ML20041E573

Interfaces for Standard Designs

ML20041E573
Person / Time
Issue date:	08/31/1976
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
NUREG-0102, NUREG-0102-DRFT, NUREG-102, NUREG-102-DRFT, NUDOCS 8203110099
Download: ML20041E573 (71)

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INTERFACES FOR STANDARD DESIGNS

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Division of Systes Safety

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, INTERFACES FOR STANDARD DrSItinS 1.

,1NTE000CTION Safety-related interfa:es must be identified and defined for standard designs submitted under Option 1 (Reference Systems) of the Connission's standardization policy

• to establish the requirements that must be met and assumptions that must be verified by other unspecified portions of a nuclear plant design to assure that systeris, cornponents, and structures within the standard design w!11 perform their safety functio'ns. The safety functions of a standard design are those essential functions that assure (1) the integrity of the reactor coolant pressure boundary; (2) that the specified acceptable fuel design limits are not exceeded as a result of anticipated transients; (3) the capability to shutdown the reactor and maintain M in a safe shutdown condition; and (4) the capability to prevent or mitigate the consequences of an accident that could result in radi.ition exposures in excess of applicable guidelines. Interfaces are utilized, therefore, to provide a basis for assuring that the matching portions of a nuclear plant design, as described in a PSAR far a CP application that references the stantiard design or in another Standard Safety Analysis Report (SSAR) for a matching portion of the plant, are compatible with the standard design regarding the safety-related aspects of the plant design.

• See WASH-1341, "Progrannatic Inforr.ation for the Licensing of Standardized Nuclear Power Plan 6s", and Amendment 1 thereto, for the specific policies and procedures established for standa:tilzation applications.

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2 This staff report describes safety-related interfaces, for light water reactors only, at the preliminary design stage of review, that should bt presented by the reacto. veMor in a Nuclear Steam Supply System SSAR (NSSS-SSAR),* and that should be presented by the architect-er.gineer in a Balance-of-Plant-SSAR (BOP-SSAR).* The interfaces for a BOP-SSAR arr. also directly applicable to an SSAR describing an entire nuclear plant (NSSS plus BOP, but exciuding utt11ty-and site-specific items). This report also describes an acceptable fomat for presenting interfaces in an SSAR.

Criteria for detemining the acceptability of interfaces are not included in this report. Acceptance criteria are part of other guidance already made available by the NRC, including the Regulations, Regulatory Guides, codes and standards, Branch Technical Positions, and other positions given in the Standard ReviewPlan(NUREG-75/087).

i The compilation of interfaces presented in this report is based on staff consideration of all safety criteria applicable to the review of nuclear power plant designs including those contained within the Regulations Regulatory Guides, Branch Technical Positions, codes M

• The specific interface items presented herein apply or.ly to an NSSS/ BOP division of design scope for a nuclear plant; they do not apply to any other division of design scope such as a nuclear island / turbine island.

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. and standards and the Standard Review Plan, and the background and experience acquired during ^.he staff review of the several standard design applications already suteltted. In this Ifght, tne staff considers the present listing of interfaces to be e.nentially complete. However, s'.andard design applications and utility applications referencing standard desig r. should not necessarily be limited to the interfaces 14'ted; any additional interfaces determined to be important to safety should be identified and addressed in these applications, especially those that may be unique to a particular plant design. It is also the staff's intent to supplement and revise the interface 'lists, as well as other aspects of this report, as additions and modifications are indicated.

!!. SOURCES OF INTERFACES Interfaces for standard designs stem from the following sources:

Requirements for safe operation of the standard design that a.

must be satisfied by matching portions of the plant design or by the utility (e.g., cooling water and electrical power requirements for the NSSS that must be provided by the BCP.

an inservice inspection program for the HSSS and B0F that

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must be provided by the utility).

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Asstseptions made for the stiMard design that sust be more precisely defined during the aesign ccordination effort between the reactor vendor and the architect-engineer or between the architect-engineer and th:, utility (e.g., ~ss and energy release rates during a LOCA specified by the NSS$ that sost be coordinated with the containnent design provideu by theB0F).

Site-related design assumptions upon which the standard design c.

is based.

d.

Criteria pertinent to the standard design described in the SSAR under review, that may be utilized for the design and staff review of matching systems, coeponents and structures (i.e., design criteria for the items within the standard design including codes and standards, General Design Criteria, Regulatory Guides, and Branch Technical Positions).

Each of the above sources was utilized by the staff and, in turn, should be utilized by reactor vendors and architect-engineers when e

identifying and defining interfaces for presentation 'n SSAR's.

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, III. INTERFACFS TO BC ADDRESSED IN SSARS The interface items that should be ad,, sed in SSARs for both norrnal and abnomal operating conditions have been identified by the staff as shown in Appendic.s A and B.

Those interfaces listed in Appendix A should be defined by reactor vendors in NSSt-SSARs.

Those Itsted in Appendix 8 should be defined by architect-engineers in BOP-SSARs or by other organizations in standard plant SSARs (NSSSplusBOP). In addressing these interfaces, the standard desir,n applicant rust clearly define t'.e scope of design encompassed by the SSAR; the definition so provided should be consistent with the gross definition of the content of NSSS-SSARs and BOP-SSARs as given in Amendnet I to WASH-1341. The sources of the interfaces Itsted in Appendices A and B are items a, b, c, and d described in Section II abave.

IV. UTILIZATION OF INTERFACES PRESENTED IN SSARs All interfaces presented in an SSAR must be addressed in a referencing SAR (either a PSAR for a CP application or another SSAR) that describes the matching portion of a nuclear plant design. The description of the matching portion must clearly indicate that each h,

interface has been recognized, utilized, and satisfied by the design h,

Wh of the interfacing system, component or structure. For those inter-g

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faces involving a design coordination effort between the reactor hih v

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54 vendor and the architect-engineer, the utility applicatia.n must clearly indicate the oatcome of this effort in terms of the resulting design of the interfacing systers, components and structures. In this way, the compatibility of ratching portions of a* plant design with regard to licensing requirements as demonstrated.

For s.ce interfaces, the utility PSAR referencing a standard design must demonstrate that the site design parameters established as the basis for the standard design are compatible with the characteristict of the proposed plant site described in the CP application.

It should be noted that acceptability to the staff of the compatibility of matching partions of a plant design with regar ' to licensing require-ments in no way relieves the utility applicant, that has re.serencers a standard design (s) in his application for licenses, from his responsibility under the Regulations to assure that all interfaces between matching systems, components and structures are satisfied for compatibility.

V.

FORMAT FOR INTERFACE PRESENTATION IN SSARs Interfaces should be presented in an SSAR in a manner tnat will facilitate their location by staff reviewers and other groups

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involved in the licensing and design processes. In addition, interfaces should be presented on a system-by-system basis

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. consistent with the approach for presenting plant design J

information established in Regulatory Guide 1.70. The following guidance for presenting interfaces in SSARs describes an acceptable format to acewlish these purposes:

a.

Chapter 1. "Iniroduction and General Description of Plant,"

should include an interface section presenting an overall

" road map" matrix to guide the reviewer to other sections in the SSAR where the specific interfaces can be found. The matrix should include:

(1) a listing of all systems and structures within the standard design that interface with matching unspecified portions of the plant; (2) a listing of other interface areas that can be referenced in support of the items listed in (1) above; (3) a listing of the particular items in the matching unspecified portion to which the standard design items l

interface (e.g. the RHR* system in the NSS-SSAR interfaces with the CCWS, Emergency On-Site Power System, Containment Sump, Refueling Water Storage Tank, etc. in a BOP-SSAR or a PSAR);

(4) identification of the se:: tion in the SSAR in which the specific interfaces are described.

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8 Examples of an acceptable approach fcr preparing the matrices for an NSSS-SSAR aid a SOP-SSAR are shown in Figures 1 and 2 respectively.

b.

