06464 neactor 77 No No J6030 1-kC-25-04464 Solenoid Valve peactor 54 eso 46 J6030 4-mC-SV-06460 Position Switch Deactor 77 No Yes too 46 J6430 1-AC-IS-06468 Solenoid Valve peactor S4 No 46 J6030 1-RC-SV-0707A Positton Switch Beactor 77 No Yes- 4b J6030 Solenoid Valve be actor 77 aso 80 0 46 1 -RC-IS-070 7A position Switch Yes 46' J6030 1-eC-SV-0707m Reactor 77 Yes No Solenoid valve meactor 77 46 J6030 1-RC-IS-4707B _ Position Switch No Yes 46 J6430 1-DC-SV-0728A Reactor 77 Yes No J6030 1-WC-2S-0728A Solenoid valve peactor 77 No Yes 46 J60 30 1-DC-SV-072sm Position Switch Beactor 77 Yes -No 46 Solenoid valve Reactor 77 46 J6030 4 -esc-IS-07 2em Position Switch No Yes 46 J60 30 1 -pC-SV-07 294 Reactor 77 Yes No 46 Solenoid Valve Deactor 77 l J603u l-mC-2S-0729A Position switch No Yes 46 meactor 77 Yes No 46 ! Amendment 13 povision 3 b 9 { I' .
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- EOuligeENT SELECTED FOR HARSH ENVI RONNENT QUALIFICATION P61 D EYSTENs POST ACCIDENT LIQUID & GAS SAMPLING M-38-0 RC I D NO. PAN TMI, ACTION .
P.O. Not e ( 5)
- NPt. NO. LOCATION' EQUIP.
COMPONENT HLDG. PLAN EQUR P. FIEv. NOTE (1) NOTE ( 2) J6030 1-RC Sv-0729s EESS REF. NO. J1@30 1-RC-IS-07298 Solenoid valve. . Reactor 77' No. Position Switch Yes 46 J1030 1 -RC-SV-07 30A Solenoid valve Reactor. 77 Yes No J1830 Reactor 162' 46 ' 1-RC-IS-0730A' Position Switch No Yes ' ' 46
. J4@30 1-RC-SV-0730s Reactor 162 Yes
.J6230 1-RC-IS-07308 Solenoid valve Reactor 162 No No 46
. J $@ 30 1 -RC-SV-07 31 A Position Switch. Reactor 162 Yes Yes 46 Solenoid Valve No 46 J633Q 1 -RC-IS-07 3 5 A Reactor. 162 No Yes J6030 1-RC-SV-0731s Position hwitch Reactor 162 Yes 46 solenoid Valve No 46 J3330 1-RC-IS-07318 Reactor 162 No J10 30 1 -RC- SV-890 3A
' Position Switch Reactor 162- Yes Ye s 46 Solenoid valve N0 46 J1930- I -RC-t S-890 3A Reactor 77 No .
-J10)O l-RC-SV-89038' Position Switch Reactor 77 Yes Yes 46
' Solenoid Valve No 46 J6030 1-RC-IS-89038 Reactor 77 No Yes Position Switch Reactor 77 46 Ye s . No 46 Amendment !3 Revision 3' e
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- NY-f HCGS FSAR TABLE 3.11-5 Page 25'. of 120 EQUI PMENT SEl.ECTED FOR HARSH ENVI RONMENT OUALI FICATION P6t O SYSTEMg NUCLEAR BOILER N-41-1
, AB I D NO. PAN TNI ACTION P.O. Note (5) MPL NO. 1DCATlON EOutP. PLAN EQUIP. COM PONENT B LIC . FIEV. NGYE (Il NirTE -( 2) EESS REF. NO. P3020 1-AE-NV-FO!!A Control Valve P1020 1-AE-28-F04IA Reactor 1 21 No No Limit Switch Reactor 1 32 P3020 1-AE-HV-F0llB 121 No No I12 Control Valve Reactor 1 21 No , P3120 1 -A E-2 5-FO! ! B . Limit Switch No 132 P3320 - 1-AB-NV-F016 Reactor 121 No
' control valve Reactor 102 No
'No l 12 P3320 1-AB-2S-F016 Limit Switch No 1 32 P3020 1 - AB-N V-F019 - Reactor 102 Yes No 112 Control Valve Reactor- 102 P)320 1 - AB-I S- F019 Limit Switch No No 1 Il M021 1 -AB-IS-F0 2 2A B21 Reactor 102 Yes No 1 31 Position Switch Reactor 100 M001 1-AB-SV-F022Al B21 Solenoid Valve Yes No 158 M011 1 -AB-S V-F0 22A2 Reactor 100 No No 160 B21 Solenoid Valve Reactor 100 No No M021 1-AB-SV-F022A3 B21 Solenoid Valve 160 M0!! l -AB-IS-F0 22H B21 Reactor 100 No No 160 Position Switch Reactor 100 Ves N001 1-AB-SV-F022B1 821 Solenoid Valve No 158 M0!! l-AB-SV-F022H2 Reactor 100 No No 160 B21 Solenoid Valve Reactor 100 No M001 1-AB-SV-F02283 B21 Solenold valve No 160 M011 I-AB-2S-F022C . Reactor 100 No No 160 N001 B21 Position Switch Reactor 100 Yes 3-AB-SV-F022Cl~ B21 Solenoid Valve No 158 M001 1 -AB-SV-F0 2 2C2 B21 Reactor - 100 No NO B60 Solenoid valve Reactor 100 No MODI l-AB-SV-F022C3 B21 Solenoid Valve Reactor No 160 M001 1-AB-2S-F022D 100 No No 160 M011 B21 . Position Switch Reactor 100 Yes No 1-AB-SV-F022D1 B21 Solenoid valve 158 MODI l=AB-SV-F022D2 Reactor 100 No No 160 B21 Solenoid Valve keactor 100 No No M001 1-AB-SV-F022D) B21 Solenoid Valve 160 M011 1-AB-2S-F028A Reactor 100 No No 160 Mull 3-AB-SV-F028Al B21 Position Switch Reactor 102 Yes No B21 Solenoid Valve R$8 M001 1-AB-SV-F028A2 Reactor 102 No No 860 M001 828 Solenoid Valve Reactor 102 No No 1-AB-SV-F028A) B28 Solenoid Valve React or 100.
160 M001 1-AB-25-F0288 No No 160 M001 821 / Position Switch Reactor 102 Yes No 158 1-AB-SV-F02881 B21 Solenold valve Reac t or 102 No NO 160 Amendment 13 hevision 3 9
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j b l- 'Q) l i . HsES FSAR Pade'26','of I20 TABLE 3.11 -5 ' . t,0UI 69 TENT' SELECTED FOR HARSH ENVI kONNENT OUALIF1 CATION P61 O SYSTENs NUCLEAR BOILER N-41-1 AB f PAN TN! ACTION I D NO. LOCATION P.O. Note (5) N PL NO.' EOU8 P. PLAN EQUEP. CON POf6E NT H L ur;. E f.EV. NOTE (l) NOTE ( 2) EESS RFF. NO. 8e011 1-AB-SV-F02882 821 Solenoid valve' Reactor 102 No NOIl 1-AB-SV-F0280s) 821 No 160 Solenoid Valve Reactor 100 No No . 10 0
- 1 l-AB-2S-F020C B21 Position Switch 160 80011 l-AB-SV-F020Cl Reactor 102 Yes No' 158 821' Solenold' Valve Reactor 102 No N0!! !-AB-SV-F02802 B21 No 160 Solenoid valve Reactor 102 No No 08021 1-AB-SV-F028C) 821 ' Solenoid Valve 160 Reactor 100 No No 160 10001 1-AB-23-F0200 B21 Position Switch Reactsc 102 NO21 1-AB-SV-F020D4 B21 Yes No 158 Solenoid Valve Reacto9 102 No No 1 N001 1-AB-SV-F02802 B21 Solenold Valve 160 Re ac tor 102 No No 160
. 80001 1-AB-SV-F02803 B21 Solenoid Valve Reactor 100 No P3020 1 -AE-HV-F0 3 2A No 160 Control Valvet Reactor 102 No No ,1 32 P3020 1-AE-IS-F032A Limit Switch Reactor 102 P3220 1-AE-HV-F0328 Yes No 'l32. Control Valve Reactor 102 No No 4 P3020 1-AE-IS-F0328 Limit Switch. I 32 Reactor 102 Yes No 1 32 P 313AQ 1-AH-etV-F067A Control Valve kwactor 102 1-AB-28-F067A' No No 1 37 P323AQ Limit Switch 14eactor 102 P333A3 1-AB-HV<F067B Yes No 137 4 Control valve Reactor 102 No No ' P303AQ I-AB-2S-F0678 Limit Switch React or 102 Yes 1 37 P 333AQ 1-AB-HV-F067C No 1 37 Control valve' Reactor 102' No No P333AQ 1-AB-2S-F067C Limit Switch 1 37 Reac tor 102 Yes No 437 i Amendment 13 Revision 3 e p >w.
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\-- 'l .' Q HCGS FSAR TAHLE 3.11-5 Page 27 .of 'l20 EQUI PMENT SELECTED FOR HARSH ENVIRONMENT OUALI F1CATlUN P61 D SYSTEMS NUCLEAR BOILER M-41-1 AB ID NO. PAN ^ TNI ACTION P.O. Note i5) NPL NO. LuCATION EQUIP.
COMPONENT BLIC. PLAN EOutP. ELEV. NOTE (ll NOTE ( 2) EESS REF. NO. P303AQ 1-Ab-HV-F0670 Control Valve P393AQ 8-AB-2S-F067D Reac tor 102 No No 1 37 Limit Switch Reac tor 102 P333AQ l-AB-HV-F071 Control Valve Yes No 137 P33 3AQ 1-AB-2S-F071 Reactor 102 No No 132 Limit Switch Rwactor' 102 P3220- AE-IS-F074A Limit Switch No No 1 12 P3020 1-AE-IS-F0749 Heactor 102 Yes No 1 14 ^ Limit Switch React or 102 N001 1 - AB-P!YF-Nu a 6A Ye s m3 M021 1-AB-PDT-N086B B21 Press Diff. Trans. Reactor 77 No No 1 34 H21 Press Diff. Trans. Reactor 77 155 Mott l-AB-Pirr-N006C B21 Press Diff. Trans. No No 155 M021 1 -AB-PDT -N006D Reactor 77 No No B21 Press Diff. Trans. Reactor 77 155 M001 1 -A B-PDT-N0 8 7A 821 No No M001 1-AB-PDT-N0878 Press Diff. Trans. Reactor 77 No No 155 B21 Press Diff. Trans. Reactor 77 155 Mott 1 -AB-PDT-N 0 8 7C B21 Press Diff. Trans. No No 155 MOO! l-AB-PDT-N007D Reactor 77 No No B21 Press Di f f . Trans. keactor 77 155 M011 1 -AB-PDT-N 088A B21' No No 155 M001 1-AB-PDT-N088B Press Diff. Trans. Re ac tor 77 No No 155 M001 1 -AB-PDT-N088C B21 Press Dif f . Trans. Reac tor ll No No B21 Press Diff. Trans. Reactor 77 155 M001 1-AB-PDT-N0880- No 155 M001 1 - AB-PDT-N 0 89A 821 Press Ditf. Trans. Heactor ll No No - No B21 Press Diff. Trans. 155 M021 1-AB-PDT-N089B 77 No No M0 tt B28 Press Dif f. Trans. Reactor , 77 leenctor No No 155 I - AB-PDT-N089C B21 Press Diff. Trans. 155 M021 1-AB-PDT-N089D Re ac tor 77 No No ISS B21 Press Diff. Trans. Reactor 77 No No 155 Amendment 13 Revision 3 a b
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HCGS FSAR TABLE 3.11-5 - pay, '28 ' of 120 EQUI PMENT SELECTED FOR HARSH ENVIRONNENT QUALI FICATION _ P5I D . SYSTEM -- NUCLEAR DOILER Au N-41-1. I D NO. PAN . TNI ACTION P.O. Nota (5) MPL 000. LOCATI ON . EQUIP. CONP008ENT BtDC. ELEV. . PLAN EQUtP. NOTE (Il NOTE ( 2) P3030 1 -Ah-HV- 36 35 A . FESS REF.'NO.
.P3220' 1-AS-IS-363!A Control Valve Reactor. 102.
P3020 1-AS-HV-36313 Limit Seitch Reactor 102 No No' No 1 132 P3220 1 -As-Is-36 3 5 m
. ContrO! Valve Reactor 102_-
No - 132 P3020 1-AS-HV-36 35C ' Limit Seitch peactor 102 Ka. No
.No 132 P3220 1 -Ah-IS-36 31 C '
Control Valve Reactor 102 No , No 132, P3020 1-AS-HV-36 3 R D - Limit TT ' ' A peactor 102 h No" 132 P3020 1 -Als-3 8-36 3R D Contro! va.se. heactor 102 No No '132 J5560. I-Sm-TE-3647A Limit Switch. -Reactor 102 No No 132-Temp. Elemt. No 132 J 5510 . 1-Su-TE-3647s Dep. Elemt. Reactor 54 Yes Reactor No . '. 4 3 J5560 4 -Sa-TE- 364 7C Temp. Elemt. 54. Yes No ^ 43 J55tQ 1 -Sle-TE-364 7D Temp. Elemt. Re ac tor 54 Yes No 43 J5560 ' l -SR-TE- 36 4 7E Temp. Elemt. Reactor. 54 Yes No J5560 - Reactor .54 43 1-St-TE-3647P. Temp.. Elemt. Yes No 41 J5510 1-SB-TE-3647G - Temp. Elemt. anactor 54 Yes . .No -43
. Jb510 1-Sis-TE-3647N -Temp. Elemt.
Reactor 54. Yes No
-heactor 54 43
~ J 5560 1-SB-TE-3647J Temp. Elemt. Yes No 41 J5560 1-St-TE-3647E Temp.,Elemt.
Reactor 54- Yes No peactor 43-J5560 1-SB-TE-3647L- Temp. Elemt. 54 Yes No - 43 J5560 1 -Sis-TE- 36 4 7st _ neactor 54 - Yes No Temp. : Elent . Reactor 54 43
.35560 1 -S h-TE- 364 7N Temp, Elemt. Yes No 43 J5560 1 -Su-TE- 364 7 P Reector. 54' Ye s ' No Temp. Elemt. Heactor 54 43 J5560 1-Sa-TE-36470 Temp. Elemt. Yes , No 43 J5510 1-SB-TE-3647a Reactor 54 Yes No Temp. Elemt. Reactor 54 43 Yes No 43-Amendment 13 Revision 3 e,
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'. TABLE 3.11-5 Page 29 of 120 SYSTEMS NUCLEAR BOILER EQUI PMENT SELECTED FOR H ARSH ENVI RONMENT OUALI FI CATION P6 t D AB M-41-1 1D NO. PAM P.O. Note ( 5) LOCATitwo TMI ACTION MPL NO. COM PEMIE hT Eput P.
PLAN EOutP. RLDG. El.EV. NOTE (1) NOTE ( 2) FENS REF. NO. J5560 1 T g- 354 3A J5560 Temp. E!*mt. 1-rB-TE-36488 Temp. Elemt. Reactor $4 Yes J5560 1-Ae-TE-364BC Reactor No 43 Temp. Elemt. 54 Yes J5560 Reactor No 43 1-AB TE-36480 Temp. Elemt. 54 Yes No M011 1 -SN-S V- 365 2A B21-FOL3 bactor 54 '43 M011 1-SM-SV-3652B~ Solenoid Valve Reactor 1 21 Yes No 41 MODI B21 -F013 Solenoid Valve- No No 159 l-SN-SV-3653A B21-FO L 1 Reactor 1 21 M011 1 -SN-SV-365 38 Solenoid Valve Reactor 1 21 No No 159 M031 B21 -F01 ) Solenoid Valve No No 1 59 1-SN-SV-3654A B2 L-F013 Solenoid Valve Reactor 1 21 No No MODI l-SN-SV-36548- B21 - F013 Reactor 12% No 159 Meil 1-SN-SV-3655A Solenoid Valve Reac tor No 159 M021 B21-F013 Solenoid Valve 1 21 No No 159 1-SN-SV-3655B B21-FOL1 Iteac t or 1 21 No MODI l-SN-SV-3656A- Solenoid Valve Reactor No 1 59 N001 821-f 313 Solenoid Valve 1 21 No No 159 I-SN-SV-3657A B21 -F011 Solenoid Valve Reactor ' 12% No No N021 1-SN-SV-3650A B 21 -F013 Reactor- 1 21 159 M0!! l-SN-SV-3659A Solenoid valve' Reactor 1 21 ' No No 159 B21 - F013 Solenoid Valve No No MOO! 1-SN-SV-3660A . Reactor 1 21 159 M004 B21-FOL3 Solenoid Valve No No 159 1-SN-SV-3661A B21 - F013 - Solenoid Valve Reactor 12t No No M001 1 -SN-SV-366 2A Reactor 1 21 1 59 M011 B21-F013 Solenoid Valve No No 159 1 -SM-SV- 366 3A B21-F013 Reactor 12% No M0il 1-SN-SV-3664A Solenoid Valve heactor No 159 M021 B21-F013 Solenoid Valve 1 24 No No 159 1*SN-SV-3665A B21 -F013 Solenoid Valve Reactor 1 21 . No No MODI l-SN-SV-3665B Reactor 159 v21-FDL3 Solenoid Valve 1 21 No No 159 J8100 1 -AB-XE-4 50 7A Reactor 1 21 No J8100 1-AB-XT-4507A Acoustic Elmet. Reactor 1 21 No I59 Acoustic Trans. Yes Yes J8000 1-AB-XE-45078 . Reactor 102 Yes 51 J8000 1-AB-XT-4507B Acoustic Elemt. Reac tor 1 21 Yes Yes 50 Jue00 1-AB-XE-4507C Acoustic Trans. Heactor 102 Ye s 54 J OOQ. I -AB-X T-4 50 7C Acoustic Elemt. Reactor 1 21 Ye s Yes Yes 50 J800Q 1-AB-XE-45070 Acoustic Trans. Reactor. 102 Yes 51 Acoustic Elemt. Yes Yes 50 J8000 1-AB-XT-4507b Reactor 1 21 Yes JOIGO . I-AB-XE-4507E Acoustic Trans. Reactor 102 Yes Yes 51 J8100 - 1-AB-XT-4507E' Acoustic Elemt. Reactor 121 Ye s 50 Acountic Trans. Tes Yes St JIDOO 1 -A B-X E- 4 50 7F Reac tor 102 Yes Acoustic Elemt. Reactor 1 21 Ye s Yes 50 Yes $1 Amt-udment I3 Rev i s ion 3
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' SYSTFNs NUCLEAR BOILER M-41-1 AB
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I D NO. . PAM TM1 ACTI ON P.O. Note (5) LOCATION EVO! P.' PLAN EOutP. MPL NO. COM PONENT BLDG. ELMV. NOTE (1) ' NOTE ( 2) EESS REF. NO. J0100 1-AS-XT-4507F Acoustic Trans. J8000 4-AB-XE-4507G Reactor 502 Yes Yes 50 J8000 Acoustic Elemt. Reactor 121 Yes 1-AB-XT-4507G' Acoustic Trans. Ye s 51 J8000 1-AB-XE-4507H Reactor 102 Ye s Yes 50 J8000 Acoustic Elemt. Reac tor 121 Yes Yes 1 - AB-XT- 4 50 7H Acoustic Trans. St J8100 1-Am-XE-4507J Reac t or 102 Yes Yes 50 Acoust ic Elemt. Reactor 12% Yes J8000 1-AB-XT-45G7J Acoustic Trans. Yes 5t
- .' J8000 1-AS-XE-4507K Reactor 102 Yes Yes 50 J8100 Acoustic Elemt. Reactor 1 21 Yes 1-As-XT-4507K Yes 51 Acoustic Trans. Reactor 102 Ye s JOIOQ 1 -AB-X E-4 507L Acoustic Elemt. Yes 50 J8000 Reactor 1 21 Yes Yes 1-An-XT-4507L Acoustic Trans. Reactor 102 51 J8000 1-AB-XE-4507M Acoustic Elemt. Ye s Yes 50 i
J8000 1-Aa-XT-4507M Reactor. 1 21 Yes Yes J8100 Acoustic Trans. Reactor 102 Ye s 51 1-AB-XE-4507P - Acoustic Elemt. Reactor 1 21 Yes 50 J800Q 1-AB-XT-4507P Ye s Yes 51 Acoustic Trans. Reactor 1 21 3 JOIOO l-Ah-XE-4507R Acoustic Elemt. Yes 'Yes 50 , J8100 1-AR-XT-4507R Reactor 1 21 Yes - Yes SI j Acoustic Trans. Reactor 12% Ye s
- M011 1 - AS-PT-58 38 A Press. Trans. Yes 50 M001' l-AB-PT-50388 . Reactor 102 No No 155A
. Press. Trans. Steactor 102 No No 155A Amendment 13 Revision 3 J
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8e011 1-SE-EAM-K002A C51 Voltage Preamp Reactor 102 No M011 1-SE-EAM-K002H No 154 C51 Voltage Preamp Reactor 102 No No se011 1 -S E-E AM-K 00 2C CSI Voltage Preamp 154 M011 Reactor' '102 No No I54 I -S E-EAM-K 00 2 D C51 Voltage Preamp Reactor 102 No No se001 l -S E-E AM-K 00 2E C51 Voltage Preamp 154 sooll keactor 102 No No 154 1-SE-EAM-K002F CSI Voltage Preamp Heactor 102 MOIL No No 154 I-SE-EAM-5002G CSI voltage Preamp Reac tor 102 No M031 1-SE-EAM-K002H No 4 54 CSI Voltage Preamp Reactor' 10'4 No NJ MOSI l-SE-RE-N001 A CSI Radiation Elemt. I54 keector 1 21 Yes No 162 80031 1-SE-RE-N00lb C51 Radiation Elemt. Reac tor 1 21 M001 1-SE-RE-N00lc CSI Yes No 162 Radiation Elemt. Reactor 1 21- Yes No M0tt 1-SE-RE-N001D C51 Radiation Elemt. 162 Reactor 1 21 Yes No 162 M011 1 -SE-RE-N00 2A CSI Radiation Elemt. Reactor 1 21 Yes No 103 M011 l-SE-RE-N0028 C51 Radiation Elemt. Reactor 121 M001 Yes No 103 1-SE-RE-N002C CSI Radiation Etant. Reactor 1 21 Yes 0e005 1-SE-RE-N002D CSI No 101 Radiation Elent. Reac tor 1 21 Yes No M001 1 -S E- R E-N00 2E CSI Radiation Elemt. 103 keactor 1 24 Ye s No 103 sootl 1 -S E-R E-N00 2F CSI M021 1 -S t-RE-N00 2G Radiation Elemt. Reactor 1 21 Yes No 101 C51 kadlation Elemt. Reactor 1 21 ~Yes No 103 80001 1 -SF-k E-N00 2H CSI Radiation Elemt. Reactor 1 21 Motl 1-88-PT-Nus04 Ye s No 10) C71 Pressure Transmitter Reactor 162 N001 1 -hs-PT-N050 B No No 155 C71 Pressure Transmitter Reactor 162 M001 No No 155 1 -BH-PT-N0 50C C71 Pressure Transmitter keactor 162 No v 80 0 *, 1 1-bS-PT-N05bD No 155 ' C71 Pressure Transmitter Reactor 162 No 80001 1 -sts-PT-N0 78A No 155 B21 Pressure Transmitter Reactor 77 No No 155 M011 1-BB-PT-N0768 B21 Pressure Transmitter Reactor 77 No M024 No 155 1 -8 B-PT-N078C H21 Pressure Transmitter Reactor 77 No No 155 Amendment 13 Revision 3 9
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k N_/ h v Y HCGS FSAR TABLE 3.14-5 page 33 og 120 . EQUI PMENT SELECTED FOR HARSH ENVikONMENT QUAL.l FICATION MID SYSTEMS NUCLEAR BOILER VESSEL INSTRU M-42-1 BB PAM TM'l ACTI ON I D NO. LOCATEON P.O. Note (5) MPL NO. FOUI P. PLAN EQUI P. COMPONENT B LIC. E LE V. NOTE (t) NOTE ( 2) EESS REF- NO. M001 1-BB-PT-M078D B21 Pressure Transmitter Reactor 77 No No M0ll 1-88-LT-M080A B21 Imvel Transmitter Reactor 77 155 MOO! l-BB-LT-N0808 No Yes 155 N001 821 . Level Transmitter Reactor 77 No Yes 155 1-BB-LT-N0s0C B21 . !avel Transmit ter Reactor 77 N0!n 1-BB-LT-N000D No Ye s 155 B21- Level Transmitter Re ac tor 77 No M011 1-SM-LT-N088A B21 Yes 155 Imvel Transmitter Reac tor 77 No Yes Mot! l-SM-LT-N0018 821 Level Transmitter 155 Reactor 77 No Yes 155 M001 1-SM-LT-M04tc B21 Imvel Transmitter Reactor 77 No MOSI 1-SM-LT-N08tD B21 Ye s 155 Level Transmitter Reactor 77 No Yes 4021 1-BB-LT-N005A B21 Level Transmitter 155 Reactor 77 Yes . Yes M011 1-BB-LT-N0s58 B21 Level Transmitter peactar 77 155 M021 1 -BB-PT-N09 0A Yes Ye s - 155 B2R Pressure Transmitter Reactor 77 No No 155 M0!! l-BB-PT-N0908 B21 Pressure Transmitter Reactor 77 No M001 1-88-PT-M090E No 155 M001 1 PT-M090P B21 Pressure Transmitter. Reac tor 77 No No 155 B21 Pressure Transmitter Reactor 77 No N011 1-BE-PT-M090J No 155 B21 Pressure Transmitter Reactor 77 No M001 1 -BE- PT-N090 K B21 No 155 Pressure Transmitter Reactor 77 No No M001 1 -BE-PT-N09 0N 824 Pressure Transmitter 155 Reactor 77 No No 155 M0il 1-BE-PT-N090P B21 Pressure Transantter Reactor 77 No M0ll 1-BB-LT-N091A No 155 B21 Level Transmitter Reactor 77 M011 laBB-LT-N0918 Yes Yes 155 B21 Level Transmitter Reactor ?? Yes N021 1-BB-LT-N09tc Yes 155 B21 Level Transmitter Reactor 77 No M031 1 -BB-LT-N09 t D B21 Yes 155 Level Transmitter Reactor 77 No Yes llrJ01 1-BB-LT-N09tE R21 Level Transmitter 155
. React or 77 No Yes 155 M001 1 -BB-LT-N091 F B21 Level Transmitter Reactor 77 No M021 1-BB-LT-N091G B21 Yes 155 laval Transmitter Reactor 77 No Yes M001 1-BB-LT-N091H B21 Level Transmitter 155 Reactor 77. No Yes 155 M011 1-88-PT-N094A B21 Pressure Transmitter Reactor 162 No No 155 Ame=ndme n t !I Revision 3
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SYSTEM
- NUCLEAR BOILER VESSEL INSTRU M- 4 2-1 BB PAM TML ACTION, I D NO. LOCAftON EQUIP. PLAN EQUIP.
P.O. Not e 15) M Pl. NO. CON PONENT BLDG, E E.E V. NOTE ( 1 ) NOTE ( 2) EESS REF. NO. se011 1 -BB-PT-N09 48 B21 Pressure Transmitter Reactor 162 No No se021 1-BB-PT-M094C B21 155 Pressu.'e Transmitter Reactor 162 No No M001 1-BB-PT-N09 4 D B21 Pressure Transmitter 155 Reactor 162 No No 155 00001 1 b8-PT-N094E B21 Pressure Transmitter feeactor 162 No No N001 1-BB-PT-N094F B21 155 Pressure Transmitter Reactor 162 No No 155 MOI! l-St'-PT-N094G B21 Pressure Transmitter Reactor 162 No No M021 1-88-PT-N094H B21 155 Pressure Transmitter Re ac tor 162 No No 155 M0!! l-S4-LT-N0958 821 Imvel Transmitter Reactor 17 No Yes 155 MO SI l-SN-LT-N095D B21 Level Transmitter Reactor' 77 No Yes MO 1 1 -BB-LT-N09 7 D B28 155 Level Transmitter Reactor 77 No No 155 MO31 1-BB-LT-N097N 821 Level Transmitter Reactor 77 No MODI l-BR-LT-N4 0 2A B21 No 155 Imvel Transmitter Reactor 77 No No 114 N001 1-BB-LT-N4028 B21 Leve! Transmitter -Reactor 17 No No M0!! ' l -BB-LT-N4 0 2E B21 114 level Transaltter React or 77 No No !!4-se011 1-88-LT-N402P B21 Level Transmitter- Re actor 17 No No N0l! l-BB-PT-N40 3A B21 !14 Press Transmitter Reactor 77 No No !!0 N011 1-BB-PT-N4038 B21 Press Transmitter Reactor 77 No No N005 1-BB-PT-N403E B21 140 Press Transmitter Reactor 77 No No . 110 se011 1-BB-PT-N403F B21 Press Transmitter Reactor 77 No No llo se021 1 -BB-R E-12019 3 B11 Radiation Elemt. Reac tor 120 Yes No l-BB-RE-13D19 3 107 MORI Bi l Radiation Elemt. Re ac tor 120 Yes No 107 se011 1-88-9E-14D493 81 1 Radiation Elemt. leeactor 120 Yes No 107 , se021 1 -BB-kE-15D19 3 B!l Radiation Elemt. Re ac tor 1 20 Ye s No 1 -BB-RE-16D19 3 107 Radiation Elemt. MORI Bil Reactor 120 Yes No 107 N001 1 R E- 21 D19 ) Bl ! Radiation Elemt. Reactor 120 Yes No 107 M001 1 -BB-RE-22DI S 3 Bi l Radiation Elemt. Reactor - 120 Yes No 107 Amendment 13 Revision 3-e
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BLDG. ELEV. NOTE (1) NOTE 12) EESS REF. NO.. 80001 1 -BB-RE- 2 3DI 9 3 M001 1 -BB-R E-24 D19 3 81 1 Rad!ation Elemt. Re ac tor 120 yes No B11 Radiation Elemt. Reactor. 120 107 M004 1-BB-RE-25Dl93 B11 Yes No 107 McIl 1 RE-26019 3 Radiation Elemt. keactor 120 Yes No Is!! Radiation Elemt. Reac tor . 120 101 M011 1 -BB-RE-27D19 3 811 Yes No 107 M001 1-BB-RE-31D193 Radiation Elemt. Reactor 120 Yes No 81 1 Radiation Elemt. 107 M0il 1 -BB-RE- 3 2Dl 9 3 14eac to r 120 Yes No 107 18071 1-BB-RE-33Dl93 B!l Radiation Elemt. Reactor 120 Yes Bi l Radiation Elemt. No 107 M005 1 -BB-RE- 34 Dl 9 3 B11 Reactor 120 Yes No 107 M011 1-BB-PE-35D193 Radiation Elemt. Reactor. 120 Yes N> Bl! Radiation Elemt. Reactor 107 N021 1-88-RE-36D193 1 20 Yes No ' Hl l Radiation Elemt. Reactor' 120 107 M0:1 1-BB-RE-37Dl93 Bl ! Yes No 107 MOSI l-BB-RE-41Dl93 Radiation Elemt. Reactor 120 Yes Bi l . Radiation Elemt. Re ac tor 120 No 107 M011 1 -BB-RE-4 2D19 3 Yes No 107 M011 Bil Radiation Elemt. Reactor 120 Yes 1-BB-RE-43D193 Bi l Radiation Elemt. No 107 Moll 1 -BB-RE-4 4 D19 3 Bll Radiat ion Elemt. Reactor 1 20 Yes No 107 MODI l -BB-RE-4 5Dl 9 3 Reactor 120 Yes No 107 M001 1-BB-RE-46D193 Bl! Radiation Elemt. Re actor 120 Yes No Bi l Radiation Elemt. 107 se00i 1 -BB-RE-4 7D19 3 Reactor- 124 . Yes No 107 80001 1-BB-RE-51D193 Bt! Radiation Elemt. Reactor 12J Yes No B11 Radiation Elemt. Reactor 107 M011 1-BB-RE-52D193 120 Yes No 107 MOO! l-BB-RE-53Dl93 B11 Radiation Elemt. Re ac tor 120 Yes No Bil Radiation.Elent. 107 00001 1 -BB-RE-66Dl 9 3 811 Reactor 120 Yes No 107 54021 1-BB-RE-72Dl93 Radiation Elemt. Reactor 120 Yes No B11 Radiation Elemt. 107 se0 El 1-BB-RE-7 3Dl 9 3 Reactor 120 Yes No 107 Moll 1-8B-RE-74D193 Bi l Radiation Elemt. Reactor 1 20 Yes No Bll Radiation Elemt. R* actor 107 10001 1-88-RE-75D193 B11 120 Yes No 107 J 3010 1-BB-LT-3622A Radiation Elemt. keactor 1 20 Yes No 107 J 30lO l-88-8.T- 36 228 . Imvel Transmitter Reactor 77 Ye s No Level Transmitter 28 Reactor 77 Ye s No 28 Amendment 13 Reession 3
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, EQUI PNENT SELECTED FOR HARSH ENVIRONMENT QUALIFICAYION P6 t D
-SYSTEN:- NUCLEAA bolLER VESSEL INSTRU N-42-1.
i BB I D NO. PAN TN! ACTION P.O. Neo ( 5) LOCATEON EQUIP. PLAN EQUIr. MPL NO. COMPOWENT .. Bf,tC. E I.E V. NOTE ( 1 ) NOTE ( 2) EESS REF. NO. J 3010 1-pse-LT- 364 2A J30lO Level Transmitter .* Reactor 77 No . l -BB-LT- 360 28 Level Transmitter peactor Yes 28 33010 1 -se-LT- 36 e 3A 77 No Ye s . 28 level Transmitter Reactor 77 J30lO l-as-LT-3603a level Transmitter
- No Yes 28 J3010 1 -se-PT- 368 4A Reactor 77 ' No Yes Pressure Transmitter 28 J30lO l-MB-PT-36848 Reactor 77 Yes- No 28 J30lO Pressure Transmitter peactor 17 Yes No l -GS-PT- 4 960A 2 Pressure Transmitter 28 J30lO l-GS-PT-49 60A3 - Reactor 162 Ye s Ye s - 28 J3010 1 -GS-PT-49 608 2 Pressure Transmitter teactor 162 Yes No: 29 I Pressure Transmitter Reactor. 162 Yes J 30l O l-88-PT-78 5 3A Pressure Transmitter Reactor 77 Ye s 28 J 30lO l-be-PT-78530 No No 28 J 30l O l-ha-L T-78 54 Pressure Trans.eitter' Reactor 77 No ho 28 Level Transmitter haactor .17 No se001 No Tag No. B11 -D19 2 Yes 28 Ie001 Mo Tag No.
