ML18026A514
| ML18026A514 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/02/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-702, NUDOCS 8104060507 | |
| Download: ML18026A514 (54) | |
Text
I REGULATOR NFORMATION D'ISTRIBUTION . TEM (RIDS)
ACCESSION NBR:8104060507 DOC ~ DATE! 81/04/02 NOTARIZED: NO, DOCKET FACIL':50'87 Susquehanna Steam, Electrfc Statfon~ Unft ir Pennsylva 05000387 50 388 Susqueh'anna'team BYNAME'UTHOR Electrfc Statfoni Unft 20 Pennsylva 05000388 AUTH AF F IL'IATION CURTISiN ~ Ns Pennsylvanfa Powet'" 8 Lfght Co ~
RKCIP ~ iVAME'~ RECIPIENT AFFILIATION C'UBJECTS YOUNGBLOODgB ~ J Lsfcensfng Br'anch 1
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Fot'wards r esponse'o Questf on 260 ~ 1 re FSAR ~
DISTRISUTION CODEs S001S COPIES'ECEIVED'LTR f'NCL j'. SIZEI:
PSAR/FSAR AMDTS and Re.lated Correspondence St0'ITLE:
NOTES!Send I8,E1 3 copies" FSAR Send IBE' copfesIFSAR 8
8 all all amends,'5000387 amends;"
05000388 RECIPIENT COPIES RECIPIENT'D COPIES'TTR ID CODE/NAMEl LTTR ENCl.>> CODE/NAME. ENCL>>
ACTION: A/D LICENSNG 1 0 YOUNGBLOOD B 1 0 RUSHBROOKgM ~ 1 0 STARK,R.. 04 1 1 ACCID EVAL BR2'6"'NTERNAL!
1 1 AUX SYS'R 07 1 is CHEM ENG BR 08 1 1 CONT'YS BR 09" 1 1 CORK PERF BR 10. 1 1 EFF. TR SYS BR12 1 1 EMERG PREP 22'. 1 0 EQUIP QUAL BR13 3 3 GEOSC IKNCKS 14 1 1 HUM FACT'NG BR 1 1 HYD/GKO'R 151 2 2 ILC SYS BR 16 1 1 I 8 Kl 06 3 3 LIC GUID BR 1 1 LIC QUAL BR 1 MATL ENG BR 17 1 MECH ENG BR 18 1 MPA 1 0 NRC PDR" 02'P 1 1 OKLD 1 0 LIC BR 1- 1 PONKR SYS BR 19 1 1 PROC/TST" REV 20 1- 1 QA BR 21 1 1 ~
LE'1S STRUCT'NG BR25 BR22' 1 1
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1 1
REAC SYS BR SIT ANAL'R 24 SYS INTERAC BR 23 1 1
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1 EXTERNAL'! ACRS 27 16 16 LPDR 03 1 1 NSIC 05s 1- 1
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TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEs t215) 770-5151 NORMAN W. CURTIS Vice President-Engineering 8 Construction-NucIear 770-5381 April 2, 1981 MI-. B.J. Youngblood Licensing Branch 1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Susquehanna Steam Electric Station Docket Nos. 50-387 and 50-388 Response to (}uestion 260. 1 ER100450 Fi l e 841-2 PLA-702
Dear Mr. Youngblood:
Attached is the response to guestion 260. 1 Very truly yours, N.W. Curtis Vice president-Engineering and construction-Nuclear cc: R.M. Stark bcc: N.W. Curtis W. E. Barberich B.A. Snapp C.T. Coddington QOO/
R.J. Shovl in 5
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PENNSYLVANIA POWER 8 LIGHT COMPANY
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7 Ug SSES-FSAR UESTION 260.1:
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.'ou are request'ed to supplement and 'clarify the Q-li.st in Table 3.2-1 of the FSAR in accordance with the following:
a.'he following items from the Q-list need expansion and/or clarification as noted. Revise the list as indicated or justify not doing so.
7w ~
- 1) Clarify that the Control"Rod Drive System includes the scram accumulators.
- 2) Clarify that discharge piping included in the HPCI, RCIC, RHR, fillandlines and jockey pumps Core Spray Systems. ~
are
- 3) Clarify that the Emergency Cor'e 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) 'SSM Spray Pond Emergency Spillway.
- 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 control's.
- 9) Standby Gas Treatment System '- instrumentation and controls.
- 10) Missile barriers for safety. related equipment.
~ ~
~
Rev. 22, 4/81 260.1-1
'a 0:
- 12) Equipment and drain floor - piping and containment isolation valves.
- 13) Quencher and quencher support.
- 14) 'owncomers and braces.
- 15) Primary Containment Purge System.
/
- 16) Primary Containment Ventilation System - pipirig and containment isolation valves.
17)'nsite Power Systems (Class 1E) a) transformers b) valve operators c) protective relays and control panels
- 18) Engineered safety features DC equipment - protective relays and control panels.
- 19) Biological'hielding within primary containment, reactor
'uilding, 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 b'ranch line piping up to and including first valve.
- 23) Spent fuel pool lines.
- 24) Radiation monitoring (fixed and portable).
- 25) .Radioactivity monitoring (fixed and portable).
- 26) Radioactivity contamination measurement and analysis.
- 27) Radioactive contamination measurement, and analysis.
- 28) Personnel monitoring internal,(e'.g., whole body counter) and external (e.g., TLD system).
- 29) Instrument storage, calibrati'on, and maintenance.
- 30) Decontamination (facilities, personnel, and equipment).
- 31) Respiratory protection, including testing.
Rev. 22, 4/81 260.1-2
t
- 32) Contamination control.
- 33) Feedwater spargers
- 34) Safety-related ma'sonry walls (see 1E Bulletin No. 80-11).
- 35) Measuiing and test equipment used for sfaety-related'structures,
- systems, 5nd components.
- 36) Expendable and consumable items necessary'or the functional performance of safety-related structures, systems, and components
,(i.e., weld rod, fuel oil, boric 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 I.D.2 r
- 2) Reactor coolant system vents II.B.1
- 3) . Plant shielding II.B.2
- 4) Post'accident sampling II.B.3
- 5) Valve position 'ndication II.D.3
- 6) Dedicated<<hydrogen penetrations II,E.4;1
- 7) Containment isolation dependability II.E.4.2
- 8) Accidnet monitoring instrumentation II.F.1
- 9) Instrumentation for detection of inadequate II.F.2 core-cooling
- 12) Challenges to and failure of relief valves II.K.3(16)
- 13) ADS actuation II.K.3(18)
Rev. 22, 4/81 260.1-3
- 14) Restart of core spray and ZZCI IX.K.3(21)
- 15) .RCIC suction II.K.3(22)
-1'6) .Space cooling for HPCI 6 RCIC II.K.3(24)
- 17) Power"on pump seals II.K.3(25)
- 18) Common reference level II.K.3(27)
- 19) ADS valves, accumulators, and associated II.K.3(28)
'quipment and instrumentation
- 20) Emergency plans III.A.1.1/III.A.2
~
- 21) Emergency support facilities IIX.A.1.2
- 22) Inplant I2 radiation monitoring III.D.3.3
- 23) Control-room habitability IIX.D.3.4
- d. The instrumentation and control systems and components must be iden'tified 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 of the standard format (Regulatory Guide 1.70). The "Q List" for Susquehanna SES is not a part of the FSAR. The "Q-List" is just one of a series of controlled QA program documents which serve to identify in expanded detail the ualit classification af SSES items and related services in response to FSAR commitments. Quality classifications used include but are not limited to 'safety related, ASME Code Section III related, safety impact related, fire protection related, environmental monitoring related, etc. The 'SSES QA Manual and its implementing procedures prescribe the preparation and maintenance of these quality classification documents and defines the quality assurance controls that are to be applied to such 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.
a-2 The discharge piping fill lines for HPCI, RCIC, RHR and core spray systems 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 resp'ective systems subsections "Piping beyond Outermost Containment Isolation Valves."
The line fill system adopted for perform the fill function.
SSES 'does not incorporate jockey fill function is performed pumps to The Rev. 22, 4/81 260.1"4
0 by the condensate transfer system. ,See response to Question .211;211 FSAR Section 6.3. 'nd a-3 The SSES Suppression Pool has no vortex suppression devices.
Testing is conducted to assure that vortices do not adversely affect ZCCS systems. The condensate storage tank supply line is provided with a vortex breaker;.however, it is not safety related inasmuch as the'tank is not safety related. See responses to NRC Question 211.214 for. testing information. ~
a-4 . (Later) b-'1 ESSW Spray 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'uality 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 Spillway as a safety-related structure.
b-2 All Category I buildings have watertight 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).
'or this reason site grading will not be listed on Table 3.2-1; however, watertight doors are listed in the revised Table 3.2-1.
b-3 Roof s'cruppers and parapet 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 scrupper
. failures have been considered in the structural design of the buildings. Therefore, the sc'ruppers and parapet. openings are not safety"related items and will not be 3.isted in Table 3.2-1.
b-4 Pressure-resisting doors classified as safety-related components are designed according to the criteria shown in the revised section of Table 3.2-1 (Buildings).
Rev. 22, 4/81 260.1"5
'\
0 b-5 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
'ontrols.
b-6 Not a safety system. However, 'there are 'surveillances required by .
Technical Specifications.,
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 System have a safety x'elated function. (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 System.
