ML20056C537
| ML20056C537 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 06/14/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9306240449 | |
| Download: ML20056C537 (8) | |
Text
"
GENuclear Energy G, metal Dectik Compwy I 75 Curtoer Avenue. San Jose. CA 95125 June 14,1993 Docket No, STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Schedule - SSAR Section 3.8
Dear Chet:
Enclosed is a markup of SSAR Section 3.8 which aligns it with Appendix 3H.
Please provide a copy of this transmittal to Tom Cheng.
Sincerely, 3Y Ja Fox Advanced Reactor Programs cc: Gary Ehlert (GE) -
Norman Fletcher (DOE) r, L. E D -)
n c s.
- t. '
l i
mm 9306240449 930614 FT PDR ADOCK 05200001 di i
A pyg g
1
AMM 2ax toase Standard Plant Rev n taade to permit temporary bypassing on the door 3.8.2.1.1.3 Other Penetrations interlock system during plant cold shutdown. The i
door operation is designed and constructed so The RCCV penetrations are categorized into either door may be operated from inside the two basic types.
These types differ with containment vessel, inside the lock, or from respect to whether the penetration is subjected outside the containment vessel.
to a hot or cold operational environment.
The lock is equipped with a digital readout The cold penetrations pass through the RCCV pressure transducer system to read inside and wall and are embedded directly in it. The hot outside pressures. Quick-acting valves are penetrations do not come in direct contact with provided to equalize the pressure in the air lock the RCCV wall but are provided with a thermal when personnel enter or leave the containment sleeve which is attached to the RCCV wall. The vessel. The personnel air locks have a double thermal sleeve is attached to the process pipe sealed flange with provisions to pressure test at distance from the RCCV wail to minimize the space between the seals of the flange.
conductive heat transfer to the RCCV wall.
Besides piping penetrations, several electri-cal penetrations also exist. A description of the various penetrations is given Chapter 8.
3.8.2.1.L2 Equipment Hatch 3.8.2.1.1.4 Drywell H:ad J
/
f Three equipment batches are provided. Two A 10300 mm in diameter opeling in the RCCV ~ l drywell equipment hatches, one of these serves upper drywell top slab over uhe RPV is covered the upper drywell and the other serves the lower with a removable steel torgspherical drywell l drywell via the access tunge1 The third head which is part of the pressure boundary.
l equipment hatchD0000 mm>provides personnel The drywell head is designed for removal during and equ'pment access to the suppression chamber reactor refueling and for replacement prior to airspace.
reactor operation using the reactor building crane. One pair of mating flanges is anchored The equipment batch covers have a double in the drywell top slab and the other is welded sealed flange with provisions to pressure test integrally with the drywell head. Provisions the space between the seals of the flange. A are made for testing the flange seals without means for removing and handling the equipment pressurizing the drywell. Figure 19F.31 shows l hatch cover is provided. The hoisting equipment the drywell head.
and hoisting guides are arranged to minimize con-tact between the doors and seals during opening and closing. The equipment hatch includes the electric-motorized hoist with pushbutton control stations, lifting slings, hoist supports, hoist-ing guides, access piadorms, and ladders for ac-cess to the doggsd position of the door and hoist, latches, seats, dogging devices, and tools required for operation and maintenance of the
~
hatch.
The equipment hatches and covers are entirely supported by the RCCV. Figure 3.8-15 show gen-eral details of the equipment hatch and cover.
M Arnendnxos 2 c, b
1
ABM ux-se Standard Plant Rev n For the operational test, the personnel air Figures 3.8-17 and 3.8-18 and Figures 1.2 2 locks are pressurized with air to the maximui2 through 1.2-13 show an overview of the permissible code test pressure. All welds and containment including the internal structures.
seals are observed for visual signs of distress or noticeable leakage. The lock pressure is then The summary report contained in Appendix 3H.1 reduced to design pressure and a thick bubble contains the figures for the reactor pedestal i
solution is applied to all welds and seals and and the diagphram slab. Including but not observed for bubbles or dry flaking as indica-limited to structural steel details, rein-tions of leaks. All leaks and questionable areas forcement details, loads, load combinations, are clearly marked for identification and concrete stresses, reinforcement stresses, liner subsequent repair.
stresses, and structural shell stresses.