Specific interfaces should be presented on a system-by-system basis to the maxiream extent practicable, and should be shown in a separate subsection, as identified in Appendices A and B, directly associated with the sys*m description (not in tha section assigned by Regulatory Guide 1.70 for the interfacing system description). The subsection should incorporate drawings, p&10s, an..4eles either directly or by referer.ce (providing the interfaces intended to be referenced are cle.1rly indicated therein). In general, descriptive rsaterial in other sections that stay contain interfaces should not be referenceo, Interfaces of a broader nature that apply to classes of c.

systems, coeponents or structures, such as ite.s (2), (3),

l (4), and (16) in Section d (below) for an NSSS-SSAR, should be presented in the appropriate sections of other chapters of the SSAR (e.g., Chapter 3). These are supporting interfaces that should, in turn, be referenced in the interface subsections for tne systems and structures described in the l

SSAR. Examples include site design parameters, protection

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9 against missiles, protection against pipe whip, industrial security, etc.

d.

For an hSSS-SSE, W interfaces identified in Appendix A should be presented in :ne following categories to facilitate review:

(1) Power - Requirements for all types of power for safety systems and components.

(2) Protection Against Nat6ral Phenomena - Requirements for protection of systems and compc,nents against naturally occurring events such as earthquakes, wind, torr.adoes, I

floods, etc.

- 1 (3) Protection Against Effects of pipe Failure -

Requirements for protection cf safety-related systems, components and structures inside and outside containment against the dynamic effects resulting from the failure of piping in high-and cederate-energy systems including pipe whip, jet icpingemect, and <>ther

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t (4) Missiles - Requirerents for protection of safety l

systems, reactor coolant pressure boundary, and t-contain-ent against internally-generated missiles and N f_

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. (5) Separation - Requirements for physical separation to prevent a single event from causing failure of redundant safety systems and components.

(6) Independence - Requirements for independence to prevent a failure in a safety system or cocponent in>m causing failure in its redundant safety system or component.

(7) Thennal Limitations - Requirencnts for heating and/or cooling of safety systems and co ponents including fluid conditions and limitations.

(8) Monitoring - Requireme6ts for performance surveillance.

testing, and inspection of safety systems and components.

(9) Actuation / Controls - Requirements for actuation of safety systems and corponents and for control of their subsequent operation.

(10) Chemistry /Sa gling - Requirements for fluid chenistry, purity and sampling.

(11) Materials - Requirements for materials for safety systems and components.

(12) System / Component Arrangement - Location requirements (including inservice inspection and testing) that safety systcas and components place on plant arrangement.

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• (13) Radioactive Waste - Requirements for the collection, treatment, and disposal of radioactive wastes.

(14) Related Service - Requirements for other services for safety systems and components (e.g., ihterfaces from item e below, fire protection, compressed air, etc.).

(15) Overpressure Protection - Require-ents for assuring that pressure limits for safety systecs are not exe.eeded.

(16) Environmental - Requirements for environmental conditions that must be provided for proper operation of safety systems and components.

(17) Mechanical Interaction Between Systems - Requicements for consideration of differential motion including seismic effects and thermal expansion.

(18) Design Criteria - Criteria upon which the !!SSS system

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des'.gn, or portion thereof, is based.

For a BOP-SSAR, interfaces identified in Appendix B should be presented in the following categories to facilitate review:

(1) Power - Requirements for all types of power for safety systems and compor.ents (e.g., offsite power to plant during certain conditions, power from plant to site-specific components).

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(2) Site Parameters - Site design paramter., based on site characteristics (seismic, geological, hydrologics!, ar.d K

lreteorological), utilized for the desir,n of systems, components.nd structures against naturally occurring

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(3) Missiles - Missiles generated by natural phenomena utilized as the ' oasis for the design of systems, components and Structures.

(4) Thermal Limitations - Requiretrents for coolirg safety systems and ccetponents including fluid s.onditions and

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(5) Mor,itoring - Requirements for performaxe surveillance, testing, and inspection of interfacing safety systems and components.

(6) Actuation / Controls - Requiremtnts for actuation of interfacing safr ty systerr.s anc corrponents and for

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g (7) Materials - Requirements for materials for safety systems and components.

(8) System /Cceponent Arrangement - Location requirements (including inservice inspection and testing) that I

safety systems and components olace on plant arrange: rent.

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. (9) Radioactive Waste - Release of radioactive material to the environment.

(10) Related Service - Requirements for othat services for safety systems and cormonents (e.g. interfaces from e below, fire protection, compressed alt, etc.).

(11) Mechanical Interaction Between Systems and Buildings -

Requirerents for consideration of differential cotton including seismic effects and tisernal expansion.

(12) Design Criteria - Criteria upon which the BOP system design, or portton thereof, is based, The physical points of interface for fluid systems should be e.

indicated on piping and instrurnentation diagrans (PSIDs), and for electrical systems on elemntary/ schematic / logic diagrams and block diagrams to clearly show the line of demarcation between the standard design and tne unspecified matching portions of the plant. Each interface point should be uniquely labeled. Safety-related fluid and ele:trical interfaces applicable to each point, as identified in Appendices A and B, should be listed, censistent with the system-by-system basis established for the definition of interfaces (e.g., the compressed al.- requirenents for all air operated valves in the system as a group, the DC power requirements for all DC instrumentation in the system as a I

group, etc.).

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All the standard design interfaces should be utilized in a referencing SAR (either a PSAR for a CP application or another SSV) for the design of an interfacing system, component or structure, for the design nf utility specific items, or for the detennination of standard plant / site compatability. The specific interfaces used for each interfacing area should be identified. The identification should be presented in the " Design Bases" section of each system description. Identification should consist of appropriate references to the interfaces in the refererced SSAR; the specific interface 1, should not be rewritten or reprinted. For interfaces to P& ids and to electrical diagrans in a referencing SAR, a similar procedure should be utilized.

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. Figure 1 Example of.4strix of interface Areas for an NSSS-SSAR e

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SYSTEM INTERFACE AREAS Reactor Coolant Pressure Bour4ary X

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5.2.6 Esaargency Core Cooling Systems X

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X 6.3.6 Reactor Trip System X

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X 7.2.3 Habitability Systems X

X 6.4.7 Fuel Handling System l

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9.1.4.6 Standby Liquid Control System X

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X 9.3.5.6 Chnical & Volume Control System X

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9.3.4.6 Reactor Wate: Cleanup System X

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5.4.8.4 Residual heat Removal System X

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SUPPORT 1kG INTERFACE AREAS bh Flood Protection 3.4.3 Missile Protection 3.5.4 j

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Pipe Whip Protectier.

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Mechanical Systes & Components l

Environmental Design of Hechanical i

and Electrical Equipment 3.11.6 eg7df Inservice Inspection of Class 2 & 3 6.6.9 PS Compoa.ents ce-Fire Protection

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INTERFACE AREAS FOR SYSTEMS, COFDONENTS, & STRUCTURES Station Service Water Systen X

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9.2.1 Instrumentation and Control I

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7.8 Fire Protection X

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9.5.1.6 On-Site A.C. Pcwer Systm X

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8.3.1.5 Water Systems X

X XX 9.2.7 1.iquid Waste Managenent Systen X

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X 11.2.4 Gaseous Waste Managernent System X

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Effluent Monitoring and Sampling X

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SUPPORTING INTERFACE AREAS

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Wind and Tornado loadings X

3.3.3 Water Level Design X

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3.7.5 Design of Category I Structures X

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3.8.6 g4 Industrial Security X

13.6.3 M.u.r Mechanical Systems reA Components X

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APPENDIX A NUCLEAR STEAM SUPPLY SYSTEM INTERFACES l

NEW INTERFACE SUB5ECT10N*

(REVIEW AREA)

NSSS INTERFACE 3.4.3 1.

Safety-related NSSS equipment located (Flood Protection) outside containment that cust be pro-I tected from flooding.

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MSSS equipment located inside or out:ide l

(MissileProtection) containment that potentially could pro-duce missiles including type (i.e.. valve bonnet, studs, stems. *herro wells etc.).

l weight, size, and energy of each missile.

2.

Safety-related NSSS equipmer,t located outside containment requiring protection from externally-generated missiles (e.g.,

tornado missiles).

3.

Safety-related NSSS equipment located inside or outside containment requiring y

protection against internally-generated l

missiles.

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• New Subsection in P.egulatory Guide 1.70. Revision 2 (" Standard Fomat and 49) d Content of Safety Analysis Reports for Nuclear Power Plants") in which interfaus should be presented.