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).
b"ll Piping and associated valves to the HPCI and RCIC turbines are included in Table 3.2-1 of the FSAR under the following subsections:
HPCI- Piping beyond outer'most containment isolation valve, other" "Valves, other" RCIC- "Piping beyond outermost containment isolation valve, other" "Valves,, other" Associated restraints for the HPCI 6 RCIC turbines are not detailed 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).
b-14 See revised Table 3.2-1 (Buildings).
b-15 The Primary Containment Purge System is not safety related with the exception of the piping and valving associated with the primary conta'inment penetration boundary.'ee revised'able 3.2-1 under Primary Containment Purge System.
b-16 The Primary Containment Ventilation System should be referred to as the Dry Mell Cooling System: The Dry Mell Cooling System has no primary containment penetration.
Rev. 22, 4/81 260.1-6
b-17 Appropriate onsite electrical power system components which are are listed in Table 3.2-1. Where the specific 'afety-related components 'are part of a safety-related (class lE) system, they appear in Table 3.2-1 as subsets of the Onsite Power Systems.
b-18 Engineered safety features DC equipment listed under electric systems are safety-. related. See Table 3.2-1. The protective
'elays 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 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.
b-21 With the exception of cooling water piping and valves associated with the primary containment penetration boundary, the reactor building chilled water system is not safety-related.
b-22 Main steam system piping is safety-related up to and including the outermost isolation valves as already described in Table 3.2-1 under Nuclear Boiler System. See also Comment 20 in Notes to Table 3.2-1.
b"23 Spent fuel pool lines are addressed in Table 3.2-1, under "Fuel Pool Cooling and Cleanup System".
b"24 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.
b-25 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 in Chapter 17 'of the FSAR and Section 6.8 of the Technical Specifications describe the QA program coverage of procedural controls.
b-26 This item is not a "structure, system or component" requiring entry in Tab'le 3.2-1. Control of this activity is provided by appropriate procedures. 'hapter 17 of the FSAR and Secti;on 6.8 of the Technical Specifications describe the QA program coverage of procedural controls.
b-27 This item is not a "structure, system or component" requiring'ntry in Table 3.2-'1.. Control of this. activity is provided by appropriate procedures. Cha'pter 17 of the FSAR and Section 6.8 of the Technical Specifications describe the QA program coverage of procedural controls.
Rev. 22, 4/81 260.1-7
0 0 b-28 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
'ontrols.
'-29 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.
b-30 Decontamination equipment and facilities are not safety related.
Decontamination piping and valves are a part of the "Liquid Radwaste Management Systems -- I,iquid 8 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 is provided by appropriate procedures in Chapter 17 of the FSAR and Section 6.8 of the Technical Specifications describing the QA 'program coverage of procedural controls.
b-31 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.
b-32 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.
b-33 The feedwater spargers are a subset of "Reactor System -- Reactor Internal Structures -- Other" on Table 3.2-1.
b-34 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 construction/operational QA program.
b-36 The classification of these items is beyond the definition of a "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.
Rev. 22, 4/81 260.1-8
C ~
Introduction:
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. Hany 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 les question has.been 'to identify major 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). For all modifications that are eventually required "d'or SSES, safety-related classifi-cation will be determined. For more information, refer to PPK's
" response to NUREG 0737.
c-1 At this time, the Safety Parameter Display System (SPDS) quality classification has not been determined. When determined, the Table will be updated accordingly,.
c-2 The vaious reactor 'coolant system vent paths are safety-related.
They are designated in Table 3.2-1, as follows:
The RCS vessel head vent is a subset of "reactor vessel appurtenances, pressure .retaining portions" under "Reactor System" The main steam relief valves with their ads function are a subset of "safety/relief valves" under "Nuclear Boiler System."
c-3 'hield walls identified as a result of the Plant Shielding Study (NUREG 0737 Item II.B.2) will be reviewed for classification..as...
safety-related structures. Table 3.2-1 will 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 int'erfaces will be covered in the appropriate
'f systems the in their piping/valve descriptions. Specific description E'ASS in Table 3.2-1 will be incorporated upon completion of design.'ASS 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 specifications describing the QA program coverage of procedural contr'ols.
c-5 Valve position indication is .a subset of Safety Relief Valve under Nuclear Boiler System in Table 3.2-l..
Rev. 22, 4/81 260.1"9
c-6 Not applicable to SSES. Hydrogen recombiners are inside containment.'-7 Containment isolation valves are safety-related as shown in Table 3.2-1. This subject was'part of a study from whfch no changes to Table 3.2<<1 resulted..
'c-8'ccident monitoring has both safety and non-safety related listings 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's safety related. See revised Table 3.2-1 under Post Accident Monitoring.
(e) Containment suppression pool water level instrumentation is safety, related. See revised Table 3.2-1 under Post Accident Monitoring.
(f) Containment H /0 monito'r system is safety related. See revised Table 3.)-l under Post Accident Monitoring.
c-9 . 'As a result of this study, no additional instrumentation was required,
. 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 study is still in the evaluation phase. Table 3.2-1 will be modified as necessary.
. c-13 The BWR owners group is still evaluating this requirement. If the study so indicates, Table 3.2-1 will be modified accordingly.
c-14 This study determined that no changes were required to Table 3.2-1.
The changes resulting from the requirements of'UREG U737, Item II.K.3(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.
Rev. 22, 4/81 260.1"10
~ I
P c"17 Response to the THI issues is under study/evaluation. Any modifications to the SSES design will be reflected in Table 3.2-1's appropriate.
c-18 This study resulted in no changes to SSES equipment. Entries in Table 3.2-1 are not required as they are included within the individual systems.
.Resp'onse to thi.s THE issue is under study/evaluation. ':.Any modifications I'-19 to the SSES design will be evaluated to determine if they are safety related. 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 t'.f is activi'ty 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.
c-21 These items are not safety related. Justification is contained in NUREG 0696 paragraph 2.5 and 4.2 (Table 2 and footnotes). 'The Emergency Facilities are not requir'ed 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 insta'lied 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.
c-22 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.
c-23 Control room habitability is maintained by safety related equipment.
This equipment is identified in Table 3.2-1 under the section heading HVAC System-Control Structure.
- d. Instrumentation and Control systems are identified only at the .
system, level in Table 3.2-1 without providing information on the individual'omponent level. The quality classification of individual components has been identified in expanded detail in controlled QA program documents (e.g. "Q-List" and the instrument index).
Rev. 22, 4/81 260.1-11 .
SSES-FSAR TABLE 3.2-1 SSES DESIGN CRITERIA SUNHARY Page 1 Principal Quality Construc-Source Group tion Quality FSAR of Loca<< Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards ~Ct ( g R~euie t C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- Reactor S stem 4,5 Reactor vessel GE C A III-A Y Reactor vessel support skirt GE C NA III-A Y Reactor vessel appurtenances, pressure retaining portions GE C A III-A Y CRD housing supports GE C NA X Y Reactor internal structures, 15 engineered safety features GE C NA Reactor internal structures, other GE C NA Other X N/A Y Control rods GE C NA 2 X I Y Control rod drives GE C NA 2 III-2 I Y Core support structure GE . C NA 2 III-1 I Y Power range detector hardware GE C B III-2 Y 10 Fuel assemblies GE C NA X Y Nuclear Boiler S stem 4,5 Vessels, level instrumentation condensing chambers GE C A III-1 I Y 1O ]15 Vessels, air accumulators P . C C III-3 I Y Air supply check valves, piping downstream of air 16 supply check valve C C III-3 Piping, relief valve discharge C C III-3 Piping, main steam, within outermost isolation valve GE C A I Y Pipe supports, pipe restraints, main steam C A I Y Piping, other within outermost isolation valves C A III-1 I Y 10 Piping, instrumentation beyond outermost isolation valves P R,T B III-2 Note 20 N 15 Safety/relief valves GE C A III-1 I Y Valves, main steam isolation valves GE C,R A III-l guenchers and quencher supports P C C III-3
