ML18026A360

Forwards Revised Response to SER Outstanding Issue 71 Re Design Criteria.Info Will Be Included in Next FSAR Amend

ML18026A360
Person / Time
Site:	Susquehanna
Issue date:	05/19/1981
From:	CURTIS N W PENNSYLVANIA POWER & LIGHT CO.
To:	YOUNGBLOOD B J Office of Nuclear Reactor Regulation
References
PLA-812, NUDOCS 8105260310
Download: ML18026A360 (29)

Text

REGULATOl INFORMATION DISTRIBUTION r STEM (RIDS)ACCESSION NBR:8105260310 DOC~DATE: 81/05/19, NOTARIZED:

NO FACIL:50 387 Susquehanna Steam Electric Stations Unit 1P Pennsylv 50 388 Susquehanna Steam Electric StationP Unit 2P Pennsylva 05000388 AUTH'AME AUTHOR AFFILIATION CURTIS~AH.

Pennsylvania Power L Light Co~RECIP~NAME RECIPIENT AFFILIATION YOUNGBLOODrB

~J.Licensing Branch 1

SUBJECT:

For wards.revised response to Q'uestion 260~1~Info will be included in next FSAR amend.DISTRIBUTION CODE: BOOIS COPIES RECEIVED:,LTR g'MCI.$SIZE:.~TITLE.'.PSAR/FSAR AMDTS and Related Correspondence NOTES:Send ILE 3"'copies FSAR L all amends'cy:BHR"LRG PM(L,.RIB)

Send ISE 3 copies FSAR L al l amends.1 cy:BlSR LRG PMi(L~RIB)05000387 05000388 RECIPIENT ID CODE/NAMEi ACTION: A/D LICENSNG RUSHBROOKPM

~INTERNAL: ACCID EYAL BR26 CHEh1 ENG BR 08 CORE" PERF BR 10 EMERG PREP 22" GEOSCIENCES 14 HYD/GEO BR 15 ISE~06 LIC QUAL BR MECH ENG BR 18 NRC PDR 02 OP LIC BR PROC/TST REY 20 RAD ASSESS BR22 01 NG BR25 COPIES'TTR ENCL 1 0 0 1 1 1 1 1 1 1 0 1 1 2 2 3 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME LIC BR 42 BC STARKPRB 04 AUX SYS BR 07 CONT SYS BR 09 EFF TR SYS BR12 EQUIP QUAL BR13 HUM FACT ENG BR ILC SYS BR 16 LIC QUID BR MATL ENG BR 17 MPA'OELD POWER SYS BR 19 QA BR 21 REAC SYS BR 23 SIT ANAL BR 24 COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 1 3 3 1 1 1 1 1 1 1 1 1 0 1 0 1 1 1 1 1 1 1 1 EXTERNAL: ACRS NSIC 27 05 16 16 1 1 LPDR 03 MAY~7 1981 FV TOTAL NUh1BER OF COPIES REQUIRED: LTTR~ENCL v II P1 J I N IT D e e~V, f l g t I I P'h)f~k'l~t PPc,lL TWO NORTH NINTH STREET, ALLENTOWN, PA.18101 PHONE: (215)821-5151 NORMAN W.CURTIS Vice President.

Engineering IL Construction 821-5381 May 19, 1981 Mr.B.J.Youngblood, Chief Licensing Branch No.1 U.S.Nuclear Regulatory Commission Washington, D.C.20555 SUSQUEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ISSUE 871 ER 100450 FILE 841-2 PLA-812 Docket Nos.50-387 50-388

Dear Mr.Youngblood:

In reply to Susquehanna Safety Evaluation Report Outstanding Issue/$71, attached please find PL's revised response to Question 260.1.This information will be included in the next FSAR amendment.

Very truly yours, N.W.Curtis Vice President-Engineering S Construction-Nuclear TEG/mks Attachment foot j/(8x o52eo SIO PENNSYLVANIA POWER&LIGHT COMPANY 111 Il s't I'

~~SSES-FSAR r Section 17.1.2.2 of the standard format (Regulatory Guide 1.70).requires the identification of safety-related structures, systems, and components (Q-list)controlled by the QA program.You are requested to supplement and clarify the Q-list in Table 3.2-1 of the FSAR in accordance with the following:

a~The following items from the Q-list need expansion and/or clarification as noted.Revise the list as indicated or-)ustify not doing so.1)Clarify that the Control Rod Drive System includes the~scram accumulators.

2)'larify that discharge piping fill lines and jockey pumps are included in the HPCI, RCIC, RHR, and Core Spray Systems.3)Clarify that the Emergency Core Cooling and RCIC Systems include the mechanical vortex suppression devices.4)Identify the"equipment associated with a safety action" as regards the Leakage Detection System.For'example, it is not clear that post-LOCA ECCS Leakage Detection Systems are included.b.The following items do not appear on the Q-list.Add the following items to the list or justify not doing so.'1), ESSW Spray Pond Emergency Spillway.Cr 2)Site grading.3)Roof scuppers and parapet openings.4)Pressure resisting doors.5)Meteorological data collection programs.6)Refueling Interlock System..7)Rod worth minimizer.