Connector - SRN/lRN Reactor No No 811-D194 Connector- PRD DET 15 3A Reactor No No 151 4 Amendment 13 Revision 3 l 4 4 4 q
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- N001 1 FT-N014A 831 Flow Trans. Reactor 77 N021 1-us-FT-N014e 831 Flow Trans. Yes No - 155 N001 1-88-FT-N014C h31 heactor 77. No No NOSI l-58-FT-N014D Flow Trans. Reactor 77 No ISS _
831 Flow Trans. No 155 Not! l -St-FT-N0 24A Reactor 17' - No No B31 Flow Trans. Neactor 77 155 , NO21 1-DB-FT-N0248 Yes No Flow Trans. B31 15% N004 1 -BR-FT-N0 24C Heactor 77 No No - NO31 B31 Flow Trans. heactor 17 No 155 $ 1 -ht-FT-N0 24 D h31 Flow Trans. No ' 155 ' P 333A0 1-ar-NV-38004 Reactor 17- No No P333A0 1-DF-2S-38004 Control. Valve peactor 77 No 155 Limit Switch No I 39 P 30 3AO I-be-NV-38008 Reactor 77 Yes No Control Valve 1 39 Pau)AQ 1-br-IS-38006 Itoac tor 77 No No 1 39 Limit Switch Reac tor 77 JSSIO l-BN-SV-4310 Solenoid Valve. Yes No 139 . J10 30 1-ha-2S-4 310 heactor 12% No No Position Switch peactor. 46 J1030 1-BB-SV-43tl solenold Valve 1 21 Yes No - 46 J6030 peactor 145' 1-8a-2S-4341 Position Switch No No 46 peactor - 145 Yes No 46 Amendment t3' Revision 3 l t l i 1
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.. P. O . NOTE (51 LOCATION EOul P. PLAN Foul P.
, NPL NO. CoseIOc4ENT ' Bl.11G. EI.EV. N(YrE (I) NOTE ( 2) EESS REF. No.
' P3020 1-BG-HV-F001 Contr. Valve P3020 1-mC-zs-r001 Reactor 145 No . No 1 32 Linkt Switch Reactor 145 Yes P3020 1 -IIG-HV-F004 Contr. Valve No 132 P3020' l-hG-IS-F004 Reactor 145 No No 1 32 -
Linkt Switch Reactor 145 Ye s P3030 1-BG-HV-F034 Contr. Valwm No' 132
- P3020 - 1-BG-IS-F034 Limit Switch Reactor . Il 'No No 1 32 P 3030 P*pG-HV-F035 Reactor 77 No ' No . 132 Contr. Valve Reactor 77 No P3020 1-BG-28-F035 Limit switch No 1 32 i- P3020 1 -AE-HV-F0 39 Reactor 77 No No Contr. Valve 132 P302Q 1-AE-28-F039 Reactor 102 No No 1 32 Llatt Swltch Reactor 102 Yes N001 1-BG-fT-N012A G33 . Flow Trans. No 432 j #0001 1-DG-FT-N012D Reactor 77 No W G33 Flow Trans. Reactor 102 l55 i
N001 1 -leg-FT-NO 36A G33 No No - 155' Plow Trans. Reactor ; 77 No se021 1 -bG-F T-NO 36 D G33 Flow Trans. No 155 . i 80001 1 -6G-FT-N0 41 A Reactor 77 No No 155 G33 Flow Trans. Reactor' 102 No j te005 1-bG-FT-N041D G33 Flow Trans. No 155 Reactor 102 No No 155 Amendment I3-Revision 3
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! ~ EQUI PMENT. SELECTED FOR HARSH ENVIRONMENT QUALI FICATION -~ P61 D N-45-1 (f SYSTENs CLEAN-UP FI LTER/ DEN (NERALI 2ER - oc - . PAN- TNI ACTION 1 D NO. LOCAT!ON' ,. P.O. NOTE (5) EQOf P. PLAN EQUIP. NPL No. COM M)NENT BLDG. ' El.EV. NOTE (I) i . NOTE (2) EESS REF. DH). ]. P30 )AQ . ~ 1 -IIG-HV- 39 00 Contr. valve Reactor. I 32 j; No' No - 1 39-P30 3AQ , I-IsG-3S-39s0' Limit switch Reactor 132 No No r
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. TAFLE . 3.11-5 .Page 41 ~ of/120 4' EOuligeENT SELECTED FOR HARSH ENVI RONMENT QUALI FICATION. ,
' P61 D SYSTENs CONTROL DOD DRIVE HYD-PART 9 M-47-5
'Isr I D NO. .
'PAM TML ACTI*'*S i P.O. esOTE (5)' NPL NO.
LOCATItW EQtfi P. PLAN Er ,p, COfelViefENT HLDG. ELEV. NOTE ii) NOTE (J) EESS Hrp. MO. se001 ' l -8F-LS-N 013D Cll Le ts! ' Swi tch } sepel 1-BF-LS-N013E Cl l Reactor 102 . Mo .No NOSI IAvel Switch heactor 102 I SI y
' l -bF-LS-NO R 3F. . ' Cil Level Switch No No 151 4
NO31 1-tr-LS-N013G- . Cll Imvel switch feeactor - 102- N No - 15% ' 80031 1-sF-LS-N013H Cil Heactor lu2 .No No Level Switch Reactor 102 111 ' 8e001 1 -Isr-SV-I t ? . Cll- Solenoid Valve, No No ilI Reactor 102' No' N 4 122 Typical of 185 Solenoid Valves"
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' P3110 1 -DIPH V-F010 Yes No I 32 '
Control valve Reactor 54 No No P3010 4-B WIS-F010' Limit Switch Reactor 54 126 P3020 l -BD-HV-F012 No No . 126 Control valve Reactor 54 No P3320 1-StP2S-F012 Limit Switch No 1 33'
-P3020 Reactor 54 No No 1 -WD-HV-F013 control Valve Reac tor 1 33 P3320 1 -S D F013 102 No No 133 Limit Switch Reactor 102 J6030t 1 -B D-SV-F019 Solenotd Valve Reactor 77 '
Ye s No 533 JL830 1 -BD-2 S-F019 No No 47 Position Switch Reactor 77- Yes P3220 1 -BD-H V-F0 2 2 Control Valve- 'No 47 P3320 'l-b>2S-F022 Re actor 77 No No 133 Limit Switch Reactor 77 No i P)33AQ I-FC-SV-F025 No 133 Solenoid Valve keactor 54 ' No No I40 tv Ame nilme n t 13 Revision 3i x ._ - a- , , - - - , , , ..c , .-,
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- f.- - EQUll9eENT SELECTED FOR HARSH ENVIRONMENT QUALI FICATION .
ej. . P6 t D SisTENs REACTOR COPE ISOL COOL. M-49-1 '
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I D NO. , PAN TNI ACTI ON P.O. ' LOCATION EOutP. Pt.AN EQUIP. NOTE ( 5) NPl. NO. COM PONENT , HLOG. El.EV. NOTE (l) NOTH ( 2) EESS RFF.' NO. P30 3AO ' 1-FC-38-F025' ' Position Switch Reactor 154 P333AO ! <C-SV-F0 26 - No No ' Solenoid Valve Reactor .51, No - 141 P303AQ 1-PC-IS*F026 Position Switch Re ac t or No 140' P3080' l 8D-HV-F031 54: No No <- 141J l 1 Control Velve ' Reactor 54 No , , P3110 8-ht> 35-F031 Limit Switch Reactor 54 No ' 526 JL810 1-FC-SV-t054' Solenoid Valve Reactor 54-Yes ~ No ' 126 JtolO l-FC-IS-F054 No No; 44 .
' Position Switch . Reactor 54 No No P30lO - .1-FC*HV*F059 Control Valve Reactor 17~
45 P30lO l -FC-IS-F0 59 No No 126 ' Limit Switch-
- Reactor 77 P333AO I-FC-NV-Fu60 Yes no 126 ,
P333AO l-FC-IS-F060 Control Valve. Reactor 54 No No 1 38 Limit Switch ~ koactor 54 Yes P3210 1-FC-HV-F062 No I 18 Contro! Valve Reactor 54 No
- P3010 1-FC-IS-F062 Limit switch Reactor 54 No 7- 127 P303A) 1-FC-HV-F076 Yes No-I 27 Control Valve Reactor 100 No I P 333AQ 1-FC-3S-F076 No 1 19 Limit Switch- - Reactor .100 Yes, No P3210 1-FC-HV-F084 , Control Valve 1 39 1
P32iG .4-PC-38-F084 mactor 77 No4 No 127 ' Limit Switch - Reactor 77 -Yes NOM l-PC-FT-N00 3 E51 ' Flow Trans No. 127 pe0erl Reactor 54 Yes' - 155 , 1 -FC-PT-N007 E51 Press. Trans Reactor . 54 , No No ' peUSl . I-FC-LSH-N010 E51 lave! Switch High No 106 Reactor 54, No No N0 98 1 -bD- PT=N0 50 ES!. 1 Press. Trans Reactor 54 ' I50 M0ut I -b D-FT-N0 51 - - No . No 155 t ESI Flow Trans - Reactor 54 ' No , No M001 1 -FC-PDT-N0 57 B E5I Press. Diff. Trans' 155 ' Reactor 77 No No .155 - " N021 1-FC-PDT-N057D ESI Press. Diff. Trans Reactor . 77 y No No 155 , _ Amendment 13 Revision 3 i 6 4 4
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- EQUI PMENT SEIECTED FOR HAMSH ENVIRONMENT QUALI FICATION . ' P61 D '
SYSTEMS REACTOR CORE ISOL Coot., - M-49-4 i
.WD E D NO. PAN TMI ACTION P.O. LOCATit*l asofE (5) MPL No. COMPONENT HLDG.
' EOH L P. . PLAN EOutP.
E l.E V. N(YTE (1 ) ' NOTE ( 2) EESS REr, No. NC U) 1 -FC-PT-N0 583 E51 Press. Trans 80001 I-FC-PT-NOSSD Reactor . 7 7. . No ' No '1%S' se001 E51 Press. Trans. Reactor 77 No <. 1 -FC-PT-N058F E51 . Press. Trans No 155 I pe0'J1 I-FC-PT-NOSSN- E51 Reactor 77 No No 15% Press. Trans. leeactor 77 J 30lO l -st> PT- 4157 Press. Trai.s. penetor No ~ No !$$ J 30l O l-FC-FT-4158 54 No No 6
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. EQUll9eENT SELECTED FON *tARSH ENVI RONMENT QUALI FICATION . P6 t D :
SYSTEM: NCI C PUMP TURBINE ' FC IDNO. . PAN TMS, ACTION P.O. IIOTE (5) LOCATION EOHIP., PLAN equip. MPL NO. COM PONENT . 19 L14. El.E V. NOTE (1) NOTE ( 2) 'EESS REF.' NO.
- se001 to-S-212 .E51-C002 RCIC Turbice. .
M004- IO-P-219 .sE51-C002- Reactor ~54- No' 'No
. Vacuum Fump Notor les ac tor . ; 54 '157 N021 IO-P-220 E51-C002 Condensate Pump notor- h No 157 se021 10-S-221 Reactor 54 No . No E51-C002 teCIC Turbine Governor Reactor 54 I57 geG8*Q 18-P-228 Jockey Pump flotor, ECCS No - No. 157 P333AQ 1-FC-SV-F004 Re_a,ctor' 54 No No Solenoid Valve heactor. 54 80 P333AQ I-FC-IS-F004- ' Position Switch leeactor - 54 M: No- 140
'J1080 l-FC-SV-F005 No ' No 144 Solenoid Valve- Reactor 54 No.
J&S10 1-FC-IS-F005 Positton Switch No 44 PP320 1-FC-NV-F045 keactor. ' 54 No - .No Control Valve- Reactor ~ 54 . No
-45 P3020 1-FC-35-F045 Limit Switch- No' i13 P333AQ I-SD-HV-F046 Reactor- 54 No No 1 I) .
'.P303AQ 1-DO-38-F046 Control Valve- Reactor 54 No No Limit Switch seeactor I Alf feell . . 1 -BD-PT-N028 El l Press. Trans-
$4' No 'No 1 38 pe021 1 -BD-PT-It0 5 2
'E51 Reactor- 77 . No No 106-Press. Trans Reactor 77 No IcC01 1 -D 4-PT-es05 ) ESI No '155
-Press.'Trans Reactor 77
. MO2I l -FC-PT-N0 55e E51 Press. Trans No ' No 155 30011 1-FC-PT-se055D- Reactor- 77 No No 155. E51 Press. Trans 10001 1 -FC-PT-N055F Reactor 77 No- No 155 E51 Press. Trans i N001 1-FC-PT-IB055N. Iteactor 77 h No . I55
. ESI Press. Trans 80021 Reactor 77 No No L55
' 1 -FC- PT-N0 56a ~ .E51- Press. Trans peactor 54 10038 l-FC-PT-N056F E51 Press. Trans
-h No' 155 se001 1 -FC-IS-4 275 Reactor 54 h No E51-C002 Position Sw. Reactor 54 No i55
.' -80001 1-FC-PSL-4 276 : E51-C002 No 157 Press. Sw. loe Reactor 54 No No 157-1
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' i EOU!a90ENT SELECTED FOR HARSH ENVIRONNENT OUALI FICATION - P6t D -
SYSTENs RCIC PUNP TUR8INE
- j. FC PAN TNf ACTION
' I D NO. , LOCATION-P. O. 800TE 15) N PL NO. COfsPONENT ' EQUIP. PLAN EQUIP. B l.OC. ElEV. I NOTE (1)^ NOTE ( 2) EESS REF. NO. & , 88041 1 -PC-TSH- 4 27 7 '. E51-C002 Temp. Sw. High'
.' se031 1-FC-TSH-4278 Reactor . .54- No No I57, E51-C002 Temp. Sw. High Reactor 54 No
! 180E1 1 -FC-PDSH-4 279 - a;51-C302 No 157 Press, Diff..Sw. High Reactor 54 No No 80001 l-FC-SE-4289 E51-C002 Speed Elemt. Reactor 54 157 *
- 10011 l -FC-H V-4 282 E51-C002' Control Valve
' No .No - 157 !
30001 1-FC-FY-4283 Reactor 54 No N - 157- !' E51-C002 Cbnverter- . Reactor 54 No -[ 00001 1-FC-LSH-4288 - E51-C002 No 857
- Imvel bw. High Reactor 54 No i' N001 ' 300 TAG MO. E51-Cuo2 Position Switch 54, Ni > 157-Reactor No No 157
- J 30lO .. 1-Bt> PT-4303 Press. Trans. . Reactor 54 No No 29 4
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!' EQUI PMENT SELECTED FOR HARSH ENV! RONMENT OUALI FICATION - Phi D ' SYSTEM: RES!IJUAL HEAT REMOVAL SYSTEM M-51-1 BC I D NO. PAM TMI ACTION , P.O. LOCAT!ON EQUIP. PLAN EOutP. NOTE (5( M PL NO. COM PONENT HL[x;. ELEV. NOTE (l! NOTE ( 28 EESS REF. NO. M021 IA-P-202 Ell C002 RHR Pump Motor I 30001 I B-P-20 2 Reactor 54 No No I16 El! C002 RHR Pump Motor Reactor 54 N02) I C- P- 20 2 No No 116 Ell C002 RHR Punnp Motor - Reactor 54 m) MORI ! !>- P- 20 2 E!! C002 RHR Pump Motor No !!6 se0920 IC-P-228 . Reactor 54 No No
' Jockey Pump Motor, ECCS ll6 M0020 ID-P-228 Reactor 54 No No 80 Jockey Pump Motor, ECCS Reactor 54 No P3flO l-bC-HV-F003A Control Valve No 80 '
P3010 1 -bC4 5-F00 3A Beactor 54 No No 127 Limit Switch Reactor 54 No P3010 1 -BC-H V-F00 38 Control Valve No 127 P3110 1 -DC-IS-F00 38 Reactor .54 No No 127 Limit Switch Reactor 54 No P30!O l-DC-HV-F004A No 127 Control Valve Reactor- 54 No P3ito 1-BC-IS-tD04A No 1 27 Limit Switch peactor 54 Yes
-P3:40 labC-HV-F004a control Valve koactor 54 No 127 - P 3110 1-bC-25-t1043 No ' No 127 Limit Switch Reactor ~e Ye s P 3110 1-BC-HV-7004C No 127 Control valve Re ua 54 No P 3110 1-bC-IS-F004C No 127 Limit Switch Reactor. 5 Yes No P30lO l-bC-HV-F004D Control valve Reactor 54 127 P30lO l-BC-IS-t004D No No 127 Limat Switch Reactor 54 Yes No P3010- 1 -SC-H V-t'0 06A Control Valve Re hetor 127' 54 + No No P1110 1-BC-IS-F006A ' Limit Switch Reactor 54 1 27 P) lO l-SC-HV-F0068 No No 127 Control valve . keector 54 No No P30lO l-sC-2S-Fou6u Limit Switch ' Reactor 54-1 27 P3:10 I -bC-H V-F0 074 No No 127 control valve Reactor 54, No No P3It O l-bC-IS-F007A Limit Switch 127 Reactor 54 Yes P) lO l-bC-HV-F007b Control Valve. Re ac tor $4 No N0 127 P30lO .1-BC-28-r007s No 127 Limit Switch- Reactor 54 res No 1' 127 ,
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EQUI PMENT SELECTED FOR HARSH ENVlltONMENT QUALI FICAflON P61 D DYSTENs RESIDUAL HEAT REMOVAL SYSTEN 'M-St-l, WC I D NO. PAN TMI ACTI ON P.O. IAJCATI ON . EQUIP. PLAN F.OutP. NOTE (5) MPL NO. COM PONENT H LIC. E l.EV. NOTE (l) NOTE ( 2) FESS Rt:F. NO. P1110 1 *DC-HV-F014 7C Control Valve peactor
. P)18 0 - I-mC-IS-F007C 54 No No 127 Limit Switch. Reactor '54 Yes No ,
P 3080 1-RC-HV-F00?D , control Valve 'lemactor 54 t27 P3020 3 -hC-38-F008 .No No 127 Limit Switch Reactor 102 Yes No P)320 1 -DC-H V-F009 Control Valve peactor
')32 P3329 l-hC-28-F009 102 N No 1 12 Limit Switch' Reactor 102 Yes P)llO . 1-hC-MV-F010A Control Valve- Reactor 54 No 132 P3010 1-hC-35-F0 LOA No- No 127
. Limit Switch peactor 54. Yes No 127 P30lO l -DC- ' -FO R OS Control Valve' feeactor 54 P30lO l-eC- Fot om No No 127 Limit Switch leeactor 54 Yes No P 3110 4-hC-u -F0llA Control Panel 127 Iteactor 54 No No P3180 ' l-mC-IS-Foll A Limit Switch peactor 54 Yes 1 27 P3010 I-SC-NV-F0lls No 127' Control Valve peactor 54 No No P30lO l-hC-IS-F0llt Limit Switch 127 teactor 54 Ves No - 127 P 3020 1-DC-HV-F015A' control Valve peactor' 102 P 3020 1-hC-3S-F015A No ' No -112
. Limit Switch Reactor 102 Yes No 132
.P3020 1 -hC-N V-F015m Control Valve peactor. 102 No "P)120 1-DC-35-F015e No 132 Limit Switch heactor 102- Yes No P 304 0 . 1-bC-HV-F0164 Control valve peactor 102 No
.I12-P3110 1-mC-IS-F0164' No 127 Limit Switch - Reactor 102 Yes No P)TIO l-DC-HV-F016e control Valve 127 lee ac tor 132 No No
'P)olg I-DC-2S-F016e Limit Switch Reactor 132 1 27 Yes No 127 P3020 ' I-DC-HV-F017A . Control Valve peactor 102 No P):20 1-bC-IS-F017A. No i12 Limit Switch Reactor 102 Yes No P3020 - 1-hC-NV-F0178 Control Valve 1 12 Reactor 102 No No 1 32 P)E20 1-bC-IS-F017B Limit Switch' meactor 102 P3220. 1-pC-HV-F017C Yes No 132 Control Valve - leeactor 102 No No 1 12 Amendment !)
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HCGS FSAR ' TAHLE 3.11-5 Page 50 of 120'.
. EQUI PMENT SELECTED FOR HARSH ENVI RONNENT OHALI FICATION P6 t D
' SYSTEM: RESIDUAL HEAT REMOVAL SYS*EM M-51-1
' WC .
I D No. PAM TM1 ACTION P.O. sNyrE (5) LOCATION EOut P. Pt. Alt EQUI P. nPL No. - Con FsweENT B LIC. ELEV. NOTE ( 1 ) NOTE ( 2) EESS REF. NO. P3020 l -BC-IS- F017C .Linnt Switch P3020 1-hC-HV-F017D Reactor 102 Yes No 132 Control Valve Rcactor 102 No F3020 1-bC-IS-F017D Limit Switch No ! 12 P3110 1-SC-Hd-F021A Reactor 102 Ye s No 1 12 Control Valve Reactor - 102 No P30lO l-pC-IS-F0 2t A Limit Switch No 127 P3010 1-8C-HV-F02tB Reactor. 102 Yes No 1 27 Control Valve Reactor 132 No P 30lO l-mC-2S-F02tu Limit Switch Reactor 1 32 No' 127 P3320 1-SC-HV-F022 Yes No 1 27 Control valve Reactor 145 No P3220 'l-bC-2S-F022 Limit Switch Reactor 145 No . L32 P3320 1-DC-HV-F023 Yes No , 1 32 Control valve Reactor 145 . No P 3029 l-pC-IS-F023 Limit Switch No -l12 P3110 1-bC-HV-F024A Reactor 145 Yes No 1 12 Control valve Reactor 54 P3!!O t -mC-IS- F0 24A Limit Switch No No 127 P3140 1-bC-HV-5024h Reactor 54 Yes No Control Valve Reactor 127 P 30lO ' l -IsC-IS- F0 248 54 No No - 127-Limit Switch Reactor 54 P3110 1-SC-HV-F0264 Control Valve Yes No 127 P3110 1 -aC-Is-F0 26A - Limit Switch ' Reactor ~ 54 No No $27 P11t o I-hC-HV-F0268 Reactor 54 No No' 127
' Control valve Reactor 54 P3110 - 1 - DC-IS-F0 268 Limit Switch ' No No 127 P3110 Reactor 54 No No 1-hC-HV-F027A Control Valve 127 P3040 1-BC-IS-F027A Reactor 77 No No 127 Limit Switch Reactor 77 P30lO l-HC-HV-F027H Yes No 127 Control valve Reactor 77 P3010 1-BC-2S-F0273 Limit Switch No . No a27 P31tQ 1-hC-HV-F040 Reactor 77 Yes No 1 27 Control Valve. Reac tor 77 No.
P3210 ~ 1 -aC-IS- F0 4 0 No 127 Limit Switch Reactor 77 No P3it Q I-BC-HV-F04 7A Control Valve No 127 P3110 1-sC-IS-F047A Reactor 77 No No 127 Limit Switch Reactor 77 No No P3090 1-bC-HV-F047tl Control Valse 1 27
- Reactor 77 No No 127 Amendment 13 Hevision 3 a
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i. HCGS FSAR TAHLE 3.11-5. pag, , 5 g; og 3 20 EQUI PNENT SELECTED FOR HARSH ENVIRONNENT QUALIFICAt!ON P6 t D SY3 TENS RESIDUAL HEAT RENOVAL SYSTEN N-51-1 BC
. I D NO. -
PAN TNI ?CTION P. O. NOTE (5) IDCATION EQUIP. PLAN EQUI P. NPL NO. CONPONENT Hl.14. El EV. NOTE (I) NOTE ( 21 FESS REF. NO. P3310 ' l -SC-2 S- F0 4 7ts Limit Switen JM50 1-bC-HV-F048A Rem <. toa 77 No No Control Valve 1 27 J1450 1-BC-2S-F0488 Reactor 77 No No 49 Limit Switch keactor 77 No J6350 1 -bC-HV-F04 88 Control Valve No 49 J1050 1-bC-2S-F0488 Reactor ~ 77 No No '49 Limit Switch Reactor 77 No P3110 1-bC-HV-F049 Control valve No 49 . P3*lO l-BC-2s-F049 Reactor 77. No Nu 127 Limit Switch Reactor 77 No P3220 1-bC-HV-F052A Control Valve No 1 27 P3020 1 -bC-IS-F0 5 24 . Reactor 77 No No. Limit Switch I32 P3320 1-HC-HV-F0528 Reactor 77 No No Control Valwe 1 32 P3320 1-bC-IS-F0528 Reactor 77 No No Limit Switch 1 32 P3020 1 - BC-2 5-F06 0A Reactor 77' No No 1 32 P3020
. Position Sw. Reactor 100 No 1-EC-2S-F060s' Posit ion Sw. Re ac tor No 13(
P3320 1-bC-IS-F065A 100 No No P3320 Position Sw. Reactor ll2 No 1 14 1-BC-IS-F0654 Positton Sw. No 1 14 P3320 1-sc-IS-F065C Reactor. 100 No No 1 14 Position Sw. Reactor 100 No P3320 1 -BC-IS-FU 6 5D Position Sw. No 1 34 . P3110 1-bC-HV-F075 Reactor 100 No No 1 34 Control Valve- Reactor ll , No P3010 1-8C-IS-F075 ' Limit Switch No 127 P3020 1-bC-25-F077' Reactor 77 No No 127 losition Sw. Reactor 102 No J1030 1-BC-SV-F0798 Solenoid Valve No 1 34 J6330 1-HC-SV-F080A Re ac t or 77 No No Solenoid Valve 46 J6030 1-SC-SV-F0808 Reactor 54 No No 46 Solenoid Valve Reactor 77 No P 30 3AQ 1-bC-SV-Fl22A Solenoid Valve No 46 P 30 3AQ l abC-IS-Fl 22A Reactor 100 No No 140 1-HC-SV-F122B Position Switch Reactor 100 Yes P 333AQ Solenoid Valve Reactor 100 No ~ l41 P333AQ 1-bC-28-F1228 No No 140 Position Switch koactor 100 Yes No P333AQ 1-bC-SV-Fl46A Solenoid Valve Reactor 100 14l No No I40 Amenihnen t 13 Revision 3 4
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u 1. HCGS FSAR TABLE - 3.!!-5 Page 52 of' 5 20 - EOUI PMENT SELECTED FOR HARSH ENV!RONMENT OUALI FICATION - ~ Phi 0 . SYSTENs RESIDUA 1. HEAT REMOVAL SYSTEM - M-St -l BC . I D NO. PAM TMI' ACTION 1.OCATI UN ' EQUIP. P.O. NOTE (5) NPL No. COMPONENT B LIM;. PLAN EQUIP. E I.E V. NOTR (l) NOTE ( 2) EESS HFF. NO. P32140 1-BC-2S-F146A Positlon Switch P333AQ 'l-BC-SV-F146B Reactor . 100 Yes- No I 4)' Solenoid Valve Reactor -100 - No P303A0 1-BC-2S-F1468. . Position Switch Reactor 100 No - 140 P33 3A0 1 -BC-SV-F14 6C Solenoid Valve 'Yes? No 145 P 30 3AO l-BC-2S-Fi46C . Reactor 100 No No 'l40 Positton Switch Reactor 100 Yes P 333AQ 1 -BC-SV-F14 6 D Solettoid Valve - No -1 41 P 303AO 1-SC-IS-F146D peactor 100 -No No -
' Position Switch . Reactor 100 Ye s ' . No 140:
M0!! 1-BC-FT-N013 Ell ' Flow Transmitter 141 MOI! ~ l -BC-FT-N015A - Reactor 102 No No: 406l El1- Flow Transmitter , Reactor 77 Yes M001 1-BC-FT-N0158 Ell Flow Transmitter No . 155' N001 1-SC-PT-N015C Reactor 77 Yes , W 155 N021 Ell Flow Transmitter Re ac tor 54 Yes 1-BC-F1-N015D Ell Flow Transeltter No 155 N001 1-BC-PT-N052A peactor 54 . Yes No El1 Flow Transeltter Reactor 77 I55' M011 1-BC-FT-N052B No No I55 u M001 E!! Flow Transmit ter . Reactor 77 No No 1-BC-FT-N052C Ell Flow Transmitter 155 M021 1-BC-FT-N052D kvactor 54 No No 155 Ein Flow Transmitter Reactor- 54 M021- 1 -BC-PT-N0 5 3A El1 . No ' No 155 Press. Trans koactor 54 No M001 1-BC-PT-N0538- Ell- Press. Trans - No 106 N001 1 -BC-PT-N0 5 3C ' El l Reactor 54 No No 106 Press. Trans' Reactor 54 No MOI! l-BC-PT-N053D Ell Press. Trans- No 106 M0 El 1-BC-PT-N0550 ^ E!! 1 Reactor 54 No No 106 Press..Trans . Re ac tor '54 No M001 1-BC-PT-N055D No I55 M001 Eli Press. Trans- - Reactor 54 No No 1 -BC- PT-N0 55F E!! Press. Trans 155 N001 1-BC-PT-N055H E!! Reactor 54 No No . I55 Press. Trans. Reactor 54' No M001 1 -BC-PT-N 0 568 El l Press..Trans No .455
- M0 21 1-BC-PT-N056D Reactor 54 -No No 155 >
El 1 Press. Trans Reactor '54 No MO DI l-BC-PT-N056F El1 Press. Trans No I55 Reactor 54 No No' 155 J d Ame nelme n t !) Revision 3 }
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- TABLE ' 3.11-5 ;
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~ EOut PNENT SELECTED FOR HARSH ENVIRONMENT OUALIFI' CATION P61 D
, M-51-1
_ SYSTEM: ' RESIDUAL HEAT REMOVAL SYSTEM ' HC, PAM - TNI ACTION; I D NO. . LOCATION . EQUIP. .. . PLAN EQUIP. NOTF'(5)- P.O.' M PL NO. COMPONENT BLDG. ELEV. NOTE (Il-- NOTE ( 2) EESS REF. NO. M0!! ~1-BC-PT-N056H Ell' - Press. Trans . Reac tor 54s No .No i155 M031 '1-BC-PT-N057 Ell Press. Trans. Reactor .. ' 77 .No No 106 M011' 1-BC-PDT-N058A ' Ell Press. Diff.'Trans. Reactor No No M001
.155 1-BC-PDT-N058B Ell. Press. Diff. Trans. Reactor' 77 No No ' 155 -
~ MO 1 . 1-BC-PDT-N058C- El1 Press. Diff. Trans. Reactor, 77- No No
;155 -
M031 1-BC-PDT-N058D El i Press. Diff. Trans. Reactor 77" No. No' .155'- M001 1 -BC-PDT-N 0 6 0A . Ell Press. Diff. Trans. 77 . No - M001 1-BC-PDT-N060B'
. Reactor No 106- 7 -
Ell Press. Diff. Trans. Reactor. ' 7 7. No No 106, lattr 1 -BC-TE-N0 2 7A Temp. Elemt. Reactor 77 Yes No later-
.1 star , 1-BC-TE-N027B Temp.'Elemt. Reactor 77 Yes No later J5560 1-BC-TE-440! Temp. Elemt. . Reactor 77 No . No 43 P3110 1-BC-HV-4420A Control Valve Reactor' 77 - No iNo 127 P3%IO l-BC-2S-44 20A . . Limit Switch ' Reactor11 Yes No 127 3
P3710 1-BC-HV-4420B Control Valve Reactor. 77 No No' '127. 1-BC-ZS-4420B P 3110 - Limit Switch Reactor 77' .Yes No' 127 P3110 1-BC-HV-4421. Control. Valve Reactor 77 .No No 127 P3 !O l-BC-ZS-4421 Limit. Switch Re ac tor '77 Yes No 1 27 P30 3AO l-BC-HV-4428 Cbntrol Valve Reactor '77 .. No No 139 P333AO l-9C-2S-4428 Limit Switch' Reactor '77 No - No 1 39 J30lO l-BC-FT-4435 . Flow Trans. Reactor '17 No -No 29 P30lO 1-BC-HV-4439 Control Valve Reactor 77 No No 127 P3010 1-BC-2s-4439 Limit switch -Reactor 77 No No 127 J 30lO _l-BC-FT-4461A Flow Trans. . Reactor 77 Ye s No 29 J 30lO l-BC-FT-4461B , Flow Trans. Reactor 77 Yes No 29
^ J 30!O l-BC-FT-4462A Flow Trans. . Reactor 102 Yes No 29 l J30lO 'l-BC-FT-4462B Flow Trans. Reactor 77 Yes No 29 ..
Amendment 13. Revision 3. t
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TABLE 3.11-5
, 'Page'54 ok 20
.EOUI PMENT SELECTED FOR HARSH ENVIRONNENT OUALIFICATION ' ' PE E D SYSTE;:s CORE SPRAY "
- BE -
1 D NO. ,~ PAN 1 - 'TN1 ACT!OM-
~P.O. NOTE (5) LOCATION. , EOU1 P. PLAN EOUIP.