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES"FSAR TABLE 3.2-1 Continued Page 2 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1 Loca-tion Classi-fication Safety Ct Codes and st*Cd rds Seismic
~tt s R~rt Assurance C t Principal Components (34*) (1)* (2)* (3)* (4)* (5)* . (6)* (7)*
Valves, other, isolation valves within primary containment P C A II I-1 I 10 Feedwater piping inside isolation valves P C A I II-1 I Valves, instrumentation beyond outermost isolation valves P C,R>T B III-2 I Mechanical modules, instrumentation with safety function GE C NA Electr'ical modules with safety function GE C NA IEEE-279/323 Y Cable, with safety function P C NA IEEE-279/ N/A 15 323/383 Recirculation S stem Piping GE C A III-1 I Y 10 Pipe suspension, recirculation line GE C A III-1 I Y Pipe restraints, recirculation line GE C NA X I Y Pumps GE C A III-l I '
Valves GE C A III-1 I Y 10 Pump Motors GE C NA NEMA/NEC I Y Electrical modules, with safety function GE/P C NA IEEE-279/323 I Y Cable with safety function P C>R NA IEEE-279/ N/A Y 15 323/383 CRD H draulic S stem Valves, isolation, water return line P C A 8, 40 Valves, scram discharge volume ,
lines P/GE R B III-2 10 Valves, insert and withdraw lines P/GE C B 2 III-2 I 35 Valves, other P C,R D Other B31.1.0 N/A Piping, water return line within isolation valves P C A III-1 Piping, scram discharge volume lines P C B III-2 Piping, insert and withdraw
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 3 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su I tion fication Class Standards C tr R R~ee' C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)k lines P C>R B 2 III-2 I Piping, other P C,R D Other B31.1.0 N/A Hydraulic control unit GE C NA 2 N/A I 12 Electrical modules, with safety function GE C NA IEEE-279/323. it)
Cable, with safety function P C)R NA IREE-279/ NA 15 323/383
/15 En ineered Safet Features Standb Li uid Control S stem 9.3.5 Standby liquid control tank GE R B III-3 SI API 650 15 Pump GE R B NPSV-II Pump motor GE R NA X Valves, explosive GE R B NPSIV-II Valves, isolation and within P C A III-1 10 Valves, beyond isolation valves P C B III-2 10 Piping, within isolation valves P C A III-1 10 Piping, beyond isolation valves P C B III-2 10 Electrical modules, with safety function GE C NA IEEE-279/323 Cable, with safety function P C NA IEEE-279/ NA 15 323/383 16 I~UIR R t 5.4.7 I Heat exchangers, primary side GE R B 2 III-2 I Heat exchangers, secondary side GE R C 3 III-3 I iIS Piping, within outermost containment isolation valves C A III-1 I 10 Piping, beyond outermost containment isolation valves R B III-2 I 10 Containment spray line piping 16 within isolation valve C>R B III-1 I Containment spray line piping beyond isolation valve P R B III-2 I Pumps GE R B NPEcV-II I 15 Pump motors GE R NA NEHA/NEC I Reactor vessel head spray line piping inside second isolation
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 4 Principal Quality Construc-Source Group tion Quality FSAR of I,oca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards ~>t or@ R~u' C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
valve P C A III-1 I Reactor vessel head spray line piping beyond second isolation valve P R B III-2 I Valves, isolation LPCI line P C,R A III-1 I Valves, isolation, other P C,R B III-2 I 10 Valves, beyond isolation valves P R B III-2 I 10 Hechanical modules GE R NA I 15 Electrical modules, with safety function GE R NA IEEE-279/323 Y Cable, with safety function P C>R NA IEEE-279/ NA 15 323/383 6.3 Piping, within outermost isolation valves C A III-1 I 10 Piping, beyond outermost isolation valves P R,C B III-2 I 116 Pumps GE R B I [i>
Pump motors GE R I Valves, containment isolation and within containment C A III-1 I 10 Valves, beyond outermost containment isolation valves R B III-2 I 10 Electrical modules with safety function GE R NA IEEE-279/323 I Y Cable, with safety function P R NA IEEE-279/ NA .Y 15 323/383 Hi h Pressure Coolant In ection 6.3 Piping, within outermost containment isolation valve P C A III-1 I 10,28 Piping, return test line to condensate storage tank beyond second isolation valve R,O D Other B31.1.0 NA Piping, beyond outermost contain-ment isolation valve, other P R B 2 III-2 I 10 Pumps HPCI turbine GE GE R
R B
NA 2
2 NPSV-II X
I I 11>38,
'5 22 Valves, within outermost
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 5 Principal Quality Construc-Source Group tion Quality Principal FSAR Section of
~Su (1)*
Loca-I tion (2)*
Classi-fication (3)*
Safety Class (4)*
Codes and Standards C t ~
Seismic Assurance RmN st C sts Components (34+) (5)* (6)* (7)*
isolation valve C A III-1 I 10 Valves, beyond isolation valves, motor operated R B III-2 I 10 Valves, other R B III-2 I 10 Electrical modules, with safety function GE R NA IEEE-279/323 Y Cable with safety function P R NA IEEE-279/ NA 15 323/383 RORIC R stem 5.4.6 Pipe Whip Restraints Piping, and valves within outermost R,C NA AISC I containment isolation valves C A III-1 I 10 >28 Piping, and valves beyond outermost containment isolation valves R B 2 III-2 I Y 10 Piping and valves: Other; return O,R D Other B31.1.0 NA N test line to condensate storage tank beyond second isolation valve; vacuum pump discharge from vacuum line to containment isolation valves, condensate pump discharge to isolation valve for RCIC pump suction; all leakoff piping from RCIC governor and throttle trip valve; gland exhaust piping from RCIC turbine RCIC barometric condenser Other - B31.1.0 NA RCIC condensate pump and condenser vacuum pump GE R Other X NA 15 Pumps GE R 2 NPEV-II I Valves, containment isolation and within containment P C A III-1 I Y 10 Valves, other P R B III-2 I Y 10 RCIC turbine GE R NA X I Y 11,38 Electrical modules, with safety function GE R NA IEEE-279/323 I Y Cable, with safety function P R NA IEEE-279/ NA Y 15 323/383 Fuel Stora e and Handlin 9.1
'> Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 6 Principal Quality Construc-tion Quality FSAR of 'oca-Source Group Classi- Safety Codes and Seismic Assurance t
Section ~Su 1 tion fication Class Standards C te~e R~ir C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- Stora e E ui ment 9.1.1, 9.1.2 New fuel storage vault P R NA Other AWS Dl.l New fuel storage racks GE R NA Other AWS Dl.l Spent fuel storage racks P R NA 2 III-2 Defective fuel storage racks P R NA 2 III-2 Control rod storage racks P R NA 2 III-2 Spent fuel pool, RX well, dryer-sep. pool, and cask pit P R NA 2 ANSI/AWS Dl.11 Channel storage racks GE R NA Other AWS Dl.l NA In vessel racks GE R NA Other AWS Dl.l I Defective fuel storage containers GE R NA 3 AWS Dl.l NA Fuel Servicin E ui ment 9.1.4 Fuel preparation machine GE R NA Other X NA New fuel inspection stand GE R NA Other X NA General purpose grapple GE R NA Other X I Irradiated fuel shipping cask P R NA Other 49CFR 173.393>
49CFR 173.396 Jib cranes R NA Other CHAA 70/ NA B30.10 Railway bay unloading crane R NA Other CHAA 70/ NA B30.10 Reactor Vessel Servicin E ui ment 9.1.4 Steam line plugs GE R NA Other X N/A Dryer S separator sling GE R NA Other X I DW head strongback GE R NA Other X I Service platform GE R NA Other X N Control rod grapple GE R NA Other X I Reactor building crane P R NA Other CMAA 70/ I 23 B30.20 Refuelin E ui ment 9.1.4 Refueling platforms R NA 2 X 23 Fuel grapples R NA Other X 23
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81.
SSES-FSAR TABLE 3.2-1 Continued Page 7 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1
. loca- Classi-tion fication Safety Class Codes and Standards Seismic C tun R~ft Assurance C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
Under Reactor Vessel Service
>~st 9.1.4 Equipment handling platform GE C NA Other X NA CRD handling equipment GE C NA Other X NA Fuel Pool Coolin gf Cleanu S stem 9.1.3 Heat exchangers R C Other III-3, NA TEHA C R C Other III-3> NA Hyd. I Skimmer surge tanks Other III-3 I Filter demineralizer vessels Other VIII-1 NA 19>31 Resin and precoat tanks Other API-650 NA Cooling loop piping and valves Other III-3 NA RHR intertie piping and valves Other III-3 I Emergency service ~ater makeup piping and valves Other III-3 I Other piping and valves Other B31.1.0 NA 19,31 Radioactive Waste Hang ement Li uid Waste Hang ement S stems 11.2 Centrifugal pumps R/RW/T D Other VIII-1/ NA 19 >31 Hyd. I Atmospheric Tanks RW/T D Other VIII-1/ NA 19,31,22 API-650 Filter vessel RW D Other VIII-1 NA 19,31,22 Demineralizer vessel RW D Other VIII-1 NA 19>31>22 Evaporator, complete system RW D Other VIII-1/ NA 19,31,22 TEMA B Laundry drain filter RW D Other VIII-1 NA Liquid and chemical waste piping and valves R/RW/T D Other B31.1 NA 19,31>22 Laundry drain waste and auxiliary piping and valves RW D Other B31.1 NA
~>ff ss R stt 11.3
+ Refer to the General Notes at the end of this table.
Rev. 22, 4/81.
