ML20035C332
| ML20035C332 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 04/02/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9304070068 | |
| Download: ML20035C332 (8) | |
Text
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g GE NucIcar Energy eenet ioc com;n 15 Cwtw Avenue, Swu Jose CA 9p?5 1
April 2,1993 Docket No. STN 52-001 Chet Poslusny, Senior Project Manager
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Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal '
Office of the Nuclear Reactor Regulation
Subject:
Submittai Supporting Accelerated ABWR Review Schedule - Chapters 3 and S DFSER Items
Dear Chet:
Attachment A addresses three DFSER items for close out: (1) Item 3.9.23-2 (Confirmatory),
on Page 3-64 of the DFSER, (2) Item 3.9.23-1 (COL Action), on Page 3-65, and (3) Item 5.2.4-1 (Confirmato.y), on Page 5-13.
Please provide a copy of this transmittal to Shou Hou, Dave Terao, Jim Brammer and Mark Rubin.
Sincerely, h*70 ack Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)
Tony James (GE)
Roy Imuison (GE)
Son Ninh (NRC)
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ATTACHMENT A.
April 2,1993 I
DFSER ITEMS (1) Item 3.9.2.3-2 (Confirmatorvt May 10.1992 Audit Commitments -
GE agreed to three items per the May 10,1992 Audit Summary. These items have been included for record as follows (a) Revise ITAAC Table 2.1.1 datedJanuary 17,1992 per Enclosure 3 of the audit i
summary. ITAAC submittal datedJune 1,1992 included the information.
(b) Include key dimensions, major design parameters and construction tolerances to the RPVS design description and ITAAC. ITAAC submittal dated June 1, 1992 included the information; Section 1.1 was referred to in RPVS ITAAC (Section 2.1.1) for major plant design parameters. The draft ofITAAC sections a
scheduled for resubmittal in the near future includes the parameters in Section i
2.1.1 per the attached markups.
(c) Update MPI 18NS07A03 list to include the referenced documents in the audit summary. The attached pages of MPL list have been updated accordingly, except for including References 7 and 12. Reference 7 (Katsuta Engineering Laboratory Report) was not an ABWR certification document; it was presented
+
for infonnation only. Reference 12 was a memo not suitable for the MPL.; the memo is a part of our design record file.
i (2) Item 3.9.2.3-1 (COL actiont Vibration Assessment Test Report In reference to the DFSER paragraph on Page 3-65, which contains this item, GE indicated in the audit that the test results from K6 Plant inJapan will be used,if available, for updating sibration prediction and planning the vibration test of the first
[
reactor constructed under certification. However, as documented in SSAR Section 3.9.7.1 on Page 3.9-45 (Amendment 23), the first COL applicant will meet all requirements of Regulatory Guide 1.20; this COL license information commitment is not predicated in any way upon having K6 Plant data available. Therefore, SSAR Section 3.9.7.1,3.9.. " or 3.9.2.4 need not be revised.
r (3) Item 5.2.4-1 (Confirmatorvt ITAAC - Add Discussion of PSI and 89 Code -
The following revised SSAR section addresses the issue of presenice inspection (PSI) in accordance with the 1989 edition of the Code as discussed in last paragraph on Page 5-13 of the DFSER. The SSAR Section 5.2.4 on Page 5.2-15.1 (Amendment 23) addresses the design to perform PSI and the Code edition to be used. The SSAR Section 5.2.6.2 on Page 5.2-28 (Amendment 26) requires COL applicants.a submit the complete plant-specific ISI/ PSI program.~ Tier 1 design description and 1TAAC include only mp level definitive information and not detailed COL action items; acrefore, the subject issues are not included in ITAAC Section 2.1.1, Reactor Pressure Vessel System.
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F A%htel ' A A
AIBWR Design Docum:nt D#
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2.1 Nuclear Steam Supply a'
2.1.1 Reactor Pressure Vessel System Design Description d
The Reactor Pressure Vessel (RPV) System consists of (1) the reactor pressure vessel and its appurtenances, supports and insulation, and (2) the reactor intemals enclosed by the vessel, excluding the core, in-cose nuclear.
o instrumentation, reactor internal pumps, and control rod drives.
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i The reactor coolant pressure boundary (RCPB) portion of the RPV System retains integrity as a radioactive material barrier during normal operation and following abnormal operational transients and design basis accidents (DBAs).
i Certain RPV internals suppon the core, flood the core during a DBA, and suppon instrumentation utilized during a DBA. Other RPV internals direct coolant flow, separate steam, hold material surveillancc specimens, and support i
instrumentation utilized for normal operation.
i The RPV System provides guidance and suppon for the control rod dnves (CRDs). It also admits and distributes the sodium pentaborate from the Standby
[
Liquid Control (SLC) System.
J The KPVSystem restrains the CRD in order to prevent the ejection of the control
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md connected with the CRD in the event of a postulr.ed failure of the RCPB 1
associated with the CRD housing. A restraint is also provided for the reactor internal pump (RIP) in order to prevent it from becoming a missile in case of a postulated failure of the RCPB associated with the reactor internal pump.
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The majokaplant design parameters are listed in Secdon 1.1 The configuration l
4 of the RPV System is shown on Figure 2.1.la, with key dimensions presented in Table 2.1.lb, and the acceptable vadations in these dimensions in Table 2.1.lc.
The RPVS parameters (postulated break areas) used in LOCA analyses are identified in Table 2.1.1d.
Reactor Pressure Vessel, Appurtenances, Supports andinsulation
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The reactor pressure vessel (RPV), as shown schematicallyin Figure 2.1.la,-
i consists of a vertical, cylindrical pressure vessel ofwelded construction, removable top head and head closure bolting and seals. The vesselincludes the cylindrical shell, flange, bottom head, reactor internal pump (RIP) casings,
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penetrations, brackets, nozzles, venturi shaped flow restrictors in the steam outlet nozzles, and the shroud suppor t, which includes the pump deck fonning the partition between the RIP suction and discharge. The shroud suppon is an assembly consisting of a shon vertical cylindrical shell, a horizontal annular
. 2.1
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ATTACHMENT A April 2,1993 DFSER ITEMS.
Pa y 3 i
i Table 2.1.le: Principal Plant Design Parameters Descripdon Value Rated Power (MWt)
_3,926 i
Rated steam flow rate, kg/hr at 215.6 C (FW temp) 7.64x106 4
Rated core coolant flow rate (kg/hr) 52.2x106 RCPB design pressure (kg/cm2 )
87.9 8
RCPB design temperature ( C) 302 Number of fuel assemblies 872 Number of control rods 205 Number ofinternal pumps 10 1
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e.1 iilTLEt-PLANT'SENERAL REOUIREMNTS DATE 92/03/20 PAGE' 4.:
- PROJECit'ASWR CERTIFICATION PROGRM
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PROJECT: ADwH CERTIFICATION PROGRM OATE 93/04/01 P A GE, '
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