During the overpressure testing, the inner 3.8.3.1.1 Diaphragm Floor door are blocked with holddown devices to prevent unseating of the seals. The internal pressure of The diaphragm floor serves as a barrier the lock is reduced to atmospheric pressure and between the drywe!! and the suppression all leaks are repaired. Afterward, the lock is chamber. It is a reinforced concrete circular again pressurized to the design pressure with air slab, with an outside diameter of 14.5 m (47 ft, and all areas suspected or known to have leaked 7 in), and a thickness of 1.2 m (3 ft,11 in).
during the previous test are retested by the bubble technique. This procedure is repeated The diaphragm floor is supported by the reac-until no leaks are discernible.
tor pedestal and the containment wall. The con-nection of the diaphragm floor to the contain-3.8.3 Concrete and SteelInternal ment wall is a fixed support. The diaphragm Structures of the Concrete floor connection to the reactor pedestal is a Containmetit hinged support. The diaphragm floor is pene-trated by 18,508 mm (20 in) diameter sleeves
? L3.1 Description of the luternal Structures for the SRV lines.
The functions of the containment internal structures include: support of the reactor vessel radiation shielding, support of piping and A 1/4 och thick, carbon steel liner plate is equipment, and formation of the pressure
- pro, a the bottom of the diaphragm floor, suppression boundary. The containment internal and is a bored to it. Thc liner plate serves structures are constructed of reinforced concrete as a forn during construction and prevents the and structural steel. The containment internal bypass flow of steam from the upper drywell to structures include the following:
the suppression chamber air space during a LOCA.
(a) Diaphragm floor 3.8.3.1.2 Reactor Pedestal (b) Reactor peArant A composite steel and concrete pedestal pro-
$5 vides support for the reactor pressure vessel, wall the reactor shield wall, the diaphragm floor, Rer.ctor %g (c) access tunnels, horizontal vents, and the lower (d) Drywell and equigment pipe support structure drywell access platforms. The pedestal consists of two concentric steel shells tied together by (c) Miscellaneous platforms vertical steel diaphragms. The regions formed by the st:el shells and the vertical diaphragms, (f) Lower drywell equipment tunnel except the vents and the vent channels. are filled with concrete. There are ten drywell (g) Lower drywell personnel tunnel connecting vent (DCV) channels connecting the upper drywell to the lower drywell and the
[ Reactor shield wall stabihze horizontal vents.
)
/G M uAnmAs Standard Plant nrv e High strength structural ASTM A572 or A441 3.8.3.8 Welding Methods and Acceptance Criteria steel plates for Structural and Building Steel Bolts, studs, and nuts ASTM A325 or A490 Welding activities shall be accomplished in (dia. p 3/4 ")
accordance with written procedures and shall meet the requirements of the American Institute Bolts, studs, and nuts ASTM A307 of Steel Construction (AISC) Manual of Steel (dia.13/4 ")
Construction. The visual acceptance criteria shall be as defined in American Welding Society 3.8.3.6.5 Other Internal Structures (AWS) Structural Welding Code D1.1 and Nuclear Construction Issue Group (NCIG) Standard, The materials conform to all applicable Visual Weld Acceptance Criteria for Structural requirements of ANSI /AISC N690 and comply with Welding at Nuclear Plants, NCIG-01.
the following:
3.8.4 OTHER SEISMIC CATEGORY I ha soecification STRUCTURES Miscellaneous platforms Same as Section Other.. Seismic Category I structures which 3.83.6.4 constitute the ABWR Standard Plant are the reactor building, control building and radwaste Lower drywell equipment ASTM A516 Grade 70 building substructure. Figure 1.2-1 shows the tunnel SA-240 Type 304 L spatial relationship of these buildings. The only other structure in close proximity to these 12wer dryweli personnel ASTM A516 Grade 70 structures is the turbine building. They are tunnel SA-240 Type 304 L structurally separated from the other ABWR Standard Plant buildings.
s hactor shield wall stabilizer The Seismic Category I structure within the
--tube sections ASTM A501 ABWR Standard Plant, other than the containment j
structures, that contains high-energy pipes are
--plates ASTM A36 j the reactor building and control building. The steam tunnel walls protect the reactor building Lower drywell floor fill A material other and control building from potential impact by material than limestone rupture of the high energy pipes. This building concrete is designed to accommodate the guard pipe support forces.
3.83.7 Testing and Inservice Inspection Requirements The reactor building, steam tunnel, residual heat removal (RHR) system, reactor water cleanup A formal program of testing and inservice in-(RWCU) system, and reactor core isolation cool-spection is not planned for the internal struc-ing (RCIC) system rooms are designed to handle t.res except the diaphragm floor, reactor pedes-the consequences of high energy pipe breaks.
tal, and lower drype!! access tuar. cts. The other The RHR, RCIC, and RWCU rooms are designed for internal structures are not directly related to differential compartment pressures, with the the functioning of the containment system; associated temperature rise and jet force.
therefore, no testing or inspection is performed.