8)Primary Containment Vacuum Relief System-instrumentation and controls.9)Standby Gas Treatment System-instrumentation and controls.10)Missile barriers for safety'related equipment.

Rev.23, 6/81 260.1-1 SSES-FSAR ll)Steam lines to the HPCT and RCIC turbines along with the associated valves and restraints.

12)Equipment and drain floor-piping and containment isolation valves.I 13')Quencher and quencher support.14)Downcomers and braces.15)Primary Containment Purge System.16)Primary Containment Ventilation System-piping and containment isolation valves.17), Onsite Power Systems (Class'1E)a)transformers b)valve operators c)protective relays and control panels 18)Engineered safety features RC equipment-protective relays and control panels.19)Biological shielding within primary containment, reactor building, and control building.20).Nuclear boiler system instrumentation piping beyond the.outermost isolation valve.21)Drywell cooling system piping and valves for coolers V-414A and B, V-415A and B, and.V-416A and B, 22)Mainsteam system piping to turbine stop valves and branch line piping up to and including first valve.23)Spent fuel pool liner.24)Radiation monitoring (fixed and portable).

25)Radioactivity monitoring (fixed and portable).

26).Radioactivity sampling (air, surfaces, liquids).27)Radioactive contamination measurement and analysis.28)Personnel monitoring'nternal (e.g., whole body counter)and external (e.g., TLD system).29)Instrument storage, calibration, and maintenance.

i 30)Decontamination (facilities, personnel, and equipment).

260.1-2 Rev.23, 6/81 SSES-FSAR~31)'espiratory protection, including testing.32)Contamination control.33)Feedwater spargers.34)Safety-related masonry walls (see IE Bulletin No.80-11).35)Measuring and test equipment used for safety-related

~str'uctures, systems, and components.

36)Expendable and consumable items necessary for the functional performance of safety-related structures, systems, and components (i.e,, weld rod, fuel oil,'oric acid, snubber oil,.etc.).c.Enclosure 2 of NUREG-0737,"Clarification of TMI Action Plan Requirements" (November 1980)identified numerous items that are safety related and appropriate for OL application and therefore should be on the Q-list, These items are listed'below.Add these items to the Q-list and/or indicate where'on the Q-list they can be found.Otherwise justify not doing so+NUREG-0737 (Enclosure 2)Clarification Item 1)Plant-safety-parameter display console, 2)Reactor coolant system vents.3)Plant shielding.

4)Post accident sampling.5)Valve position indication.

6)Dedicated hydrogen penetrations.

7)Containment isolation dependability.

8)Accident monitoring instrumentation.

I.D.2 II.B.1 II.B.2 II.B.3 II.D.3 II.E.4.1 II.E.4.2 II.F.1 9)Instrumentation for detection of inadequate II.F,.2 core-cooling..

10)HPCI&'RCIC initiation levels.11)Isolation of HPCI and rCIC., II.K.3 (13)II.K.3(15)'ev.

23, 6/81 260.1-3

SSES-FSAR 12)Challenges to and failure of relief valves.II.K.3(16) 13)ADS actuation.

14)Restart of core spray and LPCI.15)RCIC suction.16)'pace cooling for HPCI.&RCIC.17)Power on pump seals.18)Common reference level.19).ADS valves, accumulators, and associated equipment and instrumentation.

II.K.3(18)

II.K.3(21)

II.K.3 (22)II.K.3(24)

II.K.3(25)

II.K.3(27)

II.K.3 (28)20)Emergency plans.21)Emergency support facilities.

III.A.1.1/III.A.2 III.A.1.2 22)Inplant I radiation monitoring.

III.D.3.3 23)Control-room habitability.

.~r~III.D.3.4 d.The-instrumentation and control systems and components must.'be, identified on the Q-list (FSAR Table 3.2-1)to the same scope and level of detail provided in Chapter 7 of the FSAR.RESPONSE: Introduction Table 3.2-1 (SSES Design Criteria Summary)of the FSAR is intended to provide identification of safety-related structures, systems, and components as required'by Section 17.1.2.2 o'f the standard format (Regulatory Guide 1.70).The"Q List" for Su'squehanna

'SES is not a part of the FSAR.The"Q-List" is gust~one of a,series of controlled QA program documents which serve to identify in expanded detail the quality classification of SSES items and related services in response to FSAR commitments.

Quality Code Section III related, safety impact relate/, fire protection related, environmental monitoring related, etc.Th'SSES QA Manual and its impleneting procedures presecribe the.preparation and maintenance of these quality classification documents and defines the quality assurance controls that are to be applied to s'uch items/services.

a-1 The scram accumulators are a part of the hydraulic control unit..which is.indicated as, safety related in Table,3.2-1.