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. NEW INTERFACE SUBSECTION (REVIEW AREA)

NSSS INTERFACE 3.6.3 1.

Identification of 1iich-and moderate-energy (Protection Against Dynamic Effects NSSS lines inside and outside contairment.

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. (Branch Technical Position APCSB 3-1 is Postulated Ruptrre ofPiping) applicable reference).

2.

Safety-related NSSS systems / equipment located inside or outside containment rcquiring protection from the effects of high-and moderate-erergy line failures.

3.

A cosmitment to coordir. ate the design of the RCS* with interfacing BOP-designed l

i piping systems regarding postulated pipe break locations, orientation, configura-r tioas and resulting loads to assure compati-W bility.** (Branch Technical Fositions APSCB Idf iT 3-1 and MTEB 3-1 are appitcable references).

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3.7.5 1.

A listing of NSSS systens and components g-A (Seismic Destjn) that in conjunction with supporting 8(:4 structures are designed to seismic Category I I-requirenents.

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• See Table 2 for the definition of all plant system abbreviations.

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. NEW INTERFACE SUBSECTION (REVIEW AREA)_

NSSS INTERFACE 3.7.5(continued) 2.

A comitment to coordinate the design of the RCS and other NSSS components with interfecing BOP-designed structures and piping systems (Category 1 or non-Category 1) with regard to seismic re-sponse spectra, c.d seismic loads to assure compatibility.*

3.

A comitment that the enss and stiffness proper +.ies of NSSS system and co@cnents, to 1:a coupled witn the mathematical model o' the seismic system including structures aiid suoports, will be provided to th's BOP designer.*

i 3.8.6 1.

A comitment to coordinate the design of (DesignofCate-gory 1 Structures) the RCS regarding differentisi displace-ments and rotation due to loacs from the interfacing BOD-designed structures to assure co @atibility.*

2.

A cocenittnent that the structural proper-ties (e.g., support stiffnesses) of the

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i SUBSECTION (REVIEW AREA)

NSSS INTERFACE j

3.8.6(continued) 2.

(continued) supporting BOP structures that were assumed in the enalysis of the NSSS system and com-ponents util be provided to the BOP designer.*

3.

AcommitmeattococrdinatewiththeCOPdesignerh (a)alltheloadstrantaittedfromNS$$coepo-nents to supporting BOP struct;res; and (b) the sllowable deflectiols of the BOP structures supporting the HSS$ components, under all loading conditions to assure cocpatibility.*

3.9.7 1.

A connitment to coordinate the dest;n of the (Mechanical Systems and Components)

RCS and interfacing BOP-designed systems, components arvi supports when ine'astic analysis (

methods are used by either the NSSS or BOP b

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designer, to assure compatibility. Areas requiring coordination should include analytical criteria, procedures, and results.*

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A cxinitnent to provide to the BOP designer g

P preoperational piping vibration test para-meters for the h!SS system and components for (f

all ASME Class 1, 2, and 3 piping systems.*

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..1EW INTERFACE SUBSECTION (REVIEW AREA)_

NSSS l'CERFACE 3.9.7 (continued) 3.

A comitrent to provide to the utility *.he flow-Wuced vieratten test program for reactor internals.* (Regulatory Guide 1.20 is applicable reference).

4.

A comitment to coorcinate the design of NS$$ active and inactive comMnents and their supports with the design of inter-facing BOP components and supports re-garding design loading combinations to assure structural and/or functional com-patibility. The categorization of the appropriate plant and component operating conditions should be cc:rdinated with the BOP designer.**

5.

A comitment to coordiute with the BOP designer the structurni and functional aspects of over-pressure protection for NSSS-designed systems and components to assure compatibility."

• See Hote (2)

• • SeeNote(1)

. NEW INTERFACE SUBSECTION (REVIEW AREA)_

MSSS INTEDFACE 3.9.7 (contirced) 6.

A commitment to provide the BOP designer with limiting criteria affecting MSSS active comporent operability.*

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A casesitzent to coordinate the seismic l

(Seismic Quali-I ficatien of Seismic design rcquirements of a11 NSSS safety-l Category I Instru-mentatior and related 4nstrumentation and electrical i

Electrical Equipvent) equipment and supports with regard to the floor response spectra defined by the BOP designer to assure compatibility.'

3.sl.6 1.

Heat loacts and envirormental requirements (Envirornental l

Design of Mechan-for NSSS equipment locates' outside icai and Elec-trical Equipment) containment.

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2.

Maximum contairment environmental con-ditions (i.e., temperature, pressure, humidity, radiation level, etc.) to which NSSS safety-related mechanical

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and electrical equipment is qualified.

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A listing of all design criteria includ-

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(Integrity of Reactor Coolant ing codes, stardards, General Design Q

Pressure Boundary) t??

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. NEW INTERFACE SUBSECTION (REY!EW AREA}

MSSS INTERFACE 5.2 6 (contirued) 1.

(continued)

Criteria, Regulatory Guides, and Branch Technical Positions applied to the design of the RCOB.

2.

Quantity of reactor coolant transferred to secondary side of the steam ger.erator i

following a td e failure; time to effect pmssure equalization between a defective steam generator and the RCS; and minimum water voltsie and acxtrium stess voluine on I

the secondary side of a steam gee.ct: tor during ncrual operation.

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3.

Steam and feedwater conditions (i.e., flow.

pressure and tesperature) under all modes of operation including startup and shutdown.

4.

Minimum total capicity and maximum set pressures for seccndsry safety valves (ASFI l1 III); maximum accumulation; division of i4 s

relief capacity among main steam lines

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MSSS INTERFACE 5.2.5 (continued) 4.

(continued) pressure); and minimum or limiting st2am flow for atmospheric relief valves fer each main steam lirt including pressure and tesiperature.

5.

For PWRs only, design requirements for the piping connecting the pressurizer to the pressurizer relief tank (includ-ing maximim : team flow to be accessodated, and maximuss bar.4 pressure at valve discharge).

6.

Volume of reactor coolant contained within, the RCPB.

7.

Requirements for leak detection systems (e.g., type of leakage, locationn ratr.s.

etc.) to permit control rc<n monitoring of identified and unidentified leakage from the RCPB to containnent and of intersystem leakage from the RCPB (includ-ing leakage to the secondary side of a steam generator).

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NEW INTERFACE SUBSECTION (REVIEWAREAl NSSS INTERFACE 5.2.6(continued) 8.

For BWRs only, mass and energy release raw data fer safety / relief welve dis-chargM during antic,ipated trenstents.

9.

For BWRs only, assumed impulse inads to which HSSS systen and omponents may be subjected due to pool swell forces dur-inq a LOCA blowdown. These loads must be coordirated with the specific contain-ment design provided by the BOP designer to assure compatibility.

10. For PWRs only, maximum steac generator mass and energy release rate data for a spectrun of steam and feed ater line break sizes and selected plant operating I

conditions; and requirements for isolating flow to any secondary systen pipe break.

l

11. Mass and energy release rate data (see subsection 6.3.6 item 7) for selected RCS Qk break sizes and locations, and a comit-T

)

ment to coordinate the release rate data C

en M

yr l

p(kh

^y a?\\bqpipq h y %=c:~r:?;amy y esetcsenrwrav:: etu2 7::d

. NEV INTERFACE SUBSECTION

(_R_EVIEW AREA)

NSSS INTERFACE 5.2.6 (continued)

11. (continued) with the actual containment design para-meters determined by,the BOP designer to assure ccmpatibility.*

12. For PWRs only, requirements for emergency fetniwater crevisions to all intact steam generators, with or without offsite and normal onsite power available, assuming isolation of a steam generator due to a pipe break event such as a steam line brcok, feedwater line break, or a steam generator tube rupture:

a.

Reliabilityrequirements(i.e.,

redundancy, diversity,etc.).

b.

Minimun flow capability and maximun l

flow to a single steam generator.

c.

Minimu!n discharge pressure, d.

Ma).'eun time to attain full flow following d w nd signal.

e.

