ML19341C197
| ML19341C197 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/23/1981 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8103020362 | |
| Download: ML19341C197 (19) | |
Text
k
.l SourH CAROLINA ELECTRIC a GAS COMPANY 705T CF FICE BOR 764 COLuweiA, south CAROLINA 29ais T. c. Nicwo ts, J a February 23, 1981 wet Passentwf aut G40w' [EECVNE 9tAttam CrpthateOm5 Mr. Harold R.'Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 FSAR Question 421.83 - Q-List
Dear Mr. Denton:
South Carolina Electric & Cas Company (SCE6G) acting for itself and as agent for the South Carolina Public Service Authority, hereby submits forty-five (45) copies of the response to FSAR question 421.83 concerning the Q-list.
This question was incorrectly numbered as 420.83 in a previous NRC letter to SCE&G.
The response will be incorporated into the FSAR in amendment 24.
If you have any questions, please let us know.
Very truly yours,
$/
V c
sce T. C. Nichols, Jr.
NEC:TCN:glb Enclosure ec:
V. C. Summer w/o enclosure G. H. Fischer w/o enclosure T. C. Nichols, Jr. w/o enclosure E. H. Crews, Jr.
O. W. Dixon, Jr.
C. A. Price D. A. Nauman W. A. Williams, Jr.
R. B. Clary q,.
~~'
A. R. Koon A. A. Smith H. N. Cyrus J. B. Knotts, Jr.
s[ 21 ild /f533EG J. L. Skolds B. A. Bursey O. S. Bradham
.. l'rt 32 f f : '^
N!WlEld U5! 022 :
ISEG PRS NPCF/Whitaker
'E103 02 0 File
4 421.83 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 Tables 3. 2-1, 3. 2-2, 3.10-1, and.3.10-2 o f
~
the FSAR in accordance with the following:
a.
The following items do not appear on the Q-list.
Add these items or justify not doing so.
1)
Biological shielding within reactor building, control building, auxiliary building, fuel handling building, and intermediate building.
2)
Missile barriers protecting safety-related equipment within the reactor building, control building, auxiliary building, fuel handling building, intermediate building, diesel generator building pump house, anu around air intakes, vent stacks, and other outside structures as applicable.
- 3) Pressurizer spray nozzles.
4)
Steam generator steam flow restrictors.
5)
Fuel handling building crane.
- 6) Meterological data collection programs.
7)
Steel liner of the reactor building.
8)
Supports for containment heat removal system.
9)
Combustible gas control system H purge supply and exhaust system a)
H{2monitoringsystem b) c) H2 analyzer d)
Supports 10)
Cont _1.iment and emergency cooling system a)
Cooling coils b)
Ductwork dampers and supports
- 11) Onsite power systems (Class IE) a) Diesel generator packages including auxiliaries (i.e., governor, voltage regulator, excitation system) b) 4160 volt switchgear c) 480V load centers d) 480V motor control centers e)
Instrumentation, control, and power cables (including underground cable system, cable splices, connectors, and ter=inal blocks)
[
! L f) Conduit and cable trays and their supports flote--Raceway installations containing Class lE cables and other raceway installations required to meet seismic category 1 requirements (those whose failure during a seismic event may result in damage to any Class lE or other safety-related system or components) should be included.
g) Transformers h) Valve operators i)
Protective relays and control panels j) AC control power inverters k) 120 AC vital bus distribution equipment
- 1) Containment electrical penetration assemblies m) Other cable penetrations (fire stops) 12)
DC power systems (Class 1E) a)
l?5V battery, battery chargers, and distribution equipment b) Cables c) Conduit and cable. trays and their supports tiote--Raceway installations containing Class IE cables and other raceway installations required to meet seismic category 1 requirements (those whose failure during a seismic event may result in damage to any Class lE or other safety-related system or components) should be included.
d) Battery racks e) ' Protective relays and controi panels 13)
Reactor building charcoal cleanup plenums.
14)
React'or building purge exhaust plenum.
15)
Controlled access area charcoal exhaust plenum.
16)
Process and effluent radiation monitoring systems.
17)
Auxiliary. building charcoal filter system plbnum.
18)~ Buried service' water piping systems.
- 19) Safety-related masonry walls (see IE Bulletin tio. 80-11).
