ML19312A209
| ML19312A209 | |
| Person / Time | |
|---|---|
| Site: | 05000495 |
| Issue date: | 11/29/1978 |
| From: | STONE & WEBSTER, INC. |
| To: | |
| References | |
| NUDOCS 7909050292 | |
| Download: ML19312A209 (67) | |
Text
{{#Wiki_filter:SWESSAR-P1 CHAPTER S REACTOR COOIANT SYSTEM AND CONNECTED SYSTLES LIST OF EFFECTIVE PTSES Page, Table (T) , Amendment Page, Table (T) , Amendment or Fiqure (F) No. or Figure (F) No. 5-a ~ _ 33 5-1/ii 8 5-iii 24 5-1v 21 5-v 20 5.1-1 21 5.1-2 26 T5 .1 -1 (W) 21 TS .1-2 (W) 21 TS .1- 1 (W-3S) 28 T5.1-2 (W-3 S) 26 T5.1-1 (BSW) (sheet 1 33 TS.1-1 (BSW) (sheet 2) 30 T5.1-2 (B&W) 30 T5.1-1 (C-E) (Sheet 1) 23 26 9 TS .1-1 (C-E) (Sheet 2) T5.1-1 (C-E) (Sheet 3) TS .1-2 (C-E) 23 27 FS.1-1 (W) (2 sheets) 8 F5.1-1 (W-3S) (2 sheets) 17 5.2-1 thru 2A 8 5.2-3 thru 4A 32 5.2-5/6 7 5.2-6A 9 5.2-7 8 5.2-8 2 5.2-9 8 F5.2.7-1 Orig 5.3-1 2 5.4-1 2 5.5-1 25 v? 5.5-2 6 2A 33 5.5-3 20 5.5-4 24 T5.5.7-1 (h) 21 T5.5.7-1 (B&W) (2 sheets) 33 T5.5.7-1 (C-E) (2 sheets) 23 T5.5.14-1 7 F5.5.14-1 26 20
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F5.5.14-2 & 3 , p, n 7 5.6-1 2 (y [,, j ddI 5-a Amendment 33 6/30/77
SWESSAR-P1 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS Section Pace
5.1 INTRODUCTION
5.1-1 5.1.1 Schematic Flow Diagram 5.1-1 5.1.2 Piping and Instrumentation Diagram 5.1-1 5.1.3 Elevation View 5.1-1 5.1.4 Interf ace Requirements 5.1-1 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2-1 5.2.1 Design of Reactor Coolant Pressure Boundary Components 5.2-1 5.2.2 Overpressurization Protection 5.2-1 5.2c' General Material Considerations 5.2-1 5.2.3.1 Material Specifications 5.2-1 5.2.3.2 Compatibility of Material with the Reactor 5.2-1 8 Coolant 5.2.3.3 Fabrication and Processing of Ferritic 5.2-2 Materials 5.2.4 Fracture Toughness 5.2-2 5.2.5 Austenitic Stainless Steel 5.2-2 5.2.5.1 Cleaning and Contamination Protection 5.2-2 Procedures 5.2.5.2 Solution Heat Treatment Requirements 5.2-2 5.2.5.3 Material Inspection Program 5.2-2A 5.2.5.4 Unstabilized Austenitic Stainless Steel 5.2-2A 5.2.5.5 Avoidance of Sensitization 5.2-2A 5.2.5.6 Retesting Unstabilized Austenitic Stainless 5.2-2A Steels Exposed to Sensitizina Temperatures 5-i nn n Amendment 8 ((} bU J 3/28/75
SWESSAR-P1 CHAPTER S TAELE OF CONTENTS (CO!TP) Section - page 5.2.5.7 Control of Delta Ferrite 5.2-2A 5.2.6 Pump Flywheels 5.2-3 5.2.7 Reactor Coolant Pressure Boundary (RCPB) 5.2-3 Leakage Detection Systems 5.2.7.1 Leakage Detection Methods 5.2-3 5.2.7.2 Indication in Control Roon 5.2-4 5.2.7.3 Limits for Reactor Coolant Leakace 5.2-4 5.2.7.4 Unidentified Leakage 5.2-4 5.2.7.5 Maximum Allowable Total Leakace 5.2-5 5.2.7.6 Differentiation between Identified and 5.2-6 Unidentified Leaks 5.2.7.7 Sensitivity and Operability Tests 5.2-' 5.2.7.8 Interf ace Requirements 5.2-6A 8 5.2.8 Inservice Inspection and Testing Procram S.2-6A 5.2.8.1 Provisions f or Access to Reactor Coolant 5.2-7 Pressure Foundary 5.2.8.2 Equipment for Inservice Inspection 5.2-4 5.2.8.3 Recordino and Comparina Data 5.2-9 5.2.8.4 Reactor Vessel Accentance Standards 5.2-9 5.2.8.5 Coordination of Insoection Equipment with 5.2-9 Access Provisions 5.2.8.6 Perf orman ce of Insecvice Inspection 5.2-9 5.3 HERV.AL HYDPAULIC SYSTLM OESIGN 5.3-1 c.<4 5.4 REACTOR VESSEL AND APPUR"'ENANCES 5.4-1 b'd 5-ii Nnendment 8 3/28/75
SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Page 5.5 COMPONENT AND SUBSYSTEM DESIGN 5.5-1 5.5.1 Reactor Coolant Pumps 5.5-1 5.5.2 Steam Generators 5.5-1 5.5.3 Reactor Coolant Piping 5.5-1 5.5.4 Main Steam Line Flow Restrictions 5.5-1 5.5.5 Main Steam Line Isolation System 5.5-1 5.5.6 Reactor Core Isolation Cooling System 5.5-1 5.5.7 Residual Heat Removal System 5.5-1 5.5.8 Reactor Coolant Cleanup System 5.a-2 5.5.9 Main Steam Line and Feedwater Piping 5.5-2 5.5.10 Pressurizer 5.5-2 5.5.11 Pressurizer Relief Tank 5.5-2 5.5.12 Valves 5.5-2 5.5.13 Safety and Relief Valves 5.5-2 5.5.14 Equipment Supports 5.5-2 5.5.14.1 Design Bases 5.5-2A 5.5.14.2 Reactor Vessel Support Shield Tank 5.5-3 5.5.14.3 Pressurizer Support 5.5-3 5.5.14.4 Steam Generator and Reactor Coolant Pump 5.5-4 Sepports 5.5.14.5 Equipment Support to Balance of Plant 5.5-4 Structure Interface Requirements 24 5.6 INSTRUMENTATION REQUIREMENTS 5.6-1 5-iii b'Oj ri n r3 U ,UAmendment 24 4/23/76
SWESSAR-P1 LIST OF TABLES Table 5.1-1 Reactor Coolant System Interface Requirements n 5.1-2 Reactor Coolant Interface Requirements for Utility-Applicants 5.5.7-1 Residual Heat Removal System Safety Related Interface Requirements 5.5.14-1 Equipment Supports, Loading Combinations, and Design Allowable Stresses O {'} s 5-iv Amendment 21 2/20/76
SWESSAR-P1 LIST OF FIGURES Fiqure 5.1-1 Reactor Coolant System Modification, Sheet 1 5.1-1 Reactor Coolant System Modification, Sheet 2 5.2.7-1 Minimum Time to Detect Reacto. Coolant System Irakage with No Prior Activity in Containment Structure 5.5.14-1 Reactor Vessel Support Shield Tank 5.5.14-2 Deleted I g20 5.5.14-3 Deleted .
/7 PO9 O'OJ UL 5-v Amendment 20 1/23/76
P in . b jr, L (;i;, l) p)
\ i n -)
SWESSAR-P1 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS
5.1 INTRODUCTION
The reactor coolant system is described in detail in the NSSS Vendor's SAR; however, the following supplemental information for the Stone & Webster scope of design responsibility is provided herein: Section 5.2.5 Austenitic Stainless Steel 5.2.7 Reactor Coolant Pressure Boundary Leakage Detection System 5.2.8 Inservice Inspection Program 5.5.14 Equipment Supports 5.1.1 Schematic Flow Diagram This will be provided in the NSSS Vendor's SAR. 5.1.2 Piping and Instrumentation Diagram The reactor coolant system and the reactor coolant pressure boundary are within the NSSS Vendor's crope and SAR 5.1.3 Elevation View Fig. 1.2-3 offers both plan and elevation views of the reactor coolant system as arranged with the containment internal structures. 5.1.4 Interface Requirements The interf ace requirements tor the reactor coolant system, as set forth in the system interf ace requirements sections of the NSSS Vendors' SAR, are satisfied by the SWESSAR-P1 design as indicated in Table 5.1-1. Interface requirements for Utility-Applicants g are listed in Table 5.1-2. Adjustments to the reactor cuclant system interface boundary are as tollows: Westinghouse (RES AR-41) :
- 1. The Stone & Webster design provides one primary grade water containment penetration for all components requiring primary grade water inside the containment structure. This design moves the primary grade water / reactor coolant system interf ace boundary from outside the containment structure as shown on RESAR-41 Fig. 5.1-1 Sheet 2 to inside the containment structure as shown on SWESS AR-P 1 modification Fig. 5.1-1 Sheet 1.