Hintrun volume of stored condensate or standby auxiliary feedwater re-quired to bring reactor to cold

• See Note (2)

1. OSL&kli%iMsdDKO?:2 5 6 Ill' W =:&S S E 2illM Z W N'E R 2 5 5 K? G?]

. NEW L

INTERFACE F

SUSSECTION (REVIEW AREA) h3SS INTERFAr.E h

H l

5.2.6 (continued) e.

(continued) 1 shutdcwn with zero time at scram and h

no allowance to maintain reactor at cold shutdow..

k 1

l f.

Temperature limits.

l g.

Quantity and coeditics Of steam avail-able from intact steam generator for motive power (final values to be co-

.ordinated with the 809 designer to assure compatibility).

h.

Conditions within the kSSS that ini-tiate flow.

1.

Conditions within the BOP that ini-tinte flow.

j.

Requirements for compatibility of the control and power systems with the NSSS actuation and redundancy logic.

13. For BhRs only, maxieum struke tire fo -

MSLIV; requirements for the location, capacity and control arrangement of the main steam line relief ar.d dump valves L

P N S $ 5 D 5 5 t $ $ $5N $ b S]$ l [ $.*?h ? S l i i!S,% R @l'iI?N); ? D E N 1 1GQl"f?N M i

t

_m.

NEM INTERFACE SUBSECTION NSSS INTERFAC

,(3EVIEW AREA) 5.2.6 (continued)

13. (continued) and other main steam system valves located betweta the HSLIV and the main condenser; and requiremants for the feedwater control system.

14. Limiting Nat loads and coolant conditions (flow, pressure, and temperature) for the l

condensate storage facilities for all plant modes of operation including accident con-ditions; minimum water inventory for cold

~

shutdown.

15. For PWR's only, temperature, pressure, radioactivity concentrations, secondary coolant chemistry and flow rate to the steam generator blowdown system during nomal and anticipated operatier.a1 occur-rences; and isolation requirements.

16. For PWRs only, requirements to maintain secondary side water chemi try for steam generators within specified ranges

- 29 NEW INTERFACE SUBSCCTION (REVIEW AREA)_

NSSS INTERFACE 5.2.6(continued)

16. (continued)

(including steam generator blowdown, chemical addition, condensate purification, and monitor-ing). (Branch Technt$al Position MIEB 5-3 is applicable refu ence).

17. Sampling recuirements, including flow rato, sample voluce, sample frequency, temperatures and pressure, to monitor reactor coolant purity (including instrumentation for monitor-ing impurity removal and for detection of excessive chloride and fluoride content). For

(

PWRs only, requirements to sample ar.d analyze v

l reactor coolant for specified parameters at hot leg, pressurizer surge line, and pressurizer

)

steam space. (RegulatoryGuides1.44forPWRs and 1.56 for BWRs are applicable references).

$r

18. Identification of pnetmatically-operated k

valves, instruments and controls essential v

to safe shutdown of the plant including air E

flow requirements, pressure, cleanliness, and dew point.

N 1

0; e

e)

\\

"N'k 1

l

1

[,

., df 6 h4h#*,k

.f A

. c.3 9

NEW INTERFACE SUBSECTION (REVIEWAREAl NSSS INTERFACE 5.2.6(continued)

19. Reactor coolant radioactivity concentrations; noble gas release rates (B1/Rs only); leak rates from PCS to floor drains and building atmospheres.

20. Flow rate, batch volume, radioactivity con-centrations, tergerature, pressure and partition factors at each RCS interface poin,t.with the GWMS and for each leakage point to the building atmsphere during nomal and anticipated operational occurrences.

4

21. Heat loads and cooling eter flow, pressure and temperature for nomal and limiting con-7 ditions for each RCS component interfacing 4

i with the SSWS or the CCWS.

l i

5 l

A

22. Materials Interfaces (1) to (6) and (8),

Table 1.

.a t

~$h

23. !.ocations and accessibility requirements K

k;',

n for inservice inspection of ASME Code

$h

(

-;U

?SI

m

'e,

ll

~

. NEV INTERFACE SUBS"' TION (REVIEW AREA)

NSSS INTERFACE 5.2.6(continued)

23. (continued)

Class I components within RCPB. (ASME Code Section XI is applicable reference).

24. Locations and accessibility requirements for inservice inspection of reactor coolant ptsip flywheels. (RegulatoryGuide1.14 is applicable reference).

25. Locations and accessibility requirements for inservice inspection of steam generator tubes. (Regulate y Guido 1.E3 is applicable l

reference).

26. Criteria for contamination protection and

~

cleaning before, during and after welding installation of steam generators at NSSS-BOP boundaries (to avoid stress corrosten cracking of Inc9nel tubes). (Regulatory Guide 1.37 is applicable refe nee).

l

27. Compatibility requirements for materials to be used in containment spray system, 5

a -

ft

.i?

e,-k I

i-I

$11$'f frh?fikkhVh?sfW&hW } h.;*"-

t

• W'

, NEW INTERFACE SUBSECTICN (REVIEW AREA)

NSSS INTERFACE 5.2.6(continued)

27. (continued) considering reactor coolant and radiation l

environment during Accident conditions.

(Austeniticstainlesssteelnotsensitized or alternative steel specified by P.SSS l

designer for metals contacting reactor coolant and materials resistant to environ-ment). (Regulatory Guide 1.44 is applicable reference).

28. Heat loads and environmental limitations for MSSS syste :s and ccc;cnents.

5.4.6.5 1.

A listing of all design criteria including (Reactor Core Isolation Cooling codes, standards, General Design Criteria, System)

Regulatory Guides, and Branch Technical Positionc applied to the portion of the design of the RCICS in:luded within the NSSS.

c 2.

Het positive suction head requirements at h

RCICS pump suction, and required heat re-a moval capacity (including tube-side coolant conditions) during all conditions of standby

.!g-

,E.. k

&k

wdf,)ttu % : l i , NEW INTERFACE SUBSECTION (REVIEW AREA)_ NSSS INTERFACE 5.4.6 5 (continued) 2. (continued) and shutdown cooling until reactor vessel i is depressurized. 3. Mass and energy release rates for RCICS line breaks. 4. Flow rate, batch volum, radioactivity concentrations, temperature, and pressure at each RCICS interface point with the ~ LnMS, and for each leakage point to the building surm, during nomal and anticipated operational occurrences. 5. Heat loads and cooling water flow, pressure, and temperatyre foy rormal and limiting condi-( l tions for each RCICS corg. Ment interfacing with the SSWS. l 6. Materials Interfaces (1) to (8) Table 1. y y d. 5.4.7.5 1. ' A listing of all design criterin includ-

,ji

• -6 (Residual Heat Remcval System) ing codes, standards, General Design J.

jh .Xt .r. . i' k5 l l l

l l s . NEW INTERFACE i SUBSECTION (REVIEW AREA)_ NSSS INTERFACE 5.4.7.5(continued) 1. (continued) Criteria, Regulatory Guides, and Branch Technical Positions, applied to the por-tion of the design of the RHRS included within the NSSS. 2. Net positive suction head equirements at the RHRS ptsnp suction, and required heat. removal capacity (including tube-sidc coolant conditions) during all conditions of shutdown cooling. 3. For BWRs only, mass and energy release l rates for RHRS head spray line breaks. 4. Flow rate, batch volume, radioactivity [ I.. concentrations, temperature, and pressure S n r ac ek po tt he y Of) building su@, during normal and antici-s pated operational occurrences. l 5. Heat loads and cooling water flow, 9 pressure, and temperature for nomal E 44

M ER M M M M I NEW INTERFACE SUBSECTION (REVIEW AREA) MSSS INTERFACE 5.4.7.5 (continued) 5. (continued) and limiting conditions for each RHRS component interfacing with the CCWS cr SSWS. 6. Meterials Interfaces (1) to (8) Table 1. 5.4.8.4 1. A listing of all design criteria includ-(Reactor Water CleanupSyrtem) ing codes, standards, General Design Criteria, Regulatory Euides, and Branch Technical Positions appifed to the portion of the design of the RWCUS included within the NSSS. l 2. Mass and energy release rates for RWCUS line breaks. 3. Flow rate, batch volume, radioactivity content, and batch freqJency for filters, filter sludges, demineralizer resins, and evaporator bottoms transferred from RWCUS equipnent to the SWMS during norr.al and l anticipated cperational occurrences.