Rev..23, 6/81 260.1-4 SSES-FSAR O.a-2 The discharge piping fill lines for HPCI, RCIC, RHR and core spraysystems are included in Table 3.2-1 of the FSAR.These lines, between the main system piping and the condensate

~system outer isolation check valve, are included under the respective systems subsection's"Piping Beyond Outermost Containment Isolation Valves." The line fill system adopted for SSES does not incorporate)ockey pumps to perform the fill function.The fill function's performed by the condensate transfer system..See response to Question 211.211 and FSAR Section 6.3.a-3 The'SSES Suppression Pool has no vortex suppression devices.Testing is conducted to assure that vortices do not adversely affect ECCS systems.The condensate storage tank supply-line is provided with a vortex breaker;however, it is not safety related inasmuch as'he tank is not safety related.5ee response to NRC Question 211.214 for testing information.

a-4 b-1 See revised Note 39 to FSAR Table 3.2-1.ESSW Sp'ray Pond Emergency Spillway The ESSW Spray Pond Emergency Spillway was installed as part of the spray pond concrete liner.The material used to construct the spillway (concrete and reinforcing steel)was" controlled, by the same quality requirements in effect for the concrete liner.Therefore, the listing on Table 3.2-1 for Spray Pond (Structures Page 26)applies to the ESSW Spray.Pond Emergency Spi'llway as a safety-related structure.

b-2 All Category I buildings have watgrtight doors.Therefore, site grading will not affect safety-related equipment and should not be considered a safety-related item (Reference FSAR Section 2.4.2.3).For this reason site grading will not be listed on Table'.2-1; however, watertight doors are listed in the revised Table 3.2-1.b-3 Roof scuppers and openings are not part of the secondary containment structure for the.Reactor Building.Overflow will not penetrate into doors (reference response to Question 260.1.b.2).

The parapet openings are also a backup system for the primary drainage System on the roof.Roof loads as a result of scupper failure have'een considered in the structural design of the buildings.

Therefore., the scupper and parapet openings are not safety-related items-.and will not be'isted in Table 3.2-1.A discussion of the design capacities of the roof drainage system is provided in FSAR Subsection 2.4.2.3.260.1-5 Rev.23, 6/81' SSES-FSAR b-4 Pres'sure-resisting doors classified as safety-related components are designed according to the criteria shown in the revised section of.Table 3.2-1 (Buildings).

b-5 This stem is not a"structure, system or component"requiring entry in Table 3.2-1.Control of this activity is provided by appropriate procedures which are covered under a quality program.b-6 Not in Table 3.2-1.Not a safety system.However;there are surveillances required by Technical Specifications.

b-7 Not in Table 3.2-1.Not a safety system.However, there are surveillances required by Technical Specifications.

b-8 No instrumentation or controls for the Primary Containment Vacuum Relief'ystem have a safety related functin, (i.e., They are only for testing and are not used post-LOCA).

Therefore, they are not included in Table 3.2-1.b-9 See revised Table 3.2-1 under Standby Gas Treatment"and associated instrumentation" has See:e>added to Control Panels.b-.10 Those missile barriers classified as safety-related structure are designed in accordance with the criteria shown..in the revised section of Table 3.2-1 (Structures)."Piping beyond outermost containment isolation valve, other" b-ll Piping=and,associated valves to the HPCI and RCIC turbines are included in Table 3.2-1 of the PSAR under the following subsections:

HPCI-"Valves other" RCIC-Piping beyond outermost containment isolation valve,.other" ,"Valves other" Associated restraints for the HPCI and RCIC turbine~i~in,'re not detail'ed in Table 3.2-1 of the FSAR as they are.not principal components of systems.b-12 Table 3.2-1 of the FSAR has been revised to incorporate the safety related piping and isolation valves and applicable codes and standards associated with the containment penetrations.

b-13 See revised Table 3,2-1 (Nuclear Boiler System).Rev.23, 6/81 260.1-6 SSES-FSAR b-14 See" revised Table 3.2-1 (Buildings).

e The Primary Containment.

Purge System is not safety related'ith the exception o'f the piping and valving associated with the primary containment penetration boundary.See revised Table 3.2-1 under Primary Containment Purge System.b-16 The Primary Containment Ventilation System should be referred to as the Dry Well Cooling System.The Dry Well Cooling System has no primary containment penetration.

b-17 Appropriate onsite power system components whicha re safety-'elated are listed in Table 3.2-1.Where the specific components are part of a safety-related (class 1E)system, they appear in Table 3.2-1 as subsets of the, Onsite Power Systems.(E'xample:

Load CenterTransformers a'r e a subcomponent of Load Center, and Valve Operators are a subcomponent of Motor Operated Valves.)b-18 Engineered safety features DC equipment listed under electric systems are safety-related.