5.1-1 Amendment 21 7 f1 O [. 2/20/76 bOJ V
SWESSAR-P1
- 2. The Stone & Webster design provides one gaseous "ent ,
header containment penetration for venting all gaseous systems inside the containment structure. This design moves the gaseous vent / reactor coolant system interface boundary from outside the containment structure as shown on RESAR-41 Fig. 5.1-1 Sheet 2 to inside the conteinment structure as shown on SWESSAR-P1 modification Fig. 5.1-1 Sheet 2. Westinghouse (RESAR-3S) :
- 1. The Stone & Webster design provides one primary grade water containment penetra tion for all components requiring primary grade water inside the containment structure. This design moves the primary grade unter/ reactor coolant system interf ace boundary from outside the containment structure as shown on RESAR-3S Fig. 5.1-1 Sheet 2 to inside the containment structure as shown on SWESSAR-P 1 modification Fig. 5.1-1 Sheet 1.
- 2. The Stone & Webster design provides one gaseous vent header containment penetration for venting all gaseous systems inside the containment structure. This design moves the gaseous vent / reactor coolant system interface boundary from outside the containment structure as shown on RESAR-3S Fig. 5.1-1 Sheet 2 to -
inside the containment structure as shown on SWESSAR-P1 modification Fig. 5.1-1 Sheet 2.
- 3. The Stone & Webster containment structure and annulus building equipment layout requires two modifications to the RCS: (1) The connection on loop 4 hot leg, which consists of RHR pump 2 suction, SIS SI pumps dis charge , and two pressure gages with isolation valve, is moved to the same position on loop 2. (2)
The SIS SI and RHR pumps discharge connection on loop 2 hot leg is moved to the same position on loop 4. These changes will locate the ECCS pumps directly across from the loops which they serve, which provides better piping separation and minimizes the length of the RHR pump hot leg suction piping. Babcock 6 Wilcox: There are no adjustments to the reactor coolant system boundary. Combustion Engineering: Layout of the reactor coolant loops and pressurizer inside the containment structure require that the pressurizer spray and 25 surge lines be relocated from loop 1 to loop 2 in order to minimize the length of these lines.
- n. [J105 G' U .) i 5.1-2 Amendment 26 6/2/76
SWESSAR-P1 TABLE 5.1-1 REACTOR COOLANT SYSTEM INTERFACE REQUIREMENTS RESAR-41 - RESAR-41 Interface Item
- Reference SWESSAR-P1 Design Protection Against 3.4 See Sections 3.3 and 3.4.
Environmental Effects ** Seismic Capability ** 2.5.2 Section 3.7 Electric Power ** Note 1 Refer to SWESSAR-P1 Section 8.4. Ventilation ** Note 1 Refer to SWESSAR-Pl Section 9.4.5.1.6. Component Cooling ** Refer to SWESSAR-P1 Section 9.2.2. Sampling System ** 9.3.2 Section 9.3.2.6 Secondary Systems ** Refer to SWESSAR-P1 21 Section 10.1. Protection Against 3.5,1.7.1,5.6 Sections 3.5 and 3.6 Pipe Rupture and Missiles, and Separation System Layout for Appendix 5A Containment structure Operation and layout is shown in Inspection Fig. 1.2-3. Leakage Detection 1.7.1 5.2.7 Nitrogen to PRT 1.7.1 Section 9.5.8.6
- These requirements are safety related. The SWESSAR-P1 design accommodates and is compatible with all reactor coolant system interface requirements in RESAR-41.
- These interface requirements are cross referenced in RESAR-41 from RESAR-41 Appendix 5A.
Note 1. The RESAR-41 cross reference for these interface require-ments is given in the cited SWESSAR-P1 section. 7 I'd' Oh W 1 of 1 () b ] Amendment 21 2/20/76
SWESSAR-P1 TABLE 5.1-2 REAC'IOR COOLANT INTERFACE REQUIREMENTS FOR UTILITY-APPLICAITTS
- 1. The Utility-Applicant will verify in his SAR that the necessary exchange of information is implemented between 21 Westinghouse and Stone & Webster (as required by Section 5.1.4 of RESAR-41) to confirm total capability of the reactor coolant system.
- 2. The Utility-Applicant will supply at the FSAR stage the as-built volume of the reactor coolant system piping to the NSSS Vendor for ECCS analysis.
W 1 of 1 ()() } 09) Amendment 2/20/76 21
SWESSAR-P1 TABLE 5.1-1 REACTOR COOIANT SYSTEM IN!'ERFACE RIQUIREMENTS (1) RESAR-3S RESAR-3S Reference SWESSAR-P1 Design Interf ace Ite_m Protection from 3.3, 3.4, 3.8 Sections 3.3.3, 3.4.3, 3.8.6 Natural Phenomena SA 28 Seismic Capability 2.5 Secticus 3.7.6, 3.8.6 3.7 3.8 Protection from 3.5, 3.6, S.A Sections 3.5.6, 3.6.6 Rupture and Missiles Electric Power Note 2 Section 8.4 Requirements Ventilation 6.2.2, 12.2, No balance of plant require-Requirements ments 9.4.5 Section 9.4.5.1.6 Component Cooling Note 2 Section 9.2.2.6 Requirements Sampling System 9.3.2 Section 9.3.2.6 Requirements Secondary Systems 6.5, 10.1 Section 10.1.2 Requirements 28 Primary Grade Water S.A Section 9.2.7.6 to Pressurizer Relief Tank Leakage Detection 1.7.1 Section 5.2.7 Refueling Cavity Note 2 Section 9.1.5 Design Note 1: These requirements are safety related. The SWESSAR-P1 design accommodates and is compatible with all reactor coolant system interface requirements in RESAR-3S. Note 2: The RESAR-3S cross reference for these interf ace require-ments is given in the referenced SWESSAR-P1 section. b u, ) ona U/O W-3S 1 of 1 Amendment 28 8/6/76
SWESSAR-P1 TABLE 5.1-2 REACTOR COOLANT SYSTEM INTERFACE REQUIREMENTS FOR UTILITY-APPLICANTS
- 1. The Utility-Applicant will verify in his SAR that the necessary exch'ange of information is implemented between Westinghouse and Stone & Webster (as required by Appendix 5A 26 of RESAR-3S) to confirm total capability of the reactor coolant system
- 2. 'Ite Utility-Applicant will supply at the FSAR stage the as-built volume of the reactor coolant system piping to the NSSS Vendor for ECCS analysis.
W-3S 1 of 1 A () h, ), b,nc/ mendment
/
26 6/2/76
SwNSSAR-P1 TABC 5.1-1 REACTOR COOLANT SYSTEM I!TTERFACE INFORMATION (Note 1) Requirement B-SAR 205 Requirement SWESSAR Ref erence
- 1. Electric power Note 2 Section 8.4 to operate equipment 2 . atrols to operate Note 2 Section 7.8 te system
- 3. System layout for 5.7.15.1 Containment struc-operation and 5.7.15.2 ture arrangement inspection 5.7.15.4 is shown in Fig.
1.2-3.
- 4. Remote Sampling 5.7.13.1 Section 9.3.2.6 9.3.2.1 9.3.2.2 9.3.2.5 9.3.2.6 9.3.2.8
- 5. Component cooling Note 2 Section 9.2.2.6 water
- 6. Protection frcun 5.7.2 Sections 3.3, 3.4, natural phenomena 3.5, and 3.7
- 7. Separation and pro- 5.7.3 Sections 3.5 & 3.6 tection from rupture 5 .7 .4 .1 and internal missiles 5.7.4.3 and pipe whip 5.7.5.1 5.7.6 33
- 8. Reactor coolant Section 5.2.7 pressure boundary 5.7.10.1 leakage detection 5.7.10.2
- 9. Feedwater Note 2 Table 10.1.2
- 10. Steam Note 2 Table 10.1-2
- 11. Envin nment 5.7.19.1 Ccanbustible gas 5.7.19.2 control Section 6.2.5, containment spray Section 6.2.3.2, Beat re-moval Sections 6.2.2
& 9.4.5, environ-mental conditions D&W 1 of 2 bb) $6b Amendment 33 6/30/77
SWESSAR-P1 TABLE 5.1-1 (Cottr) Section 3.11
- 12. Equipnent supports 5.7.15.3 Section 5.5.14 and loadings 5.7.15.6 l30 5.7.18.2 3 5.7.18.3 Note 1. These requirements are saf ety related. The SWESSAR-P1 design accommodates and is compatible with all applicable reactor coolant system interface requirements in B-SAR-205.
- 2. The B-SAR-205 crost reference for these interface require-ments is given in the referenced SWESSAR-P1 section.