" MEW INTERFACE SUBSECTION NS$$ INTERFi.CE (REVIEW AREA)_ 5.4.8.4 (continued) 4. Flow rate, batch volume, radioactivity concentrations, teoperature, and pressure at each RWCUS interface point with the OMS, and for each leakage pint to the building sump, durira dorsal and antici-1 pated operational occurrences. 5. Heat loads and service water flow, pressure and temperature for normal and 1 tatting conditions for each RWCUS component inter-facing with the SSWS. 6. Materials interfaces (1) to (8) Table 1. 5.4.11.6 1. A listing of all design criteria includ-(Pressurizer Relief Discharge ing codes, standards, General Design System) Criteria, Regulatory Guides, and Branch Technical Positions applied to the por-tion of the design of the PRDS included within the NSSS. 2. Heat loads and cooling water flow, pressure, and taiperature for normal and limiting .s

l l . NEW 1 INTERFACE SUBSECTION (REV!EW AREA) NSSS INTERFACE f 5.4.11.6(c-atinued) 2. (continued) conditions for each PRDS :omponent inter-j facing with the CCWS. 3. He'erials Interfaces (1) to (8), Table 1 6.2.4.5 1. A listing of all design criteria inc h d-(Contaiment IsolationSystem) ing codes, standards, General Design Criteria, Regulatory Guides, and Branch Technical Positions applied to the par-tion of the design of the CIS included within the HSSS. 2. Definition of signals generated by NSSS equi; Lent (i.e., safety injection, low vessel level, etc.) for use in develop-ing diverse containnent isolation sig-nals; and characteristics of valves included in the HSSS design that are part of the CIS. Definition of BOP signals that indicate abnormal contaiment conditions and that must be coordinated with the NSSS in the design of the reactor shutdown systms to assure compatibility.

P ' NEW INTERFACE SUBSECTION (REV'.EW AREg NSSS INTERFACE 6.2.4.5(continued) 3. Maximum leahge rate and type of fluid for all contairment isolation devices included in the RSSS design.* 4. Test fluid type and maxima quantity of test fluid :equired for testing of con-tainment isolation devices included in the NSSS design. S. Identification of pneumatically-operated l valves, instruments and controls essential to safe shutdown of the plant including air 1'10w requirements, ;. essure, clean 11-ness, and dew poin'.. 6.3.6 1. A listing of all design criteria includ-(Emergency Core Cooling Systems) ing codes, standards, Ganeral Design l l Criteria, Regulatory Guides, and Branch l l Te-hnical Positions applied to the por-tion of the design of the ECCS included within the NSSS. <rc-m M m m 1;V m s:w?ca=r usen n,= x -=n

== -am- - cm

NEW INTERFACE SUBSECTION (REVIEW AREA) NSSS INTERFACE 6.3.6(continued) 2. Maximum het.d loss (friction and elevation), I and net positive suction head requirements for all ECCS ps;s for all conditions of operation (including" single failure, operator error, and minimum contaiment ambient pressure), and iden;ification of all conditions under which ECCS must provide core cooling (e.g., single failure, flooding, etc.). 3. For PWRs only, design requirements for the l piping connecting the accumulators to the RCS; and provisions for nitrogen supply. 4. For BWRs only, design requirements for the piping connecting the ADS accumulator to the relief valves; and provisions for air supply. 5. Design requirements for manually-operated valves in the ECCS; requirements for straight piping runs for flow measuring devices in ECCS; limitations on total water vol s e in the RCS cold leg up to the ECCS check valves; maximum time to achieve full l l wwemwwmua.u,w8mmyrww-mixmm

. NEW INTERTACE SUBSECTION (REVIEW AREA), NSSS INTERFACE 6.3.6(continued) 5. (continued) ECCS flow in the event of a LCCA (with and without the availability of nomal A-C power supply); ab limitations on particle size of impurities in ECCS water; requirements for venting and filling provisions for air renoval to preclude water hamer events; and design capability for preoperational testing to denonstrate all aspects of system operability. 6. Identification of pneumatically-operated valves, instruments and controls essen-tial to safe shutdown of the piant includ-ing air flow requirements, pressure, cleanliness, and dew point. 7. Asstned maximum contaiment pressure (consistent with the mass and energy l f release rate data identified in subsec-tion 5.2.6. item 11) for the ECCS analysis. l This pressure should r.ot exceed the minimum contaiment pressure calculated by the N5%C3:I?%N22ldiliiE?#G;ENATBbTL5%41M5lll&45 &M55?i2Wid i e

l NEW INTERFACE SUBSECTION (REVIEW AREA) NSSS INTERFACE r 6.3.6 (continued) 7. (continued) BOP designer, and a corrmitment should be made to coordinate the pressure with the h contaiment design p"a'rameters and analysis h i ( performed by the BOP designer to assure compatibility (see items 10 and 11 of this subsection).* 8. Minimum net positive suction head for p I safety injection pumps; and maximum flow rate,.nd fluid tmperature from the con-taiment sump or suppression pool as a function of time. E B 9. Hydrogen released by zirconium eater h E reaction in tore; maxica;m a.. cunt of hydro-g it rien dissolved in F.CS water during plant E operations (PWRs only); hydrogen generated { P" by radiolysis of water in the reactor and

h_

in the contaircent sump as a function of b' time after LOCA; surface area and thicknass of aluminum and zine provided as a part of a t NSSS aquipment inside contaircent; and C4 corapatibility requirenents for materials fj .. g of contaircent and its internal structures .3 <ylg

• See Note (2)

T hc ? MinMM;M%292nhvM8MMungiswWdntMWs

i I i NEW INTERFACE SUBSECTION (REVIEW AREA) NSSS INTERFACE 6.3.6(continued) 9. (continued) t garding hydrogen generation. (Regulatory Guide 1.7 and Branch Technical Position CSB 6-2 are applicable references).

10. For PWRs only, assumed contaiment para-meters are:

a. Maximumpassiveheatsinks(materials 'of construction, surface area, thick-ness). b. Maximum frei volume in contaiment. c. Ccniaiment initial conditions 1 (temperature, pressure and humidity). d. Maxist.a centairnent active heat re-moval capat !ity (beat removal rates, start times, contaiment spray flow l rate and temperature, etc.). Minimtsn contaiment pressure analysis must be coordinated with t'.e BOP designer using actual contaircent parameters to assure compatibility. (Branch Technical Position CSB 6-1 is applicable reference). rm l ~ ~

. NEW INTERFACE SUBSECTION (REVIEW AREA) MSSS INTERFACE 6.3.6 (continued)

11. For BWRs only, minimum containment pressure assumed is 14.7 psia; ac+wal pressure must be detemined in coordination with the BOP designer using actual containment parameters to assure compatibility.

12. Requirements on recirculation water pH for emergency core cooling and containment cool-ing., (Branch Technical Position MTEB 6-1 is applicable reference).

13. Flow rate, batch volume, radioactivity con-centrations, temperature, and pressure at each ECCS interface point with the LWMS, and for each leakage point to the building sump, during nomal and anticipated operational occurrences.

f l

14. Heat loads, cooling water flow, pressure, and temperature for normal and limiting conditions for each ECCS camponent inter-facing with the SSWS or the CCWS.

l

15. Materials Interfaces (1) to (8), Table 1.

44 MEW INTERFACE SUBSECTION (REVIEW AREA) NSSS INTERFACF 6.4.7 1. Safety-related NSSS control equipment (Habitability Systems) located in the control room. l l 2. Limi, ting design and operational require-ments of NSSS control equipment (e.g., temperature, humidity, etc.). 6.6.9 1. Locations and accessibility requirements (Inservice Inspection of Class 2 and 3 for inservice inspection of all ASME Code Components) Class 2 and 3 components within the NSSS' auxiliary systems and ESFs. (ASME Code Section XI is applicable reference). 6.7.6 1. A listing of all design criteria including (MainSteamIsolation Valve Leakage Control codes, standards, General Design Criteria, System) Regulatory Guides, and Branch Technical positions applied to the portion of the design of the MSIVLCS included within the NSSs. l l 2. MSIVLCS parameters including MSLIV leak rate, concentrations of radioactivity in steam, and setpoints on instricentation to be ..,aw.e ~. s,,.,,. ;r. u. ~....