See Table 3.2-1.The'protective relays and control panels are subsets of this'system.b-19 Biological shielding determined to be safety-related is designed in accordance with the criteria shown in the revised.section of Table 3.2-1 (Structures, Page 26).b-20 D Instrument lines are safety-related for all divisionalized loops all the way to the local instruments, These are included as a subset of the various systems identified in Table 3.2-1.'-21 With the exception of cooling water.piping and valves associated with the primary containment penetration boundry the reactor building chilled water system is not safety related.In Table 3.2-1'the com onents of the Dr ell Coolers have been listed se aratel under Dr ell Coolin~Sstem.b-22 As indicated in Table 3.2-1, under Nuclear Boiler System, the piping beyond the outermost isolation valves up to the turbine casing is Quality Group"B" and as stated in Note.20, has been designed by the use of a dynamic seismic system analysis to withstand the OBE and SSE design loads in combination with other appropriat'e loads, within the limits specified for Class 2 pipe in the ASME Section 3 Code.b-23 Spent'fuel pool liner is addressed in Table 3.2-1 under"Structures Rev.e 23, 6/81 260.1-7 SSES-FSAR b-24 This'is not a'"structure, system or component" requiring entry.in Table 3.2-1.Control and calibration of radiation'onitoring (fixed and portable)is provided by appropriate'rocedures which are covered under a quality program.b-25 This is not a"structure, system or component" requiring entry in Table 3.2-1;Control and calibration of radioactivity monitoring (fixed and portable)is provided by appropriate procedures which are covered'nder a quality program.b-26 This item is not a"structure, system or component" requiring entry in Table 3.2-1.Control of radioactivity

'ontamination measurement and analysis is provided by appropriate procedures which are covered under a quality program.b-27 This item is not a"structure, system or component" requiring entry in Table 3.2-1.Control of radioactive contamination measurement and analysis is provided by'appropriate procedures which are covered under a quality program.b-.28 This item is not a"structure, system or component" requiring entry in Table 3.2-1.Control of personnel monitoring.(e.g., while body counter)and external (e.g., TLD,system) is provided by appropriate procedures which are covered under, a quality program.b-29 This item is not a"structure, system or component" requiring entry in Table 3.2-1.Control of instrument storage, calibration and maintenance is provided by appropriate procedures which are covered under a quality program.b-30 Decontamination equipment and facilities are not safety related.Decontamination piping and valves are a part of the"Liquid Radwaste Management Systems--'iquid&'Chemical Waste Piping and Valves" as described in Table 3.2-1 of the FSAR.Personnel decontamination is not a"structure, system or component" requiring entry in Table 3.2-1.Control of, personnel decontamination is provided by appropriate procedures which are covered under a quality program'.b-31 This item is not a"structure, system or component" requiring.entry in'able 3.2-1.Control of respiratory protection, including testing is provided by appropriate procedures which hre.covered under a quality'program.'I Rev.23, 6/81 h 260.1-8 b-32 Thi's item is not a"structure, system'r component" requiring entry in Table.3.2-1.Contamination control is provided by appro'priate procedures which are covered under'a quali t y pr ogram.b-33 Masonry walls designed as safety-related structures are designed in accordance with the criteria shown in the revised section of Table 3.2-1 (Structures).

b-35 Measuring and test equipment is not safety related.-Calibration of these pieces of measuring and test equipment used to perform checks on safety functions of safety-related equipment are controlled by the constuction/operational QA program..b-36 The classifi'cation of these items is byond the'efinition of'"structure, system or component" requiring entry in Table 3.2-1.The quality classification of expendable and consumable items necessary for the'functional performance of safety-related structures.

systems or components is determined.

as part of the procurement process in accordance with the provisions of the QA program.~~c.'ntroduction Part C of the question invokes enclosure (2)to NUREG 0737 as the basis for modifying Table 3-.2-1 to include certain items.NUREG 0737 does not impose this requirement in all cases.Many of the TMI action plan requirements are intangible in that they call for studies, documentation, administrative controls, etc.Our approach in responding to Part C of this question has been to identify'ma)or structural or hardware-related requirements of NUREG 0737, and to apply quality assurance to those items, if appropriate.

Finally, for SSES, implementation of many of the identified sections of'NUREG 0737 is not yet required per enclosure (2).Foi all modifications that are eventually required for SSES, safety-related classification will be determined.

For more information, refer to PP&L's response to NUREG 0737.c-1 c-2 The Safety Parameter Display System (SPDS)is not sfaety related and therefore will not be added to Table 3.2-1..However, it will be procured and'maintained under procedures

'which are covered under a quality program.The various.reactor coolant system vent paths are safety-related.They are designated in Table 3.2-1, as follows: The RCS ve'ssel head vent is a subset of"reactor vessel appurtenances,'ressure retaining portions" under"Reactor System".Rev.23, 6/81 260.1-9 SSES-FSAR The main steam relief valves with their ADS function'are a subset of"safety/relief valves" under"Nuclear Boiler.System.".c-,3 Shield walls identified as a result of the Plant Shielding'tudy (NUREG"0737 Item II.B.2)will be reviewed for classification as safety-related structures.

Table 3.2-1 wil'1 be updated as necessary to reflect the design criteria used for design of those shielding walls classified as safety-related.

c-4 The Post Accident Sampling Station (PASS), with the exception.of its interfaces with safety related systems.will not in itself be safety related.All PASS interfaces will'e covered in the appropriate systems in their piping/valve descriptions.