B&W 2 of 2 663 ; 0 'i Amendment 30 1/28/77
SWESSAR-P1 4 TABLE 5.1-2 REAC"IOR COOLANT INTERFACE REQUIRDfEhTS FOR UTILITY-APPLICANTS
- 1. The Utility'-Applicant will verify in his SAR that the necessary exchange of information is implemented between 30 Babcock 6 Wilcox and Stone & Webster to confirm total capability of the reactor coolant system.
- 2. The Utility-Applicant will supply at tf9 FSAR stage the as-built volume of the reactor molant system piping to the NSSS Vendor for ECCS analysis.
BSW 1 of 1 Amendment 30 1/28/77 bb3 iC2
SWESSAR-P1 TABLE 5.1-1 REAC'IOR COOIANT SYSTEM INTERFACE REQUIREMEffrS (NOTE 2) Femuirement CESSAR Feference SWESSAR Feference
- 1. Electric power to operate Note 1 Refer to ShESSAR-P1 8 the equigunent Table 8.4-1.
g
- 2. Controls to operate t he Note 1 Fe=f er to SWESSAR-P1
, i systesn Section 7.8.
g'.' i
- 3. The syst em layout for 4.2.4.D.1 Containment structure y operat ion arvi inspection 5.1.4.L.1 arrangements are shown 5.1.4.0.1,3,11 in Fig. 1.2-3.
5.1.4.R.12,13 x h 4. Runote sampling 5.1.4.M.1 Section 9.3.2.6 p- ~, 5. Component cnoling Note 1 Peier to SWESSAR-P1 f- , Table 9.2.2-5. - I' 6. Protection f rom natural 3.3.3, 3.4.5 Sections 3.3.3, 3.4.3, I phenanena 5.1.4.D.1,2,3 and 3.7.6
- 7. Sepa. ration and pro- 3.5.4.1 Sections 3.5.6 & 3.6.6 07 )' tection against 3.6.5.1 21 7 Ey rupture and internal 4.2-4.D.2 D ] missiles 5.1.4.C.1,6 Es[ p 5.1.4.D.1,2,5 5.1.4.E.1 5.1.4.F.1 5.1.4.0.8
- 8. Reactor coolant pressur e 5.1.4.J, 2 Leak detection methods 1x>unda ry leakage detection discussed in Section
- 5. 2.7 reet the C-E requir esnent s .
& 9. Steam and ieedwater iluid Note 1 Reier to SWESSAR-P1 C.s system requirements Table 10.1-2. U
- 10. Environment 5.1.4.S.2, 3 SWESSAR-P1 Section 3.11 identif ies equip-
~* ment speciiication procedures which will CJ ensure t hat t he equip-va ment will be rated wit hin at least the sp eci f ica t i ons stated in (TSSAP Table 3.11-2, In puist cases, the C-E 1 of 3 Amendment 23 3/31/76
SWESSAR-P1 TARTI 5.1-1 (CONT) Requirement CESSAR Reference SWESSAR Reference specification will exceed these minimum requirements. Note 1. The CESSAR cross ref erence f or these interf ace requirements is given in the cited SWESSAR-P1 section. Note 2. These requirements are saf ety related. The SWESSAR-P1 design accommodates and is compatible with all reactor coolant system interf ace requirernents in CESSAR except as noted below.
- 1. Item 5.1.4.E.5 - This requires instrumentation to sense a blowdown line rapture and automatically isolate the broken line. The blowdown lines for the SWESSAR design have containment isolation valves to iso-late a rupture outside the containment. Since the containment is cap-able of withstanding a ruptured blowdown line, no provision for auto- 26 matic isolation has been provided. Sufficient instrumentation is provided inside containment to detect the broken line for operator action.
- 2. Item 5.1.4.I.2 - This requires main steam line flow restrictors. The SWESSAR-P1 design does not include main steam line flow restrictors since technical details have not been provided by C-E.
- 3. Item 5.1.4. K. 9- This reauires an accuracy of t 1 F f eedwater temperature measuresnent. This is not a safety-related interface requirement.
26
- 4. Item 5.1. 4.K .10 - The instrumentation listed in this item is included in the SWESSAR design with the following exceptions: (a) makeup feedwater storage tank temperature is not monitored since it is inside the annulus building, (b) emergency f eedwater pump discharge pressure is not measured remotely because the pump status and flow indication are provided to indicate proper functioning of the pump and (c) steam generator emergency feedwater flow is indicated on the mair. control board only. Flow indication is not necessary for control.
C-E 2 of 3 Amendment 26 6/2/76
<7 5 nn U( U J . V 't
SWESSAR-P1 TABLE 5.1-1 (Cotr1')
- 5. I t em 5.1. 4.K .11 - W e auxiliary shutdown panel is provided for use only
( in nonaccident situations, as described in SWESSAR-P1, Section 7.4. 3 t> . It erns 5.1.4.P.2, .3 - We activities and source terms utilized in [ f release calculations are given in Sections 11.1 and 15.1.13. j 7. Item 5.1.4.Q.1 - This requires that no isolation valves be included between the steam generators and a t>nospheric durnp valves. Manually operat ed isolation valves are provided between the steam generators and
,) the atmspheric dump valves in the OfESSAR design. The isolation valves are norinally open and are pruvided for maintenance of the 73 atmospheric dump valves.
) 8. Items 5.1.4.0.2, 5.1.4.R23 - This requires detailed design not yet 1
performed. These interf aces will te addressed in the applicatim for g Final Design Approval.
. 9. Item 5.1.4.R.24 - We CESSAR cmponent support designs are acceptable
,3 for the SWESSAR-P1 structures with the exception of the reactor vessel support shown in CESSAR Fig. 5.5-7. SEW will supply a reactor vessel
' '3
. support shield tank f or t he reactor vessel as described in Section
, 5.5.14.2 e
e ni O O LeJ C. L C-E 3 of 3 Amendment 23 3/11/76
SWESSAR-Pl TABLE 5.1-2 REACTOR COOLANT INTERFACE REQUIREMENTS FOR UTILITY-APPLICANTS
- 1. The Utility-Applicant will verify in his SAR that the p necessary exchange of information is implemented between Combustion Digineering and Stone & Webster to confirm total capability of the reactor coolant system.
- 2. The Utility-Applicant will supply at the FSAR stage the as-built volume of the reactor coolant system piping to the NSSS Vendor for ECCS analysis.