NPL NO. COMPONENT. RLDG, ELEV. NOTE (1) NOTE ( 2) EESS'RFF.'NO. P3220. _.1-BE-28-F0048 P3020
-- Limi t Swi tch ' Reactor .102- .
BE-HV-Fe05A. - Cont r. Valve :
.No - No 132' P3020. 1-BE-2S-F005A Reactor -102 No , No . 132
- Limit Switch -Reactor 102 P 3220 . 1-HE-hV-FCG58- Contr. Valve - Yes ' No . , - 132:
P3020. l - BE- 2 8- F0 0 58 ' Beactor-~ 102 No No . P30201 Limit. Switch Reactor 102 i
.. Ye s ! No
, 132 1 -B E-2 S-r007 A Positicn Switch 1 32.:
P3020 ,1 - BE- Z S- F0 0 7B Reactor- 100 , No . No .- ,134
- P30lO l-RE-HV-F0154 Position SwitchT ~. Re ac tor ., 100 'No'
. Cont r. valve . ' No . 134-P30lO l-RE-2S-F015A Reactor . 7 7 .'. .No . .No.
Limit Switch ~ , 127 P30l O : 1 -H E-HV- F015B ' meactor i 77 = /. Yes No 127 P30lO Conte. Valve Reactor 77 l-BE-28-F015B
. Limit Switch ' . No . No 127. ~ P30lO ' l-B E-HV-F0 314 . Reactor - '77- .Yes .No 127.
Contr. Valve Reactor' : 54 No P30lO ? ^ l-BE-ZS-F0 31 A Limit Switch No* 127 ' P3110 . 1 -B E-HV-FO!! R Reactor 54 Yesl No 1 27
.Contr. Valve : Reactor. . 54 No
_. P30lO l-BE-2S-F0lls- Limit switch ' No '- - . 127 P303AO l-BE-SV-F039A Reactor -54 Ye s - No 127 Solenoid Valve ,peactor. .100 No No -' .140
' Amendment 13 Revision 3 4
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. EQUI PMENT SELECTED FON H ANSH ENVI NONMENT QUALI FICATION '
P6 I D ' .I
. S YSTEM: _ CORE SPRAY . .
M-52-1. l BE 10 NO. -PAM TM1 ACTION P.O. NOTE (5) LOCATION EQUIP. M PL NO. COM PONEhT Bl.lC . PLAh EOutP." ElEV. NOTE (1) NOTE ( 2) 6:ESS der gen. j P301AO I -bE- 35-F0 39A .. E21 )- P30 3AQ 1-SE-SV-F0398 Position Switch [ Reactor _100 Ye s ~No i P303AQ 1 -bE- 3S-r0 398
'.Solarioid valve Reactor.' 100 No I 41
! .M001 1 -BE-FT-M00 3A Limit Switch keector- ,400 Yes
.No
' No
.140 i
i M001 4 -BE-PT-M00 38 E21 Flow Trans. .heactor 54 - Yes Iel
- E21 -Flow Trans. No 155 Reactor 54 Yes ' No
? 155 I i i ) j
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_1 m e 1 HCGS FSAR Page 56 of 1 20 TABLE 3.11-5 Epul PMENT SELECTED FOR H ARSH ENVI RONMENT OU ALI FICATION P61D M-52-1 SYSTEM: COME SPRAY BE PAM TMI ACTION I D NO. LOCAT)ON EQUIP. PLAN EQUIP. P.O. NOTE (5) M PL NO. COM PONENT BLDG. ELEV. NOTE (1) NOTE (2) EESS REF. NO. M001 1-nE-f T-N051 A E21 Flow Trans. Reactor 54 No No 155 MODI l-BE-FT-NP5 t h E21 Flow Trans. Reactor 54 No No 155 M001 1 -RE- PT-N 0 5 4 A E21 Press Trans. Re ac tor 54 No No 155 M001 1-HE-PT-N054H E21 Press Trans. Reactor 54 No No 155 M001 1 -BE- PT-N 0 55B E21 Press. Trans. Reactor 54 No No 155 M001 1-HE-PT-N055D E21 Press. Trans. Reactor 54 No No 155 M004 1-BE-PT-N055F E21 Press. Trans. Reactor 54 No No 155 M001 1-BE-PT-N055H E21 Press. Trans. Reactor 54 No No 155 M001 1 - RE- PDT-N 0 5 6 E21 Press. Diff. Trans. Reactor 77 No No 155 Amendment 13 Revision 3
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i 4. HCGS PSAR TABLE 3.!!-5 pag, g7 og g 2p e EQUI PNENT SELECTED FOR HARSH ENVIRONNENT QUALI FICAFION ' P61 D i SifSTE2 s FUEL POOL COOLING 6 TORUS WTR CLEANUP N- 5 3-1 3 EC
- I D NO. PAN TN! ACTION i LOCATION EQUIP. Pl.AN EOUTP.
j P.O. lHyrE - ( 5) NPL NO. COM PONEN T HIJC. EL EV.' NOTE (1) NOTE ( 2) FESS REF. NO. N002Q I A-P-211 Pump Notor, Fuel Pool ' Cooling - Reactor - 162 No NU920 I B-P-211 No 90 Pt.mp Notor. Fuel Pool Cooling F4eactor 162- No No 30
- J30lO l-EC-FT-4649A Flow Transmitter Re ac tor 162 No No J 3310 1-EC-FT-46499 29
- Flow Transmitter Reactor 162 No No 29 P 3210 1-EE-HV-4652 Control valve Reactor 54 No No P3110 1-EE-2S-4652 127 Limit Switch Reac tor 54 Yes No 127 P3010 1-EE-SV-4655 Solenoid Valve Heactor 54 No No P3310 1-EE-2S-4655 1 24 Position Switch Heactor 54 No No 125 P3fl0 1 -E E-SV-4 6 56 Solenoid valve Heactor 54 No No 1 24 i P3210 1-EE-IS-4656 Position Switch Reactor 54 No J30'Js 1-EC-LT-4661A mi 125 i Level Transmitter Reactor 162 No No . 29 J3010 1-EC-LT-46618 Level Transmitter Reactor 162 No
, P3110 1-EE-SV-4463 En '29 Solenold Valve Reactor 77 No No ' 1 24 P3%IO l-EE-2S-4663 Position Switch l 3 Reactor 77 No No 125 J 3010 1-EC-PT-4669A Pressure Transmitter Reac t cr 162 No No J 3 *10 1-EC-PT-4669B 49
- Pressure Transmitter Reactor. 162 m) No 29 '
Amendment 13 Revision 3 L ] 1
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HCGS FSAR TABLt; 3.11-5 Phe 58'. of I 20 EOut PNENT SELECTED FOR HANSH ENVE RONMENT OUALIFICATlUN PhlD .
SYSTENs FUEL POOL COOLING 6 TORUS NTR CLEANUP .N-53-1 EC I D NO. PAM . .TN! ACTION. LOCATION 0001P. . PLAN f: QUIP. P.O. NOTE (5) NPL NO. COM PONENT R LIC. ELEV.
- NOTE (1) NOTE ( 2) FESS WEF. NO.
P30lO l-EC-SV-4676A Solenoid valve Reactor 77 No P3210 1-EC-IS-4676A N 124 - Position Switch Reactor 77 No No P 30lO . 1-EC-SV-46768 Solenoid Valve 125 Reactor 17 No No 124 P3210 1-EC-2S-46768 Position Switch Reactor 77 No-P30lO l-EC-SV-4678 No 125 Solenoid valve ' Reactor 77 No - No . 424 P3!!O l-EC-2S-4678 Position Switch Reactor 77 h P3110 1-EE-HV-4679 No 125 Control Valve Reactor 54 No No P3ILO l-EE-2S-4679 Limit. Switch 427 Reactor *24 Yes No .427 P3110 1-EE-HV-4680 Control valve Reactor 54 No No 1 27 P3110 1-EE-2S-4680 Limit Switch Reactor 54 Yes P30lO l-EE-HV-4681 . No 127 Control valve Reactor .54 No No 127 P3110 1-EE-IS-4681 Limit Switch Reactor 54 Yes' J5560 1-EC-TE-4683 Temp. Elemt. 14 0 127
. Re actor 162 ' No .No 43 P30lO l-EC-HV-4689A Control Valve .. Reac tor 162 No P3730 1-EC-3S-4689A No 427 Limit Switch Reactor 162 .No. Dks 127 P30lO l-EC-HV-46898 Control Valve Reactor 162 No No 127 P3180 ~1-EC-IS-4689s Limit Switch Re ac tor 162 No No 127 Amendment 13 Revision 3-
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. EQUI FNENT SELECTED FOR HARSH F.NVI RONNENT OUALI FI CATE ON Pal D 35YSTENs HIGH PRESS COOL. INJECTION .M-55-1 ,
M 1 D NO. PAN ' TN! ACTION LOCATION EOUI P. PLAN EQUIP. $ ; P.O. N47FE (5). N PL NO. COM PONENT H l.DC. E E.EV. NOTE (1) NOTE 12) FESS REF. NO. P3020 1-FO-HV-F001 Control Valve' Re ac t or 54 NO No ' &3)
- P3020 1 -FD-2 S-F001 Limit Switch i
P3220 1 -FD-H V-F0 0 2 Reactor 54 m). ' No 1 33 Control Valve Reactor 102 No No P3320 1 -F D-2 S-F00 2 Limit Switch 1 12 Reactor 100 Ye s No 432 l P3220. 1-Fl> HV-F00 3 Control Valve Reactor: 102 No
'I j P3020 1 -F D-IS-F00 3 Limit Switch No 'I 32
, Reactor 102 Yes m> & 52 I
P3010 1-RJ-HV-F004 Control Valve Reactor 54 :NO l P3110 1-M -2S-F004 No l ~'6 Limit Switch peactor 54 ' No No P3320 1-BJ-HV-F006 Coetrol Valve .126
- Beactor 102 No No 13)
. P3320 1-M -2S-F006 Limit Switch Reactor '102 Yes No P3020 1-RJ-HV-F007 Control valve 133
- Reactor 5 4 .. Nu . No j P3320 1-M -2S-F007 Limit Switch Reactor .54 No I !) l P3220 1-M-HV-F008 . No 133 i Control. Valve , steactor 77 No No 133 a
P332Q 5-M -2S-F000 Limit Switch . Reac t or 77 No P3020 1 -AP-H V-Fe l l ._ Control Valve . No 133
, Reac tor 77 .No No 13) 4 P3020 1 - A P-2 S-F0l l Limit Switch. Reactor 77 No No (3)
P3020 1 -M-HV-F012 Control Valve , Reactor 54 .No No - i P3320 1 -M- 2 S-F012 Limit Switch l 13 i Rwactor 54 Yes No 133 i P333AO l-FD-SV-F0 28 solenoid Valve Reactor 54 No No P30 3AO l -FD-2 S-F028 I40 = Position Switch Reactor 54 No No ' P303AO l-FD-SV-F029 141 l Solenoid Valve Reactor 54 %) No 140
+
P 30 3AQ - 1 -F D-% S-F029 Position Switch peactor 54 m) No P 30lO l-M-HV-F042 contral valve Reactor' 54 . Ye s No ist , P30lO l -M-2S-F04 2 1 26 ' 'l Limit Switch peactor 54 Yes- No 126 JiS10 1-FD-SV-F054 . Solenoid valve . Reactor 54 No Ho' J1810 1 -F D-2 S-F054 44 Position Switch feeac t or 54 No No 45 i P3%10 1-FD-HV-F071 Control Valve- Re ac tor 77 No No l 26 ] , I Anwa.s.e n t !) a Nevision 3 e i l f f 4 . I
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.HCGS FSAR Page 60 ~ of ' I 20 TAnLE . 3.11-5 j . .
EOul19eENT SELECTED FOR HARSH ENVI RONNENT OUALI FICATION P6t D N-55-4 SYSTE3 HIGH PRESS COOL. INJECTION N PAN TNI ACTION
- i. I D NO. LOCATION EOul P. PLAN EOUIP.
P.O. NOTE (5) NPL NO. COMPONENT BLDG. ELEV. NOTE ( 1 ) ' NOTE ' ( 2) EESS REF. NO.
- P3020 1 -FD-HV-F0 01 Control valve Reactor 54 .No .No 13),
, P3020 1 -F D-2 S-F001 Limit Switch Reactor 54 No No '33) P3020 1 -FD-HV-F00 2 control Valve Re act or 102 No No 1 12 P3020 1 -F D-IS-F00 2 Limit Switch -Reactor 100 Yes No 1 12 P3020' 1-Fl>HV-F003 control valve Reactor 102 No No 132
- i. r3120 1-F D-IS-F00 3 Limit Switch Reactor 102 Yes No 4 32
} P 30lO l-BJ-HV-F004 -Control Valve Reactor 54 No No 126 , P3010 1-mJ-IS-F004 Limit Switch Reactor 54 .No No - 126 l P302Q 1-M -HV-F006 Control Valve Reactor 102 No No - 131
- P3120 1-BJ-2S-F006 Limit Switch Reactor' 102 Yes No 1 13 P3020 1 -IL3-H V-F007 Control Valve Reactor .54 No No' I il l P3020 1 -BJ-2 S-F00 7 Limit Switch Reactor 54 No No ll) 4 P3120 1-BJ-HV-F0 00 Control Valve < Reactor 77 No No . 1Il j P3020 1-BJ-2S-F008 Limit Switch peactor 77 No No 133-
? P3020 1-AP-HV-F0ll Control Valve . Reactor 77 No No 133 P3220 1-A P-IS-F0l l Limit Switch Reactor 77 No No 1 13 P3020 1-BJ-HV-F012 Control Valve Reactor- 54 No No 111-i P302Q 1-8J-IS-F012 Limit Switch Reactor 54 Yes No ' 135 P30 3AO . 1-FD-SV-F029 Solenoid Valve ite act or 54 No No 140 P303AQ ' l-FD-2 S-F0 26 Position Switch Reactor 54 No No 141
< P 30 3AQ 1-FD-SV-F0 29 Solenoid valve Reactor 54 No No I40 P30 3AQ 1 -F D-2 S- F0 29 ' Position Switch Reactor 54 No No- 141' P3110 1-BJ-HV-F042 control valve . Reactor 54 Yes No -- 126 ,
4 P31tQ 1 -IL3-IS-F04 2 Limit Switch Reactor 54 Ye s No 126
, JWlQ 1-FD-SV-F054 Solenoid Valve Reactor 54 No No ,44 +
! JL110 ! =FD-IS-F054 Position Switch Reactor . No No 45 j P3110 1 - F D- H V- F071 Control Valve Reactor .'77
- 54. 'No No 126 Amendment 13 Revision 3 s
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.q HCGS FSAR TATTLE 3.11-5 Pap 61 - o f I 20 -
EOUIPNENT SELECTED FOR NARSH ENVI RONMENT OllAll rt CAYRON P630
. SYSTEM: HIGH PRESS COOL. INJECTION N-55-1 BJ I O NO. PAM TMI ACTluN P.O. NOTE (5) IR ATION EOtli P. PtAN EQUIP.
NPL NO. CON RMlFWT R Li C, ELEV. N4rrE (3) b e 'E ( 2) E E:SS 5t E F . NO. P3 lO 1-FD-2S-F071 Limit Switch Reactor 77 P3IR O l -F D-HV-F07 5 Yes No 126
. Control valve Reactor 77 No No 127 P3110 1 -FD- 25-F0 7 5 Limit Switch Reactor 77- Yes No P30lO l -F D-HV-F0 79 Control. Valve 1 27 P 30lO 1 -FD-2 S- F0 79 Beactor 77 No No 127 Limit Switch Reactor 77 Yes No P303AO l - F D-H V- F100 control Valve 1 27 P323AO l -FD-25-F100 Beactor 100 No No I 19 Limit Switch Reactor 100 Yes No M001 1 -F D-F T-N00 0 E41 Flow Trans. 1 39 Reactor 54 .Yes No M0il 1 -FD-PT-N013 E41 Press. Trans. . Reactor 54 155 N001 1 -F D-LS H-M014 h No 106 E41 Level Switch High Reactor 54 N001 1 -IO - PT-N0 50 No No 150 E41 Press. Trans. Reactor 54 No No 155 M011 1-8J-PT-N051 Eel Flow Trans. . Reactor 54 h
'M001 1 -FD-PDT-N0 57A E41 No 155 M0ll Press. Di f f .1rans. Reactor 77 No M 155 1 -F D-PDT-N0 57C E45 Press.'Diff.:Trans. Reactor 77 M0tt No No !$5 1 -FD-PT-N0 58A E41 ' Press. Transmitter' Reactor 77 N011 h No 155 1 -F D-PT-N05 0C E41 Press. Transm& t ter Keactor 77 No No 155 No t t- I -FD-PT-N0 58E E41 Press. Transmitter Reactor 77 No h 155 M011 1-FD-PT-N058G E41 Press.. Transmit ter Reactor 77 No No 155 M001 1 -M-LT-N06 2A - , E41 Level Transmitter Reactor 54 No M021 1-RJ-LT-N062E Ett Emvel Trans. No - 120 Reactor 54 No No 120 J 3IlO l-BJ-PT-4 7 71 Press Trans. Reactor 54 No No J 3110 1-HJ-LT-4801 29 Level Trans. Reactor 54 Yes - Ye s 28 P 303AO 1-IsJ-HV-4 8 0 3 Control Valve Re ac tor 54 No No 1 39 P383AO - 1-uJ-2S-4803 Limit Switch' . Reactor 54 Yes No P 10 3AC l-lO-HV-4804 Control valve Reactor 54 ho h 1 39 P333AO l-hJ-2S-4804 1 $9 Limit Switch Reactor. 54 Yes No M031 1-IO-LT-4805-1 1 39 Level Trans. Reactor 54 Yes No $55A Amen.iment 13 Revision 3
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-HCGS FSAR Page 6 2 ' of ' 120..
TABl.E 3.11-5
. EQUI PNENT SELECTED FOR HARSH ENV!RONMENT. QUAL l FICATE ON P&l I) '
N-55-1 SYSTENs HIGN PRESS COOL. INJECTION
' IsJ
. PAN . TN! ACTION I D NO. LOCATlUN EQUIP. PtJut Lout P.
P.O. asOTE 15) MPL NO. COMPoesENT RLDG. E lE V. NOTE ( 1 ) NOTE ( 2) EESS MFF. NO. N001 1 -ILI-LT- 4 80 5- 2 Level Trans. .peactor 54 No No 1-M-HV-4865 ' 155A P30 3AQ Control valve- .Neactor 54- No 1-M-ZS-4065 No 1 I l$ . P 30 340 Limit Switch peactor 54 Yes No I 19 P333AQ 1-N-HV-4866 Control valve Heactor 54 No . m) l 39 P 30 3AQ 1-N -3S-4866 Limit Switch Reactor 54 Yes No I 39
'P3320 1-BJ-HV-8278 Control Valwe Reactor 102 No No- 131 P3020 1 -BJ-IS-0 278 Limit Switch '- Heactor 102 Yes No 133 t
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! D NO. LucATION EQUIP. ~ PLAN EQUIP.
P.O. NOTE (51 N PL No. CON PONENT ' H L lf.. E E.EV. ' MOTE (1) NOTE ( 25 EESS REF. No. Not! 10-S-211 E41-C002 HPCI Turbine Reactor 54 NO No 123 scelt 10-P-213 E41 -C002 Auu. Oil Pump sector Reactor 54 No No 123 - 8e011 10-P-215 E41-COO 2 FPCI Vac Tank Cond. Pump. .Beactor 54 No ; No 1 23-
- M021 10-P-216 E41-C002 HPCI Cland Seal Cond. Vac. Pump Reactor 54 .No' No 123 se021 No Tag No. E41-C002 HPCI Turbine Governor Reactor 54 No No 123 se0320 1 A-P-228 Jockey Pump Notor, ECCS Reac tor 54 No No 80 J10lO l-FleSV-F0 25 Solenoid valve Reactor 54 No No - 44 J61tQ 1 -F D-2 S- F0 2 5 Position Switch Reactor 54 No No 45 P383AQ 1-FD-SV-F026 Solenoid Valwe Reactor . 54 No- No 140 P33 3AQ 1 -F D-2 S-F0 26 Position Switch. Reactor' . No No 143 P353AQ 1 -IL3 -HV-F0 59 Control Valve Reactor ' 54 54 No No I 18 P30 3AQ 1-IsJ-IS-F059 Licit Switch . Reactor 54 No No 1 30 30011- 1 -IL3-PT-N0 5 2 w41 Press. Trans. Reactor 54 No No 106 0e011 1-BJ-PT-N003 E41 Press. Trans.
- seeactor 54 'No No 155
- se001 1 -FD- PT-N0 5 5A E41 . Press. Trans. . Reactor 77 No No 155 . ,
Amendment t3 Revision )
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Q )' i 4 . w/ %J HCGS FSAR Page 64 of'120 TABLE 3.11-5 EOut PMENT SELECTED FOR HARSH ENVE RONMENT OUALIFICATEON Phl D - SYSTEM HPCI PUMP TURBINE M-56-1 4 FD PAM TNI ACTION 10 NO. LOCATION .LOUIP. P.O. NOTE (5) MPL NO. . PLAN LOUIP. COMPOstENT H LIM. EIEV. NOTE (1) NOTE l 2) EESS REF. NO. MOIL 1 -FD-PT-N0 55C E41 Press. Traas. Reactor -- 7 7 No No N001 1-FD-PT-M055E 155 E41 Press. Trans. feeactor 77 No No Neil 1 -FD-PT-N0 55G Ett ISS Press. Trans. Reactor 17 No No 155 M001 1 -F D-PT-N05 6A Eel Press. Trans. Reactor 54 No No 155 N011 1 -FD-PT-N0 56E E41 Press. Trans. Reactor 54 No No N001 1 -F D-FV-4 8 7 9 E41 155 Flow Control Valve ktuator Reactor 54 No No 12) M011 1-FD-FV-4880 E41 Flow Control Valve Actuator Reactor 54 No m) 123 M0ll 1 -FD-LS H-4090 E44 Level Switch iligh Reactor 54 No No J30lO l-RJ-PT-4891 32) , ' Press Trans. . Reactor 77 No No 29
.M001 1 -FD-LS L-490 3 E41-C002 level Switch low Reactor 54 *n No N011 1 -FD-PSet- 4 9 0 5 121 E41-C002 Press Switch High Reactor 54 >No No !2)
M011 1-FD-2S-49d7 E41-C002 Limit Switch Reactor 54 No No 125' se011 1 -F D-PS L-4 9 09 E41-C002 Press. Switch Low peactor 54 No 1 -F D-TS-4909 No 123 N001 E41-C002 Temp Switch Peactor 54 No No 125 seoil 1-Fth PDSH-4910 E41-C002 Press Diff. Switch High Reactor 54 No se001 1 -FD-LSH L-4912 E41 -C00 2 No 12) Level Switch High Low heactor 54 No - E3 52) 4 se011 1 - F D- PS- 491 3 E41-C002 Press. Switch Reac tor - 54 No No 121 8e011 1 -F D-S E-4 9 8 9 E41-C002 Speed Etant. Reactor 54 No No 123 j Amenilment i1 Revision 1 4 4 e w 1 J s
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HCGS FSAR . Page 6 5 , of 120 ' TABLE ' 3.14 -5 '
' EQUE 19 TENT SELECTED FOR HARSH ENV1 RUNNENT QUALI FICATEON ' Ph! D .
N-57-4 f.YSTENs CONTAINetENT ATNOS. CONTRL. GS # PAN TN! ACTION I D NO. LOCATEON EQUIP. PLAN EQUIP. P0 NOTE (5} NPL NO. COM PONENT BLDG. ELEV. NOTE ( l ) NOTE ( 2) LESS REP. NO. J 3590 1A-C-200 H2/02 Analyzer PNL A Reactor 162 No. 'Yes '30 J 3590 In-C-200 H2/02 Analyzer PNL 8 Reactor '162 No Yes -30
- J 3590 IC-C-200 H2/02 Analyzer Heat Trace PNL Reector 162 No No 31 J3590 ID-C-200 ; H2/02 Analyzer Heat Trace PNL Reactor 162 No m3 31 J 3590 4-GS-TE-0351 Temperature Element Reactor '145 No Yes 31 J359Q 1 -GS-TE-0 35 2 Temperature Element Beactor 145 No Yes 31 J 3590 1-GS-TE-0353 Teng erature Element peactor 77 No Yes 31 J359Q 1 -GS-TE-0 354 Temperature Element Reactor 162 No . Ye s 31 J 3590 1-CS-TE-0355 Temperature Element .Neactor 102 No Ye s 31 J3590 1 -GS-TE-0 356 Temperature Element ' Reactor 162 No Yes 31 J3590 1 -CS-TE-0 357 Temperature Element . Reactor 162 No Yes 31
.J3590 1-GS-TE-0358 Temperature Element Reactor 162 No Yes 31 J 3590 1 -GS-T E-0 359 Temperature Element peactor 162 No Yes 31 P3150 1-GS-SV-4950 Solenoid valve Beactor 145 No No 145 P3050 1 -GS-IS- 4950 Pos! tion Switch Reactor 145 Yes Fo 146
-P301AQ 1-GS-HV-4951 Control Valve Reactor 145 No m) 1 39 P303AQ 8-GS-IS-4951 Limit Switch Reactor 145 Yes No 1 39 P3050 4-GS-SV-4952 Solenoid valve Reactor 145 No No $45 P3050 1-GS-IS-4952 Position Switch Reactor 145 Yes No 146 P30 3AQ 1-GS-HV-4955A Control valve leeac tor 162 No No 4 39 P30 3AQ 1-GS-IS-4955A Linst Switch Reactor 162 Ye s do 1 39 P30 340 1-GS-HV-49558 Control Valve. leeac tor .162 No No 13e P 303AQ 1 -GS-2S-49 55a Limit Switch Hwactor 162 Yes No 1 39 P 3050 1-GS-SV-4956 Solenoid Valve Reactor 102 No No 145 P3050 1 -ca-2S-4956 Position Switch . Reactcr 102 Yes No 146 P3050 1-cs-SV-4958 Solenoid valve Beactor 77 No No 145.
P d50 1 -Gs-25-4 9 52 Position Switch Reactor 77 Ye s No 146 P30 3AQ 1 -GS-HV-4959 A Control Valve Reactor 77 No No 1 39 Amendment 13 Revlsion 3 e
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EQUI PNe;NT SELECTED FOR HARSN' ENVIRONMENT QUALIFICATION Psi b . SYSTENi CdtTAlte00ENT ATIGOS. CONTRL. .N-57-1 GS I D NO. PAN TN! ACTION LOCATION EQUI P. . PLAN IOutP. P.O. esoTE (5) NPL NO. CON fee 6Esif Bl.DG. E I.E V. StOTE (1)' DeOTE ' ( 2) ' l'ESS REF. NO. P303AO l-GS-IS-4959A Limit Switch meactor 77 P393AO I-CS-NV-49598 Yes ma ' 1 )v Control Valve peactor 77 . m3 P30 3AO l-GS-IS-4959s Limit Switch neactor 17
. No I 19 J 30lO l-GS-PT-4960Al Yes No Press. Trans. Reactor 102 ' 1 39 J 3180 1-GS-PT-4960el Yes No 28 +
Press. Trans. Its act or 102 Yes No J 30lO 1-GS-PT-496083 Press. Trans. 28.
