ML20100M656
| ML20100M656 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/28/1985 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| FVY-85-32, NUDOCS 8504170688 | |
| Download: ML20100M656 (5) | |
Text
.
VERMONT YANKEE NUCLEAR POWER CORPORATION FVY 85-32 RD 5, Box 169 Ferry Road, Brattleboro, VT 05301 nEs tv To:
g ENGINEERING OFFICE
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1671 WORCESTER HOAD FRAMINGHAM MA3SACHt/SETTS 31701 TELEPHON E 617-872-4100 March 28, 1985 United States Nuclear Regulatory Commission Washington, D..C.
20555 Attention:
Office of Nuclear Reactor Regulation Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing Beferences:
(a)
License No. DPR-28 (Docket No. 50-271)
(b)
Letter, VYNPC to USNRC, WVY 80-106, dated July 25, 1980 (c)
Letter, VYNPC to USNRC, FVY 83-16, dated March 1, L933 (d)
Letter, USNRC to All Licensees, I&E Bulletin 79-02, dated March 8, 1979 (e)
Letter, USNRC to All Ticensees, I&E Bulleti-79-14, dated July 2, 1979 (f)
Letter, VYNPC to USNRC, FVY 84-67, dated June 27, 1994 (g)
Letter, VYNPC to USNRC, FVY 85-06, dated January 2.1, 1985
Subject:
Vermont Yankee Seismic Reanalysis Progran - Status and Results of Small Bore Pipe Support Testing Program
Dear Sir:
As part of Vermont Yankee's Seismic Reanalysis Program (SRP) [ References (b, c, f, and g)] to upgrade the safety class piping systems, we have instituted a small bore pipe suppert' testing program. The prelhninary details, methodology, factors of safety, etc., associated with. this tenting program have been discussed with Dr. John Fair of the Office of Inspection and Enfcrcement. The purpose of this letter is to provide preliminary results of the small bore pipe support testing progran.
Vermont Yankee has adopted a procedure which allows for a test load (determined by piping analysis and including dead weight, thermal, seit:mic, and-any other transient or dynamic loading conditions) to be applied directly to the pipe support at the point (s) where the piping is attached. Therie test loads are applied simultaneously (where the support has more than ene restraining direction) and have an increase factor of 1.1 times the analyzed design load.. Ioad(s) may also be applied in the reverse direction to account for worst case on the base plate and bolts (see Figures 1 and 2).
8504170608 850328 DR ADOCK 05000271 k00h p
PDR I
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- United States Nuclear Regulator Commission March 28, 1985 Attention:
Mr. Domenic B. Vassallo Page 2
.We have tested.13 small bore supports using this technique. Results of this testing thus far are very favorable with a 100% pass rate for the_ initial 13 supports tested (see Table 1), and we intend to expand our program to
. qualify all small-bore pipe supports. Our qualification program employes a staeistical sampling technique similar to the Bechtel Power Corporation's Statistical Sampling Program to Test Concrete Expansion Bolts (SFPD-7902-8) to
.; assure statistical acceptability.of the small bore supports.
In addition, we are investigating the possibility of testing some large diameter pipe " dead weight"-supports.
We will notify you in May 1985 of the results of our expanded pipe test program and its impact on our Seismic Reanalysis Program.
We trust.that this information is deemed acceptable; however, should you
. have'any questions or require additional information regarding this matter,
- please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWEP CORPORATION f,/
i R.W. Capstick Licensing Engineer N
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Figure 1 cal-lBRATED LCAD CELL.
(08 SPR/MG GAUGE)
(7YPAl )
-7reica susu sose P/PE SUPPORT
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~ STRA PS A/OTE:
FOR A TYP/ CAL TWO
- ANC//OR
~ IMA Y RESTRA ///7 BOL7~
AS 5/f0WN, TEST 40405
'(7yg) f' ARE APPUED S/MULTAN-o: fl}\\
sousLY, ZF SUFFCR7
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[AM W/TMSTAND 7WE
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.7E57 LOADS 70 AC4EFTASLS CA/TER/A A/0 FURTHEK CALCULA7/ONS
' 02 MOD /f/CA7/0NS A/EED BE PERFCKMED-
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U APPLIEC>
LOAD 4
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Figure 2 TEST Ch bGAb%JElGW-y,13..:
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h TYPICAL.
DEADWElGMT SLIPPCE?T.
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[r5Nt TEST.
- l. D19COMMECT Eob
- c. ArTTACM WIR E
- 6. APPLY. TEST LDAD.
J. DccuME.NT R E=.JLILTs.
TMsT LoAb.
- >q M.com u
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SYSTEM LOADS FAIL Fxf=151 RCIC - H93 RCIC-145 P
Fz
=
RCIC - HD93A
.RCIC Fy = -168 P
g Flat = 68
F2
& 33
=
i RCIC - HD93.
.Fy = -130 P
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Flat = 18 RCIC - HD93D RCIC Fy =--1.1
.P Flat = 6 RCIC
-HD94A RCIC Fy = -92 P
.HPCI - H66-HPCI Fy = -154, P
Fx = -287
'Fy = -264,'
Fx = -514
. HPCI - HD66B
'HPCI Fx = 153 P
Fz = 42E Fy=-2g3'
'P HPCI - HD66C HPCI Fx = 53 Fy=-11(('
Fz = 132' Fy=-4f HPCI - HD66C HPCI P
-Fy = -21 P
- Two Support Incations
'l RCIC - Reactor Core Isolation Cooling (System)
HPCI -- High Pressure Coolant Injection '(System)
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