SSES-FSAR TABLE 3.2-1 Continued Page 8 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards Cate~os ~R'ee ent C ente Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
Heat exchangers T>RW D Other VIII-1 NA 22,31 Piping T,RW D Other B31.1.0 NA 10>22>31 Valves, flow control T>RW D Other B31.1.0 NA 22>31 Valves, other T,RW D Other B31.1.0 NA 10,22,31 Hotors RW NA Other NEHA-HG1 NA 22 HEPA filters RW NA Other HSI-306 NA 22 Pressure vessels T>RW D Other VIII-1 NA 22>31 Solid Waste Mana ement S stem 11.4 Centrifugal pumps P RW D Other VIII-l, NA 19,31>22 Hyd. I Regeneration waste transfer pumps P T D Other Hanuf. NA 22 Standard Solidification system pumps P RW D Other Hanuf. NA 22 Standard Atmospheric tanks, except for backwash T D Other VIII-1/ NA 19,31,22 API-650 Filter demineralizer backwash tanks R D Other VIII-1/ NA 19 >22 API-650 Phase separators RW D Other VIII-1 NA N 31 >22 Regen. waste surge tanks T D Other VIII-1 NA N 22 Waste mixing tanks RW D Other VIII-1 NA N 22 Waste containers, HSA RW NA Other DOT 7A/ NA N D1.1 Waste containers, LSA RW NA Other D1.1 Solid radwaste collecting piping and valves R/T/RW D Other B31.1 NA 31>22 Solidification system piping and valves RW D Other B31.1 NA 22 Aux. piping and valves R/T/RW D Other B31.1 NA Backwash tank drain lines R/T/RW D Other B31.1 NA 19,22 Reactor Water Cleanu S stem 5.4.8 Filter demineralizer vessels GE R C Other I II-C NA Heat exchangers GE R C Other III-C NA Piping, within reactor coolant pressure boundary (RCPB) P R A 1 III-1 I Y 10,26 Piping, beyond RCPB P R C Other III-3 NA N 26 Pumps GE R C Other NA N
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 9 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1 Loca-tion Classi-fication Safety Class Codes and Standards Seismic C*te~e> R~t Assurance C t Principal Components (34*) (1)* (2)* (3)* .(4)* (5)* (6)* (7)*
- Valves, RCPB isolation valves and within P R A 1 III-1 I 10 >26 Valves, beyond RCPB isolation valves P R C Other III-3 NA 26 Hechanical modules GE R NA Other X NA
>~ate R ete RHR Service Water and 9.2.6 S ra Pond S stem Cross connect piping to RHR system, within second automatic isolation valve P R B III-2 I Piping and valves, chemical treatment makeup water, blowdown 0 D Other B31.1.0 NA Piping, other O,R>SW C 3 III-3 I I4 RHR SW Pumps SW C 3 III-3 I Pump motors SW NA 3 IEEE-323/ I 344 Valves, isolation C,R B III-2 Y Valves, other O,R,SW C III-3 Y Electrical modules, with safety function O,R,SW NA IEEE-279 I Cable, with safety function 0>R,SW NA IEEE-279/ NA 15 323/383 Heat exchangers O,R,G C II-3/TEHA C I Piping drain pumps 0 NA Other HYD. I NA Emer enc Service Water S stem 9.2.7 Piping up to RHR SW system O,G>R,C III"3 I / 22 T,CS, SW Pumps SW C 3 III-3 I Pump Hotors SW NA 3 IEEE-323/ I 344 Valves O,G,R, C 3 III-3 I T,CS,
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81.
SSES-FSAR TABLE 3.2-1 (Continued Page 10 Principal Quality Construc-Source Group tion Quality PSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards Cot ~oqr R tt ire eet Core t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- SW Electrical modules with O,G)R) NA 3 IEE-279 I sa'fety function T)CS SW Cable, with safety function O,G,R, NA 3 IREE-279/
323/383 NA 15 t its T,CS, SW Heat exchangers R,T,G) C 3 III-3 IeY CS Reactor Buildin Closed Coolin S~er S r.e 9.2.2 Piping and valves forming part.
of containment boundary R,C B 2 III-2 I Piping and valves, other R,C,T D Other B31.1.0 NA Tanks R D Other VIII-1 NA Heat exchangers R D Other VIII-1/ NA TEHA C Pumps R D Other B31.1.0/ NA Hyd.I Plant Service Water S stem 9.2.1 Piping and valves forming part of containment boundary P R>C - B 2 III-2 I Piping and valves, other P R,C,T D Other B31.1.0 NA Heat exchangers P R,C>T D Other VIII-1/ NA TEHA C Pumps P CW D Other B31.1.0/ NA 24 Hyd.I Turbine Buildin Closed Coolin S~ter S ste 9.2.3 Piping and valves T D Other B31.1.0 NA Heat exchangers T D Other VIII-1/ NA TEHA C Tanks P T D Other VIII-1 NA Pumps P T D Other B31.1.0/ NA 24 Hyd.I
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81,
SSES-FSAR TABLE 3.2-1 Continued Page ll Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su I tion fication Class Standards C t~> R~te r. Co t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- Circulatin Water S stem 9.2 Piping O,T,CW NA Other B31.1.0 NA Condenser T D Other 1KI NA Pumps CW NA Other VIII-1/ NA 24 Hyd.I Valves P T>CW NA Other B31.1.0 NA Cooling tower P 0 NA Other NONE NA Diesel Generator S stems 9 '.4,-.5, Day tanks P G C III-3 I Piping and valves, fuel oil system P O,G C III-3 Y Transfer pumps, fuel oil system P O,G C III-3 Y Pump motors, fuel oil system P O,G NA IEEE-323/ Y 344 Diesel generators P G NA IEEE-387 Electrical modules with safety functions P G NA IEEE-279 I Cable, with safety functions P G NA IREE-279/ NA 15 323/383 Diesel fuel storage tanks P 0 C III"3 I Diesel lube oil system piping and valves P G C B31.1 Heat exchangers, jacket water, and lube oil P G C III-3/ I TEHA C Filter housings P G C 3 VIII/B31.1 I, tube oil heater P G NA Other NONE NA Lube oil circulating pump P G D Other Hyd. I NA 24 Diesel starting air,system piping and valves from receiver to diesel P G C 3 III-3 I Piping and valves, other P G D Other B31.1.0 NA Air receivers P C 3 III-3 I Compressors P G D Other NA NA Cooling jacket water heater P G NA Other NA NA Cooling jacket water heater pump P G Other Hyd. I NA 24
- Refer .to the General Notes at the end of this table.
Rev. 22, 4/81.
SSES-FSAR TABLE 3.2-1 Continued Page 12 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1 Loca-tion Classi-fication Safety Class Codes and Standards Seismic C >*goo R~t Assurance C
nts Principal Components (34>'>) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
Dirty lube oil drain tank P G D Other NONE NA Heatin Ventilatin and Air Conditionin S stems Control Structure 9.4.1 Control Room S Computer Room HVAC Motors P CS NA NEHA HG1 I IEEE-344 Instrumentation P CS NA IREE-279 I Y I 16 Pans P CS NA AMCA I Y Prefilters P CS NA UL Class I I Y NEPA filters P CS NA HIL-F- I Y 51068C HIL-F-51079 Adsorber units CS NA AACC CS-8 I RDT H-16-1T Dampers, isolation CS NA AHCA I Y I 16 Dampers, flow distribution CS NA AHCA I Y Ductwork CS NA AISI I Y Coils, cooling CS ARI I Y Chilled water system CS D B31.1 I Y Electric heating coils CS C NEC>NEHA I Y Centrifugal water chillers (except condenser) CS D VIII I Centrifugal water chillers-condenser CS C III-3 I Rela Room Cable S readin Batte Room MVAC 9.4.1 and MVAC E ui ment Room Hotors CS NA NEHA MG1 I IEEE-344 Fans CS NA AHCA I 16 Prefilters CS NA UL Class 1 I I Coils, heating, electric CS NA NEC>NEHA I I 16 Coils, cooling - chilled water CS NA ARI I Dampers CS NA AHCA I Ductwork CS NA AISI I
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 13 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Stand d ~dat R~e ite ent Ca e ta Principal Components (34*) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
Piping & valves P CS, C 3 B31.1 Instrumentation P CS NA Other IREE-279 its SGTS E ui ment Room HSV 9.4.1.1.5 Hotors CS NA NEHA MG1 I IEEE-344 Fans CS NA AHCA I Heaters, electric CS NA NEC 424 I NFPA 90Agt90B Dampers CS NA AHCA I Ductwork CS NA AISI I Instrumentation CS NA IEEE-279 iis Reactor Buildin Reactor Buildin llVAC Zone I Hotors R NA Other NEHA HG 1 NA Fans R NA Other AMCA NA Prefilters R NA Other UL Class 1 NA NEPA filters MIL-F-51068C, HIL-F- 16 51079 Adsorber units NA Other AACC CS-8 NA RDT H"16-1T Coils, cooling P NA Other ARI NA Coils, heating P NA Other NEC > NEHA NA I 16 Ductwork P NA Other SHACNA,AISI NA Dampers, isolation P NA 3 AHCA I I 16 Dampers, other P NA Other AHCA NA Piping Connected to SGTS 3 NFPC I Remainder Other B31. 1 NA Valves Isolation, chilled water to primary containment R B 2 III"2 I itd Remainder R D Other B31.1 NA 9.4.2
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81 '
SSES-FSAR TABLE 3.2-1 Continued Page 14 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su Loca-I tion Classi-fication Safety Class Codes and S tanda rd s Ct~
Seismic R~t Assurance C t Principal Components (34*) (1)* (2)* (3)~ (4)* (5)* (6)* (7)*
Hotors NA IEEE-323/
344 Fans R NA AHCA Filters R NA NA Coils, cooling R NA ARI 16
)
Ductwork R NA AISI Piping and valves R C III-3 Emer enc SWGR and Load 9.4 Center Rooms Hotors NA NEHA HG1 I IEEE-344 Fans R NA 3 AHCA I Y Prefilters R NA 3 UL Class 1 I .Y Coils, cooling (ESSW) R C 3 III-3 I Y Coils, chilled water R NA 3 ARI I Dampers R NA 3 AHCA I Y Ductwork R NA 3 AISI I Y Piping 8 valves, ESSW R C 3 III-3 I Y Piping Ec valves, chilled water R NA 3 B31.1 NA N I 16 Instrumentation R NA Other IEEE-279 I Y Refuelin Floor HVAC Zone III 9.4.6 Hotors R NA Other NEHA HG1 NA Fans R NA Other AHCA NA Prefilters R NA Other UL Class 1 NA HEPA filters R NA Other HIL-F- NA 51079 HIL-F-51068C Adsorber units R NA Other RDT H-16-1T NA AACC CS-8 Coils, cooling gt heating R NA Other ARI Ductwork R NA Other SHACNA Dampers R NA Other AHCA Piping gc valves R NA Other B31.1 D ell Coolin S stem 9.4.5 Hotors C NA Other IEEE-334 NA