.'3050 1-GS-Sv-4962 -Reactor 102 Yes No 29 Solenoid valve meactor 77 No m3 5150 1-GS-IS-4962 Position Switch peactor 845:
7 7 .. Yes No 103AO l-GS-NV-4963 Control valve peactor 77 R46
.a 30 3AO l-CS-2S-4963 No .m) 1 39 Position Switch peactor 17 Yes No' P3050 1-CS-SV-4964 Solenoid valve asactor 77 4 39 P3050 1-CS-IS-4964 No >> I45 Limit Switch meactor 77 Yes ms
- P303AO l-GS-NY-4965A Control valve 146 peactor 77 No I 19 - P 30 3AO l-GS-IS-4965A Limit Switch peactor 77 No. P30 3AO 1-GS-Nv-4965a Yes No 139: Control valve Deactor 77- No No P30 3AO l -GS-IS-496 58 Limit Switch Reactor 77 1 39 9303AO l-GS-NV-4966A Yes No i 39 Control valve Reactor 77- :No No P 30 3AO l-GS-IS-49664 Limit Switch 1 39 Ihaactor 11 Yes No P 303AO I-CS-HV-49668 Control Valwe Deactor 102 1 39 l-GS-IS-49668 Yes m2 1 19 P 39 3AO ' Limit Switch - leesct or J5560 1 -GS-T E-4967Al 102 Yes No 1 39 Temp. Elemt. Reactor ll No J5560 1-GS-TE-4967A2 No 41 Temp. Elemt. Reactor 121 Ye s ' J 5560 1-GS-TE-4967A3 No 43 Temp. Elemt. leeactor J5560 1-GS-TE-4967BI Temp. Elemt. 1 21 No m) 43 Reactor ' 17 No No J 5560 1-GS-TE-496752 Temp. Elemt. Reactor 128 43 J5560 1-GS-TE-4967B3 Ye s No 4) Temp. Elemt. feeactor 1 28 No No 43
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[ HCGS FSAR TAeLE 3.11-5 Pa p 67.-o! I 20 ' EQUI PMENT SELECTED FOk HARSH ENVI RONNENT QUALIFICATION P6 t D EYSTEN CONTA!NetENT ATNOS. CONTRL. N- 5 7- 1 GS I D NO. PAN TN! ACTION P.a. seurg (58 LOCATION EQUIP. PLAN EQUIP. NPL NO. rossPONENT HLDG. EIEV. NOTE (1) 960TE 12) rFSS REF. 96 0 P30 3A0 1-GS-HV-4974 Control Valve Reactor 102 P30 3AQ 1-GS-IS-4974 ' .No E2 1 39 Limit Switch . Reactor 102 Yes No P3050 1-CS-SV-4978 Solenoid Valwe Reactor 102 139 P3450 1-GS-IS-4978 No No 445 Position Switch Reactor 102 Yes No P3050 1 -CS-SV-49 79 Solenoid Valve 146 P3050 .1-GS-IS-4979 peactor 102 No No 145 Position Switch peactor 1u2 Yes . No P3050 1-GS-SV-4980 Solenoid valve awactor 77 i46 . P3050 1-GS-2S-4980 No No 145 Position Switch peactor 77 Yes ho P30 3AO l-GS-HV-4983A Control valve ea- 146 Reactor No ,6a 1 39 930 3AQ R-GS-3S-4983A Limit Switch m ur 162 Yea
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P303AQ 1 -GS-HV-498 3B No' S 39 Control Valve Reactor 162 No No P 303AQ 1-GS-IS-498 38 Limit Switch Reactor 162 1 39 Yws No 1 39 P 30 34Q 1-GS-HV-4984A Control Valve Reactor 162 No P30 3AQ 1-GS-IS-49844 h 1 39 Limit Switch Heactor 162 Yes No P30 3AQ 1-GS-HV-49848 Control Valve 1 39 P 30 3AQ I-GS-IS-49048 Heactor 162 No ' No .I 19 Limit Switch Neactor 562 Yes No P303AQ 1-GS-NV-5019A Control valve l 39 Re ac tor 162 No No 1 39 P30 3AQ 1-GS-IS-5019A Listt Switch lesactor 162 Yes P30 3AQ 1-GS-HV-5019s No 1 39 Control Valve seactor 162 No No P30 3AQ 1-GS-IS-5019a 1 39 Limit Switch . Reactor 162 Yes No ea%Q l-GS-HV-5022A Control'Valwe I 19 - Re actor 77 No No P30 3AQ 1-CS-IS-5022A Limit Switch peactor 77 Yes 4 39 P30 3AQ 1-GS-HV-50228 No 1 19 Control Valve . Reactor .102 No No 1 39 P303AQ 1-CS-IS-5022s Limit Switch Reactor 102 Yes' No 1 39 J 3010 1 -GS-PDT-5029 Press. Ditt. Trans. meactor 102 No P3050 1 -GS-SV-50 29 No 28 Solenoid Valve . Reactor 77 No No 145 P3050 1 -CS-3 S-50 29 Limit Switch peactor 77 J 3040 Yes NO )46 l-GS-PDT-5031 Press. Dif f. Trans. Reactor 102 No No - 28 Amendment 13 kevision 3 ' t 4
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HCGS FSAR Page 68- of 520 ' TABLE 3.11-5 EQUI PNENT SELECTED FOR HARSH ENV! RONMENT QU ALI FICATION Pol D
-M-57-8:
EYSTEN: Ct*TAIINGENT ATNOS. CONTRL. CS PAN .TNI AC78ON-1 D NO. LOCATION EQUIP. Pt.AN LQUIP. P.9 NOTE (5) NPL NO. COM PUNENT HI.DG. E I.E V. NOTE (1) NOTE (2) FESS WEF. NO. P3050 'l-GS-SV-5031 fiolenoid valve keactor 77 No No 145 P 3050 1-GS-IS-5031 Position Switch Reactor 77 Yes No 'I46 P 30lO l-EM-SV-5035 Solenoid Valve Reactor 77 No No 124
- P3040 1-EN-IS-5035 Position Switch Reactor 77 No No 125 J 3590 1-GS-AE-5039Al Analysis Elemt. Reactor 162 Yes No 30
- J 3590 1-GS-AE-5039A2 Analysis Elemt. Reactor 162 Ye s No 30 J 3590 1 -GS- AE-50 3981 Analysis Eleet.- Reactor 162 Yes No 30 J3590 1-GS-AE-5039s2 Analysis Elemt. Reactor 162 Yes No 30-J 3590 1 -GS- Al-504 0A Anal. Indicator Reactor 162 No No 30 J 3590 1-GS-Al-5040ft Anal. Indicator Reactor 162 No No 30 J3590 1 -GS-MA- 504 2A Alarm Reactor 162 No No 30 J3590 1 -GS-x A-504 2a Alarm Reactor 162 No No 30 J 3590 1-GS-PANL-50el A Press Alarm High Low Reactor .162. No No 30 J3590 1 -GS-PAN L-50e l s Press Alarm High Low Reactor 162 No No 30 J 3590 1-GS-PSN-50SIA Press. Sw. High Reactor 162 No No 30 J3590- 1-GS-PSL-50SIA Press. Sw. Low Reactor 162 No No 30 J 3590 1 -GS- PSN- 50el B Press. Sw. High Reactor 162 No No 30 J 3590 1 -GS-PS L-50818 Press. Sw. Inw Reactor 162 No No 30 J nSO l-GS-PAL- 508 5A Alarm Point- Reactor 162' No No 30 J 35CC 1 -GS-PS L-508 5Al Press. Sw. Low Reactor 862 No No 30 J 3590 1 -GS- PSL- 50u 5A 2 Press. Sw. tow . Reactor' 162 No No 30 J3590 1 -GS-PS L-508 5A3 Press. Sw. Inw Reactor 162 No No 30 J3590 1 -GS- PSL- 5095A4 Press. Sw. Low Reactor 162 No 22 10 J3590 1 -GS-PA L-508 5a Alarm Point Reactor 162 No No 30 - J 3590 1-GS- PS L- 50u 5al Press. Sw. Low Reactor 162 No No 10 J3590 1-GS-PS L-508 582 Press. Sw. Inw Reactor 162 No No 30 J3590 1 -GS-PSL- 508 5s 3 Press. Sw. Low Reactor 162 ko No 30 J 35wO l -GS-PS L-508 584 Press. Sw. Inw Reactor 162 No %) 30 Amenstme n t I) kevision 3
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(- /. G/ ' s v 4 HCGS FSAR Page 69 of 1 20 1 TABLE 3.11-5 EOut PNENT JELECTC*) FOR HAESH ENV! RONMENT OUALI FICATION P&I D SYSTENs CONTAINNENT ATNOS. CONTRL. N-57-1 GS PAN TNI ACTI ON I D No. LOCATEON EQUIP. PLAN EOut P. P.9 NOTE (5) NPL NO. CON PONENT H L fM . ELEV. NOTE (1) NOTE { 2) EESS RFF. No. ] J 3590 1 -GS-SV-508 6Al Solenoid Valve Reac tor 162 No No 30 . J 3550 1-GS-SV-5086A2 Solenoid Valve Reactor 162 No. No 30
' J 3590 4-GS-SV-5086sl Solenoid valve Re ac tor 162 No No 30 J 3510 1-GS-SV-508682 Solenoid Valve beactor 162 No No 30 J 3590 1-GS-M S-500 7A . Hand Sw. keactor le2 No No 30 J 3590 1-GS-SV-5087Al Solenoid Valve Reactor 162 No No 30 J 3590 1-CS-SV-5087A2 Sclenoid Valve Re ac tor 162 No No 10 J3590 1-CS-MS-50878 Hand Sw. . Reactor 162 No No 30 J 3590 1-GS-SV-500781 Solenoid Valve Reactor 162 % No 30 J 3590 1-GS-SV-508782 Solenoid valve Reactor 162 No . No 30 J 3590 1 -CS-TAN- 509 2A Temp. Alarm Higin Reactor 162 No No 30
, J3590 4 -CS-TAL-509 2A Temp. Alarm Low Reactor 162 No No 30
! J 3590 1-GS-TAH-5092u . Temp. Alarm High Reactor 162 No No 30 J 3590 1 -GS-TA L-509 22 . Temp. Alarm Low Raector 162 No No 30 a J 3590 1-GS-TSH-5Cl2A Temp Sw. High Re n tor 162 No . No 30 J 3590 1 -GS-TSL-509 2A . Temp. Sw. Low R6 actor 162 No No 30 J 3590 1-GS-TSH-50928 Temp. Sw. High Reactor 162 No No 30
.J3520 1 -GS-TS L-509 2u Temp. Sw. Iow Reactor 162 No No 30 J 3590 1-GS-FAN-5094A Flow Alarm High peactor 162 No No 30 J 3590 1 -GS--FAL-509 4B Flow Alarm Low -Reactor !62 .No No 30 J 3590 1 -G S- PDS-509 4 A1 Press. Diff..Sw. Reactor- 162 No No 30 J 3590 1-GS-PDS-5094A2 Press. Diff. Sw. Reactor 162 No No 30 J 3590 l -GS-PDS-509 481 Press Diff. Sw. Reactor 162 No No 30
; J3590 1 -GS-PDS-509 4 82 Press Diff. Sw. Reactor 162 No No 30 P 30 3AG l-GS-HV-5741A Control valve , Reactor 132 No No I 19 P303AO l-GS-IS-5741A Limit Switch Heactor 132 No No 4 39 P30.1AO l-GS-HV-5741B Control Valwe Reactor i 32 . No No 1 39 P13 3AO l-GS-IS-57418 Limit Switch Heactor i32 No No 1 39 J 3590 NO aAG NO. He at Tr ac 6 ng Reactor N/A No No 31 Amendment i3
, Revision 3 J
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'HCGS FSAR ' Page 70 of - 8 20
TAhLE 3.ll=5 EQUI PNENT SELECTED FOR HARLt ENVI RONNENT OUALI FICAYlON , P& l D ' N-58-1 SYSTENs CONTA!sestENT HYDROGEN RECONet NATION SYSTEN CS PAN TNI ACTION I D NO. LOCATI ON EQUIP. PLAN EQUIP. P.e. seOTE (5) NPL NO. Cost PuMFNT Hl.fC. E l.E V. NOTE (1) MrYE ( 21 EESS REF. feO. Is047AO 1A-S-205 Hydrogen Recombiner Reactor 162 No No 55 00047AO 18-S-205 Hydrogen Recombiner . Reactor .162 E3 No 55 M047AQ IA-C-215 . Power Panet Reactor 162 No ' No 54 seu(7AQ 1A-E-215 Heater steactor 162 No No 56 se047AO 1A-V-215 Fan Motor Reactor 162 No No 52 se647AO IB-C-215 Power Panel Reactoa 162 No No 54 .se047Ao 18-E-215 esen te r Reactor 162 No *% 56 N047AQ IB-V-215 Pan pector Reactor 162 No No 52-P3040 1 -GS-H V- 5050A Contr. Valve Reactor 145 No Yes 127 P30lg 1-GS-IS-5050A Limit Switch feeactor I45 Yes No ^ 127 P30lO l-GS-ttv-5050s contr. Valve steac tor 102, No Ye s 127 P30!g 1-GS-IS-Sa50s simit Switch Reactor 102 Yes No 127 P 30lO l-GS-HV-5052A c...tr. Valve Reactor 145 No Yes 1 27 P3010 1-GS-IS-5052A I t alt Switch Reactor 145 Yes No '127 P3010 1-GS-isv-50 5 2s Contr. Valve . Reactor 102 No Yes 1 27 P3019 l-GS-IS-505 2a Limit Switch Reactor 102 Yes No 127 P30lO l-GS-HV-505 3A Contr. Valve ' Reactor 77 No Yes 127 P3010 1 -GS-IS-505 3A Limit Switch Reactor 77 Yes No 127 P30lO 1-GS-HV-5053n Contr. valve Reactor 77 . . No Ye s 127 P30lo 1-GS-IS-5J53B Limit Switch Reactor 77 Yes No 127 P 30lO l-GS-HV-5054A Contr. Valve Reactor 77 No Yes 127 P3010 1 -GS-IS-505 4 A Limit Switch feeact or 77 Yes No 127 P30lO l-GS-HV-5054H contr. Valve . Reactor 77 No Yea 'I27 P3It o 1-GS-IS-50548 Limit Switch peactor 77 Yes No 127 P333AO 1-SC-HV-5055A contr. Valve Re actor 54 No No 1 39 P333AQ 1-bC-2S-5055A Limit Switch feeac tor 54 No No 1 19 P 30 3AO l-eC-HV-5055a Contr. Valve Reactor 77 No No 1 39 Amendment i3 Revision 3
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y b f HCGS FSAR TABLE 3.11-5 Page 71 ~of 120 EQUIPNENT SELECTED FOR HARSN ENVIRONMENT QUALI FICA flON Phl D gYMEN s CONTAINNENT HYDROGEN HECOMBINATION SYSTEN N-58-1 GS 1 D NO. PAN .TNI ACTION P.O. NOTE (5) 1.OCAT!uN EQUIP. PLAN I; QUI P. NPL No. CONFONENT . 89 L[4. - E I.E V. NOTE (Il NOTE ( 2) FESS REF. NO. P 30 3AQ 1 -BC-IS-5055a Limit Switch Reac tor 77 P30 3AQ 1-GS-HV-5057A No No 1 19 Contr. Valve Reactor 54 m) P30 3AQ 1-GS-IS-5057A Listt Switch Reactor 54 No I 39 P30 3AQ 1 -GS-HV-50578 No E2 1 19 Cont r. Valve Reactor 17 No No P303AQ 1-CS-2S*50578 Limit Switch Reactor 77 139 Gb47AQ 1 -GS-FT-506 6A No No I 19 Flow Trans. Reactor 162 No No N04 7AQ 1 -GS-F1 -50668 Flow Trans. Reactor 57 N047AQ 1-GS-FT-5067A 162 No No 57 Flow Trans. Reactor 162 No No se047AQ 1-GS-FT-50678 Flow Trans. Reactor 162 57-se047AQ 1-GS-TE-5068A No No 57'~ Temp. Elemt. Reactor ~ 162 see47AQ 1-GS-TE-50688 No No 58 Temp. Elemt. Deactor 162 N047AQ 1 -GS-TE-5069 A No No. 58 Temp. Elemt. Reactor 162 N047AQ 14S-TE-50698 No No 58 Temp. Elemt. Reactor 162 No N047AQ R-GS-TE-5070A Temp. Elemt . No 58 s8047A0 1-GS-TE-50708 Reactor 162 No No 58 Temp. Elemt. Reac tor 162 N047AQ 1 -GS-TE-507 34 No No 58 - Temp. Elemt. Reactor 162 No se04 7AQ 1 -GS-TE-507 38 Temp. Elemt. No 58 se04740 1-GS*T E-507 4 A1 seeme t or 162 No No 58 Temp. Elemt. Reactor 162 se647AQ 1-GS-TE-5074A2 No No 58 Tump. Elemt. Re ac tor 162 No 88047A0 1-GS-TE-5074al No 58 Temp. Elemt. Reactor 162 No se047AQ 1-GS-TE-507482 Temp. Elemt. No 58 se647AQ 1 -GS-TE-507 5A Temp. Elemt. Re actor . 162 No No 58 s0047AQ 1-GS-TE-50758 Reactor 162 No No 58 Temp. Elemt. Reactor 162 No se04 7AQ 1-GS-TE-5076A Temp. Elemt.
.No 58 se047AQ 1-GS-TE-5076s Reactor 162 No N0 58 Temp. Elemt. Reactor 162 No se647AQ 1-GS-HV-5077A No 58 Contr. Valve Reactor 162 No No se047AQ 1-GS-ZS-5077A Limit Switch 59 Reactor 162 No No 59
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.HCGS FSAR TABLE 3.11-5 . Page 7 2 of 120-EQUI PNENT SEi,ECTED FOR HARSH ENVI RONNENT QUALIFICATION ' Phi D S YSTEN: CONTAINNENT HYDROGEN RECONBINATION SYSTEN N- 58-l .
GS PAN TNI ACTION I D NO. LOCATION EQUIP, P. O. NOTE (5) NPL NO. COM PONENT PLAN EQUIP. HLDG. ELEV. NOTE (1) NOTE (2) EESS NEF. NO. N047AQ 1-GS-HV-50778 Contr. valve peactor 162 No N047AQ 3-GS-IS-50778 No 59 Limit Switch anactor- 162 No No
. se647AQ 1-GS-NV-5078A Contr. Valve 59 Reactor 162 No No feG47AQ 1-GS-IS-5078A Limit Switch Reactor 162 No 59.
se64740 1-GS-NV-5070s No 59 Contr. Valve Reac tor 162 No No 59 N047AC 1-GS-IS-5078a Limit Sw&tch Reactor 162 No -No. %
-3e047A0 1-GS-HV-50004 Contr. Valve peactor 162 No N047AQ 1-GS-2S-50804 No 59 Limit Switch . Reactor 162 No No 59 se047AQ 1-GS-HV-5080s Contr. Valve Beactor 162 No It04 7AQ 1-GS-IS-50808 No 59 '
Limit Switch Beactor 162 No No fee 47AQ 1 -GS-TE- 5097A Temp. Elemt. 59 leeactor 162 No No 58 N047AQ 3-GS-TE-50978 Temp. Elemt. Reactor 162 No No 5e le047AQ 1-GS-PT-509 8A Press. Trans. Noactor 162 No 1 -GS-PT-509 88 No 60 se047AQ Press. Trans. Reactua 162 No No 60 Amwndment 13 Revision 3 J i i
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' TABLE 3.11-5 Emst 690ENT SELECTED FOR HARSH ENVI RONMENT QUALIFICATION ' P6 8 D M-59-1 SYSTENs PRIMARY CONTAIN8 TENT INSTRUMENT CAS KL
.PAM TMI. ACTION I D No. LOCATION -EQUIP. PLAN EQUIP.
P.O. esOTE (5) MPL NO. COM 50ssENT RLDG. E LE'I. NOTE (l) N(YTE 12) FESS R44 NO. 880480 I A-K-20 2 Compressor Instr. Gas' -Reactor 132 No NG 72 se0400 IB-K-202 Compressor Instr. Gas Reactor 132 No No 72 880400 RA-C-213 Compressor A CTRL PNL peactor 132 No No 77,79 [ N0480 IB-C-213 Compresssor B CTRL PNL Reactor 132 No No 77,79 N0400 1A-S-934 Instr. Gas Compressor Pkg. Reac t or 1 32 No No 71
.90048Q I B-S-9 34 Inst r. Gas compressor Peig.
Reactor 132 No No 7)
-880480 . 4 -KL-ME-50 31 A Moisture Element Reactor 1 32 W No 73 880480 1 -K L-MI SH-50 31 A seoisture Ind. Switch-High Reactor 1 32 No No 71 se0400 1 -K L-stE-50 31 ts seoisture Element Reactor I32 No No 73 se048Q 1-K L-NI S H-50 318 poisture Ind. Switch-High Reactor 132 No No 71 P303AQ 1 -K L-H V-5124A Control Valve Reactor 102 No No 1 39 P 30 3AQ 1 -K L-2 S-512 4 A Limit Switch Reactor 102 No No I$9 P 30 3AQ R -K L-H V-5124a control valve Reactor 1 21 No No I 39 P 30 3AQ 1-K L-IS-512 48 Limit Switch Reactor 1 21 No No 1 39 P 303AQ 1 -K L-Hv-5126A Control Valve Reactor 102 No No 1 39 '
P303AQ 1-KL-2S-5126A Limit Switch Reactor 102 Yes No 1 49 P 30 3AQ 1 -K L-HV-51268 Control valve Reactor 102 No No I 39 P303AQ 1 -K L-2 S-5126 a Limit Switch Reactor 1u2 res .No 1 19 se0400 1-Kl.-PSL-Sl 30A Press Switch law Reactor 132 No No 74 N048Q 1-K L-PS L-513 08 Press Switch Low Reactor 132 No No 74 380400 1 -KL-PSH-5135 A Press Switch H4gh Reactor 132 No No 74 N048Q 1 -K L-PSN-51318 Press Switch High Reactor 132 No No 74 88048Q 1 -K L- PSLL- 5132A Press Switch thw Low Reactor 132 No No 74 N0480 1 -K L-PSLL-513 2B Press Switch Low Low Reactor 132 No No 74 3e0400 1 = K L-H S- 5137A- 2 Hand Switch Reactor !32 No No 7) 180480 1 -K L-H S-513 7ts-2 Hand Switch RJactor 132 No No 7)
- 880400 1 -K L-PSH-514 0A Press Switch High Re ac tor 132 Nc No 74 r
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v Q v 4 HCGS F4AR TAHLE 3.11-5 . pag,'74 of 120 EQUI PNENT SELECTED FOR HARSH ENVIRONNEar? OUALIFICATION P6t p SYSTE::ta PRIMARY CONTAINNENT INSTRUNENT GAS N-59-1 KL PAN - TH E ACTI ON I O NO. LOCATION P. O. NOTE (5) NPL NO. COP PONENT EQUIP. PLAN EQUIP. . hlDC. ELEV. NOTE ( I ) h0TE (2) EESS REF. NO. .N0480 1-K L-PSH-5140s Prams Switch High heactor 132 N0450 1-KL-TSH-514tA No No 74 Temp. Switch High Reactor 132 No No N0400 1-K L-TSH- 51418 Temp. Switch High 75 N0400 Reactor 132 No No 75 1 -K L-PS L-514 2A Press Switch Inw peactor i12 NetSO No No 74 1 -K L-PS L-514 28 Press Switch Low Reactor N0400 1 32 No No 74 1-K L-TSH-514 34 fenp. Switch High Reactor 132 No N0480 I-KL-TSH-514 38 Iday. Switch High
,ho 75 N0480 1-KL-TSH-514 4A Reactor 132 No No 75 Temp. Switch High Reactor 132 No No N0480 1 -K L-TSH-Si 448 Temp. Switch High 75 N048Q Reactor 132 No No 75 1 -K L-PS L-514 5A Press Switch low . lemactor 1 12 N0440 No No 74 1 -K L- PSL-514 5s Press Switch Low - Reactor 132 P30 3AO 1 -K L-HV-514 7 No No 74 Control Valve peactor 145 No No P 30 3AO 1 -K L-25-514 7 Limit Switch 4 19 Reactor 145 Yes No I 19 P 30 3AO 3 -K L-HV-514 e Costrol valve Reactor 145 P30 3AQ 1 -K L-IS-5148 No No . 1 39 Limit Switch Reac tor 145 Yes Nu P30 3AO l-K L-HV-515 2A Castrol valve I 39 P30 3AO 1-K L-IS-515 2A Reactor 100 No No 139 Limit Switch Reactor 100 . ves No P 30 3AQ 1 -K L-HV-515 2s Coetrol Valve 1 19 Reactor 100 No No 1 39 P30 3AO 1 -KL-25-5152s Limit Switch Reactor 100 P30 3AO 1 -K L-SV-5154 Yes No I 39 Solenoid valve peactor 17 No No P303A0 1-K L 5154 Position Switch 140 Reactor 77 .Yes No 141 P30 3A0 1-KL-SV-5155 Solenoad valve. Reactor -77 No P303Ao 1 -K L 5155 No 140 Position Switch Reactor 77 Yes No P303AQ 1-KL-SV-51564 Solenoid valve .. Reactor 132 No 14%
No 140 P30 3AQ 1-K1-IS-5156A Position Switch heactor 1 32 No No 141 Amende nt 13 kewasinn 3 4 e
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LOCATION . EQUIP. PLAN EQUI P. P.e. NOTE ( 5) NPL NO. COs0 PONEN T B Ll4. E l.E V. NOTE (1) NOTE ( 2) EESS REF. NO. P303AQ 1 -K L-SV-51568 Solenoid valve Reactor 'I32 No .No 140 - P30 3AQ 1 -K L-2 S-5156u Positinn Switch puactor 132 No No 141-se0480 1 -K L-SV-5157A Solenoid Valwe seactor 1 32 No N0 76 88048Q 1-K L-SV-515 78 Solenoid valve peactor' S32 No M 76
-N048Q 1 -K L-PSL-5158A Press Switch Low peactor 132 No No 74 se0480 1 -K L-PS L-51588 Press Switch Low Reactor 132 No No ' 74 N0400 1 -K L-TSN-5159A Temp. Switch High Reactor 132 No No lb s00400 1 -K L-TSH-5159 u .Te g . Switch Isigh Reac tor 532 . No No 75 P303AQ 1 -K L-N V-5160A control Valwe Reactor 132 .No No 1 39 P303AQ 1-K L-2 S-516 04 Limit Switch peactor 132 No No L 39 P 30 3AQ 1 -K L-HV- 5160s Control valve peactor 132 No No I 19 P30 3AQ 1 -K L-IS-516 0s Limit Switch Reactor 132 No No I 39 P303AQ 1-SE-SV-5161 Solenoid valve peactor 100 No % 440 P 303AQ 3-SE-2S-5161 Position Switch peactor 100 res No 141 P 303AQ 1 -K L-HV-516 2 control Valve Reactor 132 No No I 39 P30 3AQ 1 -K L-IS-516 2 Limit Switch Reactor 432 yes No 1 39 N0480 1 -K L-SV-5164A Solenoid Valve Reactor 132 No No 76 N0480 .1-KL-hv-5164m Solenoid Valve peactor I 32 No No 76 P303AQ 1 -K L-H V-517 2A Control Valve peactor 102 No 23 1 19 P30 3AQ 1-KL-2S-Sl72A Limit Switch Reactor 102 No No I 19 P303AQ 1 -K L-HV-5172s Control valve peactor 102 No No I 19 P303AQ 1-K L-IS-517 28 Limit Switch peactor 102 No No 1 39 N0400 1 -K L-TSH-522t A Temp. Switch High Reactor 1 32 No No 75 88048Q 1 -K L-TS H-52 21 B Temp. Switch High Reactor 132 No No 75 88048Q 1 -K L-TSH-5 2 2 3A Temp. Swatch High peactor 132 No No 75 se0423 1-KL-TSH-52238 Temp. Switch High Reactor 1 32 No No 75 Amwndment !I P= vision 3 O
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- P3010 1 -189-3 S- F020-1 Limit Switch aeactor 77 Yes P 3050 1-MS-HV-5262 No' 127 Control Valve peactor77 No No 1 27 P3010 1 -Me-IS-526 2 Limit Switch peactor- '77 No No 127 P3110 1-MM-HV-5275 Control valve beactor 77 No N* 1 27 P3010 1-No-2S-5275 Limit Switch - neactor 77 No No -527 Ameminen t i3 kewiston 3-
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TAaLE 3.11 1
! EQUI PMENT SELECTED FOR HARSH ENVI DONMENT QUALIFICATION ' ' P6 t D : i j SYSTEst: SOLI D AAltlASTE COLLECTION M-66-0' sec -
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- j- P3650 1 -cas-N w- 5541 'Contr. valve' meactor 77 j . P3050 1-CN-IS-5543 No . No I44
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. P3010 1-eec-NV-5551 No No 444
- Contr. Vatwe - heactor 132 .No .t P3110 1-3C-IS-5551 Limit switch peactor too '427 't 132 -No- -127
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- PAN -1NI ACTSON a
1 D NO. } P.O. setFFE ( 5 ) LOCATItwe - EOut P. PLAN D: QUI P. N PL 000 COct PONENT BLDC. E E.EV. NOTE (!) ErrE ( 2) EESS REF. NO. 80 0
- 1 1 -Bit-PT-5SI4 A Press Trans. Reactor 77 IIDOI l-58-PT-5824s Yes No ' 155A '-
Press Trans. Reactor 77 Yes No 155A'
. J 60 30 1 -E L-POV-58 25A Press. Diff. Contr.. Valve-J6030 1 -E L-PDV-54 25e peactor 102 No km 46 J30lO l -E P-PT-5827A Press. Dit f. Cont r. Valve peactor - 102 No No 46 Press Trans. heactor 102 Yes No
- J 3013 1-E P-PT-58 278 -Press Trans. Reactor 102 29 i
P303a0 3 -E P-esV-58 29A Yes A 29 Control Valve peactor 102 No m) . j P30 3a0 1 -E P-2 S-58 29 A Limit Switch peactor 102. No I 39 4 P30 340 1 -E P-HV-58 298 No 1 39 Control Valve peactor. 102 No No P303a0 1 -E P-IS-58 29s Limit Switch peactor 1 39 P30340 1 -E P-H V-58 34A 102 No No- l 19 Control Valve heactor 102 No No
'30901 1-A3-PT-5834A 1 39 Press Trans. . Reactor 102 No No ISSA -
P30 hO l-E P-2S-5s 34A Limit Switch heactor 102 P30 3AQ 1 -E P-tev-Se 3 4m Ye s m) I 19
- 800 ~1 Control Valve shnactor 102 No No 1-AD-PT-58340 Press Trans. 139 4
1-E P-2 5-Se 34a Noactor 102 No No I SSA P303AQ Limit Switch Reactor 102 No No $ 39 4 J
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-TAhLE 3.11-5 EQUI 19eENT SELECTED FOR HARSH ENVI R(mMENT OuALI FICATE ON PhiD CVSTEssa STAIN STEAN ISO VLv SEAL SYS N- 7 2-1 EP
. PAN TNI ACTION I O NO.
LOCATEON- EQUIP. PLAN EQUIP. P. O. IeOTE (5) NPL 800. CONF 000ENT BIE. E E.EV. NOTE (B) N(RTE ( 2) EESS REF. NO. P 303AO l-EP-NV-58 354 - Control valve' meactor 102 No , No 1 39 18001 1 -AB-PT-58 35A Press Trans. Reactor 102 Yes No P303AO l-E P-2s-58 354 155A Limit Switch peactor 102 Ye s . No . I 19 P303Ao 1-E P-MV-58 35a Control Valve peactor 802 No - No 4 39 N011 l =Ab-P't-58 358 Press Trans. Reactor 102 No En '155A P30 3AO l-E P-2S-58 358 Limit Switch peactor -102 No No 1 39 P30 3AO l-E P-HV-58 36A Control Valve Reactor 102 No No ' l 39 N001 1-AM-PT-5836A H ess Trans. Reactor 102 Yes No - 155A P30340 1-EP-2S-58 36A . Limit Switch . Reactor 102 Yes na n 19 P303AO -I-EP-HV-58 368 Control Valwe Reactor 102 No No I 39-NO El 1 -AD-PT-58 36a Press Trans. -Beactor 102 No . No I%A P30 3AO l-E P-IS-58 36a Limit switch peactor 102 m) No I 19 P303AQ 1-EP-HV-5837A Control valve peacter 102 No km i 19 se001 1-AS-PT-5837A Press Trans. Reactor 102 Yes No 155A P30 3AQ 1 -E P-2 S-58 37A Limit Switch Reactor 102 Yes Ns 1 19 P30 3AQ 1-E P-HV-58 3 71s Control Valwe peactor 802 ** No 1 39 Amendment i3 Revision 3
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' - TAHLE 3.11-5 t
, EQUI PMENT SELECTED FOR HANSH ENVI RONNENT QUALI FICATION Pal D I SYSTENs NAIN STEAN ISO VLV SEAL STS N-72-1 I' EP PAN TNI ACTION I D NO. LOCATIUN DUUI P. PLAN EQUIP.
i' P.O. NOTE (5) ' NPL NO. COpeloseENT BLIC. E l.E V. NOTE (1) NOTE ( 2) EENS REF. NO. s ,i N001 AS-PT-58 37a Press Tranr,. seeactor 102 No No 155A P3B 3AO I-KP-IS-54378 - Limit Sw1tch seeactor . 102 No No 1 39 , . J30lO l -R P-FT-6 P5 3A Flow Trans. Reactor 102 No No 29 1
.J3110 . 1 -E P-Ft-40 5 38 ~ Flow Trans. Reactor 102 No No 29 P 333AO l-EP-SV-6055A - Solenoid valve peactor 77 No No 140 P333AQ 1 -K P-IS-605 5A Position Switch- Reactor 77 No No let t
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^ HCGS FSAR Page 82 of 120 TAHLE 3.ll-5
. EQUI PMENT EELECTED FOR HARSH ENVIRONNENT QUALIFICATION P6t D N-8 3-1 SYSTEM: MEACTOR BLOG. SUPPLY CONTROL DI AG.
GR PAN TNI ACTION I D NO. LOCATIUN EQUIP. PLAN EQULP. P.O. NOTE (St MPL NO. COM MJNENT hl.DG. ElEV. NOTE (1) NOTE ( 2) 1ESS BEF. NO. E7860 IAC-04) Heater Control Panel keacto* 132 m) ' No 100 C7860 18C-043 . Heater Control Pane! Ilheactor 178 No No 100 K7860 ICC-04) Heater Control Panel Iteactor 1 32 No m) 100 K7810 IDC-043 ' Heater Control Panel peactor 54 No No' 100 M7860 IAC-044 Heater Control Panel peactor 162 No No , 100 C7860 lbC-044 Heater Control Panel peactor 17fs .Nu >> 100 E7110 1A-VH-208 Unit Cooler Reactor 54 No No 81 E7!!O IB-VM-208 Unit Cooler aeactor 54 No No 81 '. C7140 IA-VH-209 Unit Cooler. Reactor 54 No No St C71tQ !D-VH-209 Unit Cooler peactor 54 No No 88 K7110 I A-VH- 210 Unit Cooler peactor 54 No No 88 E7 t lO IB-VH-210 Unit Cooler ~ Reactor 54 No - No El M7110 I C-VH- 210 Unit Cooler peactor 54 No No 81 M71 t Q ID-VH-210 Unit Cooler stnac t or 54 No No 81 M71LQ IE-VH-210 Unit Cooler peactor 77 No No 81 M71!O IP-VH-210 Unit Cooler peactor 77 No No Si CDilQ IG-VH-210 Unit Cooler peactor 54 No m) St E7tlO IH-VH-210 ' Uni t Cooler peactor. 54 No No 84 E7810 lA-VH-211 Unit Cooler Peactor 54 No No BL M7tlO I S-V H-211 Unit Cooler . Reactor 54 N0 No 81 27110 I C-VH- 211 Unit Cooler peactor 54 No No St M78 to I D-VH-2L B Unit Cooler leeactor 54 No No St K7110 IE-VH-211 Unit Cooler Reac tor * .. 54. No No 81 M7110 IF-VH-2tl Unit Cooler Reactor 54 No No 81 887180 BC-VH-211 Unit Cooler peactor* %4 No No St R7tlO IH-VH-2Il LAelt Cooler Reactor 54 No No El 9171 30 IA-V-213 Fan & E-H Actuator peactor 112 No No 81 27130. IB-V-213 Fan & E-H Actuatur iteac tor 178 m) No 81 Amensiment 13 Nervieson 3
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EQUI PMENT SELECTED FOR HARSH ENVI RONMENT OUALIFICATION P6t D
- SYSTEM: REACTOR BLOG. SUPPLY CONTROL DI AG. M-8 3-1 GR PAM TMI ACTI ON I D NO. LOCATluN P.O. NOTE ( 5) MPL NO. EQUIP. l'LAN EOulP.
COM PONENT Hl.ic. El.EV. NOTE (t) NOTE ( 2) EESS RFF. NO. E7860 IAC-043 Heater Control Panel Reactor 1 32 No No M1810 IBC-043 100 Heater Control Panel Reactor 178 N No M7860 ICC-04) Heater Control Panel 100 Reactor 132 No No 100
#7860 10C-04 3 Heater . control Pane t Reactot 54 No M7!60 LAC-044 No 100 Heater Control Panet Reactor 162 No M 100
, M1860 IBC-044 Heates Control Panel Reactor 178 No 1A-VH-208 No 100 K1110 Unit Cooler Reactor 54 No
- C7110 IB-VH-208 O 81
- Unit Cooler. Reactor 54 No No M7110 IA-VH-209 81 Unit Cooler Reactor 54 m3 No E7110 IB-VH-209 81 Unit Cooler Reactor 54 No No 587110 IA-VH-210 81 Unit Cooler Reactor 54 No No 81 M1110 18-VH-210 unit Cooler Reactor - 54 No No St M7110 I C-VH- 210 Unit Cooler Reactor 54 No 1D-VH-210 No St M7110 Unit Cooler Reactor 54 No M7110 IE-VH-210 No 81 '
Unit Cooler Reactor 77 No No 88 M711Q IF-VH-210 Unit Cooler Reactor 77 No No . M7110 I C-VH- 210 Unit Cooler Reactor 54 No
- t No 81 M7110 1H-VH-210 Unit Cooler Reactor 54 No No i
M7110 1A-VH-211 88 Unit Cooler Reactor 54 No No 81 M7 t l O IB-VH-211 Unit Cooler Reactor' 54 No No M7110 B C-VH- 211 84 Unit Cooler Reactor 54 No No M7110 ID-VH-211 81 Unit Cooler Reactor 54 No m) M7110 I E-VH-241 81 Unit Cooler Reactor 54 No No 81 M7110 IF-VH-211 Unit Cooler Reactor 54 No No M7810 IG-VH-211 8t Unit cooler. Reactor 54 No No St E7110 IH-VH-211 Unit Cooler Reactor 54 No No M7130 1A-V-213 81 Fan & E-H Actuator Reactor 132 No No 83 M7130 IB-V-213 Fan 6 E-ll Actuator Reactor 178 No No 83 Amendment I) Revielon 3
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HCGS FSAR Page 84 of 120 TABLE 3.11-5 EQUI PMENT SELECTED FOR HARSH ENVIRONNENT OUALIFICATION P61 D +
. SYSTEM: REACTOR BLDG SUPPLY CONTROL DI AC. M-83-1 GR PAM TMI ACTION 1 D NO. LOCATEON EOUt P.
