ML20115J596
| ML20115J596 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/23/1992 |
| From: | William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-92499, NUDOCS 9210280263 | |
| Download: ML20115J596 (7) | |
Text
__
M Log # TXX-92499 fi1e # 10010 0-j 903.7 (clo) 903.9 (clo)
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Ref. # 10CfR50.55a TUELECTRIC u nnm j c.hm,Jr.
October 23, 1992 w,,,,,. v,, a,,,a,,,,
U. S.
Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
UNIT 2
+
DOCKET NO, 50-446 ADVANCE FSAR SUBMITTAL - UNIT 2 ASME CODE CASE USAGE Gentlemen:
The attachment to this letter provides an advar. cPSES FSAR submittal to facilitate NRC Staff review of the subject area in support of licensing Unit 2.
The attachment is organized as follows:
1.
A descriptic.a/ justification of each change.
2, A copy of the revised FSAR pages (changes are indicated in the margin by the word ' draft").
The attached material will be incorporated in CPSES TSAR Amendment 87 which is currently scheduled for December, 1992.
If you nave any questions regarding this submittal, please contact Mr. Carl Corbin at (214) 812-8859.
Sincerely, W
h-
) h.
William J, Cahill, Jr.
By:
M Roger D. Walker Manager of Regulatory Affairs for NEO CBC Attachment c-Mr. J. L. Mi'hoan, Region IV Resident inspectors, CPSES '2)
Mr. T, A,. Bergman, NRR Mr. B. E. Holian, NRR
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l ATTACHME T to TXX-92499 PAGE 1 OF 6 DETAILED DESCRIPTION FSAR Page (a1 amended)
Description 3.7B-4 2
Added the required details concerning usage of ASME Code Case N-411 for Unit 2.
Update In accordance with the provisions of Regulatory Guide 1.84, the required details are provided regarding the usage of Code Case N-411 for Unit 2.
FSAR Change Request Number : SA-92-781.1 Commitment Register Number :
Related SER : 3.7.1 SSER :25 SER/SSER Impact
- No 3.9N-76 2
Added the required details concerning usage of ASME Code ran :-318 for Unit 2.
Update In accordance with the provisions of Regulatory Guide 1.84. the required details are provided regarding the usage of Code Case N-318 for Unit 2.
FSAR Change Request Number SA-92-805.1 Commitment Register Number :
Related SER : 3.9.3 SSER :25 SER/SSER 1mpact
- No Table 3.98-1F 2
Added the required details concerning usage of ASME Code Case N-318 for Unit 2.
Update In accor
.e with the provisions of Regulatory Guide 1.84, ti. required details are provided regarding the usage of Code Case N-318 for Unit 2.
FSAR Change Request Number : SA-92-781.2 Commitment Register Number :
Related SER : 3.9.3 SSER :25 SER/SSER Impact
- No Table 3.98-1F 2
Added the required details concerning usage of ASME Code Case N-318 for Unit 2.
Update In accardance with the provisions of Regulatory Guide 1.84, the required details are provided regarding the usage of Code Case N-318 for Unit 2.
FSAR Change Request Number SA-92-805.2 Commitment Register Number.
Related SER : 3.9.3 SSER :25 SER/SSER impact No
ATTACHMENT'to TXX-92499 CPSES/FSAR PAGE 2.0F 6 3.78.1.3 Critical Damoina values The specific percentages of critical damping values used for Category I structures, systems, and components are based on the materials, stress levels, and type of connections of the particular structure or component.
They'are determined in accordance with the recommendations-77 of NRC Regulatory Guide 1.61 and Reference (141 For riping systems analyzed by the response spectrum method, ASFE Code Case N-411 damping values may also be used in lieu of the camping values in Regulatory Guide 1.61.
Structure and component damping values used in the response spectrum-ORAFT and time history analyses are given in Table 3.78-1.
With the exception of piping stress analysis problem number 1 081, all non-NSSS piping stress analysis of safety related piping at CpSES uti'izes Code Case N-411.
This includes all analysis of new piping and support 78 optimization work, as well as all pipe stress reconciliation work.
Damping factors associated with foundation springs are discussed in 78 Section 3.78.2.4. Damping values used for qualifying Westinghouse piping and equipment are shown in Section 3.7N.
3.78.1.4 Succortina Media for Seismic Cateaorv I Structures All. seismic Category I structures are founded on the firm, unweathered Glen Rose Limestone which constitutes the principal bedrock formation on the site.
Below the Glen Rose unit lies the Twin Mountains-Formation, which forms a gradational contact with the Glen Rose unit and is composed principally of sandstone, limestone, and clay stone.
The portion of the Glen Rose unit which provides the founding material for the Category I structures consists of argillaceous limestone with lenses and zones of calcereous clay stone. Approximately 150 to 160 ft of Draft Version 3.78-4
ATTACHMENT to TXX-92499 CPSES/FSAR PAGE 3,0F 6 3.9N.3.1.1 Design Loading Combinat!ons The design loading combinations for ASME Code Class 2 and 3 components and supports are given in Table 3.9N-4.
The design loading combinations are categorized with respect to normal, upset, emergency, and faulted conditions.
Stress limits for each of the loading combinations are cocponeni. oriented and are presented in Tables 3.9H-5, 3.9N-6, 3.9N-7, and 3.9N-8 for tanks, inacthe* pumps, active pumps, and valves, respectively. Active ** pumps and valves are discussed in Section 3.9N.3.2 The component supports are designed in DRAFT accordance with the ASME Code,Section III Subsection NF. Details regarding the application and usages of Code Case N-318 are as listed in Table 3.98-1F.
