ML20246L675
| ML20246L675 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/31/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89641, NUDOCS 8909070021 | |
| Download: ML20246L675 (25) | |
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MEE Log.'# TXX-89641-C File # 10010 C
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903.9-7UELECTRIC -
Ref. # 10CFR50.34(b)
August 31, 1989-
' Executive Yke Presidens -
U. S. Nuclear'Regulutory Commission
. Attn: Document'Contr01 Desk
- Washington, D.-~C.
20555.
n
' COMANCHE PEAK STEAM ELECTRIC. STATION (CPSES)
SUBJECT.:
DOCKET NOS. 50-445 AND 50-446 ADVANCE FSAR SUBMITTAL REACTOR: COOLANT SYSTEM (RCS) PIPING AND PIPING SUPPORT STRESS TABLES y.
Gentlemen:
This. letter provides an advance copy of a change to be included in a future FSAR amendment This change incorporates updated information on RCS piping
!and piping support. stress as a result of final as-built reconciliation.
In order to' facilitate NRC' staff review of this change, the attachment is organized as follows:
1.
' Draft revised FSAR tables, with changed portions indicated by.a bar
-in the margin, as they.are to appear in a future amendment.
't 2.
A detailed description / justification for the change.
3.
A copy of the related SER section.
4.
A page containing the title of a " bullet" which consolidates and
- categorizes similar individual changes by subject and related SER section.
3 078 4
I i
890907002" 890831 PDR ADOCK 0500o445 PDC 4M North Olive Street LB 81 Dallas, Texas 75201
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.TXX-89641-31, 1999
August Page-2'of 2
. 5'. -
.The marked up version.of the revised FSAR pages referenced by.the-
~
detailed description /. justification for the changes identified above.
The marked up version facilitates review of the revisionL by clearly identifying-the changes to the-current FSAR amendment, s
Sincerely, Y
1
)
William J. Cahill, Jr.
sy:-
47 he R. DI Walker Manager, Nuclear Licensing HAM /smp
' Attachment c-- Mr. R. D. Martin, Region IV
-Resident Inspectors, CPSES (3) l l
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Attachment to TXX-89641 August 31, 1989 Advance FSAR Submittal Concerning Reactor Coolant System (RCS)
Piping and Piping Support Stress Tables Item 1 Draft Revised FSAR Tables 2-10 Item 2 Detailed Description / Justification 11 for Changes Item 3 Related SER Section 12 Item 4 Bullet. Title 13 Item 5 Hars d Up Version of 14-23 Revised FSAR Tables
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Attachm;nt to TXX-89641 91
'Page 8 of 23.
p TABLE 3.9N-18 PRiffARY PTPE RESTRAINT LOADS AND STRESSES Stresses Loading Load (Pct.of-Restraints Condition (kids)
Allowable)
Crossover leg bumper.
Upset SG side Faulted-
[a]
Crossover leg bumper.
Upset RCP side Faulted
[a]
Crossover leg vertical Upset run-Faulted
[a3 77 Steam generator inlet Upset Faulted
[a]
Primary shield wall (hot leg)-
Faulted
[a]
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-(cold leg)
Faulted
[a]
~
i I
[a] The postulated break dynamic effects associated with the primary pipe whip restraints are no longer required to be considered as justified L
'by leak-before-break application to the primary coolant loop piping.
AMENDMENT 77 SEPTEMBER 8,1989
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%ttachzent to TXX-89641 DETAILED. DESCRIPTION Page 11 of FSAR.Page (as amended)
Group Description
. Tab 1e'3.9N-14. 15 2-
'See Sheet No(s): Tables 3.9N-16, 17, 19 and 21 Tables.are updated as a result of final as-built veri-ficaticn and~ stress reconciliation of-Reactor Coolant Loop piping and piping supports.
Update:
Tables updated reflect the completion of verifying the design analysis is consistent with the as constructed piping, pipe support configuration and design bases of-the plant.
FSAR Change Request Number: 89-450.1 Related SER Section: 3.9.3:. SSER21 3.6.1 SER/SSER Impact: No Table 3.9N-18
'4 Clarification that Primary pipe whip restraints are no longer required since Primary Coolant Loop pipe breaks are no longer postulated.