, -20)
Expendable and consumable items' necessary for the functional perform-ance of CSSC (i.e., weld rod, fuel oil, boric acid, snubber oil, etc.).
+
4 4
g
- 21) Measuring and test equipment.,
- 22): ; teak detection system (per FSAR Section 5.2.7).
l23)
Pressuri er safety and relief ~ valves,-block valves, and associat.ed l actuators.
24)
Steamline safety valves and PORVs'.
. 25)
Pressurizer discharge line to pressurizer drain tank.
26)
Containment sump, sump screen, and sump vortex suppression devices.
- 27) Radiation monitoring (fixed and portable).
~
- 28) Radioactivity monitoring (fixed and portable).
29)
Radioactivity sampling (air, surfaces, liquids).
30)
Radioactive contamination measurement and analysis.
31)
Personnel monitoring internal (e.g., whole body counter) and external.(e.g., TLD system).
32)
Instrument storage, calibration, and maintenance.
l
- 33) Decontamination (facilities, personnel, and equipment).
34)
Respiratory protection, including testing.
35)
Contamination control. of NUREG-0737, " Clarification of TMI Action Plan Requirements"
't b.
(November 1980) identified numerous items that are safety-related and appro-priate for OL application. and therefore should be on the Q-list for the These items are listed below. Add these Virgil C. Summer Nuclear Station.
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 1
2)
Reactor coolant system vents.
II.B.1 II.B.2 3)
Plant shielding.
4)
Post' accident sampling.
II.B.3
- 5). Valve position indication.
II.D.3
- 6) Auxiliary feedwater system.
II.E.1.1
- 7) - Auxiliary feedwater system initiation II.E.1.2 and~ flow.
- 8). Em$rgency power for pressurizer heaters.
II.E.3.1 9)
Dedicated hydrogen-penetrations.
II.E.4.1
~%*
9
. l i
- 10) Containment isolation dependability.
II.E.4.2 11 ) Accident monitoring instrumentation.
II.F.1 I
12)
Instrumentation for detection of inadequate II.F.2 core-cooling.
j t
- 13) Power supplies for pressurizer relief II.G.1 valves, block valves, and level indicators.
i
- 14) Automatic PORV isolation.
II.K.3(1)
- 15) Automatic trip of reactor coolant pumps.
II.K.3( 5) t 16)
PID controller.
II.K.3(9)
- 17) Anticipatory reator trip on turbine trip.
II.K.3(12)
~
18)
Power on pump seals.
II.K.3(25) 19)
III.A.l.1/III.A.2
- 20) Emergency suoport facilities.
III.A.l.2 radiation monitoring.
III.D.3.3 21')
Inplant 12 22)
Control-room habitability.
III.D.3.4 The instrumentation and control systems and components must be identified c.
on the Q-list to the same scope and level of detail provided,_in Chap,ter_7 of the FSAR.
(Tables 3.10-1 and 3.10-2.are too general.)
Include safety-related display instrumentation such as source range neutron flux monitors.
Also include applicable items listed in Section 3.11.
..we=**
,w
>%ww.
d I
4 e
Response
Section 17.1.2.2 has been revised to include Tables 3.10-1 and 3.10-2 as a part of the Q-list.
Tables 3.11-0 and 3.11-Oa, as shown in Section 17.1.2.2 have been a part of the Q-list.
These tables, along with Tables 3.2-1 and 3.2-2, have been revised as necessary to include items requested by this question as discussed below.
The te'rm safety related in this response is defined in 10CFR 50 Appendix B as these systems, structures and components i
that prevent or mitigate the consequences of potential accidents that could cause undue risk to the health and safety of the public.
j a.1)
Included in revised Table 3.2-2.
a.2)
Included in revised Table 3.2-2.
a.3)
The pressurizer spray nozzles are safety related and are an integral part of the pressurizer.
The pressurizer is included in Table 3.2-1.
a.4)
The steam generator steam flow restrictors are safety related and are an integral part of the steam generators.
The steam generators are included in Table 3.2-1.
a.5)
The fuel handling building crane is not safety related and is not included as an item on the Q-list.
a.6)
The equipment associated with meteorological data collection is not safety related.
Refer to Section 2.3.
Also, see Note 1 of this response.
a.7)
Included in revised Table 3.2-2.
a.8)
Included in revised Table 3.2-1.
These items a.9a)
H, removal is bv use of internal H$recombiners.