Pa. NOTE IS) MPL NO. PLAN EQUIP. i COM PONENT BLDG. ELEV. NOTE ( 1 ) NOTE ( 2) EESS prF. NO. M7130 IC-V-213 Fan & E-H Actuator Reactor 1 32 No No C7830 1 D-V-213 . Fan & E-H' Actuator 83 Reactor 162 No No 83 I E7130 I E-V- 213 Fan & E-H Actuator peactor 162 No No 317130 I P-v-213 81 ' Fan & E-H Actuator Reactor 178 W No 83 C7110 1A-VH-214- Unit Cooler Reactor 102 No No E7110 18-VH-214 81 Unit Cooler Heactor 102 No No 81 IC-VH-214 M7dlO Unit Cooler keactor 102 No No M7110 ll>-VH-214 81 Unit Cooler Reac tor 102 No C40 81 M730AQ - IA-C-281 Unit Cooler Ctrl Pnt. Reactor 102 No No 9 t ,9 7,9 8,166 , M7:0A0 IB-C-281 Unit Cooler Ctrl Pnt. Reactor 102 No Ms M780AQ IC-C-281- 91.97,98,866 Unit Cooler Ctrl Pnt. heactor 102 No El 91,97,98,166 i M78EAQ ID-C-281 Unit Cooler Ctrl Pnl. Reactor 77 No No 98,97,98,166 ' r I 6 I h Amen 1 ment !J Hewision 3 i i m
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N { (, xj J 1 HCGS FSAR- Page 85 of 120 TAhLE 3.18-5 EQUI PNENT SELECTED FOR HANSH ENVI RONNENT QUALIFICATION P6l D S YSTEM: CHILLED NATER SYSTEM N-83-1 GB I D NO. PAN TNI ACTI ON LOCATION ' EQUIP. PLAN EOulP. P.O. NOTE (5) NPL No. COMMINENT B LIC. ELEV. NOTE (1) NOTE ( 2) FESS REF. NO. N7280 1-GU-SV-9370s Solenoid Valve Reactor 178 No No 517280 1 -GU-2 S-9 3 7 0B - 88 Position Switch Reactor 178 Yes No 69 M780AQ 1 -GU-SV-9 3 7 2A Solenoid Valve Reactor 162 No No 837170 1 -GT-2 5-9 3 7 2A 90 Position Switch Reactor 145 Yes No 86 M780A0 1 -Gu-SV-9 37 2C Solenoid valve Reactor 162 No No 90 E7170 1 -GT-2 S-9 3 7 2C Positton Switch- Reactor 162 Yes No 86
- M7130 1 -GU-FD-9 3 7 7A Flow Damper Actuator Reactor 145 Na No 84
. M700AQ 1 -GU-FT-9 37 7 A Flow Trans. Reactor - 132 No No 99 C78UAQ 1-GU-PDT-9 377A Press. Diff. Trans. Reactor 132. No No 99
- M780AQ 1 -GU-TE-9 3 7 7A Teesp. Elem t . Reactor 132 No No 93 R780AQ 1 -GU- PDSH-9 37 7Al Press. Diff. Sw. High Reactor 132 No No M7170 1 -GU-H I)-9 3 7 7 A-1_
92 Hand Damper Actuator Reactor 132 No No 87 M7170 1 -GU-H D-9 377A- 2 Hand Damper Actuator Reactor 145 No Ei 87 G781AQ 1 -GU-FS L-9 37 7AA Flow Sw. Low Reactor 132 No No 92 I:780AQ 1 -GU-FSL-9 37 7AB Fl ow Sw. Low Reactor 1 32 No No 92 N7130 1 -GU-FI)-9 37 78 Flow Damper Actuator Reactor 145 No No - 84 R700AQ 1 -GU- FT-9 37 78 Flow Trans. Reactor 178 No No 99 M7E0AQ 1 -G U- PDT-9 t? ? B Press. Di f f . Trans. Reactor 178 No 1 -GU-TE-9 3 778 No ' 99 M780AQ Temp. Elemt. Reactor 178 Iso ' No 9)
- M782AQ 1 -GU-PDSH-9 37 7H1 Press. Diff. Sw. High Reactor. 178 No No 92 E7170 1 -GU- HD-9 377P-1 Hand Damper Actuator Reactor 1 78 No No 87 Ame n.lme n t 13 Revision 3 1
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m 6 . E. () r , v HMIS FSAR Page 56 of 120 TABLE 3.11-5 EOUI PMENT dELECTED FOR HARSH ENVIRONMENT QUALI FICATION P61 D SYSTE:!s CHILLED WATER SYSTEM M-83 ' GB PAM TMI ACTION I D NO. LOCATION t,0UI P. PLAN EQUIP. P.O. NOTE (5) MPL NO. COM PONENT RLDG. E IEV. NOTE (1) NOTE ( 2) EESS REF. NO. I!7170 1 -GU-H D-9 3 7 7B- 2 Hand Damper Actuator Reactor 178 No No H7
.. M78 0AO . 1 -GU-FS L-9 37 7BA Flow Sw. Iow Reactor 178 No No 92 M700AQ' l-GU-FS t.-91778u Flow Sw. Low Reactor 178 No No 92 E7130 1-GU-F D-9 37 7C ' Flow Damper Actuator Reactor 145 No No 64 C780A0 1-GU-FT-9377C Flow Trans. 132 No No 99 %
G780A0 1-GU-PDT-9377C Press. Diff. Trans. Heactor Reactor ' 132 No flo 99 c7Z0A0 1 -GU-TE-9 3 7 7C - Temp. Elemt. Reactor 1,2 No No 93 M780A0 1 -GU-PDSH-9 37 7Cl Press. Dlf f . Sw. High Reactor 132 No No 92 K717Q 1 -GU-H D-9 3 7 7C-1 Hand Damper Actuator Reactor 1 32 No No 87 M7170 1 -GU-H D-9 37 7C- 2 Hand Camper Actuator Reactor 14% No No 67 E7:0AQ 1 -GU- FS L-9 3 7 7C A Flow Sw. Low Reactor 132 No. No 92
%781AQ 1 -GU-FS L-9 37 7CB Flow Sw. Iow Reac tor 132 No No 92 M7130 1-GU-FD-9377D Flow Damper Actuator Reactor 145 No No 84 51780AQ 1-GU-FT-9377D Flow Trar.s. Reac tor 162 No No 99 r700AQ 1 -GU-FDT-9 3 77 D . Press. Diff. Trans. Reactor 162 No No 99 %780A0 1 -GU-TE-9 377D Temp. Elemt. Reactor 162 No No 93 M780AQ, 1 -GU- PDSH-9 37 7D) Press. Difl. Sw. High- Reactor 162 No No 92 M7170 1 -GU-H D-9 37 7 D-1 Hand Damper Actuator Reactor 162 No No 67 M7170 1 -GU-H D-9 37 7 D- 2 Hand Damper Actuator Reactor. 162 No No 87 M780A0 1 -G U-FS L-9 37 7DA Flow Sw. Iow Reactor 162 No No 92
- M780A0 1 -GU-FS L-9 377DB Flow Sw. Low Reactor 162 No No 92 Amendment 13 Revision 3 W t
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EQUI PMENT SELECTED FOR HARSH ENV1 RONMENT QUALIFICATION Psi D CYSTEM: CHILLED WATER SYSTEM M-83-1 GB I D NO. PAM TMI ACTIGN LOCATEON EQUIP. PLAN EOut P. P.O. NOTE (5) MPL NO. COM PONENT Bl.tM;. Et.EV. NOTE (1) NOTE ( 2) EESS RFF. NO.
. 35713Q ' l-GU-FD-9 377E Flow Deeper Actuator peactor 145 No Mc 84 E780AQ 1 -GU-FT-9 37 7E . Flow Trans. Re ac t or 162 No No 99 E7EGAO l-GO-PIYT-9 37 7E Press. Diff. Trans. Reactor 162 No No 99 M780AQ 1 -GU-TE-9 37 7E Temp. Elast. Reactor 162 No M780AQ 1-GU-PDSH-9377El No 93 Press. Di f f. Sw. High Reactor 162 No No 92 M7170 1 -GU-H D-9 37 7 E-1 Hand Damper Actuator Reactor 162 No No 87 8:7170 1 -GU-H D-9 37 7E- 2 Hand Damper Actuator Reactor 162 No No. 87 M7130 1 -GU-FD-9 37 7F Flow Damper Actuator Reactor 145 No No 64 St?20AQ 1 -GU-FT-9 37 7F Flow Trans. Reactor 178 No No 99 M78!AQ 1 -Gu-PDT-9 3 7 7F Press. Diff. Trans. Reactor .178 No No 99 M730A0 1-GU-TE-9377F Temp. Elemt. Reactor 175 No No 95 C:78!AQ 1 -GU-PDS H-9 37 7FI Press. Diti. Sw. High Reactor 178 No No 92 5
M7170 1 -GU-H D-9 37 7F-1 Hand Damper Actuator Reactor. 162 No No 87 4 M7170 1 -GU-H D-9 37 7 F- 2 Hand Damper Actuator - Heactor B78 No No 87 0:7t0A0 1 -GU-TE-9 37 8 A Temp. Elemt. Reactor 132 No No 93 M780AQ ,1 -GU-TE-9 37 8B Te mp. Elemt. . Reactor _ 178 No No 93 M780AQ 1-GU-TE-9378C Temp. Elemt. Reactor 1 32 No No 93 M780AQ 1 -GU-TE-9 37 8 D Temp. Elemt. Reactor 162 No No 93 M780AQ 1-Gu-TE-9 378E Temp. Elemt. Reactor 162 No No 93 M73EAQ 1 -GU-T E-9 3 7 8 F Temp. Elemt. Reactor 178 No No 93 q Amendment 13 kevision 3 4I i d S d 9
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EQUI PMENT SELECTED FOM HARSH ENVE RONMENT OUALI FICATION P& R D S YSTEM: ChlLLED NATER SYSTEM M-8 3-1 GN I D NO. PAM TME ACTSON P.O. NOTE (5) LOCATION EOU S P. M PL NO. COM PONE NT h t.DG. PLAN EQUIP. ElEV. NOTE (1) NOTE (2i EESS kEF. NO. M720AQ l -GU-ME-9 379A Molsutre Trans. 88710A0 1 -GU-MT-9 379 A Neactor 1 32 No N Molsture Trans. Reactor 165 R7160 1 -GU-MY-9 3 79 A i 32 No No l65 33730AQ 1 -GU-M E-9 3 798 D6oisture Controller (SCN) Heactor i 32 h No Molsture Trans. heactor 178 det* LOO % % M710AQ 1 -GU-MT-9 3 798 No No
.R7260 Molature Trans.. keactor 178 No No 165 1 -GU-M Y-9 3 79H 165 N780AQ 1 -GU-ME-9 3 79C Misture Conta o!!wr (SCR) Neactor 178 No No 9720AQ 1 -GU-MT-9 379C Moisture Trans. Re actor 1 32 h No 44$ 10015r >-
Monsture Trans. bactor 165 M7260 1 -GU-MY -9 3 79C 132 No N 165
+ C710AQ ~ 1 -GU-M E-9 379 D Moisture Controller (SCM) Heactor 1 32 No No set (O O 4-b -
McLature Trans. Reactor 162 No
-27EGAQ 1 -Gu-MT-9 3 79D h iature Trans. No ' 165 M78tQ 1 -GU-M Y-9 3 79D koactor 162 M No 165 M7EUAQ 4 -Gu-ME--9 3 79E m isture Controllr (SCH) 'Heactor 162 Nu No 144000 W M7!OAQ I -GO-M T-9 3 7 9 E Molstuse Trans. heactor 162 No No Moisture Trans. 165 M7810 1 -GH-M Y-9 379 E Heactor 162 No No 865 M7EZAQ 1 -GU-M E-9 3 7 9F Moisture Controller (SCH) Reactor .162 h No A#p 100 Q n710A0 m isture Trans.' Heactor 178 No I-Go-MT-9 3 79F m isture Trans. No , 865 #731Q 1 -GU-M V-9 3 7 9 F kesctor 178 No No 165 M7EGAQ 1 -G N-HS-9 38 t A Molature Cont roller (SCH) peactor 178 No No M720AQ 1 -GR-TE-9 !al A Hand Switsch kv ac t or 102 No M w 60 0 Ac h Temp. Blust. 96 M7EGAQ l-GN-TS-9 3dl A Reactor 54 No No ' 9i Temp. Sw. Neactor 54 M730AQ 1-GN-FSL-9 39t Al No No .
Flow Sw. Low Huactor 54 No 95 No 92 Amernstmen t i1 Nev&sion 3 i A-w Fs A R. Ane ,,.t.teo l 4 cp ,,7 gg,o,, T ag .
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- SYSTE*ls CHILLED WATER SYSTEM M-83-1 Ga' l, 1 D NO. PAM
- TNI ACTION LOCATION EQUEP. PLAN EOtl1P.
P.O. NOTE (5) MPL NO. COMPONENT HlDC. ElEV. NOTE (1) NOTE ( 2) EESS REF. NO. j E780A0 1 -GR-FSL-9 381 A3 Plow Sw. Low Heactor 54 No 1 ' t:78 0AQ 3 -GR-HS-9 38 t B No 92 Hand Switch Reactor 102 No No M780A0 1 -GR-TE-9 381 s Temp. Elemt, 96 heactor 54 No No 93 K780AQ - 'l-GM-TS-93818 Temp. Sw. Reactor 54 No No
.M730AQ 1-GR-FSL-9 38181 95 Flow Sw. Low Reactor 54 No No . 92 M781AQ 1 -GR-FSL-9 38 t b3 Flow Sw. Iow Reactor 54 No M780A0 ! <R-H S- 9 38 2A No 92 Hand Switch Reactor 102 No No 96
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, C780A0 1-GR-HS-93838 Hand Switch Re ac tor 102 No No 96 C700A0 1 -GR-TE-9 38 38 Temp. Elemt . Reactor 54 No No 93 M780A0 1 -GR-TS-9 38 3u Temp. Sw. Reactor 54 No No 95 M780A0 1 -GH-FS L-9 38 3bt Flow Sw. Iow Reactor' 54 No No 92 M72fAO l -G R- PS L-9 38 3B 3 Plow Sw. Low Reactor 54 No No 92 M78?AO l-GR-HS-9 38 3C Hand Switch Reactor 102 No No 96 M780A0 1 -GR-TE-9 38 3C Temp. Elemt. Reactor 54 No M78!AO l-GR-TS-9381C No 93 Temp. Sa. Reactor 54 No No 95 M780A0 1-Gk-FSL-9 38 3Cl Flow Sw. Low Reactor 54 No No 92 H78?AO l-GR-PSL-9 38 3C3 Flow Sw. Iow Reactor 54 No No 92 . M7f0A0 1-GR-HS-93830 Hand Switch Reactor 77 No No 96.
M780AO l-GR-TE-9 38 3D . Te mp . Elemt. Reac tor 54 No : No 93 M780A0 1-GR-TS-9383D Temp. Sw. Reactor 54 No No 95 M780A0 1 -GR-FS L-9 38 301 Flow Sw. law Reactor 54 No No 92 Amerw1 ment 13 Revision 3
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- 120AQ 1 -GR-TE-9 38 3E No 96
' Temp. Elemt. keactbr 77 No No M78!AQ 1 -GR-TS-9 38 3E Temp. Sw. 93 Reactor 77 No No 95 C780AQ 1 -GR- FSL-9 38 3El Flow Sw. Low heactor 77 No 2780AQ 1 -GR-FS L-9 38 3E 3 Plow Sw. Low No 92 peactor 77 No No 92 0780AQ 1 -GR-HS-9 38 3F Hand Switch Reactor 102 No No 96 M78IAQ 1 -GR-TE-9 38 3F Temp. Elemt. Reactor 77 No 31780AQ 1-CR-TS-9383F No $3 Temp. Sw. Reactor 77 No No 95 M781AQ 1 -C R-PS L-9 38 3 F1 Flow Sw. Irw Reac tor 77 No No 92 M78IAQ 1-GR-PSL-9 38 3F3 Flow Sw. law Reactor 77 No C780AQ 1 -GR-HS-9 38 3G Hand Switch No 92 Reactor 102 No No 96 C787AQ 1 -GR-TE-9 38 3G Temp. Elemt. Reactor 54 'No No 93 L 82780AQ 1 -GR-TS-9 38 3G Temp. Sw. Reactor 54 '80 No 95 0780AQ 1 -GR-PSL-9 381G1 Flow Sw. Iow Reactor 54 No No C780AQ 1 -G R-FS L-9 38 3G 3 92 Flow Sw. Inw Reactor 54 No No 92 M780AQ 1 -GR-HS-9 3 8 3H Hand Switch Reactor ' 77 No No M787AQ 1-GR-TE-9383H 96 Temp. Elemt. Reactor 54 No No 93 M7E0AQ 1-GR-TS-9 38 3H Temp. Sw. Reac tor $4 No No 95 M78CAO 1 -GR-FS L-9 38 3H1 Flow Sw. Iow Reactor 54 No No 92 M780AQ 1 -GR-FSL-9 38 3H 3 Plow Sw. Low. Reactor 54 No No M780AQ 1-CR-HS-9384A 92 Hand witch Reactor 102 No No 96 M7XGAQ 1 -GR-TE-9 30 4 A Temp. Elemt. Reac tor 54 No No M710AQ 1-CR-TS-9384A 93 Temp. Sw. Reactor 54 No No 95 0780AQ 1 -GR-FSL-9 38 4 A1 Flow Sw. Low Reactor $4 No No 92 M720AQ 1 -GR-PSL-9 38 4 A3 Flow Sw. Iow React or 54 No No M780A0 1 -C R-H S-9 3 8 4 B 92 Hand Switch Reactor 102 No No 96 M780AQ 1 -GR-TE-9 38 4 B Temp. Elemt. Reactor 54 No No 93 1-Amenilment I3 Revision 3
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I ~k v-l HCGS FSAR Page 92 of 120 TABLE 3.11-5 EOut PnENT SELECTED FOR HARSH ENV1 RONMENT QUALIF1 CATION P61 D - SY3 TEM: REACTO# BLDG. SUPPLY CONTROL DI AG, M-8 3-1 GR PAM TMI ACTION I D NO. LOCATION EQUE P. PLAN EOutP. P. O . NOTE (5) M PL NO. COM PONE NT BLDG. ELEV. NOTE (1) NOTE ( 2) EESS REF. NO. M780A0 1 -G R-TS-9 38 4B Temp.'Sw. Re actor 54 No No 95 E780A0 1 -GR-FS L-9 38 4 BI Flow Sw. Low Reactor 54 No No 92 5780A0 1 -G R-FSL-9 38423 Plow Sw. Low Reactor 54 No No 92 Ct?80A0 1 -G R-HS-9 38 4C Hand Swit.ch Reactor 102- No No 96 E780A0 1 -C R-TS-9 38 4C Temp. Sw. Faactor 54 No No 95 M780A0 1 -G R-TE-9 J8 4C Temp. Elemt. Reac t or 54 No No 93 M780A0 1-GR-FSL-9384Cl Flow Sw. Low Re ac tor 54 No No 92 - 2780A0 1 -G R-FS L-9 38 4 C3 Flow Sw. ImW Reactor 54 No No 92 M780A0 1 -GR-H S-9 38 4 D Hand Switch Reactor 77 No No 96 M?8 TAO 1-GR-TE-9384D Temp. Elemt. R9 actor 54 No No 93 Cll80A0 1 -CR-TS-9 39 4 D Temp. Sw. Re ac t or 54 No No 95 M780A0 1 -GR-FS L-9 38 4 D1 Flow Sw. Low Reactor 54 No No 92 A780A0 1 -GR-FSL-9 38 4 03 Plow Sw. Low Reactor 54 No No 92 M787AO l-GR-HS-9 38 4 8 Hand Switch . Reactor 102 No No 96 R780A0 1 -GK-TE-9 38 4E Temp. Elemt. Reactor 54 No No 93 C780A0 1-CR-TS-9384E Temp. Sw. Reactor 54 No No 95 M780A0 1 -GR-FSL-9 38 4E1 Plow Sw. Low Reactor 54 No No 92 C780A0 1 -G R-FS L-9 38 4 E 3 Flow Sw. Low Reactor 54 No No 92 M780A0 1 -GR-HS-9 38 4 F Hand Switch Reactor 102 No No 96 C780A0 1 -GR-TE-9 38 4 F Temp. Elemt. Reactor 54 No No 93 M780A0 1 -GR-TS-9 38 4F Temp. Sw- Reactor 54 No No 95 - 2780A0 1 -GR-FS L-9 38 4 F1 Plow Sw. Low Reactor 54 No No 92 5780A0 1 -GR-FSL-9 38 4F3 Flow Sw. Low Reactor 54 No No 92 2780A0 1 -GR-HS-9 38 4 G Hand Switch Reac tor 102 No No 96
'M780A0 1 -GR-TE-9 38 4 G Temp. Elemt. Re actor $4 No No 93 M787AO l -C R-TS-9 38 4 G Temp. Sw. Reactor 54 No No 95 M780A0 1 -GR-FSL-9 38 4Gl Flow Sw. Low Reactor 54 No No 92.
Amen.tment 13 Revision 3 _ - ~
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HCGS FSAR Page 93 of 120 TABLE 3.11-5 4
' EQUI PMENT SELECTED POR HANSH ENVIRONNENT OUALI FICATION . P61 D SYSTEM: REACTOR BLDG. SUPPLY CONTROL DI AG.
M-83-1 GR PAM TMI . ACTION 1 O NO. LGCATION EQUEP. PLAN EQulP. P.O. No'TE (5) M PL NO. COM PON E NT HLDG. ELEV. NOTE (1) NOTE ( 2) FESS BEF. NO. C78;AQ 1 -GR- FSL-9 38 4G3 Flow Sw. Low Re,ector 54 No No 92 E7 MAO l-G R-HS-9 38 4 H Hand Switch Reactor 77 No No 96 M780A0 1-CR-TE-9384H Temp. Elemt. Reactor 54 No No 93 C780A0 1 -G R-TS-9 38 4 H Temp. Sw. Reactor 54 No No 95 278IAQ 1 -GR-PS L-9 38 4H1 Flow Sw. Low Reactor 54 No No 92 E78IAQ ' l-GR-FSL-9 384H 3 Flow Sw. Low Reactor- 54 No No 92 M780AQ 1 -G R-H S-9 38 5A Hand Switch Reactor 102 No No 96 M78tAQ 1 -G R-TE-9 38 5A Temp. Elemt. Reactor 102 No No 93 M7MAQ 1-GR-TS-9385A Te mp . Sw. . Reactor 102 No No 94 M780A0 1 -GR-FSL-9 38 5Al Flow Sw. Low Reactor 102 No No 92
=7E0A0 1 -C R- PS L-9 38 5A 3 Flow Sw. Low Reactor 102 No No 92 63780AQ 1 -GR-HS-9 38 5B Hand Switch Raactor 102 No No 96 R780AQ 1-GR-TE-9 38 58 Temp. Elemt. Reactor 102 No No 93 K780A0 1-GR-TS-93858 Temp. Sw. Reactor 102 No No 94 M700AQ 1 -G R-FS L-9 38 5HI Flow Sw. Low Re actor 102 No No 92 M78%AQ 1 -GR-FS L-9 38 583 Plow Sw. Iow Reactor 102 No No 92 1
Amendment 13 Revision 3 L 1 i
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d HCGS FSAR TABLE ).!!-5 Page 94 ut i 2d EQut PMENT SEL.ECTED FOR HANSil ENV1 NONMENT QUALL FlCATEON P68 D SYSTEMS REACTON BLDC. SUPPL 1 CONTROL DI AG. M-8 3-1 GR 10 NO. PAM TMt ACTION 1.OCAftON equip. Pl.AN EDULP. P.O. NOTE (5) MPl. NO. COM PONENT H l.f MI. ELEV. NOTE (l) NOTE 12) EESS REF. NO. M7t?AQ 1 -GR-HS-9 385C Hand Switch Reactor 77- No No 96
.E7tIAQ 1 -G R-TE-9 38 5C . Temp. Elemt. bactor. 102 No C78IAQ 1 -G k-TS-9 38 5C Temp. SW. No 93 keector 102 No No 94 C7MAQ I -CH-FSL-9 38 5Cl Flow Sw. Low Reactor 102 No nl:0AQ I -GH- FSL-9 38 5C 3 No 92 Flow Sw. Low keactor 102 h ' No R78:AQ 1 -C H-H S-9 38 5 D hand Switch 92 Reactor 77 No M 96 M780A0 1-CN-TE-9 3850 Temp. Elemt. kuactor 102 No No 93 R780AQ 1-GR-TS-9385D Temp. Sw. Reactor 102 h M7E0AQ R-GN-FSL-9385DI No 94 Flow Sw. Law kometor 102 No No M720AQ 1 -GM-FS L-9 38 503 Plow Sw. Low 92 Reactor 102 No No 12 J 3210 1-GU-PT-9194A Flow Trans. keactor L )2 JJ010 1 -GU-F T-919 48 h No 29 Flow Trans. Heactor 178 No . No 29 J 3210 1 -Gu-FT-919 4C Flow Trans. Reactor 1 32 N J 3010 1 -GU-FT-9 49 4 D No 29
' Flow Trans. Iteac tor . 162 . No No 29 J3010 l-Gu-FT-9394E Flow Trans. koactor 162 No I
J30lO l -GU-FT-919 4 F No 29 Flow Trans. Reactor 178 No No 29 M7EUAQ 1 -GU-SV-9 39 5A Solenoid Valve keector lie No No -90 C1170 1 -GU-2 S-9 39 5A Position Switch Reactor 178 No R-GU-SV-93958 No 86 M710AQ SolefKnid Val-e peactor !78 No No - 90 E1170 1-GO-IS-9 39 58 Positson Switch hoac tor 178. No MPE0AQ 1-GU-ME-9425A No 86 Moisture Trans. Reactor 145. No No 165 M730AQ 4 -GU-M T-9 4 2 5A Moisture Trans. keector 145 No No 165 27E60 l -Gu-M Y-9 4 25A Mol t re Contcoller (SCN) Heactor 145 No n?80AQ 1 -GU-M E-9 4 2 58 No Def 100 b 4 Moisture Trans. Reac t or 145' No No 165 M7EGAQ 1-GU-MT-94258 Moisture Trans. Hoactor 845 No E7310 1 -G U-M Y-94 2 5p No 165 Moisture Controller (SCR) Reactor 145 No . No *44$-lO O $ h Ameniment 43
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.. Qn,1 .hv l-HCGS FSAR TABLE 3.11-5 Page.95 of 120 S YSTE,*.
REAC BLDG EXH CONTRL EQUI PMENT SELECTED FOR HARSH ENVI RONMENT OUALIFICATIONP6tD ' GU M-84-1 ' I D NO. PAM P.O. NOTE 15) LOCATION. TMI ACTION MPL NO. ' COMPONENT EUUIP. Rt.DG . ELEV. PLAN EQUIP. M7E60 RAC-045 NOTE (I l' NJITE (2) EESS REF.'NO. 27!60 18C-045 Heater Control Panet Reactor i IS No ) 57130 IA-V-206 Heater Control Panel Reactor !45 No
'No 100 E7130 IB-V-206 . Fan & EH Actuator Reactor '145 No 100' Fan & EH Actuator No No G7280 1-GU-SV-9414A Reactor 145 83 417280 1-GU-zS-9414A solenoid Valve Reactor 1 78
. No No 83 M7280 1 -GU-SV-9 4148 Position Switch' React or 175 No No 88 M7280 1-GU-ss-94148 Solenoid Valve Reactor. 178 Yes No 89 Position Switch No No
~ J33tO l-GU- FT-9 4 25A React or 178 88 M78DAO l-GU-PDT-9425A Flow Trans. . Reactor 145 Yes No 89 No 487C0A0 1 -GU-TE-9 4 25A Press. Diff. Trans.
Temp. Elemt. Reactor 145 No No 29 M717C No 99 1 -GU-H D-9 4 25Al Hand Damper Actuator keactor 145 No No C7170 1 -Gu-?ID-9 4 25A 2 Reactor 162 No 93 G7170 Hand Damper Actuator No 1 -GU-f D-9 4 2 5A3 Flow Damper Actuator Reactor 145 No No 87 M7170 1-GU-FD-9425A5 Reactor 145 87
- ' J 3140 1 -G U-FT-9 4 2 58 Flow Damper Actuator Reactor 145 No No 87 Flow Trans. No No M710A0 1 -GU-PDT-9 4 258 Reactor 145 87 Prvas. Diff. Traas. No No M780A0 1 -GU-TE-9 4 2 58 keactor 145 No 29 Temp. Elemt. No 99 C7173 1 -GU-H D-9 4 ? $81 Reactor 145 No M7470 Hand Damper Actuator No 93 1 -GU-H D-9 4 2 582 Hand Damper Actuator Reactor I62 No No K7170 1 -GU-FD-9 4 258 3 Reac tor 145 No 87 M7170 Plow Damper Ac tuator Reactor No 87 1 -GU-FD-94 2585 Flow Damper Actuator 145 No No M7130 1 -GU-FD-9 426A Reactor 145 87 Flow Damper Actuator No No
, R720A0 1 -GU-FT-9 4 2 6A Reactor 145 87 Flow Trans. No No M7:0A0 1 -Gu- FS L-94 26Al Reac to r 145 84 Flow Sw. Low No No 99 G780A0 1 -GU-PDT-9 4 26 Al Reactor 145 No C710A0 trGU-PSL-9 4 26A2 Press. Diff. Trans. Reactor 102 No No 92 M78fAO l -GU-PDT-94 26 A2 Flow Sw. Low Reactor 145 No 99 Press , Dif f . Trans. No No Reac tor 102 92 No hu 99 Amendment 13 Revision 3-
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L x , HCGS FSAR' Page 96 of 120 TAHLE 3.11-5 EQUI PMt;NT SELECTED FOR HARSH ENVI RONMENT QuALI FICATION Phl D . SYSTEM: REAC BLDG EXH CONTRL ' GU M.b4-1 I D NO. PAM . TMI ACTION >
' LOCATION EQUIP. PLAN FQUIP.
P.O. NOTE (5) MPL No. COMPONENT HLDG. El.EV . NOTM (1 ) NOTE (2) FESS REF. No. .- a E7860 1AC-045 Heater Control Panel Reactor - 145 No No 100 C7 0 ',o 18C-045 Heater Control Panet Reactor- 145' No No , 100 8171 30 1A-V-206 Fan & EH Actuator Reactor 145 No No 83
- M7130 10-V-206 Fan & EH Actuatorx Reactor 145 No No 81' i 57280 1-GU-SV-9414A Solenoid Valve Reactor 178 No No Sn
.C7280 1-GU-2S-9484A Pos! tion Switch Reactor 178 Yes No 89 537280 1-GU-SV-94146 Solenold Valve Reactor.- 178 No No 88 M7280 1-GU-2S-94143 Position Switch Reactor 178- Yes No 89 J 3010 1-GU-PT-9425A Flow Trans. Re ac tor 145 No- No . 29 M780AQ 1 -G3-PDT-9 4 2 5A Press. Dif f. Trans. Reactor 145 No No 99
- 73IAQ 1-GU-TE-9425A Temp. Elemt. keactor 145 No No 93 M7170 - 1 -GU-H D-9 4 2 5 Al Hand Damper Actuator Heactor 162 No No 87 '*
M7170 1 -GU-Hl>9 4 25A 2 Hand Damper Actuator Reactor. 145 No No 87 E7170 1 -GU-FD-9 4 25 A3 ' Flow Damper Actuator Reactor 145 No No 87 4 827170 1-GU-FD-9425A5 Flow Damper Actuator Reactor 145 No No 87 J)0lO l-GU-FT-9425H Flow Trans. Reactor 145' No No 29
- M780A0 - 1 -GU- PDT-9 4 258 Press. Diff. Trans. Reac tor 145 Mo No 99 i
i K78tAQ 1 -GU-TE-9 4 2 5H Temp. Elemt. Reactor 145 No .No 93 3 M7170 1 -GU-HIN9 4 25H1 Hand Dager Actuator Reactor 162 No No 87 M7170 1 -GU-H D-9 4 25H2 Hand Damper Actuator Reactor 145. No No 87 . E7170 1 -GU- FD-9 4 25H 3 Plow Damper Actuator- React or 145 No No 87 M7170 1 -GU-F D-9 4 25H5 - Flow Damper Actuator Heactor 145 No No 87 i M7130 1 -GU- FD-9 4 26A Flow Damper Actuator Reactor 145- No No 84
! M18tAQ 1-GU-FT-9426A Flow Trans. Reactor 145 No No 99 .
1 i'700AQ I-GU- FS L-9 4 26Al Flow Sw. l.ow Reactor 145 No NG 92 M780AQ 1 -G U-PDT-9 4 26 Al Press. Dit t . Trans. keactor. 102 No No 99 i M7EGAQ 1 -GU-FS L-9 4 26A2 Flow Sw. Low Reactor 145 No No 92 i ,SI?8?AQ 1-GU-PDT-9426A2 Press. Diff. Trans. Reactor. 102' No No 99 AmenElmen t 11 i Revision 3 f 1 I
rr~ _ 1 p~ . V V U HIMS FSAR page 'g7 og . I 20 TAHLE 3.11-5 EQUI PMENT SELECTED FOR HARSH ENVI RONNENT OhALI F3 r.ArgUN ' P610 SYSTEM: EEAC BLDG EXH CONTRL GU M-84-1 PAM TNI ACTION, 1 D NO. 14CATlON EQUI P. PLAN EQUIP. j P.O. NOTE (51 MPL NO. COMPONENT B LIC . Etr/. NOTE (11 NOTE (21 EESS REF. NO. C71 }Q 1-GU-FD-9426B Flow Damper Actuator Reactor 145 No - No 84-K787AO 1-GU-FT-94268 Flow Trans. Reactor 145 No No 99 , M780A0 1 -GU-F3 L-9 4 2681 Flow Sw. Low Reactor 145 No No 92 E781AO l-GU-PDT-9426B1 Press. Diff. Trans. Reactor 102 No No 99 H780AQ 1 -GU-FSL-9 4 268 2 Flow sw. Low Reactor 145 ' No No 92
'C710A0 1 -GU-PDT-9 4 2 682 Press. Diff. Trans. Reactor 102 No No '99 C180AQ 1-GU-HS-9428-1 Hand Switch Reactor 102 No No 96 C780AQ 4 -GU-PDSH-9 4 28-1 ' Press. Dif f . Sw. High Reactor 102 No No 92 M7C0A0 1-Gu-TE-9428-1 Temp. Elemt. Reactor 102 Nu No 91 %78IAO l-GU-HS-9 4 28- 2 Hand Switch Reactor 102 Nt. No 96 M710AQ 1 -GU- PDSH-9 4 28 - 2 Press. Ditt..Sw. High Reactor 102 No No 92 M7:0AQ 1-GU-TE-9428-2 Temp. Elvet. Reac t or 102 No No 91 K7170 1 -GU-PD-9 4 28Al . Press. Damper Actuator Reactor 102 Nu No - 85 E7170 1-GU-zS-9428A1 Position Switch Reactor 102 No No 86 M7170 1 -GU- PC-9 4 28A 2 Press. Damper Actuator Reactor 102 No No 85 M7170 1-GU-2S-9428A2 Position Switch Reactor 102 No No 86 C7170 1 -GU- PD-9 4 28H1 Press. Damper Actuator- Reactor 145 No No 85 57170 1-GU-2S-942F31 Position Switch Reactor 145 No No 86.