. n, m.,3-;. y p.,yvr+-kp+-k q y y. _... r,a., m :. y ec. u. -... m e+ . NEW INTERFACE SUBSECTICN (REVIEW AREA) NSSS INTERFACE 6.7.6(continued) 2. (continued) interlocked with leakage control system. (Regulatory Guide 1.,96 is applicable reference). 3. Identification of pneumatically-operated l valves, instrunents and controls essential to safe shutdown of the plant including air flow requirenents, pressure, cleanliness, and dew point. 4. Flow rate, batch volume, radioactivity con-centrations, temperature, and pressure at each MSIVLCS interface point with the LWMS, and for each leakage point to the building su=p, during normal and anticipated operational occurrences. 5. Materials Interfaces (1) to (8), Table 1. 7.2.3 1. A listing of all design criteria including (ReactorTrip System) codes, standards, General Design Criteria, t l Regulatory Guides, and Branch Technical } I Positions applied to the portion of the ,2 v.$.- \\ 9 ,5 ',' ,.a

M: _ NEW INTERFACE SUBSECTION (REVIEW AREA) HSSS INTERFACE 7.2.3(continued) 1. (continued) design of the RTS included within the NSSS. 2. Requirements for anticipatory trips (e.g., turbine trip signals as input to the reactor trip systan). 7.8 1. A listing of all design criteria includ-(Instrumentation andControls) ing codes, standards, General Design Criteria, Regulatory Guides, and Branch Technical Pesitions applied to the por-tion of the design of the I&C system included within the NSSS. 2. For each NSSS system, requirects for l NSSS instrtmentation energized by the plant instrumentation power supply system: a. Steady-state load, b. Transient / step load. c. Nominal system voltage, d. Allowable voltage regulation W Xii U d E [ d.7'r"i E S+ E i[ CA*1 J1 Ta5 E _' E E?-~d'E~D'" ~ M - 7M T M "" * *- - '4"-

. NEW INTERFACE SUBSECTION (REVIEWAREAl NSSS IhTERFACE 7.8(contiri.ed) 2. (continued) e. Allowable harmonic content. f. Allowable frequency fluctuation. g. Grounding requirements. h. Power supply assignment. 3. For each NSSS system, requirements for BOP sensors that provide inputs to accomplish NSSS functions and for associated instru-ment lines: a. Range (including accident conditions). b. Measurement accuracy. c. Repeatable accuracy. l d. Maximum expected transient. l e. Response time (maximum allowbie time to achieve sensor output af ter reach-ing trip level for nessured variable), f. Trip setpoint. r I g. Snubbers. h. Orifice. 1. Arrangement for instrument lines. L i i[ 4. Number of logic trains utilized for the k G, control of safety systems.

q; w.

5 <7 y, !.y V$x 1 7;4v27 byspwcNe'ur<=. :mmmewr:rm.nwwww,2 -vi M ELM:::.Ec 13: I

48 - NEW INTERFACE SUBSECTILM [ l (REVIEWARES NSSS INTERFACE l 8.2.3 1. For each NdSS system, requirments for (Offsite Power Systems) offsite power: a. Steady-state load. b. Inrush KYA for motor loads. l l c. Nominal voltage. 1 d. Allowable voltage regulation. e. Nominal frequency. f. Allowable frequency fluctuation. g. Maximum frequency decay rate and limiting underfrequency value for l reactor coolant pump coastdown. ' h. Minimur number of ESF trains to be energized simultaneously (if more than two trains provided). 8.3.1.5 1. For each NSSS system, requirments for (Onsite A.C. Power Systems) onsite A-C power: a. Steady-state load. b. Inrush KVA for motor loads. c. Nominal voltage. d. Allowable voltage drop (to achieve l full functional capability within required time period). I e. Load sequence. f. Nominal frequency. C;L;>" MW 2xGs%X :va%Thietv~;a w'WME%.a>2.iwiM%=3 M&m;MW

( . NEW INTERFACE SUBSECTION (REVIEW AREA)_ NSSS INTERFACE 8.3.1.5(continued) 1. (continued) g. Allowble frequency fluctuation. h. Neber of trains. 1. Minimum number of ESF trains to be energized simultaneously (if more than two trains provided). 8.3.2.3 1. For each NSSS system, requirements for (D.C. Power Systern ) onsite D-C power: a. Steady-state load. b. Surge loads (including energency conditions), c. Load sequence. d. Nominal voltage. e. Allowable voltage drop (to achieve full functional capability within required time period). l f. Number of trains. l g. Minimum neber of ESF trains to be I energized simultaneously (if more than two trains provided). 9.1.1.4 1. Rack dimensions, weight, materials of (New Fuel Storage) construction, uplift forces, and mounting requirments; number of racks and total ~IfndE5dl5?5%QiM2"NMI?itVAf5 MrW2C'C2dWhi:M'FicMi~i LLEG

50 - NEW INTERFACE SUBSECTION NSSS INTERFACE (REVIEW AREA)_ 9.1.1.4(continued 1. (continued) storage capacity; minimum rack spacing and associated K,ff (with floh 'an-borated water and wi'th optimum moderator acueous foam); vault drainage requirements. 9.1.2.4 1. Rack dimensions, weight, materials of con-(Spent Fuel Storage) struction, uplif t forces, and mounting re-quirements; neber of racks and total storage cr.pacity; minimum rack spacing and associated 4,ff (borated and unborated water and with optimm moderator aqueous feam); allowable fuel pool water chemistry.(e.g., pH, conduc-tivity, boron concentrations) and limiting water temperature. 2. Minimum depth cf wtar above spent fuel arrey to w et shielding requirements of 10 CFR 20; minimum depth of water above spent fuel bundle if accidentally dropped and positioned horizontally across top of spent fuel array; spent fuel pool nomal and maximum decay heat loads (including fraction of core and minimum cooldown time prior to placing in the pool); po-l $8A2N'hS2f5/@fQEMU$d$81M55!-Z ASAEYd6?ESERSCW2$(shd5 E'E9

, NEW INTERFACE SUBSECTION (REVIEW AREA) NSSS INTERFACE 9.1.2.4(continued) 2. (continued) tential corrosion rate of racks and cladding, and expected iission product leakage as a functioii of taperatura and l l water chemistry. 9.1.4.6* 1. A listing of all design criteria includ-(Fuel Handling Systs) ing codes, standards, General Design Criteria, Regulatcry Guides, and Branch Te:hnical Positions applied to the por-tion of the design of the Fuel Handling System included within the NSSS. 2. Installation requirments (i.e., crane weights, power, compressed air, hydraulic requirernents, etc.); storage requirercents; capacity of bridge cranes and new fuel elevator; installation requirements for transfer tube, :arriage and upender; equipment interlocks and special built-in safety features; and other special require-ments to preclude unacceptable accidents.

• Fuel Handling System assu=td to consist of the following NSSS items: bridge cranes; new fuel elevator; transfer tube, and carriage; upender; and lifting rigs, slings, and other essential equipment integral to the NSSS.

kN NfSI.lidY23$7EffNUS $ h2,M@NP2b@d N NNNf[f$$MMdNNE$.FNE 9

I . NEW INTERFACE SUBSECTION (REVIEW AREA)_ NSSS INTERFACE 9.3.4.6 1. A listing of all design criteria includ-(Chemical and Volume Control ing codes, standards, General Design Systen) Criteria, Regulatory Guides, and Branch Technical Positions applied to the por-tion of the design of the CVCS included within the NSSS. 2. Location cf the CVCS letdown line radiation monitor, and requirennts to perfom its alam and control function. 3. Flow rate, batch volume, radioactivity content, and batch frequency for filters, filter sludges, demineralizer resins, and evaporator bottoms trarsferred from the CVCS equipment to the SWMS, curing nomal and anticipated operational cccurrences. 4. Flow rate, batch volume, radioactivity concentrations, temperature, pressura and partition factors, at each CVCS interface point with the G'nNS and for each leakage point to the building atmosphere, during normal and anticipated operational occurrences. . w a'n u r'm u M /,%rsmew msaun u' _marmanc.e a+ u ^ AV