Clarification:
Table is clarified to explicitly note that the Primary pipe whip restraints are no longer required due to ap-plication of Leak-Before-Break (LBB) in accordance with.
General Design Criteria (GDC) 4.
FSAR Change Request Number:.89-450.2 Related SER Section: 3.9.3:
SSER21 3.6.1 SER/SSER Impact: No
______.________________]
y Attachrsent to TXX-89641 t'
' Piga 12 of 23
-expected when plant shutdown is required.
The specified component operability assurance test program comolies with SRP_Section 3.9.3 and satisfies the applicaele portions of GCC 1, 2, and 4.
3.9.3.3 Design and Installation of Pressure Relief Devices The staff has"rtvi d ed th? desi;n and installation critarin ecolicacia to tre mounting of pressur2 reliaf davicas (scfe:y and relief valves) for.. 2 over-pressure protection o.f ASME Class 1, 2, and 3 components.
The ecolican: nas provided an acecuate cascription of the calculation procedures and coccuter programs used in the analyses and design for both closed and open cisenarge systemst Information relating to the various design and service loading conditions and combinations thereof, as well as the corresponding stress-criteria used in the design of the mounting of pressure relief' devices, has been provided.
The method of evaluating the structural response of tne piping and support system stiffness in the dynamic analysis of these mountings has also been discussed.
The design criteria specifi2d by the applicant are consistent with those provided in Regulatory Guide 1.67.
Stress computation and stress libits ire in accord with applicable rules of the Code.
The design and installation proceoures comply with SRp Section 3.9.3 and satisfy tne applicable portions of GDC 1, 2, and 4.
3.9.3.4 Component Supports The review of information submitted by the caplicant includes an evaluation of Code Class 1, 2, and 3 component supports.
The review includes an assessment of the cetign and structural integrity of the suppcrts and their effect on tne operability of active components.
The review addresses three types of supports and their function:
plate and shell, l'inear, and component standard.
The specified design and service loading combinations used for the design of ASME Code Class 1, 2, and 3 component supports in systems classified as seismic Category I provide assurance that, in the event of an earthquake or other service loading caused by postulated events or system-operating transients, the resulting combined stresses imposed on system components will not exceed allowable stress and strain limits for the materials of construction.
Limiting the stresses under such loading combinations provides a conservative basis for the design of support components to' withstand the most adverse combination of loading events without loss of structural integrity re supported component operability.
The design and service load combinati;c; and associated stress and deformation limits specified for ASME Code Class 1, 2, and 3 component supports c;omply with SRP Section 3.9.3 and satisfy the applicable portions of GDC 1, 2, and 4.
3.9.4 Control Rod Drive Systems The staff's review under SRP Section 3.9.4 covered the design of the hydraulic control rod drive system up to its interface with the control rods.
The staff reviewed the analyses and tests performed to ensure the structural integrity and operability of this system during normal operation and under accident conditions.
The staff also reviewed the life-cycle testing program to demonstra:2!
the reliability of the control red system over its 40 years of life.
3-25
"Ai"
.httach ent~to TXX-89641 7
- P,8gef13 of 23"
,7. -
.3.9.3' ASME' Code Class 1. 2 and 3 Components. Component Suncorts and Core Suncort Structures v
. EMEB
- 21. - The FSAR has: updated the. reactor coolant system support
.and' piping stress tables of Section:3.9N (Tables 3.9N-14.
>through 3.9N-19 and 3.9N-21).
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'Attachhnt to TXX-89641 TABLE 3.9N-18.
f
,,P%g2 21 of 23.
l PRIMARY PIPE RESTRAINT LOADS AND STRESSES a]
Stresses Loading Load (Pct of Restraint Condition (kips)
Allowable)
Crossover leg bumper, Upset SG side Faulted Crossover leg bumper, Upset RCP side Faulted
-Crossove-leg vertical Upset (g7 run Faulted Steam generator. inlet Upset Faulted Primary; shield wall 76 (hot leg)
Faulted C#3 Primary shield wall (cold leg)
Faulted
[a] The postulated break dynamic effects associated with the primary pipe whip restraints are no longer required to be considered as justified by leak-before-break application to the primary coolant loop
.P ping.
i Amendment 76 May 1, 1989
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