M7170 1 -GU- PD-9 4 2b82 Press. Damper Actuator peactor 145 No No 85 C7170 1 -GU-3 S-9 4 28 82 Position Switch Reac t or 145 No No 86 Ct7 3.0AQ 1 -GU-H S-9 4 29-1 Hand Switch Reactor 102 No No. 96 i K78"AO l-GU-PDSH-9429-1 Press. Diff. Sw. High. Reactor. 145 No No 92 , M710A0 1 -GU-TE-9 4 29-1 . Temp. Elemt. ' Reactor 145 No No 93 E780A0 1 -GU-H S-9 4 29- 2 Hand Switch . Reac tor 77 No No $6
- M780A0 1 -GU- PDSH-9 4 29 -2 Press. Diff. Sw. High Reactor 145 .1o No 92 M780AQ 1 -GU-T E-9 4 29- 2 Temp. Elemt. Reac t or 145 No No 9)
M7170 4 -GU- P!P 9 4 29 Al Press. Damper Actuator Reactor 145 No No 85 E7170 1-GU-IS-9429Al Position Switch Reactor 145 No No 86 Amn.* men t 13 Revision 3
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4 5 HCGS FSAR TABLE 3.11-5 l'<,;e 9 8 of 120 S YSTEX: REAC BLDG EXH CONTRL EQUI 8 MENT SELECTED FOR ifARSH ENVI RONMENT QUALI FICATION d6t D GU M-84-1 , I D NO. PAM TM1 ACTION - t>A' ATE ON EQUIP. PLAN EQUIP. a P.O. NOTE (5) MPL NO. COMPONENT HLtd. E!JV. NOTE (1 ) NOTE (2) EESM REP. NO. M7470 1 -GU-PD-9 4 29A2 Press. Damper Actuator Reactor 145' M1170 No No 85 1 -G U-IS-9 4 2 9 A2 Position Switch Reactor 145 No No ~86 E780AQ 1-GU-HS-9432-1 Hand Switch Reactor 102 No G78IAQ 3-GU-PDSH-9432-1 No 96 Press. Diff. Sw. High Reactor 54 No No 92, K7:0A0 1-GU-TE-9432-1 Te mp . Elemt. Re ac tor 77 No - E78:AQ 1-GU-MS-9432-2 No 93 Hand Switch Reactor 102- No No 96 C7 00AQ 1-GU-PDSH-94 32-2 Press. Diff. Sw. H!gh Reactor 54 M780AQ 1-GU-TE-9432-2 Temp. Elemt. No. No 92 Reac tor 77 No No 93 M7173 1 -GU-PD-9 4 3 2Al Press. Damper Actuator Re actor 77 No G7170 1-GU-2S-9432A1 No ' 85 Position Switch Reactor- 77 No No 86 M7170 1 -GU-PD-94 32A2 Press. Damper Actuator Re ac tor 77 No M7170 1 -GU-IS-9 4 3 2A2 No 85 Position Switch Reactor 77 No No 86. M7170 1 -GU-PD-9 4 3 2B1 Press.' Damper Actuator Reactor 54 No No 85 M7470 1 -GU-2 S-9 4 3 281 Position Switch Reactor 54 No i C7170 1 -GU-PD-94 3 2H2 Press. Deeper Actuator No 86
~ Reactor 54 No No 854 M7170 1 -GU-2 S-9 4 3 2B2 Position Switch Reactor 54 No .M780AQ ! <.0-MS-9 4 3 3-1 Hand Switch No. 86 Reactor 102 No No 96 G700A0 1 -G U-PDS H-9 4 3 3-1 Press. Diff. Sw. High Reactor 54 No No 92 M780A0 1 -GU-TE-94 31-1 Temp . Elemt. Reactor 77 No . No E700A0 1 -GU-HS-9 4 3 3-2 93 Hand Switch Reactor - 77 No No 96 M7ZOAQ 1 -GU- PDS H- 9 4 3 3- 2 Press. Diff. Sw. High Reactor 54 No i
M78!AQ 1-GU-TE-94 31-2 No 92 Temp. Elemt. Reactor 77 No No G7170 1 -GU-PD-94 3 3Al Press. Damper Actuator 93-Reactor 54 No No 85 K7170 4-GU-ES-9433Al Position Switch iteactor 54 No No M7170 1 -GU- PD-9 4 3 3A2 86 Press. Damper Actuator Reactor 54 No No- 85 K7170 1 -GU-IS-9 4 3 3 A2 Poeition Switch Reactor 54 No Nn C7170 1 -GU- PD-9 4 3 3B1 86 Press. Damper Actuator Reactor 77 No No 85 M7170 1 -GU-IS-9 4 3 381 Position Switch Reactor 77 No No 86 Amendment. 13 Hevision 3 l j
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.(f 'V HCGS FSAR. page 99 og g20 TABLE 3.11-5 EQUI PMENT SELECTED FOR HARSH ENV! RONMENT QUALI FICATION Phl D j SYSTEM: EEAC BLDG EXH CONTRL GU M-84-t PAN TM1 ACTION I D NO. IDCATIUN EOUI P. PLAN EQUI P.
P.O. NOTE (5) MPL NO. COMPONENT BLDG. ELEV. NOTE (1 ) NOTE (2) EESS REF. NO. E7170 1 -GU-PD-9 4 3 382 ' Press. Damper Actuator Reactor 77 No . No '85
- 27170 1-GU-3S-9433B2 . Position Switch Reactor 77 No No 86
.C37860 1-GU-TE-9434 Temp. Elemt. Reactor 54 No No 101 M7860 1-GU-T Y-9 4 34 Temp. Converter Reactor 54 No No 101 i E780AQ 1-GU-HS-9434-1 Hand Switch Reactor 102 No No 96 278*AQ 1-GU-PDSH-9434-1 Press. Diff. Sw. High Reactor 54 No No 92 ^M780AQ 1 -Gu-TE-9 4 34-1 Temp. Elemt. Reactor 54 No No 93, iM78GAQ 1-GU-HS-9434-2 Hand Switch Reactor 102 No No 96 E780AQ 1 -GU-PDSH-9 4 34-2 Press. Diff. Sw. High Reactor 54 No No 92 lE780AQ 1 -GU-TE-9 4 34-2 Temp. Elemt. Reactor 54 No No 93 .-E7170 1-GU- PD-9 4 34 A1 . Press. Damper Actuator- Reactor 5S No No 85 27170 1-GU-3S-9434A1 Position Swatch Reactor 54 No No 86 .M7170 1 -GU-FD-9 4 3 4 A2 Press. Damper Actuator Reactor 54 No No 85
- E7170 1-GU-2S-9414A2 Position Switch Heactor 54 No No 86 M7170 1-GU- Pti-9 4 34BI Press. Damper Actuator Reactor 77 No No 85
- 27170 1 -GU-2 S-9 4 3 4 BI Position Switch Reactor 77 No No 86.
- 57170 1 -GU- PD-9 4 34B2 Press. Damper Actuator Reactor 77 No No H5 fM7170 1 -GU-3 S-9 4 3 4 b2 Position Switch Reactor 77 No No 86
. t37 860 1-GU-TE-9435 Temp. Elemt. Reactor 54 No No 101 ]u?860 1-GU-TY-9435 Temp . Converter Reactor 54 No No 10L ig780AQ 1-GU-HS-9435 1 Hand Switch . Reactor 102 No No 96 - C1780AQ 1-GU-PDSH-9435-1 Press. Diti. Sw. High React or 54 No No 92
- M78rAQ 1 -GU-TE-9 4 35-1 Temp. Esent. Reac tor 54 No No 93 2780AQ 1 -Gt!-4 9 4 35-2 . Hand Switch Reactor ~102 No No 96
'R780AQ 8 -GU- PDSH- 9 4 35- 2 Press. Diff. Sw. High Reactor 54 No No 92 M780A0 1 -GU-TE-9 4 35-2 Temp. Elemt. Reactor 54 No No 93 M7170 1 -GU-PD-9 4 35Al Press. Damper Actuator. Reactor. 54 No No 85
- E7170 1-Gu-IS-9435A1 Position Switch Reactor 54 No No 86 Amendment 13 I
Revianon 3 i
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I L V HCGS FSAR TAHLE 3.II-5 ' Page 100 of 120 SYSTE2s REAC ULDG EXH CUNTRL EQUI PNENT SELECTED FOR HARSH ENVIRONNENT QUALI FICATION CU 'P6ID N-84-1 ID NO. PAM P.O. NOTE (5) LOCATI ON TN1 ACTION NPt. NO. CONPONENT . EOUI P. PLAN EOUIP. BLLM . ElEV. NOTE (1) NOTE (2) FFSS REF. NO. C7170 1-GU- Pl>-9 4 35A2 E7470 1-GU-IS-9435A2 Press. Damper Actuator Reactor 54 Position Switch No No 4717Q 4 -GU- PD-9 4 3581 Reactor 54 85 R7870 Press. Damper Actuator Reactor . 77 No , No 86 1-GU-2S-943581 No N7173 1 -GU-PD-9 4 3 5u 2 Position Switch . Reactor 77 No No ' 85 N7170 Press. Damper Actuator Reactor 77 No 86 1-GU-23-9435B2 Position Switch No No 85 K7860 1-GU-TE-9436 Temp. Elemt. Reactor 77 No No K7860 1-GU-TV-9436 Reactor 162 86 Temp. Conve r t e r - No No 2780A0 Reactor 162 101 1 -GU-H S-9 4 36-1 Hand Switch No No
.C780AQ Reactor. 102 101 1 -GU-PDS H-9 4 36-1 Press. Diff. Sw. High No No 96 R780A0 1 -GU-TE-9 4 36-1 Temp. Elemt. Reactor 77 No No #75fAQ 1 -GU-H3-9 4 36- 2 Reactor 77 92 Hand Switch No . No 93 E780A0 1 -GU- PDSH-9 4 36-2 Reactor 77 No N700AQ 1 -G U-TE-9 4 36- 2 Press. Diff. Sw. High Reactor 77 No No 96
,K7170 Tesap. Elemt. No 92 1 -GU- PD-9 4 36At Press Damper Actuator Reac tor 77 No No ' R7170 1 -GU-2 S-9 4 3 6 Al Reactor 77 No 43 >N7170 1 -GU-PD-9 4 36A 2 Position Switch Reac tor 77 No No 85 -N7173 1 -GU-2S-34 36A2 Press. Damper Actuator Reactor .77 No 86 Position Switch No No 85
- N7170 1 -GU- PD-9 4 3681 Resctor 77 No Press. Damper Actuator No 56
- K7170 1-GU-2S-9436B1 keactor 77 No
- E7170 1 -Gu-PD-94 3682 Position Switch Reactos. 77 No No H5 Press. Damper Actuator No 56
'E7170 1-GU-2S-9436H2 Reactor 77 No IE780A0 1-GU-HS-9437-1 Position Switch Reactor 77 No No 85 2780A0 ' Hand Switch Reactor 102 No 86 1 -GU-PDS H-9 4 3 7-1 Press. Ditt. Sw. High 'No No 96 R780A0 1-GU-TE-9437-1 Temp. Elemt.
. Reactor 102 No No N780AQ Re ac tor -92 1-GU-HS-9437-2 Hand Switch 102 No No . 9)
. Reactor 102 No No 96 Amendment !3 Revision 3
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i s y/ , l HCGS FSAR Page !On of 120 i TABLE 3.11-5 EQUI PMENT SELECTED FON HARSH ENVI RONMENT QUALI FICATION , P61 D } SYSTEMS REAC BLDG EXH CONTRL Gu M-84-1' + I . I D NO. PAM TMI ACTION LOCATION EQUIP. PLAN EQUIP. lP.O. NOTE (5) MPL NO. COMPONENT HLDG. ELEV. NOTE (1) NOTE (2) 1 EESS REF. NO. IQ780AQ 1 -GU- FDSH-9 4 37- 2 Press. Diff. Sw. High Reactor 102 No No ' 92 ,M78 AQ 1 -GU-TE-9 4 37-2 Temp. Elemt. Reactor 102 No No
- M7170 1 -GU-PD-94 37Al 93 Press. Damper Actuator Reactor 102' No No 85 i C7170 1 -GU-2S-94 3 7Al Position Switch Reactor 102- No No 86
- E7170 1-GU-PD-9 4 37A2 - ._ Press. Damper Actuator Reactor- 102 No 'No 85 eE7170 1-GU-SS-9437A2 Position Switch Reactor- 102 No No 86 4G7170 1-GU-PD-9 4 37 B1 Press. Damper Actuator Reactor 102 No 'No 85 M7170 1-GU-IS-9437B1 Position Switch Reactor 102 No No 86 4c7170 1 -GU-PD-9 4 3782 Press. Damper Actuator Reactor 102 No No 85
,M7170 1-GU-2S-943782 Position Switch Reactor 102 No. No 86 iM7860 1-GU-TE-9438 Temp. Elemt. Reactor 162 No No 101 K7860 1 -GU-T Y-9 4 38 Temp. Converter Reacter 162 No No lui
- 27CSAQ 1-GU-HS-9438-1 Hand Switch Reactor 102 No No 96 tC180A0 1 -GU-PDSH-9 4 38-1 Press. Diff. Sw. High Reactor 102 No No 92
- 2780AQ 1-GU-TE-9438-1 Torp. Elemt. Reactor 145 No No 93 LG787AQ 1 -GU-H S-9 4 38- 2 Hand Switch Reactor 102 No No 96 127 MAO 1 -GU- PDSH-9 4 38- 2 Press. Diff. Sw. High Reactor 102 No No 92
'5781AQ 1 -GU-TE-9 4 38- 2 Temp. Elemt. Reac tor 145 No No 93 lE7170 1 -GU- PD-9 4 38Al Press. Damper Actuator Reactor 145 No No 85
- G7170 1-GU-2S-9438Al Position Switch Reactor 145 No No 86 lK717Q 1 -GU-PD-9 4 38A 2 Press. Damper Actuator Reactor 145 No No 85 iK7170 1-GU-SS-9438A2 Position Sentch Reactor 145 No No 86 K7170 1-GU-PD-9438B1 Press. Damper Actuator Reactor 102 No No US M7870 1-GU-IS-9438HI Position Switch ' Reactor 102 No No 86 2717Q 1 -GU-PD-9 4 388 2 Press. Damper Actuator Re act or 102 No No 85 G7173 1 -GU-2 S-9 4 3 8 H 2 Position Switch Reactor 102 No No 86 i
= Amendment 13 Revision 3 i
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'HCGS FSAR TABLE 3.!!-5 Page 102 ' of 1 20' 1
.,. SYSTEF.: REAC BLDG EXH CONTRL'
'EQU1898ENT SELECTED FOR HARSH ENVIRONNENT QUALI FICATION , ' P&I D
- j. GU N- 8 4 -3 . ;;
PAN TNI ACTI ON , 1 1 D NO. LOCATION P.O. NOTE-15)' NPL NO. EOut P. PLAN EQUIP. COMPONENT HLDG. ELEV. NOTE (l i
' NOTE (2) , EESS REF. NO.
E7870 1-GU-PD-9 4 38C1 Press. Damper Actuator Reactor 102 No
; 827170 1 -GU-IS-9 4 38CI No 85 Posttton Switch Reactor 102 No ' No
- M7170 1 -GU-PD-9 4 38C2 , Press. Damper Actuator 86
' Reac tor 102 No No 85 K7170 1-GU-IS-9438C2 Position Switch Reactor 102 No M7170 1 -GU-PD-9 4 38DI No 86 4
. Press. Damper Actuator , Re ac tor ! 32 No i 1K7170 'l-GU-IS-9438DI ' No 85 Position Switch Reactor 132 No No 86 21170 - 1-Gu-PD-94 38D2 Press. Damper Actuator .i Reactor 132 .No No 85 2M7170 1 -GU-2S-94 38D2 _ Position Switch Reantor 132 No.
-[*
E7170 1 -GU-PD-9 4 38El No .86
' Press. Damper Actuator. Reac tor 132, No ' No 85
. .' N7170 1 -GU-2S-94 38E! Position Switch Reactor 1 32 No l 5 M7173 1 -GU- PD-94 388 2 No 86 Press. Damper Actuator Reactor 1 32 No No l .l E7170 1-GU-IS-943882 85 Position Switch- Reactor I32 No No 86 1
'M7170 1 -GU- PD-9 4 38F1 Press. Damper Actuator. Reactor 132 No C7170 1 -GU-2 S-94 38 F1 No 85 Position Switch. Reactor ! 32. No No 86
) 27470 1 -GU-PD-94 30F2 Press. Damper Actuator Reactor 132 No C7170 1 -Gu-2 S-94 38 r2 No 85
- Position switch Reactor 132 ' No No 86-M7870 1-GT- PD-94 38G1 Press. Damper Actuator 162 No
.P M7173 1-GU-IS-9 4 38G1 Position Switch
' Reactor 'No- 85 Reactor 162 No No 86 C7170 1 -GT-PD-9 4 38G 2 Press. Damper Actuator- reactor ,162 No r M7170 - GT-28-9 4 30G 2 No- 85 !
3 Position Switch Reactor 162- No No 86
.817170 4 -GT- PD-9 4 34H 1 Press. Damper Actuator ' Reactor 162 No No 85 E7173 1-GU-35-9438HI Position Switch Reactor 162 No M7170 1 -GT- PD-94 38H 2 Press. Damper Actuator No 86 .
Reactor .162 No No. 85 017170 1-GU-IS-9438H2 - Position Switch Reactor 162 No No _. E7 80AQ ' l-GU-HS-9 4 39-1 86 Hand Switch. . Reactor 102 No .No 96 - M787AQ I-GU-PDSH-9439-1 Press. Diff. Sw. High peactor. 102 No ' No E78!AQ . 1-GU-TE-9 4 39-1 . Temp. Elemt. 92
. Reactor 102 No No 93 M780AQ 1-GU-HS-9439-2 Hand Switch'- Reactor 102- No No 96 , Amendownt i3 Revision 3
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HCGS FSAR TABLE 3.!!-5 pag, go3 ot 120 S YSTEM: REAC BLDG EXH CONTRL EQUI PMENT SELECTED FOR HARSH ENV!RONMENT QUALIF1 CATION GU- P&I D M-84-1 I D NO. PAM TMt ACTION P.O. NOTE (5) MPL No. LOCATION COMPONENT EOut P. PLAN EQUIP. Hl.tx1. ELEV. NOTE (1 ) M780A0 NOTE (2) EESS REF. NO. 1 -GU-PDSH-9 4 39-2 Press. Ditt. Sw. High K780A0 1 -GU-TE-9 4 39-2 Temp. ' Elemt. Reactor 102 No No t!7170 1-GU-PD-9439Al Reactor 102 92 Press. Osaper Actuator No No 93 07170 1 -GU-2 S-9 4 39 Al Reactor 102 No E7170 1 -GU-PD-9 4 39A2 Position Switch Reactor 102 No No 85 C7870 Press. Damper Actuator Reactor 102 No 86 1-GU-2S-9439A2 Position Switch No No 85 G7470 1-GU-PD-943981 Reactor 102 No C7870 Press. Damper Actuator Reactor 102 No 86 1-GU-2S-9439st Position Switch No No 85 27870 4 -Gu- Pl>-9 4 3982 Press. Damper Actuator Reactor 102 No Na 86 M7173 1-GU-ES-943982 Reactor 102 No 8;780A0 1-GU-HS-9450 Position Switch Reac tor 102 No No 85 C7280 Hand Switch i<eactor 147 No 86 1-GU-SV-9450A Solenoid Valve No No 96 M7280 1-GU-2S-9450A React or 102 No M7280 1-GU-SV-9450s Position Switch Reactor 102 No No SS M7280 1-GU-2S-94508 soler.oid valve Reactor 102- No No 89 M780A0 1 -GU-H S-9 4 57-1 Position Switch Reactor 102 No No 88 Hand Switch No 89 E780AQ 1 -G O- PDSH- 9 4 57- 1 Reactor 102 No E780A0 1 -GU-TE-9 4 5 7-1 Press. Diff. Sw. High Reactor 145 No No 96 Temp. Elemt. No 92 '%720A0 l <.U-hs-9457-2 Reactor 145 No K780A0' Hand Switch Reactor 77 No 93 l-GU-PDSH-9457-2 Press. Diff. Sw. High No No 96 5780AQ 1-GU-TE-9457-2 Reactor 145 No No E7173 Temp. Elemt . Re ac tor 145 92 1 -G U-P D-9 4 5 7Al Press. Damper Actuator No No 93 r.7170 1-GU-2S-9457Al Reactor 145 No K7170 1 -GU-PD-9 4 5 7A 2 Position Switch Reactor 145 No No 85 Press. Damper Actuator No 86 M717Q 1-GU-2S-9457A2 Reactor 145 No Position Switch Reactor 145 No No US No 86 Amendment 13 Revision 3 m
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. TABLE 3.11-5 i
EOUI PMENT SELECTED FOR HARSH ENVI RONMENT QUALI FICATION P61 D N-87-1' . S YSTEM : CHILLED NATER SYSTEM GS PAM TMI ACTJON I D NO. LOCATION EQUIP. PLAN EQUIP. P:O. NOTE (5) M PL NO. COplONENT HI.tXI. E l.E V. NOTE (I) NOTE ( 2) EESS REF. NO. P3210 1-CB-HV-9534A1 Control valve Reactor 102 No No 1 27 P3110 1-Cu-2S-953tAl Limit Switch Reactor 102 Yes No -127 P3010 1-GB-HV-9531 A2 Control Valve Reactor 102 . No No 127 P30lO l-GB-2S-953%A2 Limit Switch Reactor 102 Ye s ' ' No . j27 P 30lO l-CH-HV-9531A3 control valve Heactor 102 No No . I 27 P3110 1-GB-2S-9531A3 Limit Switch peactor 102 Yes No 127 i P 3010 1-Gh-HV-9531 A4 Control Valve Reactor 102 No No 127
- P31tQ l-GB-23-953tA4 Limit Switch Reactor 102 Yes No 127 P 3O L Q 1 -GB-HV-9 5 31 s t Control valve Reactor 102 No No 127 P3230 I-Gu-IS-953th! Limit Switch peactor 102 Yes No 127 P3010 1 -GH-HV-9 5 318 2 Control valve peactor 102 No No 127 P30lO 1-Ga-2S-953tn2 Limit Switch peactor- 102 Yes No . 127 P3110 1-Gh-HV-953183 Control Valve Reactor 102 No - No 127 P3110 1 -CB-2 S'-9 5 3183 Limit Switch Reactor 102 Ye s No 127 P 30lO l -GB-H V-9 5 3184 control valve Heactor. 102 No No 127 .t P3
- lO l-CB-25-953184 . Limit Switch peactor 102 Yes No 127 P3110 1-GB-HV-9532-1 ' Control Valve Reactor 162 No No 1 27 P3110 1-Go-2S-9532-1 Limit Switch Reactor 162 No No 127 P3210 1-CB-HV-9532-2 control valve Heactor- 162 No No 1 27 P32tO l -Gu-2 S-9 5 3 2- 2 Limit Switch peactor 162 No No 127 Amendment 13 Revision 3 4
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~ PAM '- TMI ACTION LOCAT!t28 EOUIP. PLAN EQUIP.
. P. O .' WOTE (5) MPL NO. COMPO90ENT - 8 L!#.. El.EV. e NOTE (l)- NOTE (2) FESS REF.'No. 1 '.i E1210' IO-D-251 250VDC MCC - Reactor 54- No No- 3 , E1240 10-D-261 250VDC MCC Reactor 54: No No 3 l . I- i l '! l i I i* 1 i g t
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.E118Q - 10-B-212- 480V NCC Reactor 102 No No .2 r
ElitQ 10-a-222 480V NCC Reactor 102 . No ' No - 2 Ell DQ 10-s-232 '480V NCC Eeactor 102 No No 2--
. Ell 8Q 10-a-242 480V NCC '
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' EQUI PNENT SELECTED FOR HARSH ENV! RONNENT QUALI F1 CAf t ON I P68 D SYSTENs ~ GENERI C '
PAN TN! ACTlON I D NO. LOCATEON P.O. NOTE (5) EOUEP. PLAN EOdlP. VENDOR CON PONENT HLDC. ELEV. NOTE (1) NOTE ( 2) EESS REF. NO. El290 A00 Okonite SkV Power Cable Note (3). E1290 A04 #2/A N/A 4 Okontte SkV Power Cable ' Note (3) N/A N/A 4 A35 Okonite SkV Power Cable
; ' E1290 E129Q A50 Note (3) N/A N/A 4 Okonite SkV Power Cable 230t e ( 3) N/A N/A 4 E1290 A75 Okonite ' SkV Power Cable Note (3) N/A N/A 4 51350 LAW 200 Westinghouse Electric Penetration Assy.
IbW200 Note (3) 6 (4) N/A N/A 5-E1350 Westinghouse . Electric Penetration Assy. Note ( 3) 6 (4) N/A N/A 5 E1350 ICW200 Westinghouse Electric Penet rat ion Assy. Note ( 3) 6 (4) N/A N/A .5 E1350 IDW200 Westinghouse Electric. Penetration Assy. Note (3) 6 (4) N/A E1350 N/A 5 1AW201 Westinghouse Elect ric Penet ration Assy. Note (3) 6 (4) N/A N/A 6 E1350 IBW20% Westinghouse Electric Penetration Assy. Note ( 3) 6 (4) N/A ICW201 N/A 6 i E!350 Westinghouse Elect ric Penetrat ion Assy. Note ( 3) 6 (4) N/A N/A 6' E1350 IDW201 Westinghouse Electric Penetration Assy. Note (3) 6 (4) N/A E1350 IEW4DI Westinghouse N/A 6 i Electric Penetration Assy. Note ( 3) 6 (4) N/A N/A- 6 E1350 IFW201 Westinghouse Electric Penettation Assy. Note (3) 6 (4) N/A N/A 6 .i E1350 l AW20 2 Westinghouse Electric Penetration Assy. N/A Note (3) 6 (4) N/A 5 Amendment 13 Reviston 3 4 O i i [ I 6 s e i
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! D NO. : PAN TNI ACTION P. O . NOTE (5)- VENDOR 1.OCAT!ON EQUI P. PLAN E0HI P.
CONEONENT HLEx;. ElEV. NOTE (I) NOTE ( 2) EESS NEF. NO.
~ E1350 IBW202 Westinghouse . Electric Penetration Assy.
E1350 ICW202 West!nghouse Note (3) 6-(4). N/A N/A E1350 IAW203 Electric Penetration Assy. Note ( 3) & (4) N/A N/A 5 E1350 IBW203 Westinghouse Electric Penetration Assy. Note (3) & (4) N/A N/A 5 ' E1350 LAW 204 Westinghouse Westinghouse Electric Penetration Assy. Note ( 3) & (4) _N/A N/A 5 E1350 lbW204 Electric Penetration Assy. Note (3) & (48 N/A N/A 5 Westinghouse Electric Penetration Assy. Note (3) &-(4) 5 El379 ICW204 ' Westinghouse' Electric Penetration Assy. N/A. N/A 5 i E1350 IEW204 Note (3) &,(4). N/A' N/A Westinghouse Electric Penetration Assy. 5 E1350 IFW204 Westinghouse Note (3) & (4) N/A N/A 5 E!350 1GW204 Electric Penetratian Assy. Note (3) & (4)- N/A N/A 5 E1350 IJW204 Westinghouse Elect ric Penetrat ion Assy. Note ( 3) & (4) N/A N/A Westinghouse Electric Penetration Assy. 5 E1350 1EW204 Westinghouse No t e ( 3 ) 6 (4) N/A N/A 5 E1350 1AW205 Electric Penetration Assy. Note.{3) 4 (4) N/A N/A Westinghouse Electric Penetration Assy. , Note (3) 6 (4) 5 El350 lbw205 N/A N/A 5 E1350 ICW205 Westinghouse Electric Penetration Assy. Note ( 3) & (4) -N/A N/A 5 West inghouse - Electric Penetration Assy. Note (3) & (4) N/A N/A 5 Amendment 13 I Revision 3
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- SYSTEN ' GENERI C ^
I D NO. PAN TNI ACTION
; P. O . NOTE (5) LOCATION EQUEP. PLAN EQUIP.
VENDOR CONRmENT B l.DC. ElEV. -NOTE (ll' N(RTE ( 2) EESS REF. NO.
, E1350' IDW205 Westinghouse . Electric Penetration Assy
- E1350 - IEW205 Westinghouse . Note (3) 6 (si N/A NIA 5.
Electric Penetration Assy Note ( 3) 6.443 N/A E1350 IFW205 . Westinghouse . Electric Penetration Assy .N/A. '5 E1350 IGW205 Westinghouse Note (3) & (4) N/A N/A 5 El350 IHW205 Electric Penetration Assy. Note (3) 6 (4) N/A' N/A I Westinghouse Electric Penetration Assy' 5 ' E1350 IAW206
. Note ( 3) ,6 (4) 'N/A N/A 5 E1350 IpW206 Westinghouse Electric Penetration Assy Note ( 3) 6 (4) N/A N/A
. Westinghouse Electric Penetration Assy 5 El350 ICW206 Westinghouse , Electric Penetration Assy 140t e (3) 6 .. ( 4 ) .N/A N/A 5 E1350 IAW207 Note ( 3) 6 (4) N/A N/A 5 E1350 thW207 Westinghouse Electric Penetration Assy Note ( 3) 6 (4) N/A N/A 5 E1350 ICW207 Westinghouse Electric Penetration Assy Note ( 3) 6 (4)- N/A N/A 5 E1350 IDW207 Westlnghouse. Electric Penetration Assy Note l(3) 6 (4) N/A N/A' 5 l' E1350 IAW208 Westinghouse Electric Penetration Assy Note ( 3) 6 (4) N/A- N/A 5 Westinghouse E1350 I AW209 Westinghouse Electric Penetration Assy '. Note (3) 6 (4) N/A N/A 5-E1570 CO2 Electric Penetration Assy Note ( 3) 6 (4) .N/A N/A 5 Okonite 600V Control Cable Note (3) N/A N/A 7
, Amendment 13 kewiston 3 , 'i 1 4
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i A- , I HCGS FSAR page ggO ,of 1 20 TAllLE 3.11-5 EQtJI PNENT SELECTED FOR HAHSH ENVI HONNENT QUALI FICATION ' P61 D . SYSTEN: GENERI C N/A-PAN TNI ACTION 1 D NO. LOCATION EOutP. P.O. ' NOTE ( 5) VENDOR PLAN E0utP. CONIM ENT Rt.DG. El.EV.' NOTE (1) NOTE ( 2) EENS REF. NO. E1570 CO3 Okontte 600v control Cable Note ( 3) N/A N/A '7 E1570 CO5 Okonite 600v Control cable Note ( 3) N/A N/A 7' . EI570 C07 Okonite 600V Control Cat'le Note (3) N/A N/A 1 E1570 009 okonite 600v Control Cable- Note ( 3) N/A N/A 7 4' E1570 C12 Okor.6te 600v Control Cable E1570 C19 okonite
. Note (3) N/A N/A. 7 60nV control Cable Note ( 3) N/A N/A 7 E1580 173 okonita 600V Power Cable . Note (3) .N/A N/A 8 EI580 ITS .Okontte 600V Power Cable Note ( 3) N/A N/A 8 E1580 102 Okontte 600V Power Cable . Note (3) N/A N/A 8' E1580 106 okontte 600V Nwer Cable Note.('s) N/A N/A 8-
'E1580 !!O Okonite 600v Power Cable Note (3) N/A N/A 8 e- E1580 112 Okonite 600V Power Cable Note ( }) ~ H/A N/A H E1580 120 Ok oni t e 600V Power Cable Note (3) . N/A N/A 8 E1580 135 Okonite 600V Power Cable Note ( 3) N/A N/A B E1580 140 Okonite 600v Power Cable- Note ( 3) N/A. N/A 8 E1580 150 Okonite 600V Puwer Cable Not e ( 3) .N/A N/A G E1580 202 Okontte eGOV Power Cable Note (3) N/A N/A 8
? ~ Amendment t3 Revision 3 4 1 9 ? I I
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- j. 1 D NO.
PAN TN! ACTION
, LOCATION EQUIP. - PLAN EOulP.
P. O . NOTE ( 5) VENDOR CONF 0NENT RLIX3. E l.E V. NOTE (1) NOTE ( 2) EESS REP. NO. I E!580 209 .Okonite 600V Power Cable . Note (3) N/A
. E15*Q 302 N/A' 8.
Okontte 600v Power Cable' Note ( 3) .N/A. N/A 8 E!580 304. Okonite 600v Power Cable Note (3) N/A. E1580 306 N/A 6
-Okonnte. 600V. Power Cable - , Note (3) N/A N/A 8.