Steam generated in the RHR compartment from the i
postulated pipe break exits to the steam tunnel i
Testing and inservice inspection of the dia-through blowout panels. The steam tunnel is phragm floor, reactor pedestal and lower drywell vented to the turbine building through the access tunnels are discussed in Subsection seismic interface restraint structure (SIRS).
3.8.1.7.
The steam tunnel, which contains several pipe-lines (e.g., main steam, feedwater, RHR), is al.
so designed for a compartment differential pres-sure with the associated temperature changes and jet force.
3840 Amendment 27 L
n
- - w
-4.
ABWR 23A6100AE
~
Standard Plant nrv, a f
Seismic Category I masonry walls are not used in the design. The ABWR Standard Plant does not contain seismic Category I pipelines buried in soil.
3.8.4.1 Descripties of the Structures 3.8.4.1.1 Reactor Building Structure Y
The reactor b Iding (RB) is constructed of reinforced concre e, WIN a steet trame roo@he g[.O RB has four stctries above the ground leve th ee stories below. Its shape is e of 59 meters ieThe taw airr.uig, meters is ii.. "-
- M: ~rgand a height of about 57.9 meters from the top of the basemat.
$$. [
h om,+F l
i 3.8-20.1
.l A-nd-me 29
ABM 2sastoore Standard Plant 4
REv n The Reinforced Concrete Containment Vessel The CB is a shear wall structure designed to (RCCV) in the center of the RB encloses the accomodate all seismic loads with its walls.
Reactor Pressure Vessel (RPV). The RCCV supports Therefore, frame members such as beams or the upper pool and is integrated with the RB columns are designed to accomodate deformations structure from the basemat up through the of the walls in case of earthquake conditions.
elevation of the RCCV top stab. The interior floors of the RB are also integrated with the The summary report for the control building RCCV wall. The RB has slabs and beams which join is in Appendix 3H.2. This report contains a the exterior wall Columns support the floor description of the control building, the loads, slabs and beams. The fuel pool girders are load combinations, reinforcement stresses, and integrated with the RCCV top slab e.nd with RB concrete reinforcement details for the base mat, wall. columns. The RB is a shear wall structure seismic walss, steam tunnel, and floors.
designed to accommodate all seismic loads with its walls. Therefore, frame members such as 3.8.4.1.3 Radwaste Building Substructure beams or columns are designed to accommodate deformations of the walls in case of earthquake The radwaste building substructure (RWB) is conditions, shown in Section 1.2.
m,,,4-The summary report for the reactor building is Th waste building is a reinforced in Appendix 3H.1. This report contains a coney te structure 60.4m by 41.2m by 29.5m description of the reactor building, the loads, high. The building consists of a below grade load combinations, reinforcement stresses, and substructure consisting of walls and slabs of concrete stresses at locations of interest. In reinforced concrete,1.2m thick, forming a rigid addition, the report contains reinforcement box structure which serves as a container to details for the basemat, seismic walls, and fuel hold radioactive waste in case of an accident.
pool girders.
This substructure is located below grade to increase shielding capability and to maximize 3.8.4.1.2 Control Building safety. It is supportc oper:rtf f 3, g.
foundation mat whose top is below grade. l The control building (CB) is located between In addition, a reinforced concrete su f4ner-the reactor building and the turbine building. structure 15.7m high extends above grade nd lA It is shown in Section 1.2.
houses the balance of the radwaste equipment.
b The CB houses the essential electrical, The radwaste building substructure houses the control and instrumentation equipment, the high and low conducivity tanks, clean up phase control room for the reactor and turbine separators, spend resin storage tanks, a buildings, the CB HVAC equipment, RB cooling concentrated waste storage tank, distillate tank water pumps and heat exchangers, the essential and associated filters, and pumps for the switchgear, essential battery rooms, and the radioactive liquid and solid waste treatreent steam tunnel, systems.