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued) Page 15 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section S~u I tion fication Class Standards C tu R R~e're t C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)e NEHA HG1 Fans P C NA Other AHCA 210 I Y Coils, cooling P C NA Other ARI I Y Ductwork P C NA Other AISI I Y Dampers P C NA 3 AHCA I Y Piping and valves P C NA Other B31.1 NA N 116 Combustible Gas Control S stem Hydrogen recombiners inside containment P C NA 2 NA I Primary Containment Atmosphere monitoring system (PCAHS) P C, R B, D 2 III-2 I 10, 41 Piping valves forming Contmt. Penetration Boundary P C IR B 2 III-2 I Standb Gas Treatment S stem 9.4.1 Hotors P CS NA IEEE-323/ I 16 344 Fans- CS -NA AHCA I 16 Prefilters CS NA UL Class 1 I 16 Demisters CS NA HSAR 71-45 I 16 HEPA filters CS NA HIL-F- I 16 51079 HIL-F-51068C Adsorber units CS NA AACC CS-8 I 16 RDT H-16-1T Ductwork CS NA 3 AISI I 16 Dampers CS NA 3 AHCA I 16 Piping CS C 3 NFPC I 16 Valves CS C 3 B31.1 I 16 (22 Electric heaters CS NA 3 NEHA gt NEC I Control panels C,S NA 3 NEHA I Radwaste Buildin HVAC 9.4.3 Hotors P RW NA Other NEHA HG1 NA Fans P RW NA Other AHCA NA Prefilters P RW NA Other UL Class 1 NA IKPA filters P RW NA Other HIL-F- NA
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 (Continued) Page 16 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards ~tt* rR Rnite et C t Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)>>
51079A HII.-F-51068C Coils, cooling gt heating P RW NA Other ARI 8 UL NA ~ N Adsorber units P RW NA Other HIL-C-17605 NA N RDT M-16-1T Ductwork P RW NA Other SHACNA NA Dampers P RW NA Other AHCA NA Electric heating coil P RW NA Other NEC NA Diesel Generator Buildin HVAC 9.4.7 Hotors P G NA NEHA HG-1 I Fans P G NA AMCA I I 16 Ductwork P G NA AISI I Dampers P G NA AHCA I Turbine Buildin HVAC 9.4.4 Hotors T NA Other NEHA HG1 NA N Fans T NA Other AMCA NA N Filters T NA Other NA NA N Coils, cooling T NA Other ARI NA N Ductwork T NA Other SHACNA , NA N Dampers T NA Other AMCA NA N Chilled water system T D Other B31.1 NA N Electric heating coil T NA Other NEC,NEHA NA N Emer enc Service Water Pum house Ventilation 9.4.8 Hotors P SW NA NEHA HG1 "I Fans P SW NA AMCA (16 Ductwork P SW NA AISI I Dampers P SW NA AHCA I
.Administration Buildin HVAC Hotors P 0 NA Other NEHA HG1 NA Fans P 0 NA Other AHCA NA Prefilters P 0 NA Other VL Class 1 NA Dampers P 0 NA Other AHCA NA
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 17 Principal Quality Construc-Source Group tion Quality of FSAR Section ~Su 1 Loca-tion Classi-fication Safety Class Codes and Standards Seismic
~C*t or@ R~*t Assurance C t Principal Components (34*) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- Coils, cooling 0 NA Other ARI NA N Coils, heating 0 NA Other NEC,NEHA NA N 116 Ductwork 0 NA Other SHACNA NA N Hain Steam and Power Conversion
~Sstem Hain Steam S stem 10.3 Hain steam piping to turbine P R>T B 2 III-2 NA N 20 stop valves and branch line piping up to and including first valve Hain steam piping from and P T D Other B31.1.0 NA 9>18>33 including the turbine stop valve to turbine casing and branch line piping up to and including first valve Steam piping and valves, other P T D Other B31.1.0 NA Hain Steam Isolation Valve (16 Leaka e Control S stem Piping and valves up to first isolation valve of the inboard subsystem P R A 1 III-1 I Piping and valves, other P R B 2 III-2 I Blowers GE R NA 2 NEHA-HG-I I IEEE328/344 Hain Condenser Evacuation S stem 10.4.2 Piping and components P TRW D Other B31.1.0 NA N Heat exchangers P T D Other VIII-1 NA N Air ejectors P T D Other B31.1.0 NA N Condensate and Feedwater S stem 10.4.7 Reactor feedwater piping and valves, RPV to outermost isolation valve P C>R A 1 III-1 I 32 Reactpr feedwater, piping an)
- Eefpr tq )he Gpneryg lfotep qf. ge ~~d of this tsb)e.
Rev. 22, 4/81'
SSES-FSAR TABLE 3.2-1 Continued) Page 18 Principal Quality Construc-Source Group tion Quality FSAR of Ioca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards c,su i ~es i. c Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
valves, other P RIT D Other B31.1.0 NA Steam piping to feedwater pump turbine T D Other B31.1.0 NA N /is Crossover (low pressure) piping T D Other B31.1.0 NA N Bypass (high pressure) piping, downstream of first isolation valve Condensate piping and valves T D Other B31.1.0 NA Heat exchangers T D Other VIII-1/ NA TEHA C Pressure Vessels T D Other VIII-I NA N I
16 Pumps, feedwater and condensate T D Other B31.1.0/ NA N 24 Hyd.I Condensate Cleanu S stem 10.4.6 Piping and valves P T D Other B31.1.0 NA N Pressure vessels P T D Other VIII-1 NA N Condensate Stora e an'd Transfer
~Sstem 9.2.10 Tanks P 0 D Other D100 NA N Piping and valves P O,T D Other B31.1.0 NA N Pumps P T D Other B31.1.0/ NA N 24 Hyd.I Turbine Gland Sealin S stem 10.4.3 Steam seal evaporator T D Other VIII-1 NA N Gland steam condenser T D Other VIII/TEHA C NA N Piping and valves T D Other B31.1.0 NA N Auxilia Steam S stem 10.4.11 Auxiliary boilers T D Other VIII NA N Piping and valves T D Other B31.1.0 NA N Hain Chlorination S stem 9.2.8 Pumps P CA D Other B31.1.0/ NA N 24 Hyd.I
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81.
SSES-FSAR TABLE 3.2-1 Continued) Page 19 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1 Ioca- Classi-tion fication Safety Class Codes and Standards Seismic CtV R R~tt Assurance C et Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
Hotors CA NA Other NEHA HG1 NA Piping and valves CA D Other B31.1.0 NA 10.2 Batch oil tank 0 D Other VIII-1 NA N Reservoirs T D Other API-620 NA N Pumps T D Other VIII/Hyd.I NA N 24 Hotors T NA Other NEHA HG1 NA N Centrifuges T NA Other NA NA N Heat Exchangers T D Other VIII/ NA N TEHA C Piping and valves Other B31.1.0 NA Instrumentation and Control S stems Reactor Instrumentation 7.2 Reactor Protection System All portions that must GE C,R NA 2 IEEE-279/ I 323 operate to control and safely shut down the reactor to a hot shutdown condition (Electronic modules)
Cable with safety function P C,R N/A 2 IEEE-279 N/A Y Neutron Honitoring System Piping, TIP GE C,R B III-2 I Valves, isolation, TIP subsystem GE C>R B III-2 I Electrical modules, IRH and APRH GE C>R NA IEEE-279/ I 323 Cable, IRH and APRH, with safety function P C,R NA IREE-279/ NA 383 Non-Nuclear Instrumentation
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES"FSAR TABLE 3.2-1 Continued) Page 20 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1 Loca-tion Classi-fication Safety Class Codes and Standards Seismic C~t> R~t Assurance C
t Principal Components (34*) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
All portions that input to GE C,R NA 2 IEEE-279 I the reactor protection system All portions that input to the P/GE C,R NA 2 IREE-279 I engineered safety feature actuation system En ineered Safet Features Actuation S stem 7.3 All portions GE C>R NA 2 IEEE-279 I En ineered Safet Features S stems 7.3 (controls and instrumentation required for safety associated with each actuated system)
Emergency core cooling system GE C,R NA 2 IEEE-279 I Containment isolation system P C,R NA 2 IEEE"279 I Containment purge systems P C>R NA 2 IEEE-279 I Emergency diesel generator systems G NA 2 IREE-279 I Main steam line break detection system C>R,T NA 2 IEEE-279 I Controls and Instrumentation Associated with Safe Shutdown R~tt 7.4
)15 Control room habitability system P CS NA 2 IEEE-279 I Y PCAMS P C,R B>D 2 IEEE-279 I , Y Instrumentation Associated with il5 Other S stems Re uired for Safet 7.6 Spent fuel pooling cooling system P R NA 2 IEEE-279 I /16 Fuel handling area ventilation isolation system P R NA 2 IEEE-279 I Y Control room panels P CS NA 2 IEEE-279 I Y Iocal instrument racks associated with safety related equipment P ALL NA 2 IEEE-279 I
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 21 Principal Quality Construc-Source Group tion Quality FSAR Section of
~Su 1 loca-tion Classi-fication Safety Class Codes and Standards Ct~ R~tt Seismic Assurance C t Principal Components (34*) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- Instrumentation Associated with S stems Not Re uired for Safet 7.7 Seismic instrumentation ALL NA Other NA I Y Area radiation moni.toring ALL NA Other NA NA N /te Ieak Detection S stem Temperature elements GE C>R,T N/A IEEE-323 I 39 Differential temperature switch GE C,R N/A IEEE"323 I 39 Differential flow indicator GE N/A IEEE-323 I 39 Pressure switch GE C,R N/A IREE-323 I 39 15 Differential pressure indicator switch Differential flow summer GE N/A IREE-323 I 39 GE N/A IEEE"323 I 39 Process Radiation Honitors Electrical modules, main steam line and reactor building 15 ventilation monitor GE R N/A 2 IEEE"323 I Cable, main steam line and reactor building ventilation monitors P R N/A 2 IEEE-279/ I 323/383 Electric S stems En ineered Safet Features AC
>~litt 8.3 4.16 kV switchgear 0 NA IREE-308/ I 323/344 480 V load centers 0 NA IEEE-308/ I 323/344 480 V motor control centers 0 NA IREE/308/ I 344 R~t En ineered Safet Features DC 8.3 125 V and 250 V station batteries and racks, battery chargers CS NA IEEE-308/ I
- Refer to tho General Notes at the end of this table.