(Nb C-E 1 of 1 Amendment 27 6/30/76
ANNULUS : CONTAINMENT BUILDING STRUCTURE RC S-MODI) OM : y -----T-------------~-'l (FIG.9 2.7-1) l I I I NNS4+-SC2 SC2-*+- NNS l l V l l TO l RCDT l l I CVCS 4 --{ RCPI
}-- - 1
, l-LC V- 178 l l '
CvCS ,_.:@;_ __ _ q aca 2 l i- Le'- ne i
,_go43 CvCS._[b__
l- L C V - 180 l FROM RCDT & RCS-m(DGS-2) RCP 4
* - -[ ~-
----___q l- LCV- 181 HEAT
[ EXCHANGER (FIG 9. 3.3.-2) k To PRT SWESSAR PI - ' - RESAR 41 DESIGN DESIGN ' (FIG.5.I-l SH. 2 ) FIG. 5.I-l (SH.1) RE ACTOR COOL ANT SYSTEM MODIFICATION PWR REFERENCE PL ANT SAFETY AN ALYSIS REPORT SWESSAR PI E {} I/ gL A MENDMENT 8 3/28/ 75
ANNULUS CONTAINMENT BUILDING *-*" STRUCT URE TO/FROM G ASEOUS VEN T HEADER
- FIG. 9.3.5 - 2 NNShSC2 SC2 % NNS SW ESS AR-P1 N I T RO"2E N DESIGN Fn4 REACTOR F7 PLANT GAS SUPPLY d
SY ST E M (FIG. 9.5.8 - 1) U th RESAR I D ESIG N - 41 l g$ FIG. 5.1- 1 l 0
- - - - L4- - -. -
/ I'R ESSURIZE R l RCDT j l RELIEF TANK k s------ _- s em cc FIG. 5. l-l (SH.2)
"3 REACTOR COOL ANT SYSTEM MODIFICATION
- - PW R STANDARD PLANT Ci SAFETY ANALYSIS REPORT SWESSAR-Pl E
AMEN 0 MENT 8 3/28/75
ANNULUS _ _ ,, CONTAINMENT BUILDLNG STRUCTURE FROM _ s, RCS-MODI) PGWS ' W '
- - - ~ ~~~ T - -
l l (FIG. 9.2.7-1) l l l l NNS~~SC2 SC2---NNS l g
* ~~ ~~~
R DT R l i- LCV-181 l I l CvCS _ _ _,_ l l l-LCV-l82 l I l-8045 CVCS l g l RCP 3 __1 FROM RCDT l-LCV-183 l HEAT _ [RCS-a(DGS-2)) l EXCHANGER l C' S *~ I (FIG. 933-2) RCP 4 P l-LCV-184 TO PRT SWESSAR Pl _ . RESAR 3S DESIGN DESIGN ( FIG. 5.1-1 SH. 2) FIG. 5.l-1 (SH.1) REACTOR COOLANT SYSTEM MODIFICATION PWR REFERENCE PLANT SAFETY ANALYSIS REPORT SWESSAR-PI ,,. W -3S 00- ,!U g ,'l AMENDMENT 17 9/30/75
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SWESSAR-P1 5.2 INTEGRITY OF REAC'IOR COOLANT PRESSURE BOUNDARY 5.2.1 Design of Reactor Coolant Pressure Boundary Components The design methods and procedures to be used for the components of the RCPB are within the NSSS Vendor's scope and SAR. 5.2.2 Overpressurization Protection The material in this section is providel in the NSSS Vendor's SAR. The mounting pressure relief devices in the RCPB are in a ccordance with the reouirements established by the NSSS Vendor in Section 5.2.2.2. 5.2.3 General Material Considerations 5.2.3.1 Material Specifications 8 Materials for the RCPB (NSSS Vendor Systems) are defined in the NSSS Vendor's SAR. Materials for the related auxiliary systems defined in Table 3.2.5-1 are identified in each specific section of this SAR where the systems are described. These materials are procured in accordance with the material specifications requirements of ASME III and the additional requirements of Regulatory Guides 1.31, 1.44, and 1.66 (Sections 3A.1-1.31, 3A.1-1.44, and 3A.1-1.66) . la Cold worked austenitic stainless steels, precipitation hardened stainless steels, or hardenable martensitic stainless steels having yield s trengths greater than 90,000 psi are not used in the current designs for components of the engineered safety features. If such steels are used in the future, technical j us tification will be provided to demonstrate material compatibility with the core coolina water and the containment sprays in the event of a loss-of-coolant accident. 5.2.3.2 Compatibility of Material with the Reactor Coolant The rea ctor coolant chemistry requiremen ts and contaminant controls are defined in the NSSS Vendor's SAR. The materials identified above for the auxiliary systems are selected to be canpatible with the operatina fluid durina operation and to reactor coolant leakage. The selection considers resistance to pit ting , stress norrosion cracking, provisions for adequate corrosion a llowan ce s , and/or maintenance of material properties 0 as a result of exposure to radiolytic products. The nonmetallic thermal insulation over austenitic stainless steel complies with Regulatory Guide 1.36 as described in Section 3A.1-1.36.
- he acceptable surface contamination levels of chloride and fluoride ions on the stainless steel components during fabrication and cleanina are in accordance with Regulatory Guides 1.37, 1.38, and 1.44 as described in Sections 3 A .1-1. 3 7, 3A.1-1.38 and 3A.1-1.44 The acceptable levels are maintained 5.2-1 knendment 8
,,7 1 4
3/28/75 00J lI}
SWESSAR-P1 during construction by compliance with Regulatory Guide 1.39 as described in Section 3A.1-1.39. S.2.3.3 Fabrication and Processing of Ferritic Materials Fracture toughness considerations are presented in Section 5.2.4. 8 Considerations for other fabrication and processing requirements for the auxiliary systems are in accordance with Regulatory Guides 1.34, 1.50, and 1.71 as described in Sections 3A.1-1.34, 3A.1-1.50, and 3A .1-1.71. Ferritic tubular products comply with the requirements of ASME III and Regulatory Guide 1.66 as described in Section 3A.1-1.66. 5.2.4 Fracture Toughness Information for Sections 5.2. 4.1, 5.2.4.2, 5.2.4.3, and 5.2.4.4 is given in the NSSS Vendor's SAR. In addition, if the design specificatisns for ASME Section III Class 2 and 3 comoonents supplied by Stone & Webster require impact testing, the tests shall be in accordance with NC-2300 and ND-2300 of ASME Ill. Information for Section 5.2.4.5 is given in the NSSS Vendur's SAR. The reactor vessel is supportcC by a reactor vessel support-shield tank (Fig. 5.3.14-1) . Annealing of the reactor vessel is performed from inside the vessel in this region attaining approximately 750 F. Neither the support, its cooling system, insulation, nor any surrounding structures limit the in - place annealing of the reactor vessel. 5.2.5 Austenitic Stainless Steel _ 8l The provisions in the following subparagraphs meet the requirements for unstabilized austenitic stainless steel used for:
- 1. The reactor coolant pressure boundary
- 2. Systems regaired for reactor shutdown
- 3. Systems required for emergency core cooling The requirements are related to the fabrication, shipment, storage, and construction phases. The testing and operational phases will be discussed in the Utility-Applicant's SAR.
5.2.5.1 Cleaning and Contamination Protection Procedures The procedures used to assure that the above systems are suitably cleaned and protected against contamin ants capable of causing stress corrosion cracking are presented in Sections 3 A.1-1.37, 3A.1-1.38, and 3A.1-1.39. 5.2.5.2 Solution Heat Treatment Requirements The requirerent a for solution heat treatment are presented in S ection 3 A.1-1. 4 4. O 5.2-2 Tumon dment 8 3/28/75
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SWESSAR-P1 5.2.5.3 Material Inspection Program The requirements for verifying the nonsusceptibility of unstabilized austenitic stainless steels to intergranular attack are presented in Section 3A.1-1.44. 5.2.5.4 Unstabilized Austenitic Stainless Steel The unstabilized grades ' of austenitic stainless steels with a carbon content greater than 0.03 percent that are used for the reactor coolant pressure boundary (RCPB) are AISI Types 304 and 316 mnd their cast counterparts. The criteria for heat treatment after welding and water chemistry control are presented in Section 3A.1-1.44. 5.2.5.5 Avoidance of Sensitization The requirements that will be followed for avoiding partial or local severe sensitization of austenitic stainless steel during heat treatment and welding operations are presented in Section 3A.1-1.44. 5.2.5.6 Retesting Unstabilized Austenitic Stainless Steels Exposed to Sensitizina Temperatures The requirements for retesting unstabilized austenitic stainless steels which have been exposed to the sensitizing heat range of 800 to 1,500 F, as a result of welding, heat treatment, or other heating operation, are presented in Section 3A.1-1.44. 5.2.5.7 Control of Delta Ferrite The requirement s for controlling delta ferrite in austenitic stainless steel welds, to avoid microfissuring in welds, are presented in Section 3A.1-1.31. These requirements apply to all applicable welding performed under S&W jurisdiction. When SSW installs and/or connects to an NSSS supplied system, any additional requirements of the NSSS Vendor will be met. bb3 5.2-2A Amendment 8 3/28/75
SWESSAR-P1 Case 2. If there is no prior reactor coolant leakage into the containment and the reactor coolant gaseous activity is 0.6 uCi/cc (typical of operating PWRs), a 100 gpm leak can be detected in less than 1 min, and a 1 gpm leak in 1.3 hours. Case 3. If there is prior continuing leakage of 0.5 gpm into the containment and the containment gas detector high radiation alarm setting is twice the existing steady state containment activity, it takes about 340 hours to detect a 1 gpm leak. In this case , the time to detect leakage is not a function of coolant activity level (assumed constant) but rather is a function of leak rate. This method can be used for leakage detection if there are suf ficient activated products and fission products in the RCS. If there is insufficient activity in the coolant system, other methods are used to detect the leak.
- 2. Containment Sump Level Leakage comprising liquid that does not flash or vapor that is condensed by the relatively cold concrete or metal substructures within the containment structure collects in the containment sump. The water level at each of these sumps is l7 continually monitored and a high level condition occurring at any sump is indicated and annunciated in the control room.
The minimum detectable level at each containment sump and in-core instrumentation sump is less than 60 cal in order to 7 detect a 1 gpm leak in less than 1 hr. Sump level detectors and transmitters are designed to survive total submergence.
- 3. Containment Atmosphere Recirculation Cooler Heat load Any abnormal leak from a thermally hot system within the containment increases the heat load on the containment atmosphere recirculation coolers. A 5 gpm leak from the RCPB increases this heat load by approximately 20 percent. A 5 gpm leak is detectable in about 60 minutes by monitoring the outlet temperature of the chilled water flowing through the coolers.
- 4. Containment Pressure, Temperature, and Humidity RCPB leakage causes an increase in containment pressure, tempera ture , and humidity. Values of these items are indicated in the control room and recorded in the data logger. A 5 opm leuk rate can be detected in less than 60 minutes.