The CB is a Seismic Category I str cture that Although the radwaste superstructure is not a houses control eh and operatiqn personnel Seismic Category I structure, its major and is designegyeovide missile kad tornado structural concrete walls and slabs are designed protection. Therm is constructed of reinforced to resist Seismic Category I loads.
concreteffhi~a steel ronrfThe CB has two stories above the ground level and four stories The summary report for the radwaste building i
below. Its shape is a rectangle of 56 m (183 is in Appendix 3H.3. This report contains a feet,8 inches)66 the E-W directrolts24y (78 description of the radwaste building, the loads, feet,9 inches an une N-s aircoin=, and a load combinations, reinforcement stresses, and height of about 2 m (7) feet inches) from the concrete stresses at locations of interest. In top of the base mat.
\\
addition, the report contains reinforcement detailas for the basemat, seismic walls, and j
91 9/
floors.
1 8-21 I
Amendment 29
J ABWR 23xeiooxe 4
Standard Plant arv n differential of 6 mm of water, the reinforcing 3.8.5.1 Description of the Foundations steel is designed to remain clastic during the SSE load combinations.
The foundations of the reactor building and control building are reinforced concrete mat-3.8.4.5.1.2 Staterials Criteria foundations.
Refer to the materials criteria established in These two foundation mats are separated from 3.8.5 for the strength and materials requirements each other by a s.paration gap of 2 meters (6 for the reinforced concrete reactor building.
feet. 6 inches) wide to minimize the structural interaction between the buildings.
N 3.8.4.5.2 Control Building pp. (
The reactor bu f' ding foundat[on is a a
Structural acceptance criteria are defined in rectangular reinfor concrete mat hm (1&/8T l the ANSI /AISC-N690 and ACI 349 Codes. In no casefeet,8 inches) by m (19ffect, finches) and does the allowable stress exceed 0.9 F where 5.5m (18 feet) th
. The foundation mat is
^
F is the minimum specified yield strels. The constructed of cast-in-place conventionally design criteria preclude excessive deformation of reinforced concrete. It supports the reactor the building. The clearances between adjacent building, the containment structure, the reactor buildings are sufficient to prevent impact during pedestal, and other internal structures. The a seismic event. The tornado load analysis for top of the foundation mat is app:"- Yy 20.2 this building is the same as the analysis for the m(66 feet,3 inches) below grade, reactor building.
The containment structure foundation, defined 3.8.4.5.3 Radwaste Building Substructure as within the perimeter or the exterior surface of the containment structure, is integral with Structural acceptance criteria are defined in the reactor building foundation. The l ANSI /AISC-N690 and ACI 349 Codes. In no case containment foundation mat details are discussed does the allowable stress exceed 0.9F where in Subsection 3.8.1.1.1.
F is the minimum specified yield strels. The Jo design criteria preclude excessive deformation of TheIon, trol building foundation is 4
the building. The clearance between adjacent rectan lar reinforced concrete mat 24 m by 56 m buildings are sufficient to prevent impact during by 5. m. The top of the foundation mat is [
a seismic event.
m below grade.
3.8.4.5.4 Seismic Category I Cable Trays and The radwaste build foundation is a-h { %f. wksis rectangular reinforced, concrete mat 60.4m by Conduit Supports t
b er on is, se, lac 4ed 41.2m and 2.5m thick. The top of the radwaste i
' Structural acceptancegfriterlagre defined in building mat is
- 3. m below grade. The ANSI /AISC N690 Code. In no case does tt$ foundation mat is constructed of cast-in place allowable stress exceed F where F is conventionally reinforced concrete. It supports l
C the minimum specified yield tIress.
Y the radwaste building structure.
o. cf l
3.8.4.5.5 Seismic Category I HVAC Duct and The foundation for category 1 structures is Supports contained in the summary reports for their respective buildings. The reactor building
%y 9 foundation is contained in Appendiz 3H.1, the I
gg Structural acceptance criteria are defined in i ANSI /AISC.N690 Code. In no case does thel control building foundation is in Appendix 3H.2, 3'9 allowable stress exceed 0.9 F where F' is' and the radwaste building foundation is in I
~
the minimum specified yield stYess..
Appendix 3H.3. This summary report contains a.
-I section detailing safety f actors against 3.8.5 Foundations sliding, over turning, and floatation.
This section describes foundations for all 3.8.5.2 Applicable Codes, Standards and seismic Category I structures of the ABWR Specifications Standard Plant.
Amendment 2'9 38-17
c.
' insert g
?
- The structurab. acceptance criteria for HVAC ducts if.the analysis option is. selected..will be in accordance with ANSI /ASME AG-1 Code.
The HVAC supports'will be in accordance with ANSI /AISC-N690 Code.
P
'h s
I e
r J
F 2
,,N 4
~
ee w-w
--e
<