~
are included in Tables 3.2-1, 3.10 2, and 3.11-0.
I a.9b)
Included in revised Table 3.2-1.
a.9c)
Included in Tables 3.10-1 and 3.11-0a.
a.9d)
Included in revised Table 3.2-1.
a.10a)
Included in Table 3.2-1.
Refer to Note 17 of Table 3.2-1.
a.10b)
Included in revised Table 3.2-1.
a.11a)
Included in Tables 3.10-1 and 3.11-0a.
a.11b) 7200 volt switchgear is used at the Virgil C. Summer Nuclear Station in lieu of 4160 volt switchgear.
7200 volt switchgear is included in Tables 3.10-1 and 3.11-0a.
a.11c)
Included in Table 3.11-Oa.
I a.11d)
Included in Tables 3.10-1 and 3.11-0a.
a.lle)
Included in Table 3.11-Or..
a.11f)
Cable trays and supports are included in Table 3.10-1 and 3.11-0a.
Conduit is not safety related and is not included on any of these tables.
The conduit is, however, seismically supported for safety related circuits and those non safety related circuits over safety related quipment.
a.11g)
The 480 volt vital system transformers are included in Tables 3.10-1 and 3.11-Oa.
The 7200 volt to 480 volt transformers are a part of the 7200 volt switchgear included on Tables 3.10-1 and
_3.11-0a.
-a.11h)
Included in Tables 3.10-1, 3.11-0 and 3.11-0a.
a.111)
Included in Tables 3.10-1 and 3.11-0a.
a.11j)
. Included in Tables 3.10-2 and 3.11-0.
1 r
I a.11k)
The safety related 120 volt vital AC equipment is included in Table 3.11-0a.
a.111)
Included in Tables 3.10-1 and 3.11-0a.
a.11m)
Included in revised Table 3.2-2.
a.12a)
Included in Tables 3.10-1 and 3.11-0a.
a.12b)
Included in Table 3.ll-0a.
~
a.12c)
Cable trays and supports ar'e included in Table 3.10-1 and 3.11-0a.
Conduit is not safety related and is not included on any of these tables.
The conduit is, however, seismically supported for safety related circuits and those non safety related circuits over safety j
related equipment, a.12d)
Included in Table 3.11-0a.
a.12e)
Included in Table 3.11-0a.
a.13)
Reactor building charcoal cleanup plenum is not safety related and is not included on any of the tables. Refer to FSAR Section 9.4.
l a.14)_
Reactor building purge exhaust plenum.is not safety related an,d is not included on any of the tables. Refer to FSAR Section 9.4.
a.15)
Controlled access area charcoal er.haust plenum is not safety related and is not included on any of the tables.
Refer to FSAR I
Section 9.4.
a.16)
Radiation monitors which are safety related are included in Table 3.10-1.
Also refer to the response to items a.27. a.28, a.29, a.30,
[
a.31, a.33, a.34, a.35 and b.411.
l j.
a.17)
Auxiliary building charcoal filter system plenum is not safety l
related and is not included in any of these tables.
Refer to FSAR Section 9.4.
a.18)
Inclyded in Table 3.2-1.
Buried pipe is not excluded.
a.19)
There are no safety related masonry walls at the Virgil C. Summer Nuclear Station.
a.20)
Consumable products are addressed in revised notes to Table 3.2-1.
- a.21)
Measuring and test equipment is not safety related and is not includet in any of the Q-list Tables.
The calibration program and control of equipment used in safety related activities are under the aspects 1of the quality assurance program.
a.22)
Leak detection system consisting of the following elements (flow switches,' level switches, temperature sensors, pressure transmitters and radiation monitors) meets the requirements of regulatory guide 1
1.45 as described in Appendix 3A.
The elements which are safety
.related are' included in revised Table 3.10-1 and 3.10-2. -
a.23).
Included in revised Table 3.2-1.
a.24)
Since the PORV's and Safety Valves are in between the steam
. generators and the main steam isolation valves, they are included in Table 3.2-1.
,a.25)
' Included in revised Table 3.2-1.
a.26)
The reactor building sumps and sump screens are safety related and are a part of the " reactor building. interior structures"found on Table 3-2-2.'
a.27)
The equipment involved is not safety related per ANS 18.2.