• i,.J pb

.be u = =

i 53 - NEW INTRFACE SUBSECTIJN MSSS INTERFACE (REVIEWAREA)_ 9.3.4.6(continued) 5. Flow rate, batch volume, radioactivity con-centrations, temperature, ard pressure at each CVCS interface point with the LhMS, and for each leakage pot'nt to the building surp, during nonnal and anticipated operational occurrences. 6. Heat loads, and cooling water ficw, pressure, and taperature for normal and limiting conditions for each CVCS coeponent inter-facing with the CCWS. 7. Flow rate, boron concentrations, tmpera- ? ture, and pressure et each CVCS interface point with the Refueling Water or Berated Water Storage Tank. 8. Identification of pneumatically-operated 5 valves, instrunents and controls essential k to safe shutdown of the plant including air flow requirments, pressure, clean 11-1 ness, and dew point. h I I H C l1 9. Materials Interfaces (1) to (8), Table 1. M E f b m i f J B ^ 'I* g f* o L d _,_ + _h 2 mwd k - &Lu.,are;c a ~se.xwwygess.m Lg, ex ag 5 s m: h k _E w~

54 - NEW INTERF/CE SUBSECTION (REVIEW AREA), NSSS INTERFACE l 9.3.5.6 1. A listing of al: design criteria including (Standby Liquid Control System) codes, standards. General Design Criteria. Regulatory Guides, and Branch Technical Positions applied to the portion of the design of the SLCS included within the NSSS. 2. Boron concentration, flow rate, and require-ments-for maintaining minimum temperatura. 3. Identification of pneumatically-operated valves, instrument. sad controls essential to safe shutdown of the plant in-luding air-flow requirements, pressure, cleanliness, and dew point. 4. haterialsInterfaces(1)to(8). Table 1. 9.5.1.6 1. Identification and quantification of the l (Fire Protection) NSSS items that constitute a significant I fire hazard. (Branch Technical Position k 1 APSSB 9.5-1 is applicable reference). r# q J.c I hhb t;f; bfh.l5I;a x=; l l . +. m?

~ ~h~N'-ff~

hh 5 al.wlf ~ n-j thh { k +

2. <. :

- SS - NEW INTERFACE SUBSECTION (REVIEW AREA) NSSS INTERFAg 10.4.4.X 1. Steam cor.ditions during discharge following (Turbine Bypass System) turbine trip and limiting steam flow for turbine bypass system sizing without reactor trfp including temperature and pressure. 2. Identification of pneumatically-operated valves, instruments and controls essential to safe shutdown of the plant including air flow retutr ements, pressure, cleanliness, ard dew point. 13.6.3* 1. Identification of vita' equipment as (Indu: trial Security) defined in 10 CFR 73.2, for use in develop-ing physleal security plans. Also, where applicable locations of items of vital l equipment and provisions incorporated into the design for monitoring the status of vital equipment to detect malevolent acts to impair perfomarce. 14.1.8 1. Identification of the special or unique (Initial Test Program) features ni tha '4555 design for considera-tion in developing the initial test program by the utility.

• This infor ation should be submitted as proprietary infomstion [10 CFR 2.790(d)].

3 \\ Y3Nk i l l

1 . APPENDIX B BALANCE-CF-PLANT INTEkFACES NEW INTERFACE SUBSECTION (REVIEW ARE/.1 BOP INTERFACE 2.3.6 1. Limitingneteorolog!calparameters(X/Q) (Meteorology) for design basis accidents (including use of back-up hydrogen purge systs) and for routine releases; and other extrae l meteorological conditions (tmperatures, dust storms, humidity and air quality) for the design of systes and components I exposed to the enviroment. I 3.3.3 1. Tornaos and operating basis wind loadings (Wind and Tornado Loadings) to w?tch plant structures and exposed fystes and components are designed. 3.4.3 1. Flood elevation and requirments for (WaterLevel Design) protection established for the design of systems, components and structures. 2. Hydrostatic loads established for the design of systms, components and structures. r i M nw _ _ _ -= - s e.>~~...

. NEW IKTERFACE SUBSECTION (REVIEW AREA) BOP INTERFACE 3.5.4 1. External missiles generated by natural (Hissile Protection) phenomena established for the design of systens, components and structures. 3.7.5 1. Seismic parameters ("g" values and re-(Seismic Design) sponse spectra) established for the de-sign of systems, components and structures. 3.8.6 1. Snow, ice, and rain Icads established for ~ (Design of Category 1 Structures) the design of systems, components and s tructures. 2. Required bearing capacity of foundation materials, and allowable absolute and differential settlements established for the design of systems, components and structures. I 3.9.7 1. A commitmert to provide to the utility (Mechanical Systems and Coeponents) the preopterational piping vibration test parameters for usa in developing the test programs for all ASME Class 1, 2, and 3 piping systems in the NSSS and BOP.* i

• See hote (2)

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58 - NEW INTERFACE SUBSECTION (REVIEW AREA) BOP INTERFACE 3.9.7 (continued) 2. A cocmitment to provide to the utility the locations and other requirments for developing an inservice inspection pro-gram for ASME Class Y 2, and 3 systems and cor.:ponents in the NSSS and BOP, and for reactor coolant pump flywheels (FWRs only).* 6.4.7 1. Environmental conditions.ssteed in the (Habitability Systems) design of the control room for protection of operators. 7.8 1. A listing of all tne design criteria (Instrumentation and Control) ine.luding codes, standards, General Design Criteria, Regulatory Guides and Branch Technical Positions applied to the portion of the design of the I&C systes included within the BOP. 2. Provisions included in the plant instru-mentation power supply system to acccmo-date the I&C requirements of the SSWS (and additional ecoling capacity, if anyrequired):

• See Note (2)

flew mTERFACE SUBSECTION (REVIEW AREA)_ BOP INTERFACE 7.8 (continued) 2. (continued) a. Steady-state load, b. Transient / step. load. c. Nominal system voltage, d. Allowable voltage regulatica. e. Allowable harmonic content. f. Allowable frequency fluctuation. g. Grounding requirements, h. Power supply assignment. 3. Provisions included for tie sensors and their instrument lines associated with the SSWS (and additional cooling capacity, if any required) that pmvide inputs to satisfy station safety functions: a. Range (including accident conditions). b. Measurement accuracy. c. Repeatable accuracy. d. Maxicum expected transient. e. Response time (maximum allowable time to achieve sensor output after reach-ing trip level for measured variable). f. Trip setpoint. l 'dL' .a-5 L (_ N^ 'A l l

.m. NEW INTERFACE SUBSECTION (REVIEW AREA) BOP INTERFACE 7.8 (continued) 3. (continued) g. !,nubbers. h. Orifice. 1. Arrangment for instrument lines, i 8.2.3 1. A listing of all the design criteria (Offs'te Power System) inclecing codes,.etandards, General Design Criteria, Regulatory Guides, and Brangh Technical Positions applied to the portion of the design of the Offsite Power System incit;ded within the BOP. 2. Provisions included to accomodate the offsite power requirements of the NSSS and BOP systems including the SSNS (and additional cooling capacity, if any required): a. Steady-state load, b. Inrush KVA for motor loads. c. Nominal voltag!. d. Allowable voltage regulation, e. Nominal frequency. f. Allowable frequency fluctuation. k [ I L 4 { m. I t,' _'g 3& h ( I i

}.1 NEW INTERFACE SUBSECTION (REVIE'dAREA) E0P INTERFACE 8.2.3(continued) 2. (continued) g. Maxina frequency decay rate and limiting underfrequency value for reactor coolant pump coastdown. h. Minisus number of ESF trains to be energized simultaneously (if more than two trains provided). 8.3.1.5 1. A listing of all the design criteria includ-(Onsite A.C. Power Systems) ing codes, standards, General Design Criteria, Regulatory Guides, and Branch Technical Positions applied to the portion of the design of the on,tte A.C. Power Sysiams included within the BOP. 2. Provisions included to arcamodate the needs of the SSWS (and additional cooling capacity, if required) by the onsite A.C. ?cwer Systems: a. Steady-state load, b. Inrush KVA for motor loads, c. Nominal voltage. DTE5 528 l@:25iG5515,eMrsMi>.ETi.%KMC3%%%i2Ki?%S51.2 LM-