Specific description of the PASS in Tabl'e 3.2-1 will be incorporated upon completion of design.PASS operations will not be a"structure, system or component" requiring entry in Table 3.2-1.Control will be provided by appropriate procedures in Chapter 17 of the FSAR'and Section 6.8 of the technical sp8cifications describing the QA program coverage of procedural controls.c-5 c-6 Valve position indication is a subset of Safety Relief Valve under Nuclear Boiler System in Table 3.2-1.Not.applicable to SSES.Hydrogen recombiners are inside containment.

c-7 Containment isolation valves are safety-related as shown in Table 3.2-1.This subject was part of a study from which no changes to Table 3.2-1 resulted.c-8 Accident monitoring has both safety and non-safety related listing as follows: (a)Noble gas effluent radiological monitor is non-safety related per'NUREG-0737.(b)Continuous samples of plant effluents for.radioactive iodine and particulate are non-safety related.(c)Containment Hi-range radioactive monitors are, safety related.See revised Table 3.2-1 under Post Accident Monitoring.(d)Containment pressure monitor is safety related.See revised Table 3.2-1 under Post Accident Monitoring..

Rev.23, 6/81 260.1-10 SSES-FSAR (e)Containment suppression pool water level instrumentation is safety related.See revised Table 3.2-1 under Post Accident Monitoring.(f)Containment H 20 2 monitor system is safety related, See revised Table 3.2-1 under Post Accident Monitoring.

" c-9 As a result of this study, no additional instrumentation was re'quired, therefore there is no change required in Table 3.2-1.c-10.As a result of these studies there was no change required of the HPCI and RCIC set points.There were no changes to Table 3.2-1 because of these studies.c-ll These studies resulted in minor changes to the systems but no changes'to Table 3.2-1.c-12 Response to the TMI s'tudy is still in the evaluation phase.Table 3.2-1 will be modified as necessary.

c-g3'The'WR owners group is still evaluating this requirement.

If the study s'o indicates, Table 3.2-1 will be modified accordingly.

..--".c-, 14 This study determi'ned.

that no changes were required to Table 3~2-14"~~c-15 The changes resulting from the requirements of NUREG 0737, Item II.K.2(22), did not-alter the content of Table 3.2-1.c-16 Safety-related unit coolers are provided in these rooms as necessary to maintain temperature..See ECCS Pump Room in Table 3.2-1.c-17 Response to the TMI issues is under study/evaluation..

Any modifications to the SSEs design will be reflected in Table 3.2-1 as appropriate.

c-18 This study resulted in no changes to SSES equipment.

Entries in Table 3.2-1're not required as they are included within the individual systems.c-'19 Response to this TMI issue is under study/evaluation.

Any modifications to the SSES design.will be evaluated'o determine if they are safety relatd.Table 3.2-1 will be modified as deemed appropriate.

c-20 This item is not a"structure, system or component" requiring entry in Table 3.2-1, Control of this activity is provided by'ppropriate procedures.

Chapter 17 of the FSAR Rev.23, 6/81 260.1-11 S SE S-F SAR and Section 6.8 of the Technical Specifications describe the QA pr'ogram coverage of procedural controls'-21 c-22 c-23 These items are not safety related.Justification is contained in NUREG 0696 paragraph 2.5 and 4.2 (Table 2 and.footnotes).

'he Emergency Facilities are not required for safe shutdown or immediate or long term operation following a LOCA.The failure of these facilities will not cause the release of radioactivity in excess of 10 CFR 100 limits or cause or increase severity of a DBA.The individual facilities will be designed and installed in accordance with quality plans set forth'under Section I.D of NUREG 0696.For these reasons Emergency Support Facilities will not be added to Table 3.2-1.This item is not a"structure, system or component" requiring entry in Table 3.2-1.Control of this activity is provided by appropriate procedures.

Chapter 17 of the FSAR and Section 6.8 of the Technical Specifications describe the~QA'program coverage of procedural controls.'Control room habitability is mai5taWed by safety related equipment.

" This equipment is identified in Table 3.2-1'nder tEe section heading HVAC System-Control Structure.