The programs which control _these activities are in compliance with 110CFR 50 Appendix B and are administered to meet the requirements of-10CFR 20..
a.28)
See response to a.27).
a.29)
.See response to a.27).
9M 3-'"Etrt-"7 r
r f
M-+
?!r"rY p+e*
s
+e-+--
- f
-=r
=3r
-"M- -
- y Tw*P?T--*e "r
W
l l
l a.30)
See response to a.27).
a.31)
See response to a.27).
a.32)
See response to item a.21).
a.33)
See response to item a.27).
a.34)
See response to item a.27).
a.35)
See response to item a.27).
b.1)
This item will be addressed'when NURIG 0696 Revision 1.is issued.
b.2)
Included as a part of the reactor coolant system in Table 3.2-1.
b.3)
Included in revised Table 3.2-1.
b.4)
Post accident sampling equipment is not safety related and is not included in any of the Q-list Tables.
Refer to Chapter 11.
b.5)
Limit switches are included in Tables 3.11-0 and 3.11-0a.
Critical system leak monitoring system is included in Table 3.10-2.
b.6)
The emerger.cy feedwater system is included in Table 3.2-1.
b.7)
Included in Tables 3.10-1, 3.10-2, 3.11-0 and 3.11-0a.
b.8)
Backup heaters for the pressurizer are powered from the 7200 ~
volt switchgear which is included in Table 3.10-1.
b.9)
Since SCE&G uses internal H2 recombiners, no dedicated H2 penetra-tions are required.
b.10)
The equipment involved in containment isolation is safety related and is included in Tables 3.2-1, 3.11-0 and 3.11-0a.
The program for containment isolation dependability is under the aspects of the quality assurance program and is performed as a part of the pre-operational test program of the plant.
b.11)
Table 7.5-1 provides a list of accident monitoring instrumentation.
' These instruments are included in Tables 3.11-0 and 3.11-0a.
b.12)
Subcooled monitor and reactor vessel level instrument are included in revised Table 3.10-2.
b.13)
All AC and DC power supplies for the pressurizer relief valves, block valves and level indicators are included in Tables 3.10-1, 3.10-2, 3.11-0 and 3.11-0a.
b.14)
Automatic PORV isolation is determined not to be necessary and is not included in the current design.
b.15)
Automatic trip of reactor coolant pumps is determined not to be necessary and is not included in the current design, b.16)
'The PID c'ontroller is turned off.
Refer to Figure 7.7-4.
-b.17)
'That portion of the anticipatory reactor trip on turbine trip which is safety related is on the solid state protection system which~is-included in Table 3.10-2.
- b.18)
-Refer to the response to Question 211.123.
Devices used are included
.in Table 3.11-Oa.
b.19)~
" Emergency Plans" are not a piece'of safety related equipment and is therefore not. included.on any of the Q-list Tables. The emergency plans and applicable implementing procedures are under the aspect of the quality assurance procedure.
L b. 20)
This item will.be discussed when NUREG 0696 Revision 1 is issued.
The equipment used for inplant I radiation monitoring is not aafety
'b.21) 2
'related and'is not included-in any of the Q-list Tables. The programs Lwhich control.the monitoring activities are-in compliance with 10CFR 50 Appendix R and are administered to' meet the requirements of 10CFR 20.
b.22)'
Control. room ventilation equipment is included in Table 3.2-1.
c.)'
Included in Tables 3.11-0 and 3.11-0a.
a w
w
_ _ _ _ _ ___q 1
[
j i
i i
NOTES:
l r
t 1.
Procedural coverage of some or all aspects of this equipment is covered in the quality assurance program per 10CFR 50 Appendix B.
i I
+
8 i
3 t
}
I i,
l t
I
+
i i
I l
I l'
1 L
)
l l'
i i,
4 t
1 i
t s
6 1
t 1
4 i
i I -
c F
L S
O 3
1 I
i 1
?
I 1.
t i
h I.
L,.
Q)+~.6,--..,~,._,...._.-,r.m.,..--.