2 A 4 (' i? ) i iN 5.2-5 Amendment 7 2/28/75
SWESSAR-P1 The analysis of a through-wall flaw producing detectable leakage is described in Section 5.2.7.4 of the NSSS Vendor's SAR. 5.2.7.5 Maximum Allowable Total Leakage Refer to Section 5.2.7.5 of the NSSS Vendor's SAR. 5.2.7.6 Differentiation between Identified and Unidentified Leaks The plant design has provisions for identifying the source of RCPB leakage, or at least systematically eliminating several candidates from consideration, during normal operation by analyzing vater inventories and heat loads generated by the leak. For example, the level instrumentation in the containment sump has a sensitivity capable of detecting a 1 gpm change in the leakage rate into the sump within 1 hour. However, this instrumentation is not selective for RCPB leakage, e.g., a reactor plant component cooling water system leak flows into the same sump. However, if a 1 gpm or greater change in the unidentified leakage rate into the sump is detected, procedures are initiated to identify the leakage source. These procedures include, but are not limited to, one or more of the following:
- 1. Check airborne radiation monitor indications.
- 2. Sample and analyze containment structure atmosphcre for radioactivity.
- 3. Check containment humidity, pressure, and temperature.
- 4. Sample and analyze the containment sump for radioactivity.
- 5. Check makeup rate to the RCS for abnormal increase.
- 6. Check outlet temperature at each containment atmosphere recirculation cooler.
- 7. Check water levels and other parameters in systems which could leak water into the containment structure.
- 8. Review loas for maintenance operations which may have discharged water into the containment st ructure .
5.2.7.7 Sensitivity and Operability Tests All equipment and instrumentation used for RCPB leak detection are in continuous operation. The testing and ins trument I calibration programs for each method are described under the specific section for that system as follows:
/7 1 iE (2 0 J l iJ 5.2-6 Amendment 7 2/28/75
SWESSAR-P1 Description of System Method Testing (Section) Containment Radiation Monitoring 12.2.4.1 Containment Sump Level 9.3.3.4 Containment Atmosphere Recirculation 7.3.3.4, Coolers 9.4.5.1.4 Containment Pressure, Temperature, and Humidity 6.2.6, 7.7.3.2 The periodic testing and instrument calibration programs are the g responsibility of the Utility- Applicant. 5.2.7.8 Interf ace Requirements NSSS Vendor The methods discussed above meet the RCPB leak detection g requirements of SNESSAR-Pl. Tables 5.1-1, 5.5.7-1, and 6.3-3. 5.2.8 Inservice Inspectipn and Testing Program The reactor pressure vessel, system piping, pumps, valves, and components which recuire inservice inspection and/or testing, as defined by the ASME Boiler and Pressure Vessel Code, Section XI (ASME XI) , are designed, fabricated, and erected with the objective of full compliance with the requirements of ASME XI and its addenda in effect on the date of docketing for a construction permit as stated in the proposed changes to Title 10 of the Code of Federal Regulations Part 50.55a, paragraph (q) . Inservice inspection and testing of Class 2 and 3 systems are discussed in Section 16.4.2. 5.2.8.1 Provisions for Access to Reactor Coolant Pressure Boundary Systems and components which require inspection in accordance with the requirements of ASME XI are designed with adequate physical access to allow the recuired inspection. Piping systems requiring volumetric (ultrasonic) inspection are designed so that all welds requiring inspection are physically accessible for inspection with ultrasonic equipment. Access is provided by leaving adequate space around pipes at these welds and by means of removable insulation and shielding as required. The surfaces of welds requiring ultrasonic examination are smoothed and contoured to permit ef fective use of ultrasonic hDJ l 60 5.2-6A Amendment 9 4/30/75
SWESSAR-P1 transducers, and pipes adjacent to fittings are arranged to permit meaningful examination by avoidance of irregular surface geometries. Piping systems requiring surface or visual examination are designed to allow access and visibility adequate for performance of such examinations, except that buried portions of systems which otherwise require. only visual inspection are provided with isolation valves to permit pressure testing on the buried pipes as provided for in ASME XI. The following areas of the installed irradiated reactor vessel are available for visual and/or nondestructive inservice examination when the closure head and internals are removed:
- 1. Full penetration welds in the following areds:
Vessel shell inside surface Primary coolant nozzles inside surface Closure head inside and outside surfaces Bottom head inside surface Field welds between the reactor vessel nozzles and main coolant piping
- 2. Closure studs, nuts , and washers
- 3. Vessel flange, stud holes, and sealing surface The reactor vessel presents access problems because of the radiation levels and the fact that access for inspection is under water. Because of these limitations, several considerations for bb3 5.2-7 Amen dment 8 3/28/75
SWESSAR-P1 meeting the ASME XI requirements are incorporated into the vessel design as follows:
- 1. All reactor internals are completely removable.
The tools and storage space required to permit reactor internals removal are provided.
- 2. The design of ,the reactor vessel shell in the core area is a clean, unobstructed cylindrical surface to permit oositioning of the inspection equignent without obstruction.
- 3. The closure head can be stored dry in an accessible area to provide direct access for inspection.
- 4. All reactor vessel studs, nuts, and washers are removed to dry storage to permit inspection.
- 5. Removable sections of insulation and shielding are provided to allow access for surface and visual examinations of the reactor vessel nozzle saf e-end welds.
- 6. upenings in the lower portion of the reactor vessel support shield tank are provided to permit remote visual inspection of the in-core instrumentation shell penetration welds. Reactor vessel insulation in this area is specially designed to permit access for inspection.
Inservice inspection access to other major reactor coolant system components is provided as follows:
- 1. Man-ways are provided in the steam generator channel head to provide access for internal inspection of the steam generators.
- 2. A man-way is provided in the pressurizer top head to allow access for internal inspection of the pressurizer.
- 3. The insulation covering all component and piping welds and adjacent base metal are designed f or ease of removal and replacement in areas where external taspection in planned.
.. Penoveble floor sections are provided for inservice utspection access to the numps.
- 5. The reactor coolant loop compartments are cesigned to allow personnel entry during refueling ooerations to permit direct inspection access to the external portion of the piping and compment s .
47 J(uJ 1 'O iu 5.2-8 Amen dment 2 8/30/74
SWESSAR-P1 5.2.8.2 Equipment for Inservice Inspection Various equipment is available to perform reactor vessel and nozzle inservice inspections. The specific inspection tools used depend upon the contractor selected to perform the inservice inspection. The inspection equipment consists of remotely operated arms and linkages with an attached device capable of ultrasonically inspecting all reactor vessel and nozzle welds from inside the vessel. Details of the inservice inspection equipment will be described in the NSSS Vendor's and Utility-Applicant *s SARs. 5.2.8.3 Recording and Comparing Data Appropriate examination records are compiled by the Utility-Applicant of the preoperational examination for the purpose of comparison with the examination results of subseque nt inservice inspections. Data from remotely operated ultrasonic inspection devices will be continuously recorded in all areas where reportable indications are observed. The same type recording device will be used for the baseline and subsequent inservice inspections in accordance with the requirements of ASME XI. 5.2.8.4 Reactor Vessel Acceptance Standards The acceptance standards used to establish acceptability of the reactor vessel are in accord ance with Article IGB-3000 and Appendix A of ASME XI through the addenda specified by the requirements of 10CFR50. 5.2.8.5 Coordination of Inspection Equipment With Access Provisions Access to areas requiring inservice inspection is provided to allow use of currently developed equipment. When new equipment must be developed, liaison with manufacturers of inservice inspection equipment will be maintained to ensure compatibility of inspection equipment with plant design. 5.2.8.6 Performance of Inservice Inspection The requirements for performance of the inservice inspection and 8 testing program are described in the Technical Specifications, Section 16.4.2 of this SAR. O i bbJ
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PARTICULATE MONITOR (S E N SITIVITY = lo-' h id io-a io 3 io-2 io-' RESPONSE TIME (HOUR) FIG. 5.2.7 -l MINIMUM TIME TO DETECT REACTOR COOLANT SYSTEM LEAXAGE WITH NO PRIOR ACTIVITY IN THE CONTAINMENT STRUCTURE PY!R STANDARD PLANT SAFETY ANALYSIS REPORT SWESSAR-Pi 663 12i
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SWESSAR-P1 5.2.6 Pump Flywheels Reactor coolant pump flywheels are within the NSSS Vendor's scope and SAR. 5.2.7 Reactor Coolant Pressure Boundary (RCPB1 Leakage Detection Systems General Design Criteria 30 (Section 3.1.30) requires that means be provided for detecting and, to the extent practical, identifying reactor coolant pressure boundary (RCPB) leaxage. To minimize leakage from the reactor coolant system (RCS) , components are interconnected by a Safety Class 1, Seismic Category I piping system. Iaakage from the RCPB to the containment atmosphere is described in this section. Intersystem leakage to the main steam system (Section 10.3) and to the reactor plant component cooling water system (Section 9.2.2) is 32 monitored by the process and effluent radiation monitoring system (Section 11.4) . Intersystem leakage to the NSSS ECCS systems are described in the NSSS Vendor's SAR. However , the rollowing methods of leak detection are supplied in accordance with Regulatory Guide 1.45 (Section 3A.1-1.45) . There methods do not form an RCPB leak detection " system," since each of these methods is a part of its own specific systen governed by other Regulatory Guides and General Design Criteria. 5.2.7.1 Leakage Detection Methods Leakage into the containment atmosphere from the RCPB can be detected ny any one of the following methods:
- 1. Containment Radioactivity Monitoring (Gas and Particulate)
The containment atmosphere is continuously monitored and the radiation levels are displayed in the control room for detection or abnormal radioactivity buildup (Section 12.2). An increase of radioactivity in the containment atmosphere is an indication of reactor coolant leakage.