d.Instrumentation and Control system are identified only at the system level in Table 3.2-1 without providing information on the individual component level.The quality classification of individual components has been identified in expanded detail in controlled QA program documents (e.g.,"Q-List" and the isntrument index).Rev.23, 6/81 260.1-12 SSES-FSAR TABLE 3.2-1 Continued Page 15 Quality Source Group FSAR of Loca-Classi-Section~Su 1 tion fication Principal Construe tion Safety Codes and Class Standards Quality Seismic Assurance Ct~~RI t C t Principal Components (34+)(1)*(2)*(3)*(4)*(5)*(6)*(7)**Fans Coils, cooling Ductvork Dampers Piping and valves Combustible Gas Control S stem P P P P P NEMA MG1 AMCA 210 ARI AISI AMCA B31.1~C NA I Y C NA I Y C NA I,-Y C NA I Y C NA NA N 116 Hydrogen recombiners inside containment Primary Containment Atmosphere monitoring system (PCA!tg)Piping valves forming Contmt.Penetration Boundary Standb Gas Treatment S stem 9.4.1 P C NA 2 NA I P CR R B>D 2 III-2.I P C>R B 2 III-2 I 10, 41 l22 Motors Fans Prefilters Demisters HEPA filters Adsorber units Ductvork Dampers Piping Valves Electric heaters Control panels and associated instrumentation Radvaste Buildin HVAC Motors Fans Prefilters HEPA filters 9.4.3 P P P P P P P P P P P P P P CS NA 3 CS NA 3 CS NA 3 CS NA 3 CS NA 3 CS NA 3 CS NA 3 CS NA 3 CS C.3 CS C 3 CS NA 3 C,S NA 3 RW NA Other RW NA Other RW NA Other RW NA Other IREE-323/I 344 AMCA I UL Class 1 I MSAR 71-45=I MIL-F-I 51079 MIL-F-51068C AACC CS-8 I RDT M-16-1T AISI I AMCA I NFPC I B31.1 I hEMA 6 hEC I hVIIA I REMA MG1 NA A'.1CA NA UL Class 1 hA MIL-F-NA Y Y Y Y N N N'16 16 16 16 16 16 16 16 16 16 l 22*Refer to the General Notes at the end of this table.Rev.23, 6/81 SSES-FSAR TABIZ 3.2-1 Continued Quality Source Group FSAR of Loca-Classi-Safety Section Su 1 tion fication Class Principal Construc-tion Codes and dt d&Quality Seismic Assurance C ton R~tt C t Principai Components (34+)(1)*(2)*(3)*(4)*(S)*(6)*(7)*All portions that input to the reactor protection system GE C>R NA 2 IEEE-279 I All portions that input to the engineered safety feature actuation system En ineered Safet Features Actuation S stem 7'P/GE C>R NA 2 IEEE-279 I All portions En ineered Safet Features S stems 7.3 controls snd instrurentation reciufred for safety associated with each actuated system)Emergency core cooling system Containment isolation system Containment purge systems (pressure boundry only)Emergency diesel generator systems Main steam line break detection system Controls and Instrmentation Associated with Safe Shutdown~Sstems Control room habitability system PCA!ig GE C>R NA 2 IEEE-279 I GE P P C>R NA C,R NA C,R NA 2 IEEE-279 I 2 IEEE-279 I 2 IEEE-279 I P G RA 2 IEEE-279 I P C>R,T NA 2 IEEE-279 I P CS NA 2 IEEE-279 I P C,R B>D 2 IEEE-279 I Y Y Y Y Y[23/iS Instrumentation Associated with Other S stems Re uired for Safet 7.6 Spent fuel pooling cooling system Fuel handling area ventilation isolation system Control room panels Iocal instrument racks associated P R P R P CS 2 IEEE-279 I 2 IEEE-279 I 2 IREE-279 I Y Y/is/ig*Refer to the General Notes at the end of this table.Rev.23'/81 SSES-FSAR TABLE 3.2-1 Continued page 21 Quality Source Group FSAR of Loca-Classi-Safety Section~Su 1 tion fication Class Principal Construc-tion Codes and Standards Quality Seismic Assurance eton R~tt c t Principal Components (34>>)(1)*(2)*(3)*(4)*(5)>>(6)*(7)*vith safety related equi~nt Instrumentation Associated vith S stems Not Re uired for Safet 7.7 P ALL NA 2 IREE-279 I Seismic instrumentation Area radiation monitoring Leak Detection S stem Temperature elements Differential temperature svitch Differential flov indicator Pressure svitch Differential pressure indicator svitch Differential flov suss>er I Process Radiation Monitors nt~g.2.5 P ALL NA Other NA P ALL NA Other NA GE GE N/A 2 IEEE-323 I N/A 2 IEEE-323 I GE C,R>T N/A 2 IEEE-323 I GE C,R N/A 2 IEEE-323 I GE N/A 2 IEEE-323 I GE C,R N/A 2 IREE-323 I Y N Y Y 39 39 39 39 39 39 (23 15 Electrical modules, main steam line and reactor building ventilation monitor Cable, main steam line and reactor building ventilation monitors Electric S stems GE R N/A 2 IREE-323 I P R N/A 2 IEEE-279/I 323/383 Y En ineered Safet Features AC~EI t t 4.16 kV svitchgear 480 V load centers 480 V motor control centers 8.3 0 NA NA NA IEEE-308/323/344 IEEE-308/323/344 IEEE/308/344 En ineered Safet Features DC E~t 8.3*Refer to the General Notes at the end of this table.Rev.23, 6/81 t SSES FSAR TASLE 3.2-1 Continued Quality Source Group TSAR of Loca-Classi-Safety Seetfon~Su 1 tion fication Class Princfpal Construc-tion Codes and Standards 22 Quality Sefsnfc Assurance Ct~R~lt C t Princfpal Couponents (34*)(1)*(2)*(3)*(4)*(5)*(6)>>(7)*125 V and 250 V statfon batteries and racks, battery cbargers 125 V s>>itchgear and distribution panels 120 V Vital AC S ste>s E ui ent 8.3 Static invcrters 120 V distribution panels Electric Cables for ESF E ui ent 8.3 P CS NA 2 IEEE-308/I 323/344 P CS NA 2 IEEE-308/I 323/344 P CS NA 2 IEEE-308/I 323/34>4 P CS>R NA 2 IREE-308/I 323/344 5 kV pover cables 600 V pover cables Control and instrunentation cables ALL NA ALL NA ALL NA 2 IEEE-308/383 IREE 308/383 IEEE-308/383 NA NA 15 15 15 Miscellaneous Electrical Priuary contafnnent bui)dfng electrical penetration assc=blies Conduit supports, safety related Tray supports, safety related Euergency lfghtfng systens Euergency coo>aunicatfons syster>s Dfescl generator Auxilia S stens Coupresscd Air and Instrurient Gas Svstcns 9.3.1 P P P P P ALL NA ALL NA ALL HA ALL NA G NA 2 IEEE-317/I 344/383 2 IREE-344 I 2 IEEE-344 I 2 IREE-344 I Other NONE NA 2 IREE-387 I Y Y Y N Y 15 15 Co~ressors Pressure vessels, for safety related equfpnent P T NA P C>R C Other NONE NA h 3 III-3 I T*Refer to the General Notes at the end of this table.