_m 24 TABLE 3.2-1 AMENDMENT 38 APRIL, 1979 MECllANICAL EQUIPMENT CLASSIFICATION ANS Code Seismic QA Component Scope Sa fety Class Code Class Category Clas_s Notes MECHANICAL COMPONENTS (by systeJn)
REACTOR COOLANT SYSTEM Reactor Vessel NSSS 1
AStE III 1
I 1
1 Ful1. Length CRDM llousing (48)'
.1 ASME III 1
I 1
2 Part Length CRDM llousing (5).
~ NSSS 1
ASME III 1
I 1
NSSS 1
ASME III 1
I 1
2 Reactor Coolant Pump Assemblies (3)
Reactor Coolant Pump Casings (3)
NSSS 1
ASME III 1
'I I
2 Reactor Coolant Pump Internals (3).
NSSS 1
ASME III 1
I 1
2 Reactor Coolant Pump Motors (3)
1 2
Steam Generator, tube side (3)
NSSS 1
ASME III 1
I 1
2 y
Steam Cenerator, shell side (3).
I 1
2,3 t;3 Pressurizer-NSSS 1
ASME III I
I 1
2 u
. Reactor. Coolant Thermowell NSSS 1
ASME III 1
I 1
4 Reactor. Coolant Piping and Fittings NSSS 1
ASME III 1
I 1
1,5 Surge Pipe and Fittings NSSS 1
ASME III 1
I 1
1 Loop B pass Line NSSS 1
ASME III 1
I 1
1 f
ASME III 1
I 1
4 Relief Valves (3),Sifety WJver(8),81===W/**8(S) NSSS 1
ASME III 1
I
_I 1
. Valves to Reactor Coolant System NSSS/ BOP 1
ASME III 1
I 1
6
'Q,'
Boundary Piping to Reactor Coolant System NSSS/ BOP 1
ASME III 1
1 1
5,6 pr.,,
,. nharye INe to PAT 80?
- dS
- *#/* ##Y I
i
~
if
~
Pressurizer Relief Tank (,I'Rd NSSS NNS ASME VIII 4
CRDM liesd Adapter Plugs '
NSSS 1
ASME III I
I 1
4 Fuel Assemblies NSSS NA I
1 CHEMICAL AND VOLUME CONTROL SYSTEM Regenerative IIcat Exchanger NSSS 2a ASME III 2
I 1
1 Letdown IIcat Exchanger, tube side NSSS 2a ASME III 2
I 1
1 Letdown l{ca t Exchanger, shell side NSSS 2b ASME III 3
I 1
1,7 Mixed Bed Demineralizers (2)
NSSS 3
ASME III 3
I 1
4
. - ~
W:.
O n
Q q)
O.a e.
-:c TABLE - 3. 2-1 (Continued) 29 AMENDMENT 4 N, 1HR MEC11ANICAL EQUIPMENT CLASSIFICATION M eck,#1FO ANS Code Seismic QA
-Component Scope Safety Class Code Class Category Class Notes r
NUCLEAR SAMPLING SYSTEM Residual Heat Removal Sample Cooler ' BOP 3
ASME III 3
I 1
' Pressurizer Sample Cooler BOP 3
ASME III 3
I 1
. Pressurizer Sample Vessel
. Reactor Coolant Sample Cylinders (2)
BOP NNS ASME VIII l4 Reactor Coolant Sample Coolers (2)
B0P 3
ASME III 3
I 1
Steam Generator Blowdown Sample BOP 3-ASME III 3
I 1
t Coolers.(3)
Volume Control Tank Gas Space Sample BOP NNS ASME VIII w
Sample Sink BOP NNS 4'
Steam Generator Blowdown Sample BOP 3
ASME III 3
I 1
5 g
Piping w
Steam Generator Blowdown Sample BOP 3-ASME III-3 I
1 5
l
-Valves Nuclear Sampling System Piping BOP 3
ASME III 3
I 1
5 Nuclear Sampling System Valves BOP 3
ASME III 3
I 1
5 Reactor Coolant Sampling Delay BOP 2a ASME III 2
I 1
Coils-(2)
CVCS Sampling Delay Coils (2)
BOP 3
ASME III 3
I I
e.ad - Sample
[ 28 POST ACCIDENT HYDROGEN REMOVAIASYSTEMS s.
' Electric 11ydrogen Recombiner NSSS 2a ASME III 2
I 1
Sample Vessel BOP.
NNS ASME VIII Piping and-Valves a sJ S.pferTs,
BOP-2a/NNS ASME III/-
2/-
I/-
1/-
5 2't j
REACTOR MAKEUP WATER SYSTEM Reactor Makeup Water Storage Tank BOP 2b ASME III 3
I 1
Reactor Makeup Water Pumps (,2)
I 1
9
.,w-.