. NEW 2" ' INTERFACE SUBSESTION (REVIEW AREA)_ BOP INTERFACE 8.3.1.5(conti.7ued) 2. (continued) d. Alicable voltage drop (to achieve full functional capability within required time p'e'riod). e. Load sequence, f. Nominal frequency. g. Allowable frequency fluctuation. 8.3.2.3 1. A listing of all the design criteria (D.C. Power Systems) including codes, standards, General Design Criteria, Regulatory Guides, and Branch Technical Positions applied to the portion of the design of the D.C. Power Systens included within the BOP. 2. Provisions included to acconnodate the needs of the SSWS (and additional cooling capacity, if required) by the D.C. Power Systems: i l a. Steady state load. b. Surge loads. c. Load sequence. l d. Nominal voltage. Q]:)Q!;)QQ7.){QJ;t]:B f[.57 Q:f l }fQ } h {f ?9$J R l}it'? W FGT2 M D R S3 h y

- NEW INTERFACE SUBSECTION (REVIEW AREA) B09 INTERFACE 8.3.2.3(continued) 2. (continued) e. Allowable voltage drop (to achieve full functional capability within required time period). 9.2.7 1. A listing of all the design criteria (Water Systems) i including codes, standards, General Design Criteria, Regulatory Guides, and Branch Technical Positions applied to j the portion of the design of the SSWS included within the BOP. I 2. Integrated heat load (decay heat and station heat load for all NSSS and BOP systems, as a function of time for the various modes of plant operation and limiting accider.t conditions) that must be transferred to the Ultimate Heat Sink, maximum and minimum temperature limits, pressure, flow rate, plant SSWS prer.sure i drop, etc. 3. Coolant flo,', pressure, temperature and l l integrated condensate storage capacity 1 'G Md85I821?SkNNS$IIS$54DM5ES6$$@$E$8bi$b39?[dMis??Ml$E5N1 1 1 4 g ? INTERFACE SUBSECTION (REVIEW AREA)_ BOP INTERFACE 9.2.7 (continued) 3. (continued) to satisfy total plant needs during nomal operation, shutdown, and accident conditions. 4. Limits on quality of make-up wat.er to the station including conductivity, pH, oxygen, chlorides, fluorides, solids, carbon dioxide, particulates, and silica; and limits on make-up water flow, taperature and pressure. l S. Requirments for location and arrangment t of Potable and Sanitary Water Systes to preclude adverse effects on safety systems and components in the event of failure. j 9.5.9 1. Site-related requirments to satisfy the (Other Auxiliary Systss) Fire Protection Program. (BranchTechnical PositionAPCSB9.5-1isapplicablereference). 2. Requirements for fuel oil storage and trans-j fer system for the diesel generators includ-ing capacity and location. en_ a h l

NEW IhTERFACE SUBSECTION (REVIEW AREA)_ BOP !NTERFACE 11.2.4 1. Expected release rates of radioactive (Liquid Waste Manageraent Systems) material to the environment from the L)MS. 11.3.4 1. Expected release rates of radioactive (GaseousWaste ManagementSystems) materials to the envirornent from the GWtS and from other relea;e points including: , Location of all release points. a. b. Height above grade. c. Height relative to adjacent buildings. d. Effluent temperature. e. Effluent flow rate. f. Effluent velocity. g. Size and shape of flow orifice. 11.5.3.X 1. Requirements for offsite sampling and (Effluent Monitoring andSampling) monitoring of effluent concentrations. 13.6.3* 1. Identification of vital equipment, as (Industrial Security) defined in 10 CFR 73.2, for use in

• This infomation snould be submitted as proprietary information [10 CFR 2.790(d)].

N W 8 1$??? $ll $ 0 $(?R b??s E0$ G & biSt"[ l5 2 D': W U M E $ Ia?5 2 $ B M NEW INTERFACE SUBSECTION (PIVIEW AREA) BOP IliTERFACE 13.6.3(continued) 1. (continued) developing physical security plans. Also, where applicable, logations of items of vital equipment and provisions incorporated into the design fer wenitoring the status c of vital equipment to detect malevolent acts to impair performance. 14.1.8 1. Iderttification of the special or unique (InitialTest Program) features of the NSSS and BOP designs for consideration in developing the initial test program by the utility. F-K k u ? t f I D L

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l, Table 1 MATERIA!.S INTERFACES (1) Criteria for contamination protection and cleaning before and during field welding and after complete installation of austenitic stainless steel components at NSSS-BOP boundaries. (RegulEcry Guides 1.37 and 1.44 are applicable references). (2) Requirements for control of sensitization of field installation welds joining austenitic stainless steel components at NSSS-80? boundaries. (Regulatory Guide 1.44 is applicable reference). (3) Requirements for control of delta ferrite in field installation welds i joining austenitic stainless steel components at NSSS-BOP boundaries. (Regulatory Guides 1.3. and 1.44 are applicable reference). (4) Weiding requirements for field welding installation of territic steel components and austenitic stainless steel components at t:SSS-80P bour.daries, including preheat temperature control, welding materials, and clad welding requirements. (Regulatory Guides 1.43 and 1.50 are applicable references). (5) Requirements for icw halide nonmetallic thennal insulation on austenitic stainless steel at NSSS-B0P boundaries. (Regulatory Guide 1.36 is applicable reference). I hYhh 55hbhY5$Y$5bYh $fhkfh$k h

Table 1 (Continued)_ (6) Material requirements for B0P piping connected to the RCS and components within the NSSS. (RegulatoryGuide1.44isapplicablereference). (7) Requirements for fluid sampling to monitor perforda'nce and impurities including flow rate, sample volume, sample frequency, temperature and pressure. (8) Regairements for capability to control fluid purity and chemistry within specified ranges during operation. (Regulatory Guides 1.44 for PWRs and 1.56 for BWRs are applicable references). e 4 A

,'able 2 c ABBREVIATIONS FOR NUCLEAR PLANT SYSTEMS Automatic depressuri:atico system. ADS Balance-of-plant (all systems, structures, and com,,onents 30P comprising a total plant excluding the NtSS and site-and utility-specific item; see Amer.dment I to MASd-1341). Component cooling water system. CCWS Contairrant isolation system. CIS Chemical and volume. 1 system. CVCS Emergency core cooliry systems. ECCS Engineered safety feature. ESF Gaseous waste management system. GWMS Instrurr.entation and control. I&C Liquid waste management system. LWM2 Hain steam isolation valve leakage control system. MSIVLCS Main steam line isolation valve. MSLIV Nuclear steam supply system (components and piping canprising MSSS the RCS and directly related auxiliary systems; see Amendment I toWASH-1341). Pressurizer relief discharge system. PRDS ,t Reactor core isolation cooling systm. RCICS Reacto. coolant pressure boundary. RCPB Reactor coolant system. RCS Residual heat removal system. RHRS mase manammaregeman

I fable 2 (Continued) Reactor water cleanup system. RWCUS Station service water system. SSWS l Solid waste marugement systen. SkNS I i-i ? (, e O t T I,, m %%!y:Mr?AEW:3r=*5?EuniMw im UxiuiBm x wu<mv~n m m:::a L 1 ..s

.s o~ MOTES: Note (1): This interface requires exchange of infor 1ation among the utility, the NSSS designer, and the BOP designer. The e.-change of information for this interface shall take place in accordance with the requiremenn of 10 CFR 50 Appendix B. Notef2): The staff recognizes that the information may not be available at the PDA stage of review. If all of the in-formation needed by the staff and ACRS to complete their ~ review of this interface is not provided'in the applica-tion for a PDA, the PDA will te subject to a condition that either the dditional information shall be provided to the utility for inclusion in a CP application referencing the PDA, or the utility shall demonstrate in its CP applica-tion that, such infomation may reasonably be left for later consideration in accordance with 10 CFR 50.35(a). Issuance of a PDA shall not foreclose staff and ACRS review of interfaces subject to such a condition. k N ws.c;cn.c,y.uw 3 - m w.-msyr m u ;;,_.m e r m a m_, m u n g p e y W ( _s _. _._}}