Rev. 22, '4/81
SSES-FSAR TABLE 3.2-1 Continued Page 22 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards c ta R ~Rt t c t Principal Components (34*) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
- 323/344 125 V switchgear and distribution panels P CS NA IEEE-308/ I 323/344 120 V Vital AC S stem E ui ment 8.3 Static inverters P CS NA IREE-308/ I 323/344 120 V distribution panels P CS,R NA IEEE-308/ I 323/344 Electric Cables for ESF E ui ment 8.3 5 kV power cables AIL NA IEEE-308/ NA 15 383 600 V power cables ALL NA IEEE-308/ NA 15 383 Control and instrumentation cables ALL NA IEEE-308/ NA 15 383 Hiscellaneous Electrical Primary containment building electrical penetration assemblies C NA IEEE-317/
344/383 Conduit supports, safety related AIL NA 2 IREE-344 I Y 15 Tray supports, safety related ALL NA 2 IREE-344 I Y 15 Emergency lighting systems ALL NA 2 IEEE-344 I Y Emergency communications systems ALL NA Other NONE NA N Diesel generator G NA 2 IEEE-387 I Y Auxiliar S stems Compressed Air and Instrument Gas S stems 9.3.1 Compressors P T NA Other NONE NA Pressure vessels, for safety related equipment P C,R C 3 III-3 I Pressure vessels, not for safety related equipment P AI.L D Other VIII-1 NA
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81-
SSES-FSAR TABLE 3.2-1 Continued Page 23 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards c*teaLu R~ae t c t Principal Components (34+) (1)* (2)>> (3)* (4)* (3)* (6)* (7)*
Piping and valves forming part of containment boundary P C,R B 2 III-2 I Piping and valves, safety related P C>R C 3 III-3 I Piping and valves, other P ALL D Other B31.1.0 NA Nitrogen storage bottles P R NA Other DOT I /16 Sam lin S stems 9.3.2 Sample coolers C,R,T,D VIII-1 NA N RW
[as TEMA C Piping and valves on III-1 systems C A III-1 I 10 Piping and valves on III-2 systems C,R B III-2 I 10 Piping and valves on III-3 systems R>T,RW C 3 III-3 I 10 Piping and valves, other systems R,T,RW D Other B31.1.0 NA 10 Piping and valves, containment penetration, isolation C B III-2 I 10 Fire Protection S stem 9.3.1 Tanks- P 0 D Other API-650/ NA D100 Pumps, piping and Mater system components P ALL NA Other NFPA/NEPIA NA N Gas system components (CO and Halon 1301) P CS NA Other NFPA/NEPIA NA Pire and smoke detection and alarm system P . ALL NA Other NFPA/NEPIA NA Generator External H dro en S stem Vessels T D Other VIII-1 NA N Piping T D Other B31.1.0 NA N Valves T D Other B31.1.0 NA N Vessels P 0 Other VIII-1 NA Piping P 0 Other B31.1.0 NA
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 24 Principal Quality Construc-Source Group tion Quality Principal FSAR Section of
~Su 1 Loca-cion Classi-fication Safety Class Codes and Standards Seismic Ct~r R~t Assurance C
t Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (7)*
Valves P 0 D Other B31.1.0 NA Plant Chilled Water S stem 9.2.12 Chillers P ALL D Other B9.1 NA Chilled Mater heat exchangers P ALL D Other VIII-1/ NA TEHA C Pumps P ALL D Other VIII-1/ NA 24 Hyd.I Piping P ALL D Other B31.1.0 NA Valves P ALL D Other B31.1.0 NA Safet Related Chilled Water S stem Chillers CS D ARI/B9.1 I Heat exchangers CS D VIII"1/ I TEHA C Pumps CS D VIII-1/L I Hyd.I Hotors CS NA IEEE-323/ I 344 Piping CS D B31.1 I Valves CS D B31.1 I E ui ment and Floor Drains 9.3.3 Piping, radioactive P ALL D Other B31.1.0 NA f15 Piping, nonradioactive P ALL D Other B31.1.0 NA Piping gt valves, containment penetrating isolation P R,C B 2 III-2 I
-Demineralized Water Hakeu S stem 9.2.9 Tanks P CW D Other VIII-1 NA Pumps P CW D Other B31.1.0/ NA 24 Hyd.I Hotors P CW NA Other NEHA HG1 NA Piping and valves P ALL D Other B31.1.0 NA Reactor Building P R B 2 ACI/AISC I
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 Continued Page 25 Principal Quality Construc-Source Group tion Quality of Loca- Classi- Safety Seismic Assurance t~> ~R' FSAR Codes and Section ~Su 1 tion fication Class Standards C C Rt Principal Components (34+) (1)* (2)* (3)* (4)* (5)* (6)* (I)*
- Pressure resistant doors R B ASTH/AWS NA AISC 22 Watertight door R B ASTH/AWS NA R. B. Equipment door R B ASTH/AWS NA Primary Containment C B ACI/AISC/ I 27>30 III Access hatches/locks/doors P C B 2 III-HC I Y Liner plate P C B 2 III-HC I Y Penetration assemblies P C B 2 III-HC I Y 29 Vacuum relief valves P C B 2 III-2 I Y Downcomers P C B 2 III-MC I Y Downcomer Bracing P C B 2 AISC I Y P2 Diesel generator building P G NA 2 ACI/AISC I Control structure P CS NA 2 ACI/AISC I Y.
Radwaste and offgas building P RW NA Other ACI/AISC NA N 22 Turbine building P T NA Other ACI/AISC NA N 21 Administration building P 0 NA Other ACI/AISC NA N Circulating water pump house P 0 NA Other ACI/AISC 'A N ESSW pumphouse P 0 NA 3 ACI/AISC I Y Structures Spray pond gt Emergency Spillway 0 NA 3 ACI I Y (22 Condensate storage tank 0 D Other D100 NA N Spent fuel pool R NA 2 ACI/AISC I Y Spent fuel pool liner R NA 2 ACI/AISC I Y [22 Refueling water storage tank 0 D Other D100 NA N Pipe Whip Restraints R,C NA 3 AISC I Y Hissile Barriers for safety
. related equipment C>R, NA Other AISC I CS,SW, G
Biological shielding within Primary containment> reactor Building and control building P C>R, NA Other ACI/AISC I 42 22 CS Safety related masonry walls P R>G, NA Other ACI/UBC I CS Post accident monitorin Containment Radiation Honitoring Equipment P R NA 323/344 I
- Refer to the General Notes at the end of this table.
Rev. 22, 4/81.
SSES-FSAR TABLE 3.2-1 Continued Page 26 Principal Quality Construc-Source Group tion Quality FSAR of Loca- Classi- Safety Codes and Seismic Assurance Section ~Su 1 tion fication Class Standards C tegoo R~ui t C t Principal Components (34*) (1)* (2)* (3)* (4)* (5)* (6)* 0)*
SRV position indication system P R NA 323/344 I Noble gas effluent radiological monitor P R NA ANSI N13.1 I Continuous samples of plant effluents. for radioactive iodine 8 particulates P R NH ANSI N13.1 I Containment hi-range 22 radiation monitor P R NA 323/344 I Containment pressure monitor P R NA 323/344 I Containment Suppression pool water level instr. P R NA 323/344 I Containment H /0 monitor system P R NA 323/344 I Rev. 22, 4/81
- Refer to the General Notes at the end of this table.
r /
~
- I I'SES-PSAR TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
(Continued)
Pa e:27 3
,General Notes and Comments
')
GE = General Electric P = Bechtel as agents for Pennsylvania Power 6 Light
- 2) Location C Part of or within primary containment R Reactor Building T Turbine Building CS Control Structure RW Radwaste and Offgas Building G Diesel Generator Building I Intake Structure A Administration. Building CW Circulating Water Pumphouse SW Engineering Safeguards Service Water (ESSW) Pumphouse CA Chlorine and Acid Storage Building 0 Outdoors, Onsite
- 3) A,B,C,D - Quality group classification as defined in Regulatory Guide 1.26. The equipment shall be constructed in accordance with codes listed in Tables 3.2-2, 3.2-3, and 3.2-4.
NA - Not applicable to quality group classification.
- 4) 1,2,3,4, other = safety classes defined in ANSI-N212 and Section 3.2.3.