.._,m
TABLE 3. 2-1 (Continued)
AMENDMENT
- M MECllANICAL EQUIPMENT CLASSIFICATION ANS Code Seismic QA-JComp~onent Scope Safety Class Code Class Category ~ Class Notes
' VENTILATION EQUIPMENT Reactor Building Cooling Units (4)[thI BOP 2b ASME III 3
I 1
16,17 II s
Reactor Building Charcoal Cleanup BOP NNS I
1 18 System Fans (2)
Reactor Building Purge Valves BOP 2a ASME III 2
I 1
Auxiliary, Building Charcoal Exhaust BOP
-NNS 13 System Fans (4)
Fuel.llandling Building Exhaust Fans BOP 3
I 1
la Spent Fuel Pool Supply Fan BOP NNS 13 BOP.
2b ASME III 3-I 1
17,18 Residual licat Removal / Spray Pump _
7 Room Cooling-Unit-
! Charging Pump Room Cooling BOP 2b ASME III 3
I 1
17,18 l3 os Unit-Auxiliary Building Charcoal Filter BOP NNS~
13 System Plenum (2)
. Fuel'Ilandling Building Charcoal BOP 3
1 1
13 Filter Plenum (3);
Iritermediate Building. Pump Area BOP 2b ASME III 3
I 1
17,18 Cooling Units (2) f3 I
1 18 Control Room Emergency Filtering BOP 2b System Fans Control Room Normal Supply Units BOP.
2b ASME III 3
I 1
17,18
-Relay Room Cooling System Units BOP 2b ASME III 3
I 1
17,18 Battery Room Air Supply Fans BOP 2b I
1 13 Battery Room Exhaust Fans BOP 2b I
1 18 IIVAC Water Chillers BOP 2b ASME III 3
1 1
IIVAC Chilled Water Pumps.
I
,1 9
4
e n
a o
O
~
TABLE 3.2-1 (Continued)
AMEND!ENT 3 E 8/
W M Arch,1991 ffEC11ANICAL EQUIPMENT CLA9SIFICATION ANS Code Seismic.
QA Componen t -
Scope Sa fety Class Code-Class Ca te go ry Class Notes I
1 18 Service Water Pumphouse Supply-BOP 2b'-
Fanc (2)
ESF Switchgear Room Cooling BOP 2b ASME III 3
I 1
17,18 3
Units (2)
Speed Switch Room Cooling BOP 2b AStfE III 3
1 1
17,18 Units (2)
Motor Con trol. Center 12-28 BOP 2b ASME III 3
I 1
17,18 Cooling Units (2)
- Switchgear 63-01 ~ Cooling BOP 2b ASifE III 3
I 1
17,18 Unit (1)
I
.1 z'/
p>.
S=rwar,IA-res, sw%
av g
y s f ry Rat rd W~r'il.n' 3
symm n.
s e
4 b
e 4
---~
TAELE 3.2-1 (Continued) s b
)
,?
PECHANICAL EQUIPMENT CLASSIFICATION NOTES TO TABLE 3.2-1 4
fall Certain pressure retaining parts exist within a system which do not within the normal definition of pipes, pumps or valves.
In scme cases these are not ccmmercially available f abricated f rom materials conforming (J
to ASTM specifications allowed in ANSI B31.1, ASME III or ASME VIII; in addition, instrumentation is specifically excluded from ASME III.
Exam-ples of these items are strainers, sight glasses, level switches, pressure These items are specified and procured transmitters, thermowells, etc.
in a manner which ensures that these components are comparable with the rcmainder of the systems to preclude their structural failure under operating, accident or test conditions. W*i c *' " c ' ' ' * -
- Uc t ' J" " ' d / *
- a -l" ~5 w
wel.f evd, aJ m'e ry rs k rsd. Gmt " 6 f H < sc l
i n ~ s u r<-
w, n,.inb o lsta nd c y,'y-s m re c o -s id s esco's), 1,M e %,y sten 2<, e re,
)
e d.esst f ~
l, belc Meets " Quality Control System Requirements," Westinghouse OCS-1, 1.
which satisfies the requirements of 10 CFR 50, Appendix B.
c.
Meets the quality assurance program of one of the Westinghouse NES 2.