E1580 308 okonite 600v Power Cable Note (3) N/A E!580 309 N/A 8 / Okonite 600V Power Cable Note ( 3) N/A .N/A 8 E1580 31 2 Okonite 600V Power Cable Note 13) ^ N/A E!580 320 N/A 8 Okonite' 600V Power Cable Note ( 3) N/A N/A 8 E1500 340 Ok on i ts 600V Power Cable . Note (3) E1580 402 N/A N/A 8 Okonite 600V Power Cable Note ( 3)
- N/A N/A N
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} E!580 404 okonnte 600V Power Cable Nte (3) N/A N/A 8
^
4 El580 409 Okortte 600V Power Cable Note ( 3) N/A 412 N/A H j, E1580 Okonite 600V Power Cable. Note ( 3) N/A N/A 8 ! E1580 420 Okonite 600V Power Cable Note ( 3) N/A 510 N/A B. Okontte a
' 600v Power Cable " Note (3) N/A N/A 8
}'E!580 E1580 712 Okonite . 600V Power Cable .' Note ( 3) N/A N/A 4
' Amendment 13 4
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HCGS FSAR page 3g2 1~f og g 20 TABLE 3.16-5 EQUIPMENT SELECTED FOR HARSH ENVIRONMENT QUALI FICATION P&t D
- SYSTENs GEN"21C S PAM- TMI ACTI ON
.ID NO. toCATION equip.
P. O .' NOTE (5) VENDOR COM PONENT PLAN EOutP. HLDG. ELEV. NOTE (1) NOTE ( 2) ' EESS REF. NO. E1700 RG2 Brand-Rex Co, Tri, and Twinasial Cable Note ( 3) E1700 RG) Brand-Rax Co, Trl, and Twinasial Cable N/A: N/A 9 E1700 Note ( 3) .N/A N/A 9 pl 4 - Brand-Rex Co, Tri, and Twinamiel cable. Note (3) N/A E1700 R16 Brand-Rex .N/A 9
- Co, Tr1, and Twinasial Cable . Note ( 3) N/A N/A' 9 E!700 R5s . Brand-Rex Co, Tri, and Twinasial Cable Note ( 3) N/A 51700 R59 . Brand-Rex N/A 9 Co, Tri, and Twinasial cable. Note ( 3) N/A .N/A 9 E1700 R6 2 . -Brand-Rex Co, Tri, and Twinaxial Cable Note ( 3) N/A N/A 9 E170AQ DM1 Rockbestos '
co, Trt, and Twinasial. cable Note ( 3) N/A. N/A 12 E170AQ .RP2 Rockbestos Co. Tr t, and Twinaxial Cable E170A0 R06 Rockbestos . Co, Tri, and Twinantal Cable Note (3) N/A N/A 12 El10AQ Note ( 3) N/A N/A 10 RF9 Rockbestos ,Co, Tri, and Twinaulat Cable- Note ( 3) N/A N/A 10 E17tAQ RG11 nackbestos Co, Tri, and Twinaxial Cable E170AQ -R22 Note (3) N/A N/A 10 Rockbestos Co, Tri, and Twinaxial Cable . Note (3) N/A E110AQ S13 Rockbestos Co, Trt, and Twinasial Cable- Note (3) N/A 10 N/A N/A 11 E170AQ SI4 Rockbestos Co, Tri, and Twinarial. Cable Note (3) N/A- N/A 11 E!70AQ S16 Rockbestos Co, Tri, and Twinasial Cable E170AQ SIS Note (3) N/A N/A' 11 Rockbestos Co, Tri, and Twinasial Cable Note (3) N/A -
,K17tAQ VK4 N/A !!
Rockbestos Co, Tri, and Twinasial Cable Note ( 3) N/A N/A E1710 104 Eaton 12A 600v Shielded Instru Cable Note (3) N/A N/A 13 E1710 D01 Eaton _ 600v Shielded Instru Cable . Note ( 3) N/A E1710 N/A 13 DO2 Eaton 600V Shielded Instru Cable . Note (3) N/A N/A 13 E!710 DO3 Eaton 600V Shielded Instru Cable Note ( 3) N/A E!?tQ . Doe Eaton N/A 1] 600V Shielded instru Cable Note (3) N/A N/A I3 E1710 DOS Eaton . 600V Shielded Instru Cable Note (3) N/A , E1710 006 N/Ao 13 Eaton' 600V Shielded Instru Cable. . Note (3) N/A N/A I3 Amendment 13 Revision 3 9 0 y '
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- EQUI PMENT SELECTED FOR HARSH ENVikONMENT OUALI FICATION
~
P6t D S YSTEM t GENERIC N/A PAN TN! ACTI ON I D NO. LOCATION P.O. EQUEP. PLAN EQUIP. NOTE ( 5) ' VENDOR COM PONENT HLDG. EI.EV. NOTE (1) NOTE ( 2) EESS HEP. NO. _ E1710 007 Eaton 600V Shielded Instru ' Cable Note ( 3) DOS N/A N/A 13 E!?lo Eaton 600v Shielded Instru Cable Note 13) N/A N/A 13 - E178 0 Dot Eaton 600V Shielded Instru Cable . Note (3) N/A N/A L3 E1710 D30 Eaton 600V. Shielded Instru Cable Note ( 3) N/A E1710 D31 N/A 13 / Eaton 600V Shielded Instru Cable Note (3) N/A- N/A. 13 E17to 012 Eaton '600v Shielded Instru Cable Note ( 3) - N/A E1710 D33 .N/A 13 102 Eaton 600V Shielded Instru Cable Note (3) N/A N/A 13 E1710 Eaton '600V Shielded Instru Cable Note-l3) N/A E1740 103 y N/A I3 ' Eaton 600V ShiePded Instru Cable . Note (3) N/A N/A 13 E1710 104 Eaton 600V Shielded instru Cable . m)te ( 3) N/A N/A i1 El ?!O IO6 .Eaton 600V Shielded Instru Catele . Note (3) N/A E!7tO 110 N/A I3 Eaton 600V Shielded Instru Cable Note ( 3) N/A N/A I3 E1710 112 Eaton 600V Shielded Instru Cable Note (3) N/A E1780 120 N/A I3 Eaton 600V Shielded.Instru Cable Note ( 3) N/A N/A . 13 E1710 3 24 Eaton 600V Shielded Instru Cable . Note (3). N/A 128 N/A 13 E171Q Eaton 600v Shielded Instru Cable Note ( 3) N/A N/A 13 Amendment 13 Hewiston 3 Y
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yy a L ,. ,{- HCGS FSAR TABLE 3.11-5 'Page I'l4 .ofl120 ' EQUI PNENT SEl.ECTED FOR HARSH ENVI RONNENT OUALI FICATION P6t p SYSTE;1: GENERIC N/A, I D NO. PAN- TNI . ACTION LOCATION EQu!P. PLAN EQUIP. P. O . NUTE (5) VENDOR COMPONENT - hl.DC.. FLEV. kf rte ( 1 ) NOTE (2) EESS REF. NO. E1710 IT2 Eaton ;600V Shielded Instru Cable'
' E1710 IT3 Eaton
. Note (3) N/A' N/A 13 600V Shielded Instras Cable - Note ( 3) . N/A N/A in E1710 -174 Eaton 600V Shielded Instru Cable E! 71Q IT6 Note (3% N/A N/A 13 E1710 NOS Eaton 600V Shielded Instru Cable Note ( 3) N/A N/A 13 Eaton 600V Shielded Instru Cable - Note ( 3) N/A N/A I3 E1780 SO3 Eaton 600V Shielded Instru Cable E! 710 S19 Note (3) N/A N/A 13 E1710 S24 Eaton 600V Shielded Instru Cable - Note (3) N/A N/A 13 ;
Eaton 600v Shielded Instru Cable Note ( 3) N/A N/A 13 E1710 S28 Eaton 600V Shielded Instru Cable' Note (3) E1710 TAL N/A N/A 13 E1710 TA2 Eaton 600V Shielded Instru Cable Note ( 3) N/A N/A I3 Eaton 600V Shielded instru Cable Note ( 3) N/A N/A II E1710 Thi . Eaton 600V Shielded Instru Cable E1710 TB2 Note ( 3) - N/A N/A- 13 Eaton 600V Shielded Instru Cable Note (3) N/A N/A I3 E1710 TH1 Eaton 600V Shielded Instru Cable Note ( 3) E1710 TH2 - Ea t on N/A N/A 11 TH3 600v Shlalded Instru Cable Note (3) N/A N/A 13
. E178 0 Eaton 600V Shielded Instru Cable Note ( 3) ..N/A N/A- 13 Amendment 13-Revision.3 s
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a
'ID NO.
PAN TN! ACTI ON LOCATION - EQUIP. PLAN EQUI P. P.O. NOTE (5) VENDOR CON PONENT HLDC. ElEV. NOTE (t) NOTE ( 2) EESS REF. NO. 2 E1710 TPl Eaton 600V Shielded Instru Cable Note (3) N/A N/A 13 i E171Q TP2 Eaton 600V Shielded Instru Cable Note ( 3) N/A N/A 13 i E1710 TP3 Eaton 600v Shielded Instru Cable Note (3) N/A N/A 13
, E1719 TP4 - Eaton 600v Shielded Instru Cable Note ( 3) N/A N/A I3 F 3537 30-1 -I F RAT-85) Thomas & Hetts Pressure Terminal Connectors Note (3) N/A' N/A 14 i
F353730-1-IP RAT-36 3 Thomas 6 Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14 F3537)Q-1-!F RAT- 8 7 3 Thomas & Betta Pressure Terminal Connectors Note (3) N/A N/A 14 , F353130-1-1F RAT-713 Thomas & Betts Pressure Terminal Connectors Note ( 3) N/A N/A 44
< F353730-1-!F etBT-0 5 3 Thomas & Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14 s
F353730-I-!F RkT-463 . Thomas 6 Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14
' F351730-1-IF kBT-873 Thomas 6 Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14 j F353730-1-IF RBT-713 Thomas 6 Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14 F353730-1-lF kCT- 33 3 Thomas 6 Betts Pressure Terminal Connectors Note (3) N/A N/A 14 F353730-!=lF RCT-863 Thomas & Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14 F353730-1-IP RCT-363 Thomas & Betts Pressure Terminal Connectors
' Note (3) N/A N/A 14 F353730-1-!F RCT-713 Thomas & Betts Pressure Terminal Connectors Note ( 3) .N/A N/A- 14 Amendment 13 Revision 3 4 p. t O i I 9 y k l
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4 s ICf5 FSAR j . tad.E 3.11-5 Page 116 of I20 l 2001 PNENT SELECTED FOR HARSH ENVI RONNENT QUAll F1 CATION , P61 D ' SYSTDIs GENERIC - " ' I D No. PAN TNI' ACTION P. O . NOTE (5) LOCATION EQUIP. . PLAN EOUIP. . VENDOR- COMPONENT BLDG. E l.E V. NOTE (1) ' NOTE ( 29 EESS REF. NO. , F353730-1-!F RCT-703 Thomas 6 Betts Pressure Terminal Connectors -Note (3) N/A
- F353730-1-IP RCT-733 Thomas & Betts Pressure Termin.nl Connectors Note (3) N/A N/A~ 14
- F353730-1-lF N/A 14 f353730-I-IF RDT-10 361 Thomas 6 Betts Pressure Terminal Connectors Note (3) N/A N/A 14 F353730-1-tr RDT-137t1 Thomas 6 Betts Pressure Terminal Connectors Note (3) N/A .N/A '14 l'F353730-1-lF RDT-10721 Thomas 6 Betts Pressure Termina) Connectors Note (31 N/A N/A' 14 RDT-107 31 ' Thomas 6 Betts Pressure Terminal Connectors , Note ( 31 N/A N/A F353730-1-IF RET-10264 Thomas & Betts Pressure larminal Connectors - Note ( 3) 14 4
F353730-1-IF N/A N/A 14 F353730-1-tr RET-10711- Thomas &_Betts Pressure Terminal Connectors Note ( 3) N/A N/A 14 RET-10721 , Thomas 6 Betts Pressure Terminal Connectors Note (31 N/A N/A , F353730-1-lF 14 ! F3537 30-1-IF . RET-107 31 Thomas 6 Betts Pressure Terminal Connectors ' Note ( 3) N/A N/A 14
. F353730-1-IF RFT-10261 Thomas & Betts Pressure Terminal Connectors Note (3) N/A N/A 14
' RFT-10711 Thomas 6 Betts Pressure. Terminal Connectors Note (3) N/A N/A F353730-1-lF RFT-10721 Thomas 6 Betts Pressure Terminal Connectors Note (3) 14 F353730-1-IF N/A. N/A 14 RFT-107 31 Thomas & tietts Pressure Terminal Connectors Note ( 3) N/A N/A 14 Amendment 13 i
- Revision ' 3 d
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HCGS FSAR TABLE 3.11-5 Page !!7 of 120'- EQUI PNENT SELECTED FOR HARSH ENV!RONNENT OUALIFICATION P61 D SYSTEN: GENERIC I D NO. PAM TNI ACTION P. O. LOCATION' EOUI P. PLAN. EQUIP. NOTE ( 5) VEN DOR COM PONENT HLDG. ELEV. NOTE (l) NOTE ( 2) EESS REF. NO. F 3 5 37 30-1 -l F . RGT-9 261 Thomas & Betts Pressure Terminal Connectors Note ( 3) F353730-1-IF RGT-97 t l N/A N/A 14
. Thomas 6 Betts Pressure Terminal Connectors Note ( 3) ' N/A. N/A 14 F353730-1-lF RGT-9721 Thomas 6 Betts Pressure Terminal Connectors Note (3) N/A F353730-1-IF RGT-9731 N/A 14 Thomas & Bette Pressure Terminal Connectors Note ( 3) N/A N/A 14 F3537)Q-1-IF RGT-9751 Thomas 6 Betts Pressure Terminal Connectors Note ( 3) N/A F353730-2-IF N/A 14 T YZ-2 3N TtKunas 6 Betts TV-RAP Cable Tie Note ' { 3) N/A N/A 15 F 35 37 30-2-t r TYt-25N Thomas 6 Betta TY-RAP Cable Tie Note ( 3)
F353730-2-IF 1YZ-27N N/A N/A 15
. Thomas 6 Betts TY-RAP Cable Tie Note ( 3) N/A ,N/A 15 F3 53730-2-I P T YZ-2SN Thomas & Betts TY-RAP Cable Tie Note (1) N/A N/A 15 F372170-1-IP . NO B10 6 - Amerace Corp Terminal and Fuse Blocks Note (3) N/A N/A F372170-1-IF 16 NOB 106S Amerace Corp Terminal and Fuse Blocks Note ( 3) N/A N/A 16 F372170-1-lF NOBi l 2 Amerace Corp Terminal and Fuse Blocks Note (3)
F372170-1-IF h/A N/A 16 NOBi l 2S .Amerace Corp Terminal and Fuse Blocks Note (3) N/A N/A 16 F379170-1-IF NQO213 Amerace Corp Terminal and Fuse Blocks Note ( 3) N/A F379170-1-lF N/A 16 NOO212 Amerace Corp Terminal and Fuse Blocks Note (31 N/A N/A 16 F372170-1-IP NQO230 Amerace Corp Terminal and Fuse Blocks Note ( 3) N/A F37917Q-!=lF N/A 16 NOO310 Amerace Corp Terminal and Fuse Blocks Note (3) N/A N/A 16 Amendment 13 kevision 3 t
i . . . . . .. _ , _ , . . . .. ,
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- - ' ~
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9 .q i HCGS FSAR TABLE 3.11-5 page ggg og g 20, , EQUI PNENT SELECTED FOR HAkSH ENVIRONNENT QuALI FICATIUN ' F65 D - 8Y0 Test: CENER1C 1 D NO. PAN TNI ACTION F. O. LOCATEON EQul P. PLAN EQUIP. NOTE (5) VENDOR Cast PONENT BLDG. E l.E V. NOTE (1) NOTE ( 2) EESS REF. NO. F379170-1-!F NOOl61 Amerace Corp Terminal and Fuse Blocks Note (3) N/A F377370-1-IF NOO362 Amerece Corp Terminal and Fuse Blocks .N/A 16 F373170-1-IP NOO5tl Note (3) N/A N/A '16 Amerace Corp Terminal and Fuse Blocks . Note (3) N/A N/A 16
, F372170-1-IP NOO514 Amerace Corp Terminal and Fuse Blocks Note (3) N/A F371370-1-!F NQO530 Amerece Corp N/A 16 t
Terminal and Fuse Blocks Note (3) N/A N/A 16 F373170-1-lF 0351 Amarace Corp Terminal and Fuse Blocks Note ( 3) F373170-1-IF 0352 Amerace Corp N/A' N/A 16 Terminal and Fuse Blocks Note (3) N/A N/A 16 F379170-1-IP 60 Amerace Corp Terminal and. Fuse Blocks Note ( 3) F379170-1-lF 68 N/A N/A 16
. .Amerace Corp Terminal and Fuse blocks . Note ( 3) N/A N/A 16 F435tlO-t-!F 433999-0143 Anaconda Flexible Liquidtight Conduit Note ( 3) N/A F4 35110-1-1 F 434009-0143 Anaconda Flexible Liquidtight Conduit N/A 17 Note ( 3) N/A N/A 11 F435110-1-lF 434019-0143 Anaconda Flexible Liquidtight Conduit Note ( 3) N/A F4 35110-1-t r 434029-0143 Anaconda Flexible Liquidt ight Conduit N/A 17 Note (3) N/A N/A 17 I
Amendment 13 Pevision 3- + l 1 b 4
~
,a . e% . .
HCGS FSAR page 139 og ggo. TABLE 3.11-5
+- LOUI PNENT
- ELECTED FOk HARSH ENVI HONNENT QUALI FICATION ' P&I D .,
N/A EYSTEN: GENERI C
' PAN .TN! ACTION IDNO. LOCATION . EQUIP. PLAN EOHIP.
P.O. NOTE (5) VENDOR CON PONENT HLOG. E E.EV. NOTE (l) NOTE ( 2)' EESS REF. NO. F4 35110-1 -! F 434039-0143 Anaconda Flexible Liquidtight Conduit Note ( 3) N/A N/A 17 F4 35110-4 -l F 434049-0143 Anaconda Flexible Liquidtight Conduit Note ( 3) N/A N/A 17 F4 35110-1-I F 434059-0143 Anaconda Flexible Liquidtight Conduit . Note ( 3) N/A N/A 17 F435110-1-IF .434069-0143 Anaconda Flexible Liquidtight Conduit Note (3) N/A N/A 17 F4 35t lO-1 -I F '434079-0143 Anaconda Flexible Liquidtight Conduit Note ( 3) N/A N/A 17 F435110-1-IF 434099-0143 - Anaconda Flexible Liquidtight Conduit Note ( 3) N/A N/A 17 F4 35L IO-1-lF 436151-0142 Anaconda. Flexible Liquidtight Conduit Note (3) N/A N/A 17 F435140-1-IF 436361-0142- Anaconda Flexible Liquidtight Conduit Note (3) N/A N/7 17 F4 351 tO-t-2F F R-E P Anaconda 1/C Low Voltage 6 Power Cable Note ()) N/A N/A 18 F4 35t l O-t - 2F FR-EP/CPE Anaconda 2/C Cantrol 6 Instrument Cable Note ( 3) N/A N/A 18 F4 35t L O-1-2F FR-EP/CPE Anaconda 7/C 600V Flame GRD Cntrl Cable Note (3) N/A N/A 18 ' F4 36 200-1-!F Raychem Corp. High Voltage Terminations Note ( 3) N/A N/A 19 F478880-1-!P N-NCK Raychem Corp. Notor Connection Kit Note (3) N/A N/A 20 F4*4790-1-IF NCSF-N Raychem Corp. Cable Breakout Kit Note ( 3) N/A N/A 21 F484790-1-!F maychen Corp. Cable End Sealing Kit Note (3) N/A N/A 21 F185110-!=lf NPKS.NPKX.NPEC Raychem Cos p. Cable Splice Assy Note ( 3) N/A N/A. 23 F4051t O-1 -I F Raychem Corp. Thermot at Insulation Sys Note (3) N/A N/A >22 F512160-1-!F N-21009-01 Conas Corp. Electric Conductor Seal Assy . Note ( 3) N/A N/A 24 Mendmen t !3 Revision 3
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-TABLE 3.11-5 Page 120 of 120 '
,. NOTES i i i . . 1 (!) This column identifies the equipment located in a harsh environsunt required for post accident monitoring as defined in R.G.I .97 and FSAR Section 4.8.1.97.1. f . -( 2) .This column 0137. identifies the equipment located in a harsh environment identif ied as TNI . Action Plan Equipment as def ined .in 4 NUREG 2 ( 3) liens that are generic are purchased and used throughout the plant and may be used in the Dita Harsn Environment. (4) i Electric Perstration Assemblies for control and instrumentation circuits include inlina. splice connnector kits. (5) Limit or position switch tag numbers have been created by using the "ZS* designator in lieu of. the valve (HV) designator schematicsfor or purposes of equipment indes. quaittication accountability only. These tag ' numbers may not be found in P61 D's, 4 i the instrument Eucoptions to this occur when position switches are mounted on manual valves or are i* 1 ut. der N005 (NSSS) P.O. In that case the tag numbers may be found in the instrument inden and applicable P61 D's. l i,
- 5. Amendment 13 kevision 3 I
i l 1 i t I l $ I { f t i f y _v .
4 .
.,A
. M. J ..-..a. -- -ssed hm- m -. #-+ " *d - M- *-d- -Ja..- a.- ----- . --
i i l I i l l 1 l l d e 4 FSAR TABLE 3.11-6 O 1 b 4 4 1
!I ' - - v s w-v vw~ -m m en. _ _ _ _ _ -__ -e --rw wav-__ -w- ,v- e,,wn -w e---e,w w e r
,, - ~ -
pw-h' w~ h - O 1 4 Page I of 3 HCGS FSAR TABLE 3.11-6 SAFETY-RELATED EQUIPMENT LOCATED IN A HARSH ENVIRODMENT EXEMPTED FROM ENVIRONMENTAL QUALIFICATIOd REQUIREMENTS EQUIPMENT TAG ND. MPL NO. DESCRIPTION REASON 1 AVE 261 Electric Duct Heater, SLC i I CVE 261 Due to reactor building temperature increase during a D8A, the duct heaters will not Electric Doct Heater, SLC 10 VE 259 function due to the tear,erature control settings, which is belox DBA building i Electric Duct Heater, RCic 10 VE 260 temperature. The heater circults are protected by primary and backup IE breakers. Electric Duct Heater, NCl 1 AM 205 4.16 KV Breaker - RRS Pump Motor 1 BN 205 The IRS pump motor breakers trip upon receipt of a LOCA signal shutting down the pump < 4.16 KV Breaker - RRS Pump Motor 1 CN 205 The breakers are no longer required to perform a safety-related function. , 4.16 KV Brooker - RRS Pump Motor 1 DN 205 4.16 KV Breaker - RRS Pump Motor
- 10 Y 201 Panel 10 Y 202 These panels and transformers are located in the reactor building and feed non-critic Panel 10 Y 203 class IE loads. They sre protected by primary and backup IE breakers.
Panel , 10 Y 204 Panel 10 K 201 Transformer 10 K 202 Transformer 10 K 203 Transformer 10 K 204 Transformer j I-SK-TE-N016 Temperature Elements 1-SX-TE-N012A These tcaparature elements are ret quallflod for submergence caused by a feedwater Temperature Elements I-SK-TE-N012C Temperature Elements line break In the ' rr ' E 5-: n ' r:_ d:-!::: ::::?_ ' t; h :_-_ 'c __ r;_ . , 1-SK-TE-N010A Temperature Elements b Sienn knnel. ~lhey ha.uc Leen fowiecf Los W . I-SK-TE-N0108 Temperature Elements gyg gp g gg4 ,3 QCaje,{ gh { 1-SK-TE-NOIOC 1-SK-TE-N0100 Temperature E!ements Temperature Elements he fM,htn( ee st;ted,, . K4 I-SK-TE-N0128 l-SK-TE-N0120 Temperature Et a ts Temperature Elements M FSAKf/mm,ame ne pq g % ,.
! I-GU-TE-9428-1 Temperature Elements l-GU-TE-9428-2 Temperature Elements Idp
/gg7sy s 4
1
.p.
9 O v Poge 2 of 3I HCGS FSAR TABLE 3.11-6 SAFETY-RELATED EQUIPMENT LOCATED IN A leRSH ENVIRONMENT EXEMPTED FRGE ENVIR0l#4 ENTAL QUALIFICATION REQUIREMENTS I EQUIPMENT TAG NO. MPL NO. DESCRIPTION REASON 1-AE-HV-F030 Motor Operated valves These motor operated valves are not qualified for sutunergence l-AB-HV-F071 Motor Operated valves caused by a feedwater line break in the steam tunnel. They have been provided with I-KP-HV-5829A,8 Motor Operated Valves primary and backup IE bus protective devices located in tha hazard free area, l l-KP-HV-4834A.B Motor Operated Valves 1-KP-HV-5835A,B Motor Operated Valves 3 1-KP-HV-5836A.B Motor Oparated Valves i 1-KP-HV-5837A,B Motor Operated Valves l l-BJ-HV-8278 Motor Operated Valves l-AB-HV-F067A Motor Operated Vcives 1-AB-HV-F0678 Motor Cperated Valves l-AB-HV-F067C Motor Operated valves 1 1-A8-HV-F067D Motor Operated valves ) j No Targ No. C11-FolG Position Switch These NAMCO limit switches perform no safety functions. Failure modes and effect' No Tag No. Cll-F0ll Position Switch analysis has shown that there are no possible fallure modes which can adversely No Tag ho. Cll-F180 Position Switch ef fect flie IE power supply. 1 No Tag No. Cll-Fl81 Position Switch ] . 1-BE-SV-F006A E21 Solenoid valve These solenold valves and position switches perform no safety functions. However, ! No Tag No. E21-F006A Position Switch because of their association with a IE power supply, they have been provided with I-BE-SV-F006B E2I Solenold valve primary and backup protective devices, j No Tag No. E21-F0068 Position Switch 1-BC-SV-F041A Solenold Valve Eli j No Tag No. Ell-F041A Position Switch
; 1-BC-SV-F041B Ell Solenold Valve j No Tag No. Ell-F041B Position switch i l-BC-SV-F041C Eli Solenold Valve No Tag No. Ell-F041C Position Switch
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~Pege 3 of 3 1ABLE 3.11-6 5
SAFETY-RELATED EQUIPMENT LOCATED .N A HARSH ENVIRONMENT EXEMPTED FROM ENVIRONMENTAL QUALIFICATION REQUIREMENTS EQUIPMENT TAG NO. MPL NO. ' DESCRIPTION REASON
- 1-BC-SV-F041D E11 Solenold Valve These solenold valves and position switches perform no safety functions.
No Tag No. Ell-F0410 Position Switch However, because of their association with a IE power supply, they have 1 1-BC-SV-F050A Ell Solenold valve been provided with primary and backup protective davices. No Tag No. Ell-F050A Position Switch 1-BC-SV-F0500 E11 Solenold valve Note: All of the equipment in this table is quellflod for its function In No Tag No. E11-F0508 PosIflon Switch in accordance with 10CFR50.49 requirements, i e e 1 i a
a ,,- a4g---a -ep-w..a -a--- & g s .s-_e s- eg.- ,6 %,- A a= .s~m--,,s4 en. a -a.s-M -,_ un.e4- F_ a 4-n 4w--h na--4. * " " ,, . - - -.- -- - -s _s,,a T 4-t a 4. 4 L i i e>= 3 ,. Ih
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r FSAR TABLE 3.11-8 f t 4 1
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r l 1 f f i l r 4 1 R 4 r __ - , __ , _ _ , . ,_ m-__,,,,,__m_
/ e U f V d NCGS FSAR TABLE 3.18-8 page g og 3 i
SYSTEMS FROM NCCS FSAR TABLE 3.2-1 NOT INCLUDED IN TABLE 3.!!-5 OR 3.11-6 DESCRIPTION _ -
.- REF. TO TABLE 3.2-1 REASON
- 1. Reactor System
_= __=.............- _=- 2. I Fuel Nandling and Storage System Mechanical
- 3. Fuel Servicing Squipment VIII Mechanical 3.1 Fuel Preparation Nachines Vill la) Mechanical
- 4. Reactor Wessel Servicing Equipment VIII (a) 3. Non-IE 4.1 neactor Ridg. Polar Crane Vill (b) Mechanical
- 5. In-Vessel Service Equipment VIII (b) 4. Non-lE 6 Refueling Equipment VIII (c) Mechanical
, 7. Storage Equipment VIII (d) Mechanica!
- 4. Undervessel Service Equipment VIII to) Mechanical
- 9. Fuel Oil Storage a94 Transfer Sytem Vllt (I) Mechanical
- 13. Lubricant System III (at Nechanical 13.1 Nester Ill te) Mechanical 10.2 Pump. Motor Driven Prelube Keepware XII to) 5. Non-le 10.3 Notors, Prelube/teepuare and Prelube Pumps XII (e) 7. Non-lE
- 11. Start!ng and Control Air System Elf (en 11. Non-IE 12 Cooling Mater System III (f) Mechanical ,
13 Ccebustion Air Intake and Eahaus't System III (g) Mechanical
, 14. Male Steam and Pouer convereton System Ell (b) Mechanical i 15 Nata Steam Supply System XIV Mechanical I
IS. Main Condenser Evacuation System XIV (a) Mechanica1 17 Feeduator and condensate Sytem IIV (b) Mechanical
, 10 Condensate Cleanul. System XIV (C) Mechanica!
19 Circulating Mater System XIV (d) Mechanical
- 20. Steam Seal Systea XIV (e) Mechanical
! 21.
- Lube Oil Systee XIV (f) Mechanical 21.1 Notore XIV (g) Mechanical
- 22. Gen. H2 and CO2 Purge Systee XIV (g) 3. Non-!E
- 23. Buildinga XIV th) Nochanical
- 28. Primary Ccatainment XVIII Nechanical
- 25. Aust!!ary Building (Diese! Area) XVIII (a) Mechanical
- 25. Ausillary Building (Diese! Area) XVIII (b) Mechanical
- 26. Aust!!ary Sullding (Contalsment Area) XVill (b) Mechanical
- 27. Auxillary Building (Radwaste Area) XVIII (c) Mechanical
- 28. Turbine Su11 ding XVIII (d) Mechanical i 23. Administration Facility XVIII fe) Mechanical
- 34. Circ. Mater Pump leouse XVIII (f) Nochenical
- 31. Reactor Building. Including Pressure-metaining Door XVIII (g) Mechanical
- 32. Plant Cancelled Area XVI!! (h) Nochanical
- 33. Structures XVIII (!) .Nochanical i
- 34. XIX Nochanical
- 35. Station Service Meter Intake Structure XIX (a)
Condensate Storage Tank Nachanical XIX lb) stochanical 33 Pe5 60/05 3/4-er t
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Q G J t NCGS FSAR TABLE 3.11-8 PaSe 2 of 3 SYSTEMS frost HCGS FSAR TABLE 3.2-4 NOT INCLUDED IN TASLE 3.18-5 OR 3.11-6
- _ _ . . . . . - _ = __- == -
DESCRIPTION __== -__=_....- _.-- _ _ . = - - - .-- -- REF. TO TABLE 3.2-1 REASON 36. Die,sel Gen. Fuel Tank Rocs _ XIX (c)
- 37. Station Eattery Rooms Mechanical
- 38. Spent Fuel pool, meactor Nell, Neu Fuel Vault, IXE (4) Mechenical Dryer, Separator Pool, and Tank Cask Pit XIX ' 31
- 39. Circulating teater Structures .
Mechanical
- 43. Unit vent, North and South XIX (f) Mechanical XIX (g) Mechanical
- 48. Condensate Storage Tank Dike
! 42. Spent Fuel Pool Liner XIX (h) Mechanica!
! 43. Skiemer Surge Tank XII (1) Mechanical
- 44. XIX (j) Mechanical Missile / Jet Barriers i 45. Structural anckft!! III (k) Mechanisal
- 45. Post-Accident Shielding XIX !!) Mechanical
- 47. Siemaic Category I, Electrical Duct Banks Manholes XIE (m) Mechanica!
- 48. Nitrogen System III (n) Mechanical
- 49. V (d)) Non-lE Primary Containment Leakage pate Testing System V (e) Non-lE
- 53. Caseous Raduaste Systee
- 51. I (b)
Turbine Ausillary Cooling System Non-lE i 52. Portable and Sanitary Mater System XI (d) Non-IE
- 53. II (h) Non-le
- Primary Containment ventilating System MIII (b) soon-I E
- 54. Ausillary Sullding Serv. and Baduaste Area i
Ventilating System j 55. Turbine Building ventilation Systee XIII (d) Non-IE
- 56. Miscellaneous Etructures ventilating System XIII (f) Non-lE 1 57. . Turbine sypass System XIII th) Non-lE
- 53. . Safety-Related Display Instrumentation alv 11) Non-lE
- 59. Control and Instrumentation for Systema Not XV (4) Non-lE/ Mild Required for Safety i 60. Process Samp!!ng Systee XV (f) Non-IE j 61. Fire Protection System XVII (c) Non-lE
, 62. Ausiliary Boiler System XVII (e) Non-IE 4
- 63. Equipment and Floor Drain System Evil (f) Non-It
- 64. Breathing Air EVII (g) Non-RE
- 65. Lighting System XVII (in Non-!E C6 XVII (j) Non-IE 67.