- 2. Containment Sump Level All reactor coolant and cooling water leakage collecting on the pitched floor of the containment drains to either of two containment sumps where it is collected prior to being pumped to the radioactive liquid waste system (Section 11.2) . The containment sumps collect all drainage, including that transferred trcxn the in-core instrumentation sump which collects any instrumentation tube leakage in the in-core instrumentation room. High level alarms in both sumps indicate possible RCS leakage.
1 97 (, (, ,) \LL 5.2-3 Amendment 32 5/11/77
SWESSAR-P1
- 3. Containment Aemnsphere Recirculaticri Cooler Heat Load The contaiment atmosphere recirculation coolers (Section 9.4.5) normally maintain the containment atmosphere at its design operating terperature and humidity. Leakage from the RCS increases the heat load on the coolers, thus increasing the chilled water outlet temperature which is monitored in the control room.
- 4. Containment Pressure, Temperature, and Ihtmidity Any abnormal increase in containment pressure, temperature, or humidity indicates possible RCPB leakage.
5.2.7.2 Indication in Control Room 'Ihe following parameters are indicated and/or alarmed in the control room to provide means for detecting RCPB leakage:
- 1. Containment high radiation alarm with indication
- 2. Containment sump high level alarm, in-core instrumentation sump high level alarm
- 3. Containment atmosphere recirculation coolers chil l ed water outlet temperature with indication only
- 4. Containment temperature and humidity are indicated in the control room. Containment pressure is indicated and alarmed.
For a further description of saf ety related indicating devices, see Section 7.5. 5.2.7.3 Limits for Reactor Coolant Leakage Refer to Section 5.2.7.3 of the NSSS Vendor's SAR for the limit on, and a discussion of, RCS leakage. 5.2.7.4 Unidentified Leakage 'Ihe total normal expected leakage from the RCS is described in the SAR subnitted by the NSSS Vendor. The sensitivities and response times of RCPB leak detection methods are as follows:
- 1. Containment Airborne Radiation Monitoring Experience has shown that this monitor responds rapidly to RCS leakage and provides a sensitive indication of such leakage. The time required to detect reactor coolant leakage depends upon the size of the break, reactor coolant activity level, and containment background activity. Sensitivity is as follows:
Case 1. If there is no prior reactor coolant leakage into the containment and there is 1 percent failed fuel, a 0.1 gpn reactor coolant leak can be detected in approximately 2 minutes as shown in Fig. 5.2.7-1. h h,3 l 5.2-4 Amendment 32 5/11/77
SWESSAR-P1 The particulate detector is more sensitive than the gas detector to small leaks, while the gas detector has faster reponse for leak rates greater than 1.2 gpm.
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bbJ i,14 5.2-4A Amendment 32 5/11/77
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SWESSAR-P1 5.3 TH AMAL HYDRAULIC SYSTEM DESIGN 2 The thermal hydraulic design of the reactor coolant system is described in the NSSS Vendor's SAR. O bb) l20 5.3-1 Amendraent 2 8/30/74
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SWESSAR-P1 5.4 REACTOR VESSEL AND APPURTL' NANCES 2 the reactor veasel and appurtenances is The discussion of j provided in the NSSS Vendor's SAR. bb) '2.) 5.4-1 Amendment 2 8/30/74
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SWESSAR-P1 5.5 COMPONENT AND SUBSYSTEM DESIGN 5.5.1 Reactor Coolant Pumps This section is within the NSSS Vendor's scope and SAR. The Utility-Applicant will ensure that the component cooling water 25 requirements of Section 9.2.2.6 are met. 5.S.2 Steam Generators Estimates of the radioactivity levels anticipdted on the secondary side of the steam generators are discussed in Se ction 11.1.2. Secondary side water chemistry is discussed in Section 10.4.6. Steam generator design and discussion are within the NSSS Vendor's scope and SAR. 5.5.3 Reactor Coolant Piping This section is within the NSSS Vendor's scope and SAR. 5.5.4 Main Steam Line Flow Restrictions This section is within the NSSS Vendor's scope and S;R. 5.5.5 Main Steam Line Isolation System Main steam isolation is discussed with the main steam system, Section 10.3. 5.5.6 Reactor Core Isolation Cooling Svstem This section is within the NSSS Vendor's scope and SAR. 5.5.7 Residual Hedt hemoval System Westinghouse (RESAR-41) The residual heat removal system is described in the NSSS Vendor 'c 3 AR. Table 5.5.7-1 lists the safety related interface requirements for this sytem. hestinghouse (RESAR-3 S) The residual heat removal system is described in the USSS Vendor's SAR. Interface information is included with the ECCS information (Section 6.3. 6) . i" 5.5-1 %,hdmJd]25 4/30/76
SWESSAR-P1 Combustion Engineering The residual heat removal system is described in the GSSS Vendor's SAR in Section 9.2.7. Table 5.5.7-1 lists the safety related interface requirements for this system. System modifications and additional interface requirements coamon to both this system and the ECCS are discussed in Section 6.3. Babcock and Wilcox The decay heat removal system is described in the NSSS Vendor's SAR in Section 9.3.6. Table 5.5.7-1 of SWESSAR lists the safety related intarface requirements for this system. Interface requirements particular to ECCS operation are discussed in Section 6.3. With reference to B-SAR-205 Fig. 9.3-5, a connection is not required to and from the spent fuel pool because spent fuel cooling is done exclusively by the fuel pool cooling system. However, the decay heat removal pump discharge 33 line, designated as a backup to fuel pool cooling, is connected to the refueling cavity for filling operations during refueling. The decay heat removal pumps described in B-SAR-205 Section 9.3.o are single stage, horizontal, centrifugal pumps. The SWESSAR-P1 design replaces these pumps with deep well pumps in onler to simplif y the structural design of the SWESSAR-P1 base mat. 5.5.8 Reactor Coolunt Cleanup System This section is within the NSSS Vendor's scope and SAR. 5.5.9 Main Steam Line and Feedwater Piping fiain steam lines and feedwater piping are discussed in the nuln steam system, Section 10.3, and the feed and condensate systems, Section 10.4.7. 5.S.10 Pressurizer This section is within the NSSS Vendor's scope and SAR. 5.5.11 Pressurizer Relief Tank This section is within the NSSS Vendor's scope and SAR. 5.5.12 Valves This section is within the NSSS Vendor's scope and SAR. 5.5.13 Safety and Reliet Valves This section is within the NSSS Venoor's scope anu SAR.
< - i'1 bh,7j i)6 5.5-2 Amendment 33 6/30/77
SWESSAR-P1 S.S.14 Equipment Supports The major equipment of the RCS includes the reactor vessel, steum The generators, reactor coolant pumps, and a pressurizer. responsibility of support design is given in division of Table 1.8-1. 5.5.14.1 Design Basis The equipment supports within the Stone & Webster scope or work are designed to ensure system integrity during normal operat2on and faulted conditions. For the normal operating condition, the 9 IJ.L bO) 5.5-2A Amendment 33 6/30/77
SWESSAR-P1 major equipment supports are designed to maintain structural integrity under a rm hination of loads which consider equipment deadweight, steady-state thermal operating conditions, and the operating basis earthquake (OBE) . Cyclic loading of the component supports is also considered in the design analysis for normal operation; however, past experience indicates no significant fatigue loading is imposed on the supporta. Under the faulted condition, the equipment supports witt: stand the combined effects of the safe shutdown earthquake (SSE) , pipe rupture, and equipment deadweight loads. The SSE is a mmbination of two horizontal components and one vertical component acting simultaneously with an instantaneously applied pipe rupture load. For the pipe rupture condition, piping failures are considered as described in Section 3.6. A dynamic analysis of the equipnent supports is performed using hydraulic forcing functions for each of the reactor coolant pipe rupture cases based on the NSSS Vendor's blowdown analysis. The design loading categories, load combinations, and stress limits for the supports are shown in Table 5.5.14-1. The steam generator, reactor coolant pump, pressurizer, and reactor vessel supports are classified as Class I ccxuponent supports. The design of these supports is based on Subsection NF Component Supports of ASME III for normal operating conditions and Appendix F of ASME III for the faulted conditions. 5.5.14.2 Reactor Vessel Support Shield Tank The reactor vessel is supported at four of its nozzles by sliding foot assemblies mounted on a cylindrical support structure. These assemblies are within the NSSS Vendor's scope of design 20 responsibility. The reactor vessel support structure is a double walled cylindrical structure designed to transfer loadings to the heavily reinforced concrete mat of the containment structure and to the reactor cavity wall. The water filled portion of the support structure provides cooling for the reactor vessel supports and also serves to minimize gamma and neutron heating of the concrete reactor cavity wall and to attenuate neutron radiation outside the wall to acceptable limits. The base of the reactor vessel support is fastened down by anchor bolts. Overturning moments and horizontal forces, which would be induced on the support during normal operation or an accident condition, are resisted by the anchor bolts, shear keys, and the reinforced concrete reactor primary shield wall which surrounds \20 the support structure. Any resulting vertical uplift force is reacted by the anchor bolts. 5.5.14.3 Pressurizer Support This is within the NSSS Vendor's scope of design responsibility. @ 663 133 5.5-3 Amendment 20 1/23/76
SWESSAR-P1 5.5.14.4 Steam Generator and Reactor Coolant Pump Supports This is within the NSSS Vendor's scope of design responsibility. 5.5.14.5 Equipment Support to Balance of Plant Structure Inter-face Requirements Interf ace information is given in Tables 3.7.6-1 and 3.8.6-1. O 663 mg 5.5-4 Amendment 24 4/23/76
SWESSAR-P1 TABLE 5.5.7-1 RESIDUAL HEAT REMOVAL SYSTEM SAFETY RELATED INTERFACE REQUIRDENTS RESAR-P1 . RESAR-41 SWESSAR-P1 Interface Item
- Reference Design Electrical ** Note 1 Refer to SWESSAR-P1 requirements Section 8.4.