Manufacturing Divisions, and is in accordance with 10 CFR 50',
Appendix B.
As permitted by Paragraph NA-2134 of the ASME Code,Section III, 3.
this component is upgraded from the minimum required Code Class 2 to Code Class 1.
4 Meets " Quality Requirements for Manufacture of Nuclear Plant Equipment," Westinghouse QCS-?, which satisfies the requirements
-1 of 10 CFR 50, Appendix B.
f "L/
The classifications shown are for the predc=inant portion of the 5.
system.
There may be portions that are classified higher or lower.
Safety class boundaries are shown on applicable system diagrams.
Seismic category, code and QA classes for other safety classes are j
consistent with those other safety classes.
Aneadnear 24 bi s ec k 1961 3.2-20
e TABLE 3.2-1 (Continued)
==
MECHANICAL EQUIPMENT CLASSIFICATION
- 15. Main steam and feedwater piping, excluding branch lines, between -the l
12 C. e associated isolation valves and the wall between the intermediate building and turbine building satisfies all requirements, except for 12 stamping, of the ASME Code,Section III, Code Class 2.
- 16. No code.
The fans and motors are specifically designed for opera-tion in the containment atmosphere under both normal operating and -
post LOCA conditions.
- 17. Code and Code Class apply to unit coils.
- 18. No code.
TheAfans are designed and manufactured in accordance with the intent of ANS Safety Class 2b.
C..
19.'No code. Ductwork is designed to withstand expected pressures and shocks' for the section of the plant in which it is located.
- 20. Any' reactor vessel internal, the single failure of which could cause release of a mechanical' piece having potential for direct damage (as to 'the vessel cladding) or flow blockages, sha.11 be classified to a minimum of Safety Class 2a.
e
- 21. Failure can cause no nuclear safety problem, although an economic loss may result.
- 22. Portions which transmit loading from CRDM seismic supports are
(
Safety Class 2a.
- 23. Applicable code is Crane Manufacturers Association of America, Specifi-
~
cation No. 70 for Electric _ Overhead Traveling Cranes.
13
'24. Equipment is not' ANS Safety Class but is safety related.
~
25, 5 pers f.e re.crwr.bvilA**y coef Jry w#!7s are safey related.
l19 3.2 AMENDMENT g ty must, ines 64 Arsh,196l
e o
n O
3 O
O TABl.E 3.2-2 AMENDNENT & l'/
assese, w I9 I CLASSIFICATION OF STRUCTURES
/
Seismic Hon-Seismic Method of Tornado Tornado Missile
}
Caterory i Category Nissile Protection Crade to 30 Feet Above 30 Feet Licer ReactorBuilding."PenetrationsandItatches(I)[b) i X
A. C 1,2,3,4,5.6.7 3.5,6.7 l?
Reactor Building interior Structures X
Reactor Building Reactor Building Reactor Building Control Building UI(h X
A,B.C,D E
1,2,3,4.5.6,7 3.5,6.7 Aux 11'f ary Building (S)(h X
A.B.D,E 1,2.3,4,5,6,7 3.5,6.7
-Fuel llandling Building (5)
X a.
Ceneral structures for fuel pools and protective barriers for equipment (see Figures 3.8-58. 3.8-59, 3.8-60)
A, B, C. D, E 1.2.3,4.5.6,7
- 3. 5, 6, 7 l7 b.
Steel superstructure (
'(see Figures 3.8-58, 3.8-59, 3.8-60)
(4)
(4)
(4)
I Intermediate Building X
A,B,C.D,E 1.2,3,4.5,6,7 3.5.6.7
. Diesel Cenerator Building X
A,B.C.D,E 1,2,3.4,5,6.7 3,5.6.7 7
Service Water intake Purphouse and Discharge
)(b X
A, B C 1.2.3.4.5.6.7 Not applicable Structuren Service Veter Fond Damn X
Not applicable Not applicable Not a.aplicable
^
l7 Supports' for Safety Class Components X
A, B. C. D. E 1,2,3.4,5,6,7 3, 5. 6 T Turbine Building X
Substation Structure and Control liouse X
Water Treatment Building X
Circulating Water Intake and Discharge Structure X
Service Building X
Aux 111ery Boiler llouse X
Warehoune(s)
X Guard llouse(s)
X F-Mnnticelin Reservoir Dams X
c==
Jetty X
Sanitary Waste Facility X
Industrial Weste Tacility X
e C'
TAELE 3.2-2 (Continued)
CLASSIFICATION OF STRUCTURES C.;_.,
l 3
f NOTES:
i 1.