SSES-FSAR TABLE 3.2-1 Continued Quality Source Group FSAR of Loca-Classi-Section~Su 1 tion fication Principal Construc-tion Quality Safety Codes and , Seismic Assurance cl dt d d c*ten R~lt c t Principal Components (34>>)(1)*(2)*(3)>>(4)>>(5)*(6)>>(I)>>Pressure vessels, not for safety related equipment Piping, and valves forming part of containment boundary Piping and valves, safety related Piping and valves>other Nitrogen storage bottler Sa lin S stems 9.3.2 P P P C IR B C IR C ALL D R Nh 2 III-2 I Y 3 III-3 I Y Other B31.1.0 NA N Other DOT I N ALL D Other VIII-1 Nh N)16 Ldg Sample coolers Piping and valves on III-1 systems Piping and valves on III-2 systems Piping and valves on III-3 systems Piping and valves, other systems Piping and valves, containment penetration, isolation Fire Protection S stem Tanks Pumpsl piping and vater system components Gas system components (CO and Halon 1301)Fire and smoke detection and alarm system Generator External N dro en S stem 9.5.1 C>R,T>D RW C A C,R B R>T>RW C R,T,RW D C B P 0 D P-ALL Nh P CS Nh P ALL NA 4 VIII-1 NA N TERA C t 1 III-1 I Y 3 Other III-2 I Y I II-3 I Y B31.1.0 NA N III-2 I Y Other API-650/Nh N D100 Other NFPA/NEPIA Nh N Other NFPA/NEPIA Nh N Other NFPA/hEPIA NA N 10 10 10 10 10[ld Vessels Piping Valves P T D Other VIII-1 Nh N P T D Other B31.1.0 NA N P T D Other B31.1.0 NA N*Refer to the General Notes at the end of this table.Rev.23, 6/81

SSES-FSAR TABLE 3.2-1 Continued Quality Source Group FSAR of Loca-Classi Safety Section SuuSlr tion f ication Class Principal Construc-tion Codes and Standards a e 24 Quality Seismic Assurance C~t*I~RC t C t Principal Components (34+)(1)*(2)*(3)*(4)*(5)*(6)*(I)*Vessels Piping Valves P P~p 0 D 0 D 0 D Other VI I I-l NA N Other B31.1.0 NA N Other B31.1.0 NA N Plant.Chilled Water S stem Chillers Chilled vater heat exchangers Pu~s Piping Valves Safet Related Chilled Water S stem 9~2.12 P ALL D P ALL D P ALL D P ALL D P ALL D Other Other Other Other Other B9.1 VIII-1/TEMA C VIII-1/Hyd.I B31.1.0 B31.1.0 NA Nh N N NA N NA H NA N Chillers Heat exchangers Motors Piping Valves E ui ment and Floor Drains 9.3'P P P P CS D 3 CS D 3 CS D 3 CS HA 3 CS D 3 CS D 3 ARI/B9.1 VIII-1/TEMA C VI I I-I/L Hyd.I IEEE-323/344 B31.I B31.I I Y I-Y Piping, radioactive Piping, nonradioactive Piping S valves, containment penetrating isolation Demineralised Water Makeu S stem 9.2.9 P P ALL D ALL D RIG B Other B31.1.0 Other B31.1.0 NA NA N N 2 III-2 I Y Tanks Pumps Motors Piping and valves P P P P CW, D CW D CW NA ALL D Other VIII-I Other B31.1.0/Hyd.I Other NEMA MGI Other B31.1.0 Nh Nh N N Nh N NA N~tRtldl~*Refer to the General Notes at.the end of this table.Rev.231 6/81

SSES-iSAR TABIZ 3.2-1 Continued Quality Source Group PEAR of?oca-Classi-Safety Section~Su 1 tion fieation Class Principal Construc-tion Codes and Standards Quality Seisnic Assurance~CC*Rn R~tt C t Principal Coscponents (34+)(I)*(2)*(3)*(4)*(S)*(6)*(I)**Reactor Building Pressure resistant doors Matertight door R.B.Equipncnt door Prinary Containnent Access hatches/locks/doors Liner plate Penetration assenblies Vacuun relief valves Do>cnconers Dovncos>er Bracing Diesel generator building Control structure Radvaste and offgas building Turbine building Adninistration building, Circulating>>ster punp house Ega pua>phouse