For core support structures, design loading conditions are given 'n Section 4.2.2.3.
Loading conditions are discussed in Section 4.2.2.4.
In general, for reactor internals components and for core support structures the criteria for acceptability in regard to mechanirsl integrity analyses are that adequate core cooling and core shutdown must be assured. This implies that the deformation of the reactor internals must be sufficiently small so that the geometry remains substantially intact.
Consequently, the limitations established on the internals are concerned principally with the maximum allowable deflections and stability of the parts in addition to a stress criterion to assure integrity of the components.
Inactive components are those whose operability are not relied upon to perform a safety function during the transients or events considered in the respective operating condition category.
Active components are those whose operability is relied upon to perform a safety function (as well as reactor shutdown function) during the transients or events considered in the respective operating condition categories.
Oraft Version 3.9N-76
ATTACHMENT to TXX-92499
^
CPSES/FSAR TABLE 3.98-1F (Sheet 2)
USES OF CODE CASE N-318 NUMBER OF PIPE SUPPORT MARK NUMBER TYPE OF WELD SIDES WELDED 78 AF-1-102-107-S33R FILLET THREE 78 FW-1-017-717-SS25 FILLET THREE 78 FW-1-102-700-C62R FILLET TWO 78 CT-1-013-405-C82S FILLET THREE 78 CC-1-050-701-A43R PARTIAL PENETRATION THREE 78 CT-1-074-411-C82R FILLET TWO 78 CT-1-039-443-C42K FILLET TWO 78 FW-2-018-441-C72R FULL PENETRATION TWO DRAFT AF-2-006-402-S33R FILLET THREE DRAFT CT-2-046-015-C92K FILLET THREE ORAFT CT-2-013-432-C52S FILLET THREE Dr iFT CT-2-013-403-C72S FILLET THREE DRAFT CT-2-013-442-C82S FILLET THREE DRAFT-CC-2-195-408-C52R FILLET TWO DRAFT CC-2-077-403-S43S FILLET TWO DRAFT SI-2-095-403-S42R FILLET TWO 0 RAFT H-FW-2-SB-023-003-5 FILLET TWO ORAFT H-PS-2-RB-007-011-2 FILLET TWO ORAFT
-H-MS-2-RB-011-005-2 FILLET TWO DRAFT SI-2-051-415-C42K FILLET TWO ORAFT SI-2-051-421-C42R FILLET THREE DRAFT SI-2-095-415-C42R FILLET THREE DRAFT.
SI-2-087-416-C42K FILLET TWO DRAFT SI-2-306-404-C42R FILLET TWO DRAFT SI-2-306-416-C42R FILLET TWO DRAFT SI-2-306-420-C42R FILLET 1HREE DRAFT Draf t Vers ion
.A7TACHMENT to 7XX-92499.
-PAGE 5 0F 6 CPSES/FSAR TABLE 3.9B-1F (Sheet 3)
"cES OF CODE CASE N-318 NUMEER OF PIPE SUPPORT MARK NUMBER TYPE OF WELO SIDES WELDE0 78 CS-2-001-45d :42S FILLET TWO ORAFT CS-2-079-408-C425 FILLET TWO ORAFT CS-2-079-409-C42S FILLET TWO ORAFT CS-2-RB-022-703-2 FILLET TWO ORAFT CS-2-079-431-C42K PARTIAL PENETRATION TWO,
ORAFT CS-2-RB-003-709-2 FILLET TWO ORAFT PS-2-RB-024-003-2 FILLET TWO ORAFT H-CH-2-SB-051-007-3 FILLET
.THREE DRAFT H-CH-2-SB-051-008-3 FILLET THREE DRAFT H-CH-2-SB-041-017-E FILLET THREE
-ORAFT H-CH-2-SB-04' -010-3 FILLET THREE DRAFT d
H-CH-2-SB-044-009-3 FILLET THREE DRAFT H-CH-2-SB-039-001-3 FILLET THREE ORAFT H-CH-2-SB-043-011-3 FILLET TWO ORAFT H-CH-2-SB-044-006-3 FILLET TWO ORAFT H-CH-2-SB-044-007-3 FILLET TWO ORAFT-t H-CH-2-SB-046-003-3 FILLET TWO ORAFT H-CH-2-SB-046-009-3 FILLET TWO ORAFT j-H-RC-2-SB-007-001-3 FILLET TWO ORAFT H-RC-2-AB-001-016-3 FILLET TWO 0 RAFT H-PS-2-RB-017-007-2 FILLET TWO-ORAFT H-CH-2-SB-043-012-3 FILLET TWO ORAFT H-CH-2-SB-044-003-3 FILLET TWO ORAFT H-CH-2-SB-046-007-3 FILLET TWO ORAFT' i
Oraft-Version
. ATTACHMENT to TC-92499 PAGE.6 0F 6 CPSES/FSAR TABLE 3.9B-1F (Sheet 4) t USES OF CODE CASE N-318 1
1 NUMBER OF PIPE SUPPORT MARK L'<BER TYPE OF WELD SIDES WELDED 78 H-PS-2-RB-010-003-2 FILLET TWO URAFT j
H-PS-2-RB-010-014-2 FILLET TWO ORAFT H-PS-2-RB-010-016-2 FILLET TWO ORAFT RC-2-097-403-C865 FILLET TWO ORAFT I
RC-2-115-417-C765 FILLET I'WO ORAFT RC-2-115-419-C66K FILLET THREE.
ORAFT H-RC-2-SB-007-001-3 FILLET TWO ORAFT H-RC-2-AB-001-016-3 FILLET TWO ORAFT Draft Version
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