~1 NA - Not applicable to safety classification
- 5) Where shown this supplements information in Tables 3.2-2, 3.2-3, and 3.2-4. Notations for principal construction codes:
1,2,'3, NF, NG, MC = ASME Boiler and Pressure Vessel Code Section III, Class 1,2,3 or MC.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 (Continued)
Pa e 28 VIII"1 ASME Boiler and Pressure Vessel Code, Section VIII, Div. 1.
NPRV-II ASME Nuclear Pressure 8 Valve Code, Class II API-650 American Petroleum Institute, Welded Steel Tanks for Oil Storage API-620 American Petroleum Institute, Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storage Tanks B9.1 ANSI B9.1, Safety Code for Mechanical Refrigeration B31.1.0 ANSI B31.1.0, Code for Pressure Piping t
SMACNA Sheet Metal 8 Air Conditioning Contractors National Assoc., Inc.
HEI Heat Exchange Institute TEMA C Tubular Exchanger Manufacturers Assoc., Class C HYD. I Hydraulic Institute AISC American Institute of Steel Construction AISI American Iron and Steel Institute, "Specification for the Design of Coldformed Steel Structural Members", 1968, "Design of Light Gage .Cold-Formed Stainless Steel Structural Members", 1968 ACI American Concrete Institute AMCA AMCA 210 "Test Codes for Air Moving Devices" AMCA 211 A "AMCA Certified Ratings Program for Air Performance" AWS Dl.l American Welding Society, Structural Welding Code CS-8T American Association for Contamination Control, AACC CS-8T, "Tentative Standard for High-effz.ciency Gas Phase Adsorber Cells" July, 1972 DEMA Diesel Engine Manufacturer Association, "Standard Practices for Stationary'Diesel and Gas Engines",
1971 D100 American Waterworks Association, AWWA-D100 "Standard for Steel Tanks Standpipes, Reservoirs and Elevated Tanks for Water Storage" Rev. 22, 4/81
SSES"FSAR TABLE 3.2-1 (Continued)
Pa e 29 National Electrical Code National Electrical Manufacturer's Association NEMA MG1 National Electrical Manufacturers'ssociation, NEMA-MG-1, 1971 "Motors and Generators" NEMA SM22 National- Electrical Manufacturers'ssociation, NEMA-SM-22, 1970, "Single Stage Steam Turbine for Mechanical Drive Service" IEEE-279 IEEE-279, Criteria for Protection Systems for Nuclear Power Generating Stations - 1971.
IEEE-308 IEEE-308, Standard Criteria for Class IE Electric Systems for Nuclear Power Generating Stations-1974 IEEE-317 IEEE-317, Standard for Electrical Penetration Assemblies in Containment Structures for Nuclear Fueled Power Generating Stations 1972
'IEEE-323 IEEE-323, General Guide for Qualifying Class IE Electric Equipment for Nuclear Power Generating Stations - 1974 IEEE-344 IEEE-344, Guide for Seismic Qualification of Class IE Electric Equipment for Nuclear Power Generating Stations - 1971 IEEE-383 Type Test of Class IE Electrical Cables, Field Splices, and Connections for Nuclear Power Generating Stations IEEE-387 IEEE-387, Criteria for Diesel Generator Units applied as Standby Power Supplies for Nuclear Power Generating Stations - 1972 HSI-306 Health and Safety Information, USAEC, Revised Minimal Specification for the High Efficiency Particulate Air Filter. Issue No. 306 NFPA National Fire Protection Association NEPIA Nuclear Energy Property Insurance Association ARI Air Conditioning and Refrigeration Institute
.DOT 7A Department of Transportation - Shipping Container Specification 49CFR178.350.
AWS Dl.l American Welding Society, Structural Welding Code. 16 Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 (Continued)
Pa e 30 UBC Uniform Building Code /zz:
NA ~ None Applicable I16 X Manufacturer's Stan'dards
- 6) I - The equipment shall be constructed in accordance with the seismic requirements for the Safe Shittdown Earthquake, as described in Section 3.7.
NA -,the seismic requirements for the Safe Shutdown Earthquake are not applicable to the equipment or structure.
- 7) Y - Requires compliance with the requirements of 10CFR50, Appendix B in accordance with the quality assurance program described in Chapter 17.
N .- Not within the scope of 10CFR50, Appendix B.
- 8) The classification of the control rod drive water return line from the reactor vessel through the third isolation valve will be Group A. Beyond the third valve will be Group D, except as noted in Table 3.2-1.
- 9) The follow'ing qualificati'on shall be met with respect to the certification requirements:
The manufacturer of the turbine stop valves, turbine control valves, turbine bypass valves, and main steam leads from turbine control valve to turbine. casting sh'all use quality control procedures equivalent to those defined in General Electric Publication GEZ-4982A, "General Electric Large Steam Turbine-Generator Quality Control Program".
- 2. A certification shall be obtained from the manufacturer of these'alves and steam leads that the quality control program .so defined has been accomplished.
Instrument and sampling piping from the point where they connect to the process boundary and through the process shutoff (root) valve(s), isolation valve(s), and excess flow check'valve, when provided, will be of the same classification as the system to which they connect.
- 2. All instrument lines which are connected to the reactor coolant pressure. boundary and'are utilized to actuate safety systems shall be Group B from the process shutoff (root) valve(s), isolation valve(s), or excess flow check valve, when provided, to the sensing instrumentation.
Rev. 22, 4/81"
~ g ~
SSES-FSAR TABLE 3.2-1 (Continued)
Pa e 31
- 3. All in'strument lines which are connected to .the reactor coolant pressure boundary and'are not utilized to actuate 'safety systems shall be Quality Group C from "the.
process shutoff (root) valve(s), -isolation valve(s),
excess flow check valves, when provided, to the sensing instrumentation.
- 4. Other instrument lines:
a) Those connected to special equipment or Group D system pressure boundaries and utilized to actuate safety systems will be Group C from the system pressure boundary through the process shutoff valve(s) to the sensing instrumentation.
b) Those connected to Group B and Group C systems and utilized to actuate safety systems shall be of the same classification as the process system to the sensing instrumentation.
c) Those connected to Group B and Group C systems and not utilized to actuate safety systems will be of Group D classification except for those Group C systems by GE utilizing capillary (filled and sealed) instrument lines.
d) Those connected to Group D systems and not utilized to actuate safety systems will be of Group D classification.
- 5. For Group A, B, and C systems, the sample line beyond the process shutoff (root) valve(s) or isolation valve(s) will be Group B through the penetration and Group D from the isolation valve to the shutoff valve outside of the sample station.
- 11) The HPCI and RCIC turbines do not fall within the applicable design codes. To ensure that the turbine is fabricated to the standards commensurate with their safety'and performance requirements, General Electric has established specific
'design requirements for this component.
- 12) The hydraulic control unit (HCU) is a General Electric factory assembled, engineered module of valves, tubing, piping, and stored water which controls a single control rod drive by the application of precisely timed sequences of pressures and flows to accomplish slow insertion or withdrawal of the control rods for power control, while providing rapid insert'ion for reactor scram.
Although the hydraulic control unit is field installed and connected to process piping, many of its internal parts
'differ markedly from process piping components because of the Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 (Continued)
Pa e 32 more complex functions they must provide. Thus, although the codes and standards invoked by the Group 'A, B, C, and 3 pressure, integrity quality levels clearly apply at all levels to the interfaces between the HCU and the connecting conventional piping components (eg, pipe nipples, fittings, simple hand valves, etc), it is considered that they do not apply to the specialty parts (eg, solenoid valves, pneumatic components and instruments).
The design and construction specifications for the HCU do invoke such codes and standards as can be reasonably applied to individual parts in developing required quality levels, but these codes and standards are supplemented with additional requirements for these parts and for the remaining parts and details. For example, (1) all welds are LP inspected, (2) all socket welds are inspected for gap between pipe and socket bottom, (3) all welding is performed by qualified welders, (4) all work is done per written procedures.
The following examplies are typical of the problems associated with codes designed to control field assembled components when applied to the design and production of factory fabricated specialty components:
- 1. The.HCU nitrogen gas bottle is a punch forging which is mechanically joined to the accumulator. It stores the energy required to scram a drive at low vessel pressures. It has been code stamped since its introduction in 1966, although its size exempts it from mandatory stamping. It is constructed of a material listed by ASME BRPV Code Section VIII which was selected for its strength and formability.
- 2. The scram accumulator is joined to the HCU by a split flange joint. chosen for its compact design to facilitate both assembly and maintenance. Both the design and construction conform to ANSI B31.1.0 Power Piping Code.
This joint, which requires a design pressure of 1750<psig, has been proof tested to 10,000~gpsi.
- 3. The accumulator nitrogen shutoff valve is a 6,000/psi cartridge valve whose copper alloy material is listed by ASME BBPV Code Section VIII. The valve was chosen for this service partly because .it is qualified by the U.S.
Navy foi submarine service.
- 4. The directional control valves are solenoid pilot operated valves which are subplate mounted on the HCU.
The valve has a body specially designed for the HCU, but the operating parts are identical to a commercial valve with a proven history of satisfactory 'service. The pressure containing parts are stainless steel alloys Rev. 22, 4/81
V SSES-CESAR TABLE 3.2-1 (Continued)
Pa e 33 chosen'or service, fabrication and magnetic properties.
The manufacturer cannot substitute a code material for that used for the solenoid core tube.
The foregoing examples are not meant to justify one pressure integrity quality level or another, but to demonstrate the codes and standards invoked by those quality levels are not strictly applicable to special equipment and part designs.