.Structures P R P R P R P R P C P C P C P C P C P C P C P G P CS P RV P T P 0 P 0 P 0 B B B B B B NA NA NA NA NA NA NA 2 2 2 2 2 2 2 2 Other Other Other Other 3 ACI/AISC ASTM/ANS AISC ASIM/AMS ASTM/ANS ACI/AISC/III III-MC III-MC III-MC III-2 III-MC AISC AC I/AISC ACI/AISC AC I/AISC ACI/AISC ACI/AISC ACI/AISC AC I/AISC I NA NA NA I I I I I I I I I NA NA NA NA I Y Y Y Y Y Y Y Y N N N N Y 27>30 29 22 21 22 I 22 Spray pond gc Energency Spillvay Condensate storage tank Spent fuel pool Spent fuel pool liner Refueling uater storage tank Pipe Nhip Restraints Missile Barriers for safety related ecluipnent Biological shielding uithin Prinary containnent>

reactor Building and control building Safety related nasonry valley Post.accident njonitorin P P P P P-P 0 NA 0 D R NA R NA 0 D R,C NA C>R>NA CS>SM, G C,R, NA CS R>G, NA CS 3 Other 2 2 Other 3 ACI~D100 ACI/AISC ACI/AISC D100 AISC I NA I I NA I Other AISC I Other ACI/AISC I Other ACI/UBC I Y N Y Y N Y 42 22 22*Refer to the General Notes at the end of this table.Rev, 23, 6/81 SSES-CESAR TABLE 3.2-1 Continued pa8e 26 Quality Source Group ESAR of Loca-Classi-Section~Su 1 tion fication Principal Construe tion Safety Codes and Class Standards Quality Seiseic Assur~ere C tun R~tt C t Principal Conponents (34>>)(1)*(2)" (3)>>(4)*(3)*(6)>>-(I)>>Containnent Radiation Honitorin8 Equipnent SRV position indication systen Nohlr gas c fflucnt radiological s>nnltor Continuous sanples of plant effluents for radioactive iodine 6 particulates Containnent hi-ran8e radiation sonitor Contai~nt pressure nonitor Containnent Suppression pool vater level instr.Containnent H/0 nonitor systen P P R hH 2 ANSI N13.1 I R NA 2 323/344 I R NA 2 323/344 I Y Y R NA R NA 2-323/344 I 2 323/344 I P R NA 2 323/344 I Y P R NA 2 323/344 I Y P R NA 2 ANSI N13.1 I N 22*Refer to the General Notes at the end of this table.Rev.23>6/81 SSES-F SA R'I~.BLE 3.2-1/Con tinueil)Page 37 d..As-cast surf aces shall be maqne ic particle or liquid penetrant.tested accordinq zo ASK,E,Section XII, Paraqraph N-232.4 or N-323.3, e..Wheel and shaft forqinqs shall be ultrasonically tested accozdinq, to AST8 A-368, r Butt-welds shall be radioqraphed accozding to ASMZ,Section III, Pazaqraph N624, and magnetic particle or liquid penetrant tested accordinq to ASM E Sect,ion III, Pa raqraph N626 cr N627 respective1y, q.Notification to be made on major repairs, and records maintained thereof,'h.Record system and tzaceabi3.ity according to ASIDE Boiler and Pressure Code Section 1, Appendix IX, Paragraph IX-225;39)These instruments initiate isolation of associated eguipment upon detectinq abnormal leakaqe.P.Xn addition to a sving check valve inside the dryvell and a positive actinq check vs.ve outside the dryvell similar to an Atvood-Norrill boiler feed pump check valve as described in their Cataloq 63,Section I,,a valve with hiqh leak-tiqht inteqrity shall be'provided outside the dzyvell.Additional'ly, a sw'inq check valve and a valve with high'leak-tiqht inteqrity shall be provided, inside and just outside the containment, respectively.

The spring-loaded piston operator.of.the positive actinq check valve will be held open by air pressure durinq normal operation.

Fail-open solenoid valves vill be used to release air pressure and to permit the check valve piston operator to'close.The positive acting check valve and the hiqh leak-tiqht inteqrity isolation valve vill be remote manually operated from the control zoom using siqnals which indicate loss of control rod drive flow.The classification of the control rod drive water return line from the reactor vessel to and including the motor operated valve outside the drywell vill be Group A.The remainder of the system will be Code Group D, except the portion between the check valve j'ust inside the containment and.the motor operated valve just outside the containment including both valves.which vill be Group B.41 Sample.pipinq and isolation valves are quality group B.Because the.analyzers are isolated from containment atmosphere on accident conditions, the piping in the analyzers is quality qroup D.Isolation is manually removed'o allow monitorinq.

42 R eactor shield vali concrete is a non-structural element (see subsection 3.'8.3.1.3) and is therefore non-Cateqory I.Rev.23, 6/81,