System layout for Appendix SA Containment operation and construction layout is inspection. shown in Fig. 1.2-3. Sampling Appendix SA Section 9.3.2.6 21
- These requirements are safety related. The SWESSAR-P1 design acconnodates and is compatible with all residual heat removal system interface requirements in RESAR-41.
- This interface requirement is cross referenced in RESAR--41 from RESAR-41 Appendix SA.
Note 1. The RESAR-41 cross reference for these interf ace requirements is given in the cited SWESSAR-P1 section.
's (g i;, J lJJ W 1 of 1 Amendment 21 2/20/76
SWESSAR-P1 TABLE 5.5.7-1 RESIDUAL HEAT REMOVAL SYS1TM SAFETY W f kELATLD I!TftRFACE REQUIREMErrPS (Notes 1& 2) Requirennent B-SAk 205 Reference SWESSAh-P1 Reference C~.,JJT y Section 8.4 (,.q
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- 1. P.? wtric power to ca.erate the equip-ment Fk)te 3 pO
- 2. Controls to oper- Note 3 Section 7.8 ate the system .
- 3. Systeus layout for 9.3.6.6.15.4 Arrangerment drawings operation and 9.3.6.6.15.5 are shown in Fig.
C D inspection 9.3.6.6.15.7 1.2-3 and 1.2-4. c:. -) p'd 4. Courponent cooling Note 2 Section 9.2.2.6 water bE I; 3
- 5. Protection frtxn natural phenomena 9.3.6.6.2.1 9.3.6.6.2.2 Sections 3.3, 3.4, and 3.7 L _;_]
Sections 3.5 and 3.6 (. .3 6. Separation and protection frun 9.3.6.6.3 9.3.6.6.5.1 33 rrm pipe rupture, pipe 9.3.6.6.5.2 g 'y . .J f witip, and internal 9.3.6.6.6 y missiles 9.3.6.6.7
- 7. Reactor coolant 9.3.6.6.10 Section 5.2.7 syst m pressure boundary leak detection
- 8. Envirorsnent 9.3.6.6.19.1 Sections 6.2.2, 9.4.2, 3.11, and 9.4.5
- 9. Instrument air 9.3.6.6.18.1 Section 9.3.1.6. The instru-ment air systems supply no saf ety related f unctions.
y
- 10. Equipet supporta, 9.3.6.6.15.9 Section 5.5.14 L4 loadings, and 9.3.6.6.18.4 seismic design
_m LJ C' B&W 1 of 2 Amendment 33 6/30/77
SW ESSA".-P 1 m TABLE 5.5.7-1 (CONT)
,- Requirement B-SAR 205 Ref erence SWESSAR-P1 keference
- 11. Sampling 9.3.6.6.13 9.3.2.6 9.3.2.1 E'] 9.3.2.2 P 7':) 9.3.2.5 9.3.2.6
- 12. Radiological waste
- a. Liquid waste 9.3.2.3 11.2.11 7 9.3.6.6.16.2a
')
I 9.3.6.6.16.2b C ;. 7 3 9.3.6.6.16.2c
. . ] c),
, b. Gaseous waste 9.3.6.t.16.3 11.3.10 g ~~.7 -
- 13. Envirtrument 9.3.6.6.18.3c 6.2.2.2 CT 9.3.6.6.18.3d T9.4-2 W .~'7 '51 Ly % Note 1. Requirements related to ECCS operatim are a&fressed in Section 6.3.6.
EL Zl.) 2. These requirements are refety related. The SNESSAR-P1 design accomanodates and is cuapatible with all applicable decay heat removal system interrace requirements in D-SAR-205. I
- 3. The B-SAR-205 cross ref erence f or these interf ace requirenen ts is given in l33 the referenced SWESSAR-P1 section.
O CN LW LJ B&W 2 of 2 Amenctaent 33 6/30/77
TABil 5.5.7-1 RESIDUAL llEAT REPWNAL SYSTEM SAFETY REIATED IhMkFACE kEQUIRFMENTS (Note 2) p'y-Requ ir ement CESSAR 'eierence
, SWESSAR-P1 Feference
- 1. Electric gewer to
')
4 operate the equip- Refer to SWESSAR-P1. ment Note 1 Table 8.4-1
- 2. Controls t o oper-7 ate the system tute 1 Refer SWESSAF-P1 Section 7.8.
4
- 3. System layout for 9.2.7.1.4.0. 3, 4 Ar rang esnent drawings ,
are shown in Fig. (- T
)
operation and inspection 1.2-3 and 1.2-4
- 4. Component cooling Note 1 Refer to SWESSAR-P1 water flow to Table 9.2.2-5.
J the puzrps and heat exchangers S. Protection from 3.3.3 Sections 3.3.3, 3.4.30 3.7.6 natural phenomena 3.4.5 I 9.2.7.1.4.H.1, 3 _J
- 6. Separation and 3.5.4.1 Sections 3.5.6 6 3.6.6 "
f- . prot ection irom 3.6.5.I rgg pipe rupture 9.2.7.1.4.C.1 0 9.2.7.1.4.D.1, 2, 3
- 9. 2 . 7.1. 4 . E .1 9.2.7.1.4.F.1, 2 9.2.7.1.4.R.6
- 7. Reactor ctx>lant 9. 2.1.7. 4 . E .7 Leak detection methods system pressure discussed in Section boundary leakage 5.2.7 meet this detect ion requirement.
p 8. Envirorunent 9 . 2 . 7 . 1 . 4 . 11 . 1 , 2 Table 9.4.5.1-3 SWESSAR-P1 Section 3.11 rd
- identifies equipment U speci f icat ion procedures which will ensure that the equipment will be rated
_a within at least the specif1 cations stated ga in CESSAR Table 3.11-2. CJ In nest cases, the speritication wi11 exceed these minimum r equir ment s (nee except ionn) . C-E 1 ot 2 Anendment 21 3/11/76
TAELE 5.5.7-1 (CONT) Note 1. %e CMSAR cross ref erence for these int erf ace requiresnents is given in the cited SWESSAR-t section. Note 2. Dese requiresnents are saf ety related. %e SWESSAR-P1 design accomodates and is Compatible with all shutdown woiinq system interf ace requirements in CESSAR (Section 9.2.7.1.4) except as noted below.
- 1. Item 9 . 2 . 7 . 1 . 4 . 11 . 2 - SIS-MODS-1 thru 16 relocate the shutdown cooling puq)s and heat exchangers to inside the containment s truct ure . Shutdown cooling equipnent required following a Dita which is locat ed insice t he containment structure is qualified to operate under the post - DBA containment structure environment.
- 2. Item 9.2.7.1.4.M.2b - This requires that the shutdown cooling systs sample be cooled to 110 F or less. The SWESSAR-P1 sampling system wolers are designed for a 125 F sample tenperature whic. is satisf actory f or sample analysis. With a component cooling water tmperature of 105 t, a sample temperat ure of 110 F would require an excessively large heat exchanger due to the low IMID.
- 3. Itm 9 . 2 . 7 . 1 . 4 . 11 . 2 - Reactor plant component cooling water system piping connected to the shutdown cooling system is carbon steel.
- 4. Item 9.2.7.1.4.S.1 - This requires independent environment control of shutdown cooling trains. A SWESSAR-P t modif ication to the ECCS relocates the shutdown cooling pump and heat exchanger to inside the containment st ruct u r e . This location will provide redundant, but not independent shutdown cooling train environment control.