Method of tornado missile protection is as follows:
A.
Reinforced concrete valls.
B.
Reinforced concrete slabs, i
C.
Reinforced concrete barriers.
D.
Orientation.
f E.
Probability studies, probability criteria < 10'.
f 2.
Numbers correspond to. tornado missiles identified in Table 3.5-5.
3.
Refer to discussion of probability study, response to Question 010.7.
2
..)
4.
Steel fra=e is designed to maintain its integrity under tornado
- nissile impaet.
i peerdt 5
' Sio\\ogical shiddin3 a.nd missi\\c barries-s h ch rol e I
st ru.ctares idad:sta 1 ram 3.t _2.
2tf j
reta.w %
ca.t4. p 3 saf ety - re.tohl.
are c.tosst ha as e.lecric.I ysHerranb W
- r * * *kY T0'Yd-(p, Fire stoft f*e c'
t
)
3.2-23a RENDMENT 2 f/
, X:
M a sk,Itti r
1 i
i O
TABLE 3.10-2 (Continued)
O IDENTIFICATION OF NUCLEAR STEAM SUPPLY SYSTEM SEISMIC CATEGORY I INSTRUMENTATION, ELECTRICAL EQUIPMENT AND SUPPORTS
~?
4 Item Method 0'
- 12. Core Subcooling Monitor-Not yet qualified; qualification to be in accordance with methods i
~
described in Section 3.10.
- 13. Critical System Leak.
Not yet qualified; qualification Monitoring System to be in accordance with methods i
i-described in Section 3.10.
S&G & A if Y
ty, M M A L I
g s..,. _.,.
.... /.,
...,,n.*
~
+:
- ...., - (; 1 g, ::,. ; :,.
- ^
~
... O i:~ b.,.
....a c.'
x:.:, l
~
A s
l'.
n AMENDMENT W
- 2 3.10-15a.
7-
^
.msrb,t9 %i I
D
-~.
-- -~~-
- ~ -. -
e I
17.2.1.6 Supporting Companies, Vendors or Contrac+or Organizations SCE6C may utilize the services of other companies to provide natcrials or. service s and' augment an t'. aupport its staf f in, selec ted plant opera-tions, or' modification and maintenance projects.. To qualify for safety-related work, supporting companies must implement an approved QA 4
program or work under the requirements of the SCE6C Operational QA Pro-gram. Use of the SCE6G Operational QA Program is limited to those cases where management functions are not performed.
After purchase order or contract award, the vendor, supplier, or contractor shall conduct all quality related activities for safety-related structures, systems or components, whether at the plant or other locations, in accordance with l
the appropriate approved QA program.
17.2.2 QUALITY ASSURANCE PROGRAM The. Operational QA Program for the Virgil C. Sumer Nuclear Station
. consists of managerial and adminstrative controls 'by involved SCE6G
'l ~ organizations, combined with surveillance and audits by the QA Department.
?~
As described generally in this section, and following sections of this chapter, the organizations responsible for implementing safety-related action are. clearly identified. _ At the discretion of SCE6G management, certain non-safety related activities may be conducted utilizing control techniq'ues specified for' safety-related activities.
These activities 7
I are outside the scope of required regulatory compliance and are dis-12 criminated by the term " Quality Related".
All " safety-related" activity i
l is ;"qualitiy : related, but not all '.' quality related" activity is "sa f et y-re la ted"..
L 0
4 i
17.2.2.1 Applicability The.0perational'QA program is applicable to startup, operation, mainte--
/
' nance, andLmodification of the structures, systems and components of
.the Virgil C.' Su=mer Nuclear Station classified as safet,y-related.
The ml r+rve mt a
safety-related designations for= those Mechanical, site =s are listed in s}f8
, ped 1.t-t D
- Tables 3.2-11 The list of Class 1E equipment required to function during -
s t go.1 3,jo,1,
,13 -
and/or ' subsequent to design basis accidents is included in Tab 1'esA.11-0 3
.and 3.11-0a.; The. Operational _QA Program, as detailed'in the Operational
.QA Plan, shall be AMESDMENT S O 17~2-1' W?!*
J.L.
z.