ML17193B297
| ML17193B297 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/03/1981 |
| From: | Janecek R COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17193B298 | List: |
| References | |
| NUDOCS 8104090484 | |
| Download: ML17193B297 (2) | |
Text
Commonwealt9dison One First Nationr;il Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 April 3, 1981
- Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Dresden Station Unit 3 Proposed Amendment to Appendix A, Technical Specifications, to Facility Operating License DPR-25
'NRC-Docket-No~*50~249- * - - * - *
- Reference (a):
R. F. Janecek letter to H. R. Denton dated April l, 1981.
Dear Mr. Denton:
Reference (a) transmitted a request for amendment to the Technical Specifications for Dresden Unit 3 to remove as many as three safety-related s~ubbers from the HPCI system piping.
As committed to in Reference (a), the following additional information provides further definition and support for _the requested amendment.
Our detailed system stress analysis has indicated that all three (3) snubbers, numbers 18, 19 and 20 in.Technical Specification Table 3.6.l, need to be Yemoved.
Attached is a revised page 9le w h i c h i n c l u d e s t h,e >S n u b b e r r em o v a l s
- The three snubbers are attac~ed to the *piping at the same location.
Stress analysis of the existing system indicated that with the snubbers present, the local stress at the snubber-to-pipe attachment was greater than the material ultimate' stress of 60,000 psi.
Following removal of the snubbers, the maximum piping stress due to seismic loads is reduced to below the IE Bulletin 79-14 operability limit.
Please address any additional questions concerning this matter to this office.
~ery truly yours,
~'-**JUA/
~~---'c..-~~~~~~~~~~-
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Robert F. Janecek cc:
Rill Inspector - Dresden
{
l996B 810409013'1
.Nuclear Licensing Administrator Boiling Water Reactors
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Table 3.6.1 (Continued)
SAFETY RELATED SHOCK......... t'PRESSORS (SNUBBERS)
Snubber No.
13 14 15 16 17 I 18 19 20 21 22 23 24 25 26 27 28 29 30 31
.32 33 34 35 1
2 3
Snubber in High_*
Radiation Area Location Elevation Azimuth During Shutdown_
- 0:-ywell Recirc. ~1ne 201::3-28" 507' 305°
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Dr;r.1ell Recirc. Lino *2c1A-28 11 507' 105° DrY1.1dl LPCI Line 1506-16 11 513'
-2~6° I.
Drywcll LPCI Line 1519-16" 513*
95° x
D r\\'~1e 11 :te ci re *
\\ Header ?.01B-22" 533 1611 195° I.
Rerroved Removed Rerroved 22° Di*yWcll ReciI-c. Header ?OlA-22 11 533 16 11
- {
Dr:i-wcll HPCI Line 2 J05-J 0 11 550' 121°
- (
Drywell Cle:inup Line 1201-8 11 537 16 11 e4°
- {
llrywcll Feed:-1a ter Line )20!'1)-12 11 5J8' 106°
- l.
Dr.)-...itill Cleanup Line 1201-8" 537 1611 78°
.t.
Orywcll Feed.,.ater Line 3::?0!µ\\-18" 537 16 11 66° Dc~....:ell Cleanup Line 120l-8i1 53[}16 11 60° Drywell Feed~nter Line )204C-12 11 540 1 73°
'/.
231° DryH:!ll Core Spray Line lll04-10 11 573' x
Dr;,*well Core Spt*ay Line 140)-10" 563' JJ6°
- x ur;r*;ell HPCI Line 2305-10" 56)'
140° x
Drywcll Target Rock Valve 203-JA 542 16 11 14°
"(
Drywell Tnrcet Rock Valve 203-)A 542 12 11 31° x
Dry:1cll Target Rock Valve 203-JA 540' 19° x
Dryucll TarGet Rock Valve 203-JA 540 16 11 34° x
Isolation Condenser Pipew3y*nooms Iso. Cond. Line 1303-12 11 558*
180° x
Is6. Cond. Line 1303-1211 568' 180° 1
Iso~ Cond. Line 1302-141 580 1
-195°
- :c
- Modifications to this table due to changes in high radiation should be submitted to.the NRC as part of the next license amendment request.
- Snubbers Inacces~lhlo Diid113 llor.rr,al Operations x x x*
x x
- 1. x x
x x x
- c x
x x x x x x*
x x x x
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Snubbera..
Accessible During Nonr,al Opor::itic'f'\\S
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