2 JJ 4 C-E 2 of 2 Anw'ndment 23 1/31/16
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, ! SHIELD TANK
'j '
PWR REFERENCE PLANT DETAIL A SAFE TY ANALYSIS REPORT r_ S WESSAR - PI
) 1 AME NOME NT 26 tv 2 / 76
SWESSAR-P1 Fig. 5.5.1f4 - 2 and 5. 5.14-3 are deleted. 20 i j; ') Amendment 20
'-)
['; g., 7 - 1/23/76
I
/
5.6 b
//7 DCJ i
INj
SWESSAR-P1 5.6 INSTRUMENTATION REQUIREMENTS ~ 2 The instrumentation provided in connection with the reactor coolant system is within the NSSS Vendor's scope and SAR. [, (1. ) l 14 5.6-1 Amendment 2 8/30 /74
VOLUME 4 PRESSURIZED WATTIR REACTOR REFERENCE NUCI. EAR POWER PLANT SAFETY ANALYSIS REPORT SWESSAR-P1 STONE & WEBSTER ENGINEERING CORPORATION P. O. BOX 232S BOSTON, MASSACHUSEFI3 02107 Copynght 19'4 by Stone & Webster Engineenng Corporation. All matenal herein is the property of said corporation under which all copy and other nghts have been reserved and no such nghts have been granted to others. Stone & Webster Engineenng Corporation millin allinstances take such steps as are necessary for the preservation ofits nghts and the enforcement of applicable law. 9 663 us
SWESSAR-P1 TABLE OF CONTENTS Section Volume CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
1 1.2 GENERAL PLANT DESCRIPTION 1 1.3 COMPARISON TABLES 2 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 2 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 2 1.6 MATERIAL INCORPORATED BY REFERENCE 2 1.7 TERMINOLOGY AND FLOW DIAGRAM SYMBOLS 2 1.8 INTERFACE WITH NSSS VENDOR AND UTILITY-APPLICANT SAR 2 CHAPTER 2 13 SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2 2.2 NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES 2 2.3 METEOROLOGY 2 2.4 HYDROLOGIC E1EINEERIIG 2 2.5 GEOLOGY AND SEISMOLOGY 2 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.2 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 2 9 3.2 CLASSIFICATION OF STRUCTURES, SYSTEPE, AND COMPONEtTIS 2 i 7 - - Amendment 13 O' u J i r0 6/30/75
SWESSAR-P1 TABLE OF CONTENTS (CONT) CHAPTER 3 (CONT) 3.3 WIND AN.2 TORNADO LOADINGS 2 3.4 WATER LEVEL (FLOOD) DESIGN 2 3.5 MISSILE PROTECTION 2 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED 2 WITH THE POSTULATED RUPTURE OF PIPDE 3.7 SEISMIC DESIGN 3 3.8 DESIGN OF CATEGORY I STRUCTURES 3 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3 3.10 SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION 3 AND ELECTRICAL EQUIPMENT 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND 3 ELECTRICAL EQUIPMENT APPENDIX 3A CONFORMANCE WITH NRC REGULATORY GUIDES 3A.1 DIVISION I REGULATORY GUIDES, POWER REACTORS 3 3A.2 OTHER DIVISION REGULA'IORY GUIDES 3 APPENDIX 3B 20l COMPUTER PROGRAMS FOR ANALYSIS OF 3 THE CONTAINMENT STRUCTURE CHAPTER 4 2 REACTOR 3 m p;7g ii Amendment 20 1/23/76
SWESSAR-P1 TABLE OF CONTENTS (CONT) .iection Volume CHAPTER 5 REACTOR COOLANT SYSTEM AND CONIECTED SYSTEMS
5.1 INTRODUCTION
3 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 3 5.3 TIERMAL HYDRAULIC SYSTEM DESIGN 3 5.4 REACTOR VESSEL AND APPURTENANCES 3 5.5 COMPO?ENT AND SUBSYSTEM DESIGN 3 CHAPTER 6 ENGI?EERED SAFETY FEATURES 6.1 GENERAL 4 6.2 CONTAINMENT SYSTEMS 4 6.3 EMERGENCY CORE COOLING SYSTEM 4 6.4 HABITABILITY SYSTEMS 4 APPENDIX 6A DATA FOR DETERMINING THE IODINE REMOVAL EFFECTIVENESS FOR THE CONTAIIDENT A'IHOSPHERE 6A.1 THE SPRAY DROP DISTRIBUTION AND CHARACTERISTIC SPRAY DROP DIAMETERS FOR THE SPRAY HEADERS 4 6A.2 THE SPRAY COVERAGE OF THE CONTAINMENT 4 ATMOSPIERE 6A.3 ANALYSIS OF SLCRS PERFORMANCE 4 APPEND 1X 6B LOCTIC Ih"I'ERFACE WITH NSSS SUPPLIED DATA 20 6B.1 POST - REFIDOD PERIOD 4 6B.2 LONG TEFN MASS - ENERGY RELEASES 4 11 i Amendment 20 ( [ ))] 1/23/76
SWESSAR-P1 TABLE OF COICENTS (CDFE) Section Volume CHAPTER 7 INSTRUMETEATION AND CONTROLS
7.1 INTRODUCTION
4 7.2 REACTOR TRIP SYSTEM 4 7.3 ENGINEERED SAFETY FEATURES SYSTEM 4 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 4 7.5 SAFETY RELATED DISPLAY INSTRUMEITI'ATION 4 7.6 ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR 4 SAFETY 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 4 7.8 INTERFACE REQUIREMENTS 5 CHAPTER 8 ELECTRIC POWER
8.1 INTRODUCTION
5 8.2 OFFSITE POWER SYSTEM 5 8.3 ONSITE POWER SYSTEM S 8.4 INTERFACE DESIGN INFORMATION 5 20 ELECTRIC HEAT TRACING 8.5 S CHAPTER 9 AUXILIARY Sryrr.MS 9.1 FUEL STORAGE AND HANDLING 6 66: ;': O iv Amendment 20 1/23/76
SWESSAR-P1 TABLE OF CONTENTS (COtc) Section Volume CHAPTER 9 (CONT) 9.2 WATER SYSTEMS 6 9.3 PROCESS AUXILIARIES 6 9.4 AIR CONDITIONING, HEATING, COOLING, AND 6 VENTILATION SYSTEMS 9.5 OTHER AUXILIARY SYSTEMS 6 CHAPTER 10 STEAM AND POWER COINERSION SYSTEM 10.1
SUMMARY
DESCRIPTION 7 10.2 TURBINE-GENERATOR AND TURBINE STEAM SYST2 7 10.3 MAIN STEAM SYSTDi 7 10.4 OTHER FEATURES OF STEAM AND POWER COTWERSION 7 SYSTEM CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE ITEMS 7 11.2 RADIOACTIVE LIQUID WASTE SYSTEM 7 11.3 RADIOACTIVE GASEOUS WASTE SYSTEM 8 11.4 PROCESS AND EFFLUENT RADIATION MONITORING 8 SYSTEM 11.5 RADIOACTIVE SOLID WASTE SYSTEM 6 11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAF 8 9
/<7 ,rr v UOJ isd Amendmen* 20 1/21 /76
SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Volume CHAPTER 12 RADIATION PROTECTION 12.1 SHIELDING 8 12.2 VENTILATION 8 12.3 HEALTH PHYSICS PROGRAM 8 12.4 RADIOACTIVE MATERIALS SAFETY (FSAR) 8 CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATION STRUCTURE 9 13.2 TRAINING PROGRAM 9 13.3 EMERGENCY PLANNING 9 13.4 REVIEW AND AUDIT 9 13.5 PLANT PROCEDURES 9 13.f PLANT RECORDS 9 13.7 INDUSTRIAL SECURITY 9 CHAPTER 14 INITIAL TESTS AND OPERATIONS 9 CHAPTER 15 ACCIDENT ' NALYSIS 15.1 GENERAL 9 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 DEFINITIONS 9 16.2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINCS 9 vi Amendment 20
/ , e, '
i' : 1/23/76
SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Voltune CHAPTER 16 (CONT) 16.3 LIMITING CONDITIONS FOR OPERATION 9 16.4 SI'RVEILLANCE REQUIREMENTS 9 16.5 DESIGN FEATURES 9 16.6 ADMINISTRATIVE CONTROLS 9 CHAPTER 17 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING DESIGN AND 9 CONSTRUCTION 17.2 QUALITY ASSURANCE FOR STATION OPERATION 9 APPENDIX A ENCLOSURE BUILDING WITHOUT MIXING 9 APPENDIX B ENCLOSURE BUILDING WITH MIXING 9 vii Amendment 20 hh3 }h2 1/23/76
- 6. ENGINEERED SAFETY FEATURES
~s u (_Dr LJ L'J}}