Group D Classification is generally applicable, supplemented by the QC techniques described above. Thus, the Hydraulic Control Unit shall be classified as "Special Equipment".
13 8 14) These notes have been intentionally left blank.
The trays and supports for safety related cables meet Seismic Category I and 10CFR50, Appendix B requirements, except in the turbine building. All Class IE and affiliated circuits, including RPS circuits located in a non-Seismic Category I structure (i.e. Turbine Building) are contained within Class IE, Seismic Category I raceways although they are supported from a non-Seismic Category I structure. (See Subsection 3.7b.2.8 for seismic information about the turbine building).
- 16) AEC Regulatory Guide 1.52, June 1973, suggests various industry standards and codes for this equipment. These references were used for system design, with exceptions as noted in section.
- 17) AMCA Publication 211A, "AMCA Certified Ratings Program for Air Performance" or AMCA Standard 210, "Test Codes for Air Moving Devices" can be used for blower design purposes.
This section of steam piping was seismically analyzed to ensure that it will not fail under loadings normally associated with an SSE.
- 19) All or part of this component is constructed to a more stringent code or standard than indicated.
- 20) The MSS from its outer isolation valve up to and including the turbine stop valve and all branch lines 2-1/2~<in. in diameter and larger, up to and including the first valve (including their restraints) shall be designed by the use of
~I an appropriate dynamic seismic-system analysis to withstand the Operating Bases Earthquake (OBE) and Safe Shutdown Earthquake design loads in combinat'ion with other appropriate loads, within the limits specified for Class 2 pipe in the ASME,Section III Code. The mathematical model for the dynamic seismic analyses of the MSS and branch line piping shall include the turbine stop valves and piping beyond the stop valves including the piping to the turbine casing. The dynamic input loads for design of the MSS shall be derived
'from a time history model analysis (or an equivalent method)
Rev. 22, 4/81
SSES-CESAR TABLE 3.2-1 (Continued)
Pa e 34 of the reactor and applicable portions of the turbine building. An elastic multi-degree-of-freedom system 'analysis shall be used to determine the input to the MS'he stress allowable and associated deformation limits for piping shall be in accordance with the ASME Section XII Class 2 requirements for the OBE and SSE loading combinations. The MSS supporting structures (those portions of the turbine building) shall be such that the MS5,and its supports can maintain their integrity.
- 21) The power conversion system structures may be constructed in accordance with applicable codes for steam power plants.
Those portions of the turbine building interacting with the main steam lines and branch lines are analyzed to show that system integrity is maintained for the main steam lines and branch lines during the SSE.
- 22) The lower quality group classification, associated construction codes and seismic category are appropriate for this system as a result of analysis per regulatory guides 1.26 and 1.29. The loss of effluent from system components was analyzed to demonstrate that the site boundary dose would not exceed'.5~~Rem. The classifications indicated in the table are considered justified for the aforementioned doses.
- 23) These components and associated supporting structures must be designed to retain structural integrity during and after the SSE but do not have to retain operability for protection of public safety. The basic requirement is prevention of structural collapse and damage to equipment and structures required for protection of the public safety and health.
- 24) There is no established standard for commercial pumps. ASME Section VIII, Division 1 and ANSI B31.1.0 Power Piping represent related, available standards which, while intended for other applications, are used for guidance and recommendations in determining quality group D pump allowable stresses, steel casting quality factors, wall thicknesses, materials compatibility and specifications, temperature-pressure environment restrictions, fittings, flanges, gaskets, and bolting, installation procedures, etc.
- 25) Regulatory Guide 1.54 applies.
- 26) The reactor water cleanup influent line out to and including the first isolation valve outside containment will be classified Group A. The remainder'of the influent line will be classified Group C. The effluent, line out to and including the first isolation valve outside containment will be classified as Group A. Prom the second isolation valve up to and including the third isolation valve will be classified Group B. Beyond the third isolation valve will be classified Group C.
Rev. 22, 4/81
SSES-FSAR TABLE 3.2-1 (Continued)
Pa e 35
- 27) The containment spray ring header and connecting piping extending from the conta'inment -isolation valve meets all of the requirements of Group B except that hydrostatic testing is not required.
- 28) The HPCI and RCIC,turbine exhaust lines extending from the containment isolating valve to the suppression pool meets all of the requirements of Group B except that hydrostatic testing of this portion of the piping is not required.
- 29) Piping which penetrates the containment, thus acting as an extension of the containment pressure boundary meets the requirements of Group B or higher. This requirement extends from the first pipe weld on the inside of the penetration to and involving the first isolation valve outside the containment.
- 30) Reinforced concrete primary containment, including drywell-head, hatches, vent pipes, penetrations and spare penetrations are in accordance with Pennsylvania Special Certification. Personnel locks are in accordance with ASME Code Section III, Subsection NE, 1971 Edition, up to and including Addenda of Summer, 1972.
- 31) Systems and components so designated conform to Quality Group D (Augmented). including seismic requirements as defined in NRC Branch Technical Position ETSB ll-l Parts B.4 and B.5.
- 32) The classification of the feedwater line from the reactor .
vessel through the second isolation valve is Group A. The classification of the feedwater line from the second isolation valve through the third valve is Group B. Beyond the third valve the classification is Group D.
- 33) 1. The main steam leads from the turbine control valve to the turbine casing meets all of the requirements of Group D plus the addition of the following requirements:
- a. All longitudinal and circumferential butt weld joints are radiographed (or ultrasonically tested to equivalent standards). Where size or configuration does not permit effective volumetric
,examination, magnetic particle or liquid penetrant examination may be substituted. Examination procedures and acceptance standards are at least equivalent to those specified in ANSI B31.1.0 Power Piping Code.
- b. All fillet and socket welds are examined by either magnetic particle or liquid penetrant methods. All structural attachment welds to pressure retaining materials are examined by either magnetic particle or liquid penetrant methods. Examination Rev. 22, 4/81
SSES-CESAR TABLE 3.2-1 (Continued)
Pa e36 procedures and acceptance standards are at least equivalent to those specified in ANS1 B31.1.0 Power Piping Code; c~ All inspection records are maintained for the life of the plant. These records include data pertaining to qualification of inspection personnel, examination prnpedures, and examination results.
or
- 2. The manufacturer of the main leads utilized quality control procedures equivalent to those defined for main steam leads in the General Electric Publication GEZ-4982, "General Electric Large Steam Turbine-Generator Quality Control Program".
A certification has been obtained from the manufacturer of the main steam leads that the quality control so defined has been accomplished.
- 34) A module is an assembly of interconnected components which constitute an identifiable device or piece of equipment. For example, electrical modul'es include sensors, power supplies, and signal processors; mechanical modules include turbines, strainers, and orifices ~
- 35) The control rod drive insert and withdraw lines from the drive flange, up to and including the first valve on the hydraulic control unit shall be Safety Class 2.
36 6 37) These notes have been intentionally left blank.
- 38) The turbine does not fall within the applicable design codes.
To ensure that the turbine is fabricated to the standards commensurate with their safety and performance requirements, General Electric has established specific design requirements for this component which are as follows:
- a. All welding shall be qualified in accordance with Section IX, ASME Boiler and Pressure Vessel Code,
- b. All pressure-containing castings and fabrications shall be hydrotested in 1.5 X design pressure, c ~ All high-pressure castings shall be radiographed according to:
ASTM E-94 E-142 maximum feasible volume E-71, 186 or 280 Severity level 3 Rev. 22, 4/81
,SSES "FSAR TABLE 3.2-1 (Continued)
Pa e 37
- d. As-cast, surfaces shall be magnetic particle or liquid penetrant tested according.to ASME, Section III, Paragraph N-232.4 or N-323.3,
- e. Wheel and shaft forgings shall. be ultrasonically tested according to ASTM A-388, Butt-welds shall be radiographed according to ASME,Section III, Paragraph N624, and magnetic particle or liquid penetrant tested according to ASME Section III, Paragraph N626 or N627 respectively,
- g. Notification to be made on major repairs, and records maintained thereof,
- h. Record system and traceability according to ASME Boiler and Pressure Code Section 1, Appendix IK, Paragraph IX-225 j
- 39) Only equipment associated with a safety action (eg, isolation) need conform to a safety function.
. 40) In addition to a swing check valve inside the drywell and a positive acting check valve outside the drywell simil'ar to an Atwood-Morrill boiler feed pump check valve as described in their Catalog 63,Section I, a valve with high leak-tight integrity shall be provided outside the drywell.
Additionally, a swing check valve and a valve with high leak-tight integrity shall be provided, inside and just outside the containment, respectively. The spring-loaded piston operator of the positive acting check valve will be held open by air pressure during normal operation. Fail-open solenoid valves will be used to release air pressure and to permit the check valve piston operator to close. The positive acting check valve and the high leak-tight integrity isolation valve will be remote manually operated from the control room using signals 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 will be Group A. The remainder of the system will be Code Group D, except the portion between the check valve just inside the containment and the motor operated valve just outside the containment, including'oth valves, which will be Group B.
41 Sample piping 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 group D. Isolation is manually removed to allow monitoring.
42 Reactor shield wall concrete is a non-structural element (see
'subsection 3.8.3.1.3) and is therefore non-Category I.
Rev. 22, 4/81
SSES-CESAR TABLE 3.2-1 (Continued)
Pa e 38 Shield wall concrete, because of concrete placement, is non- 22 safety related.
Rev. 22, 4/Sl
0 tI