Aust!!ary Dulding Control Area Chilled Nater System XI (g) Mild Standby Diesel Generator and Ausillary System III 9811d
- 68. Diesel Generator Ea t (b) Mild
- 69. Electrical Modules with Safety Functions XII (c)
I
- 73. Cable uith Safety runction Mild
- 11. III (dl Mild 4
Main Control Room and Control Building NVAC System IIII la) Mild
- 72. Standby Diese! Gen. Area Ventilation System IIII (e) N!!d i
C3 PSS 60/05 5/6-er
. - . - . , . . - - - ~- -
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i i i i 4 8 i. I NCGS FSAn TAaLE 3.13 3 Page 3 of 3 SYSTEMS Fe0N NCGS FSAR That.E 3.2-1 Mo? InctuDED IN TAaLE _3.11-5 OR 3.II-6 DEScalPTION __...........--_ . _ -
.....- - =_ ..== - _..
*EF . TO TAaLE 3.2 3 REASON
___=_.. _.. l 13. Serv. Water intake Structure ventilating System
= _=-
74. j Kill (g) _
- 75. Reactor Trip System (meactor Protection System)
Control comptes panels IIV tal Mild ___
- mild
- 75. Local Panels and packs IV (g) mild 77 120-V Vital AC Systee Equipment XV th) Mild
- 79. 125v, and 254v Station satterlee and Rocks XVI (c) Mild XVI (b) n!!d t
4 1, I i s l 1 . I s a 4 e i 5 I l t I t i i i i i G P85 60/05 7/8-ar c e - - - - ____m.-- -- _____ .
- 4 4
, ;VIII- . QUALIFICATION TESTING / ANALYSIS - ; t,
- As is noted .in HCGS. FSAR' Section' 3.11, NSSS and non-NSSS
electrical components are qualified in accordance with the I
. EQ criteria and guidelines delineated in IEEE-323-1971 and noted ~as Category II' in NUREG 0588. Upgrading to IEEE-323-1974;and to Category I as-defined in NUREG 0588 is being -
- attempted _wherever scheduling. constraints 'and technical
-feasibility allow. The. safety related components' located in '
- a. harsh environment-are being qualified by test, or a combination ~of testing'and analysis for the worst case anticipated environmental transients under which they are required to function. i For safety related mechanical equipment located in a harsh environment, the EQ program establishes, via analysis, the qualified life of the component. This analysis is per-formed by identifying'significant aging mechanisms an de-
, fined'in IEEE-627-1980, Section 4.4.1.
s. The' environmental qualification evaluation is performed by
< comparing the non-metallic part material capabilitie.s, 1 including aging analysis results, to the environmental con- ,
ditions to which it'is-exposed. The material capabilities
- _ include L the ability to withstand temperature, radiation, ,
F .and ' aging - ef fects imposed by the environmental conditions. 'O i
' The environmental conditions include both ambient and process conditions. For the process condition, the' inter-nal radiation'and process temperature have been considered.
The! applicable internal radiation was determined for. the total integrated dose at the pipe center-line and the' . _ process temperature was obtained from the design i temperature specified in the equipment data sheets. The required radiation level was obtained by adding the + internal radiation ' to the normal and ' accident radiation. n The thermal capability of the non-metallic materials was evaluated to verify that the' equipment meets process tem-perature design requirements. The equipment manufacturers have'provided replacement schedules for non-metallic parts ; based on the. specified process conditions, both radiation ' and temperature. For the operating' life of a part,'the evaluation includes exposure to the normal environment fol-lowed by an accident and/or HELB environmental condition.
- ' Summaries of. material capabilities for temperature and
- radiation'are obtained from various handbooks and manu-l facturers. The material degradation as a result of thermal aging is calculated'using the Arrhenius model. ,
. \ il A qualification analysis is performed for each non-metallic I g- material within the scope of the program. The accept- l 1 3 ability'of non-metallic parts is determined by comparing
, 'the material capabilities to the process conditions and the j enveloping ambient environmental condition of all the !
l 1 VIII-1
/
dj < 4: associatedEmaterial requisitions. If the part can sustain
.. the' postulated process and ambient environmental. effects, Cp -it-is considered acceptable. Otherwise a replacement
(
.J schedule or; substitute material is recommended.
The'EQ' program conforms with 10CFR50.49.in that testing or a ' combinationof testing and analysis .was the preferred
; method ~of proving fcomponent operability under the worst >
fcase environmental scenarios. IEEE-323 methods were used ,
.for ' the analysis.- These _ analyses, when -performed for EQ to
. supplement testing, were-justifiedcand documented in the
. appropriate EQ' packages. Additionally, analyses were.used only.when their results could be shown to be conservative.
~ Analytical techniques included similarity, extrapolation and mathematical modeling.
- The actual' implementation of.the HCGS EQ program is sub-divided into the following two sections:
(1) NSSS Safety Related Components (a) Electrical ~ Components The ~ HCGS. EQ program ef forts for - NSSS safety re- ; lated electrical components are based upon the guidelines .^and methodologies outlined in General Electric's Licensing Topical Report #NEDE-24326-P. This generic approach, when coupled with HCGS plant specific environmental parameters has (V been reviewed and .found to be acceptable by the USNRC' Division of Equipment Safety. HCGS has sub-mitted. plant' specific environments consistent with those provided in-FSAR Section:3.11 including
' seismic and dynamic input into GE's EQ. program.
These~ parameters were enveloped in~GE's qualifica-tion; program.for devices in the HCGS' scope. GE's method of approach-for environmental qualifi-cation.is designed to meet the intent of the re- - quirements stated ~in Category I'of NUREG-0588. For each component supplied by GE, a determination
.of the need'for and scope of qualification testing is based on that component's relationship to the i following criteria:
Components.that will experience the environ-mental conditions of design basis events for which they must function to mitigate said accidents will be qualified to demonstrate operability in the accident environment for the time required for accident mitigation
'with safety margin to failure. ;O VIII-2
+:
Components-that will experience environmen-
'tal . . conditions of ' design basis events (dj Q - through which they:need not function for
' mitigation of: said accidents , but-through i :which they must not fail 'in a manner detri- -
mental to plant safety or accident--mitiga-
-tion will be qualified' to demonstrate the b capability to wittstand any - accident en-vironmenttfor:the time during which..they
. must not. fail with safety margin to failure.
Components i that will- experience environmen-tal conditions of' design basis events through . which they need not function for mitigation of said accidente, and whose failure (in any F mode) is deemed not detrimental to plant . safety or accident l mitigation need not be
. qualified 1 for .any accident environment,- but will be designed for their non-accident ser-4 vice environment.
4 The components .which are included in these cate-gories are subjected to the approach methods'and tests contained; in the GE Topical Report. These
- methods include, but are not limited to, the' type of testing ( type testing, analysis,
- partial type
- testing. with justified analysis, operating exper--
L... g lence, ongoing-qualification or any combination of
. these methods) component aging-(thermal, radia- '
tion, operational, vibration) and design basis ~
- event-(DBE) exposure. Inclusive of each of these
-methods are the associated ~ performance require-ments including-appropriate margins as. delineated in the GE defined '" Product-Performance Qualifica .
tion Specification" (PPQS). L ;In addition to delineating the operational re-quirements during the DBE and performance extreme testing,1 the PPQSs will address, as applicable, s such items as. submergence, fluid sprays, monitor-
- ing requirements (including frequency) for the
~. 1 components as well as component mounting and con- + < necting configuration requirements. The GE Topical Report also delineates the documen- ! tation and review requirements ^ necessary to com-plete'each component's EQ package. As a minimum, m the qualification documentation consists of the .
- L following
- !
\
l PPQS - Pretest Evaluation j Product Analysis Report - Test Plan and Procedures i
- - Functional Requirements - Test Report '
4
- - Environmental /
Application Data - Qualification l 1 VIII-3 I . _ _ . __ _ _ . - . . _ _ . . _ . _ _ . _ , _ _ _ _ . . _ _ _ _ . . _ _ _ _ _ . _ , - _ . . _
~. . . -. . - _
The' specific seismic and dynamic qualification
- documentation will include a determination of p natural f requencies to assure that none are below "h '
Hertz.. Appropriately justified analysis and testing-will be done to verify'this depending on the equipment type being qualified. Additionally, the four following generic USNRC "Open Items" con-
. cerning GE EQ Program #NEDE-24326-1-P will be res-ponded to in the following. manner:
1
- USNRC OPEN ITEM 91 s " I '. . Application of time margins less than one hour will be justified for each piece of equipment, including any judg-ments regarding survivability limits of the equipment."
GE/BCGS RESPONSE TO OPEN ITEM 91 The Functional Perform %nce Requirements shall
- document the function times for all Class 1E equipment and the supporting Design Record Files shall contain the justification for the
, margin for each function time less than ten hours if a time margin less than one hour is used. -The qualification reports for Class 1E equipment with time margins less than one hour shall document judgments regarding the survivability limits of the equipment beyond the tested time to the one hour margin limit.
USNRC OPEN ITEM $2 y "2. The required operability time will be justified with consideration for a spec- . trum~of breaks and the potential need t for the' equipment later in an event or during recovery operations." l GE/BCGS RESPONSE TO ITEM 92 , The Functional Performance Requirements shall document the function times for all Class 1E , equipment and the supporting Design Record '
# Files shall contain the justification for the margin for each function time less than ten hours if a time margin less than one hour is used. The applicable function times for all such accidents and qualification shall be e addressed in the qualification report.
VIII-4
f USNRC OPEN ITEM $3
- / "3.- It- will . be' demonstrated that f ailure of
( ' the equipment after the required opera-bility time will neither mislead the op-erator to'take an improper action nor further degrade the event by causing a failure in systems necessary for mitiga- , .- . tion of.the. event." GE/BCGS RESPONSE TO ITEM $3 I-
. The' Functional Performance Requirements shall contain' failure analyses which address fail-ure ef fects on other, needed equipment for
. those cases'where qualification is based on a time less than the accident duration.. USNRC OPEN ITEN $4 "4. The margin applied to the required oper- , , ability time when combined with other
- . test margins will account for the uncer-tainties associated with the design,
- f . production tolerances, testing tech-
- niques, and the- number of units tested."
GE/HCGS RESPONSE TO ITEM $4 4 For function times less than ten hours with
' time margins less than one hour, tests sh'all.
be - performed on more than one sample (size, costLand availability permitting) or margins increased, and the qualification report shall clearly state'that the equipment'is
- - only qualified for the time tested which
! shall include appropria.te time margin. All
- other margins shall also be applied as re-
. quired by NEDE-24326-1-P. !
(b) Mechanical Components
.The NSSS program for mechanical equipment qualification consisted of the GE recommended listing of all the class 1 mechanical compon-i ents which met the following criteria:
- (1) Safety related as defined by U safety function / time.
(2) Located in a harsh environment. ,. 9 (3) Used to mitigate an accident
/ including post accident opera-tion.
VIII-5 i' .
.....__._-..___.,_______,~.__.m__.__...._,.-_
I (4)' Contained non-metallic parts which were known to be age sensi-
'7- tive.
This. listing, included in this EQ Summary Report and in FSAR Section 3-11 as Table 3.11-4, is inde- l pendent of other ongoing EQ efforts such as ATWS/SDS, Phase 2 efforts, Class 1E efforts inclu- _ ded in this report, HPCI EQ and mechanical'compon- 1 ents located in the main control room. (2) Non-NSSS (BOP) Safety'Related Components (a) Electrical Components The Balance of Plant (BOP) EQ program is limited to the safety related electrical com-ponents supplied to HCGS by the A/E (Bechtel) and are identified and ordered by "Q" pur-chase orders. Each purchase order includes a material specification which identifies to the component vendors the envelopes to which L the components were to be qualified. If it was determined that the component being sup-plied by the vendor had been previously qualified for safety related use, the exist-ing test document ation was compared to HCGS requirements. Upon verification that the ( component met these requirements, the compon-k ents'were designated as qualified. If either , the component 7 test data did not conform to the HCGS criteria or if the components had not been previously qualified for safety re-lated use, the vendors were required to sub-mit their test plan to PSE&G/Bechtel for re-view and approval prior to the actual perfor-mance of the EQ test. Testing approaches sore justified and documented for inclusion in the EQ central file. (b) Mechanical Components The BOP mechanical components, like the elec-trical components, were identified and ordered by "Q" purchase orders. If the iden-tified non-metallic part was found to be the same material as that identified in the NSSS/GE qualification program or other vendor / industry related approved qualifica-tion programs, the results of these programs were used and no further qualification was performed. FLr other identified age sensi-tive non-metallic parts, (gaskets, diaph-p ragms, seals, lubricating oil or grease, packing, fluids for hydraulic system, etc.) VIII-6
y
# 1 Bechtel'det' ermined if further testing'would 4 ' be ' required . .to ensure that parts failure
'; would not jeopardize the components? ability
[\_/ to perform its required safety function. If
,- so, analysis 1 was performed ' by either the
. vendor or an independent testing laboratory to determine the parts replacement interval.
. - The types of components included in ' this
. fmechanical= equipment qualification program-include' the- following . items located in a.
~ harsh environment.
Pumps- -- Motor Operated Valves Fans - (Valves Only) T .-- Hydraulic - Safety'& Relief Valves Snubbers Turbine -- Check Valves Drives The listing of these BOP safety related, mechanical. parts located in a harsh environ- , ment and requiring EQ are listed in the at-tached Table 3.11-4. Review'of Vendor Reports a. The purpose ' of the review of vendor environmental quali-
- fication reports is to assure that the applicable environ-mental' operating conditions (normal / abnormal / accident) for each component required . to operate have been considered, evaluated-and achieved, or that deficiencies have been identified and resolved.
~
, Each qualification report received by Bechtel and trans-
-mitted to PSE&G for' review is assigned a unique documenta-
, tion. identification number. For components supplied'by the NSSS: vendor (GE), this : number references a "GE Book h Number". For the remaining components, this number-is cor-related to the purchase' order identification number. In either case, when an EQ report is received by PSE&G and/or Bachtel, it'is. reviewed in detail in the manner described below.
. Items included in'the review of EQ reports include the fol-lowing:
a) Verification of the test method used (i.e., type test, analysis, operating experience or combina-
. tion).-
b) Review of the equipment type, model or product identification number, serial number, batch number and other salient component descriptions to en-
\ sure that the component being. tested is indicative of the actual component being procured for system installation.
9 VIII-7
i c) Verification that EQ documentation is traceable to
/ the component being tested.
- . d)- Correct categorization.of~the component testing to
[ applicable standards (NUREG 0588 Cat. I cr Cat. II, IEEE-323-1971 or 1974, etc.). e_) Verification of the adequacy of the . test proced-ures to address the following areas of concern:. (1) Performance of testing sequence per
- IEEE-323-1974 or justification of method used to ensure most severe sequencing.
This includes pretest preparation, com-ponent mounting configurations, inspec-tion and proper function measurements.as well as verification that the same test 4 specimen (s) is used throughout,any test- , ing. [ (2) Addition of' margins to test parameters- ! time durations and the justifications
, - for.these margin selections to meet the ,
intent of'IEEE-323-1974 and IEEE-627-1980. i (3) Verification that the aging (thermal, O radiation, mechanical cycling , electri-cal cycling, synergistic effects) tech-niques are properly analyzed, applied ~ and justified to provide the most con- t . servative end-of-life component test condition. Acceptable thermal agingf techniques for electrical and mechanical components in-
. cluded ' the Arrhenius method = or other justified methodology in accordance with IEEE-323 or IEEE-627. Thermal and radia- ,
. tion aging was considered on an indivi-
, dual' component basis in that the compon-ent must contain an age sensitive (organic) part to be applicable. ; Each ' aging method - ( thermal, . radiation, - mechanical, etc.) was reviewed to ensure that it placed- the; equipment in its end of qualified life condition before sub-jecting'it to its worst case DBA. The age related degradation verification in-cluded concerns about normal / abnormal operating. temperatures, radiation expos-ure and cyclical mechanical operation VIII-8'
,. -.u_-,_ ._,t -. -. _ . _ _ _.. _ _ _. _ _ .--,_ _ --_ , _ ._ . _ _ _ _ , . . ,
and electrical ( feeder voltage variat-ions, etc.) stresses which are antici-pated to occur during the normal (pre-( (')N DBA) qualified life operation of the equipment. (4) Verification that synergistic effects were accounted for, justified, and docu- _ mented, where applicable, in accordance-with NUREG 0588. (5) Review to ensure that variations in am - bient environmental conditions, such as non-seismic vibration, dust, humidity, moisture ingress, submergence, etc., have bean considered, evaluated and ad-dressed. (6) Verification that the most conservative DBA environmental conditions for the component being tested have been envel-oped or that deviations have been ade-quately justified. (7) Review of the test results to ensure that the component was correctly ener-gized and/or operated to simulate re-quired nortal/ abnormal /DBA operating [3j V conditions during all phases of the EQ testing. This includes review of the test parameters monitored to verify re-quired extremes in test conditions (vol-tages, currents, input / output signal ramping, loading, etc.), are achieved. Also, verification that the instrumenta-tion used to monitor, control and record test parameters has been properly cali-brated and documented. (8) verification that the determination of equipment failure has been defined and i that' resolution of any failure has been clearly identified and justified. If 1 modifications to either the component or I test setup have,been made, verify that i they are justified. l f) Verification that the documentation packages are complete and accurate and that they address: (1) Applicability of component testing to HCGS. O (j (2) Equipment performance per vendor technical specification require-ments. VIII-9
_ _ _ _ _ ~ _ _ _ _ _ _ _ _ . . _ . _ . - _ _ _ _ . l (3) Synopsis of test plan including
/' test objective; equipment tested; l test facility description; listing '
of calibrated instrumentation'used; test procedures; test data and ac-curacy; summary, conclusions _and , n recommendations; support data; and _ proper signoff and dating of EQ re-port. g) If operating experienc? is used, verify that the-components monitored and the environmental condi-tions listed are applicable to HCGS. Documentation
'and justification of applicable performance, en-vironmental, failure and maintenance conditions must be verified.
F .h) If analysis methods are used, justification for analysis and the analysis methodology must.be i . verified.- All . assumption 3, empirical values, mathematical models, failure analysis, computer , programs, extrapolations, etc. , must . be documen-ted, justified, and properly signed off/ dated. F Upon completion of this detailed review, areas of concern 4 by PSEEG/Bechtel are documented, . numbered and returned to j the component supplier for resolution. Resubmittals are in O- turn reviewed in detail and this " review / comment to vendor-
/ resolution /resubmittal" process is repeated until the EQ ,
report satisfies the concerns of PSE&G/Bechtel of the'com-ponents ability to perform its function under any postu-lated plant condition. Component Test Witnessing Stipulations within purchase orders placed with vendors sup- . plying _ safety related electrical.and mechanical equipment requiring environmental qualification testing specify. that , Bechtel and/or PSE&G be advised of the schedule.of particu-larly important stages and events of the EQ test program.
,This timely notification-has allowed the opportunity fo'r Bechtel/PSEEG to inspect both the components being tested
- and the test. facilities as well as to witness key events.
The activities, stages, and events that have been witnessed include, but are not. limited to, the following: r a) Component' physical mounting / set -up for DBA- test-
.ing.
b) Start-up of.DBA chamber testing. [' c)- Configuration of test monitoring / data collection
- instrumentation.
VIII-10
9 d) Eet up and performance of seismic testing. e) Verification of proper test sequencing. f)' Thermal aging facilities and test setups. g) Mechanical (repeated operation) and electrical-(voltage / current / frequency variations) cycling _ methodologies and test setups.
- h) Radiation exposure rates, durations and source strengths.
- 1) Component failure. recognition and determination of problem resolutions.
The above noted tasks are separate from, and in addition to, those functions performed by the Quality Assurance or-ganization noted in Section V of this EQ Summary Report.
.1 O /
I e 4 VIII-11 i
k i i
./ M h IX FOLLOW-ON PROGRAM HCGS 'is ' developing a maintenance and surveillance program to ensure compliance with 10CFR50.49 and Regulatory Guide 4
1.33. . The components for this program were selected as a
'r_esult of-detailed review of existing documentation, (FSAR, Tech-Specs, System. Descriptions, etc.), drawings.(P&ID's, loops, one lines,'etc.).and review of the Master Equipment List (MEL) and, as such, includes all safety related elec-trical and mechanical-equipment located in both harsh and mild environments. The purpose of the program is to pro-vide a documented . method to verify that the required main-tenance and surveillance are. performed. This ensures pro--
~ per equipment operation over the. equipments' identified qualified life. Maintenance of the. items ranges from periodic visual in-spection'of the equipment to detect excess wear and/or verify proper . working order to scheduled replacement of identified parts-or even total equipment replacement when
.necessary.
. The maintenance and surveillance program addresses the two. following categories:
!(1) Components in a Harsh Environment-The safety,related electrical and mechanical com-ponents located'in'a harsh environment have been iden-
.tified in Section VII-of this'EQ Summary Report.
These components are subdivided into the following cate-gories:- (A) Components. with a qualified forty- year life , which require no replacement . parts or plan-ned maintenance for their stated life. These ; i . components are listed in the maintenance and ! ,, - surveillance program and the operating pro-cedure or normal operating mode used to ver- ;
;' ify the devices operability; is also listed.
This listing is " passive" in that normal: operation provides for this operability verification. However', the components'in-clusion on~the program's list provides a mechanism to: identify unanticipated failures or abnormal' operation should they occur. In th'is way, failure trending allows identifi-1
- cation of any compromise in the components-qualified life and will allow re-analysis on l a real. time, case by case basis.
? l 4- j J IX-1 ) E i .- , - -,_a. . . _ _ . __ ._ . - _ . _ _ _ . . . . . _ . - , _ _ _ . . , _ . . . . _ . . . . -
i (B) Components with a qualified _ life .of forty ! years if. identified parts are replaced or if ! ^f the ; components are replaced in total are
-\ identified. This provides plant mainten-ance/ performance department notification, ,
of both the maintenance required and the
- date by which the action must be completed i to ensure the components operability re- :
.quirements over the plants. forty-year life.
i' The notification provides for adequate lead . time needed to procure replacement parts / components, if' applicable. (2) Components'in a Mild Environment l Using. the MEL for reference,' the safety related com- .. ponents located in a mild environment are identified i i and subdivided into the following categories: (A) Components whose operability is proven via i
~ either Tech Spec requirements (Diesel Gen-erators, SW Pumps, ESFAS, etc.) or via nor-mal. plant ~ operation (breakers, relays,- ,
valves, pumps, etc.). Maintenance and/or replacement of component parts or total , 4 component. replacement is based on a combina ; 'g p tion of-man'ufacturers'~ recommendations, good engineering judgement and/or actual plant , g experience with the components. (B). '. Components whose operability is verified via scheduled maintenance and surveillance procedures. . Frequency of procedure perfor-mance and corresponding replacement of iden-
. tified parts or total component replacement is based on a combination of manufacturers' maintenance recommendations, l good engineer-ing judgement'and/or actual plant experience on a-component by component basis.. 1 Engineering Interface-With Plant EQ Program The following engineering information exchange is provided to the station for the Maintenance and Surveillance Pro- -
' gram:
- (1) Maintenance / Surveillance documents which summar-
.ize the safety related electrical and mechanical components located in 4 harsh environment with a forty year qualified life.
O : + IX-2 I i
,.,.y -
5 - - - -- - . - - ..-, -, , . . y *-- , . , , ,e .- -.---
(2) Documents summarizing the safety related electri-cal and' mechanical components located in a harsh
.em environment which require maintenance, replace- !j ment of parts and/or total component replacement to meet. the forty year qualified life commitment.
- The documents delineate maintenance requirements and maintenance / replacement intervals. (_3) .For safety related electrical components located in a mild environment, engineering provides, where available, documents delineating mainten-
-ance requirement and maintenance / replacement in-tervals. Where the information is not svallable, maintenance requirements and maintenance / replace-ment intervals will be established by review of Technical Specification requirements, vendor documents and industry practica.
Additionally, as HCGS achieves commercial operation and as-sociated work history experience, these time intervals.may be updated to' reflect actual operating experience. Feed-back from the industry via vendor technical bulletins,
' USNRC IE Bulletins / Notices, NPRDS, INPO reporta, etc., will
' also be used to further refine maintenance / replacement inter-vals.
/ 'N 1
'k J
IX-3
,cu V X. EQUIPMENT ENVIRONMENTAL
SUMMARY
SHEETS The Equipment Environmental Summary Sheets (EESS) provide a tabulated synopsis of the EQ related data on a component-by-component basis. This data is taken from the EQ file which includes the actual EQ test data for each component. A sample EESS and the instructions for completing the EESS are included as an attachment to this section. The EESS are included in this section for all plant equip-ment which is currently qualified. These EESS will be supp-lemented.and updated as this report is revised. An index of these sheets is also ' provided for ease of reference. .Jf -f X-1
a A. sw _3g,,,4 .aM,- A4 - A,. __._ . 2i#4h.. ..a-, m 4 A . eu.2 4_# e -
.h-4 -
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J e i e f i 4 m HOPE CREEK GENERATING STATION EQUIPMENT EVALUATION
SUMMARY
SHEET (EESS) , PROCEDURE - 4 i e d a L E i
- 1 l
, i ( l
)
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t 1 O A sample Equipment Evaluation Summary Sheet with attachments and a description of sequential steps to identify and complete each item, as marked up on the' subject sheet, is attached.
- 1. System _of.whi~ch the equipment is a part (i.e., RCIC, HPCI, etc.). If more than one system is involved, indicate "Various" and demonstrate further details in attached sheets. (Refer to Note #2)
'2. Bechtel tag number ( s) . (include system designation.1 For multiple components refer to Note #2.
- 3. Generic descripcions of equipment (i.e., pressure
. transmitter, temperature element, etc.). (Use same description that is in Table 3.11-5 data base.]
- 4. Name of actual . equipment manuf acturer, (not the
. principal vendor, i.e . , GE , Westinghouse, etc.).
- 5. . Equipment manufacturer model number (preferred) or l drawing number of the equipment being used at HCGS.
'(Not of the equipment - being ' tested, if it is different)
/~'% 6. For equipment in harsh environment, give a brief
- V description of:
Safety' Function and/or Post Monitoring Function per-formed by the equipment. If the equipment is not per-forming any of the above function, but is qualified for-harsh environment since it is fed from Class IE Power Supply, state the normal function and als'o state that the equipment is fed from Class IE Power Supply. Categorize.the equipment as per Appendix E, NUREG-0588 and incorporate as a " Note". For multiple components refer to Note #2. 7a. Accuracy of the equipment / instrument as specified in the Bechtel Specification. (Not applicable if the . equipment is passive). 7b. Accuracy of the-equipment / instrument as demonstrated in the-report. _If 7b is not as accurate as 7a, then a t k O
2
.p-3 ,) note should be added directing the reader / reviewer to an explanation if this is acceptable. (Not applicable if equipment is passive.) '
- 8. Location in the plant in which the equipment can be
_found1(insert Building and Elevation and/or Room No.). For multiple components, refer to Note # 2.
- 9. Determine from the related specification if the equip-ment is subjected to Flood.ing condition. Identify "Yes" or "No".
.10 . If seismically tested, identify the test report as a reference document (See SQRT File) and the status of s Bechtel seismic evaluation.
.,. 11. If maintenance and surveillance is required, state the reference document. (Use vendor Report No. and list page no. of report).
- 12. The specified length of time, starting with DBE initia-tion,-during_which the equipment is required to perform -
its safety function or not fail detrimentally. (Refer to Note-4)
/'g'v) 13. Document'the specification for-Item 12 and page number (s).
- 14. The specified time-dependent temperature profile during the period of Item 12, for the time the equipment is required to perform its safety function or not fail detrimentally. If space'is not sufficient, include related " DATA" in a " Note". (Refer to Note-4) i.
- 15. Document the specification for Item 14 and related page numbe r( s ) .
- 16. The specified time-dependent pressure profile during
-DBE under which the equipment is required to perform its safety function or not fail detrimentally. If space is not sufficient, include related " DATA" in a
" Note". (Refer to Note-4)
- 17. Document the specification for Item 16, and related page number (s).
U o
3 18 . - The specified time-dependent profile of relative humid-ity during DBE in which the equipment is required to perform.its safety function or not fail detrimentally.
-(Refer to Note-4)
- 19. Document the specification for Item 18, and related t page; number ( s) .
20.- Incorporate specification requirement if the equipment
-is below flood / froth level elevation. "None Required" if'it is above highest flood / froth level elevation.
The entry should be consistent with Item 9 for flood.- ,
- 21. Document the requirement for Item 20 and related page number (s).
- 22. Radiation exposure expressed in RAD's. This shall be the total integrated dose (TID), including the periods of normal service and'DBE. Gamma s Beta and Neutron sources shall be addressed. Include brief calculation as " Note", if required. -(Refer to Note-4) -
' 23. Document the specification for Item 22 and related page
- numbe r( s) .
- 24. -Enter environmental and operating stress [ temperature, cycling- (e.g. valve actuator) , etc.] for 40-year period, excluding DBE; for-pipe-mounted equipment, include any specified long term vibration. In addi-tion, hydrodynamic loads of a long duration shall.be specified and applied therein.
, 25. Document the specification for Item 24 and related page numbe r ( s ) .
- 26. If applicable, state containment spray. rate. If not applicable state "N/A".
1
- 27. Document the requirement for Item 26 and related page f
number (s).
- 28. The length of time', starting with DBE initiation, dur-
- ing which the equipment has been demonstrated to per-form its safety function. (Include DBE test duration.
and equivalent time. Arrhenius Methodology shall be t included as applicable]. O
-r- -r- -.,m ,.,,,w- - . , . . - - . - - , , , - - - - . . - . , , , , , , - . - - , - ~ . . - - ,
f 4 *
- 29. The auditable exhibit
- that documents the demonstration for Item l28. Also include calculation sheet reference, if applicable. (Note #1)
- 30. The time-dependent temperature profile to which the
- equipment has been exposed and demonstrated to function p rope rly . : If: space is not' sufficient, include " DATA" in a " Note".
31.- The auditable exhibit
- that documents the demonstration of Item 30.- (Note #1) 4
- 32. The time-dependent pressure. profile to which the equip-ment has been exposed and demonstrated to function properly. If space is.not sufficient, include " DATA" in a " Note".
-33. The auditable exhibit
- that documents the demonstration of' Item 32. (Note #1) 34.- The time-dependent profile of relative humidity to which the equipment has been exposed and demonstrated to function properly.
35. The auditable exhibit
- that documents the demonstration
-( ) of Item 34. (Note #1)
[36. A statement of capability during and after submersion and/or exposure to flooding / froth.
- 37. The auditable exhibit
- that documents the demonstration of Item 36. -(Note #1)
- 38. .The total integrated radiation dose to which the equip-ment has been exposed and demonstrated to_ function
-properly. (Identify type of radiation user.).
- 39. 'The auditable' exhibit
- that-documents the demonstration of Item 38. (Note #1)
- 40. Qualified life or calculated life based on aging (Arrhenius Methodology) for conditions in Item 24. For multiple subcomponents refer to attached sheets which
-include the subject information as shown-in Example !
#2. Also refer to Note #3.
l l
. 1 l
< 5 - (-N . -]' 41. Reference the Equipment Qualification Report and 'the auditable document
- that. documents the demonstration of
-Item.40 (especially aging exposure).
- 42. _ A statement of capability during and af ter exposure to spray, if required.
43. The auditable exhibit
- thatLdocuments the demonstration of Item 42.
- 51. Entries will consist of " TEST," " ANALYSIS" - TEST " &
ANALYSIS,." or "NONE REQUIRED" as applicable.
.52. Excess of demonstrated or calculated time of operabil-ity over that.specified. (Magnitude, duration, etc.)
- 53. Temperature dif ferential between peak exposure and maximum specified. (Magnitude, duration, etc.)
54.- Pressure differential between peak exposure and maximum specified. (Magnitude, duration, etc.) -
- 55. State "Not Required."
~
'56. State "Not Required."
- 57. Difference between the TID of the radiation exposure and the TID specified.
- 58. State "Not Required." Include any.special requirement in It.em 66 and " Remark" column.
'59. State "Not Required."
' KEYS 60-67 Entries shall state "YES" or "NO,", and, if YES" "
provide reference to that part of the report containing discussion of action plan. An open item is any i' tem that is not resolved and has the potential of negative-ly af fecting the - qualification of the component.
- 68. ' Assign Sheet No. to each EESS as listed below:
Purchase Order ~No. - Component Code - Sheet No. t-i O
,--,e. -n.,--, _ , - - - ..r., ,.- ,-
6 t
- 69. Sign. Of f by the Preparer with date. (Refer to Note 5)
- 70. Sign Off by the Reviewer with date.
(Refer to Note 5) NOTE:
- 1. *Auditable exhibit shall be the actual vendor or-test lab report and number. The Bechtel " Vendor Report No."
by which PSEEG identifies documents shall be put in , parenthesis after the actual vendor or test lab report. Example: Franklin Test Lab. Report C-19720 ' -(E-1700-49(1)-5). This report identification may be
' section coded toofthe " Documentation
Reference:
" lower lef t the form. i
- 2. Multiple components may be placed on the save EESS i i
sheet if all conditions are exactly the samG except for Items 1, 2, 6, and 8. If required for multiple compo-nents, information regarding the subject items shall be provided in the table as shown in the attached-sheet. . 3. .For Switchgear, Panel or MCC, the-following approach
- shall be taken to prepare the EESS sheet.
f-~) a) ~ If the equipment is qualified by testing as a whole ( j with all the components mounted 96 it, and.quali-fled life of components are analyzed separately, prepare one EESS sheet for the whole equipment and separate EOMSIS sheets for components. Describe any limitation in Remarks column or include in Note if sufficient space is not available. b) If the different components of the equipment are qualified by testing or analysis and the equipment is not qualified by testing as a whole. Prepare EESS sheet for common information and list the balance of information on-separate attached sheets.
- 4. Review latest revisions of Dits 7.5 and respective specification. Address most conservative value. In case the component is not qualified by Dits value, address specified value, and mention the Dits Value in
" Remarks". Indicate "Open Item".
O I
--,- - .-..,-,.w---- , , , - - , , , ,,- r ----
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'5. Either Preparer or Reviewer shall be the PSEEG Environmental Qualification Engineer.
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