ML20092N682
| ML20092N682 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/29/1984 |
| From: | Sinclair J VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| FVY-84-60, NUDOCS 8407030425 | |
| Download: ML20092N682 (5) | |
Text
.
4 VERMONT YANKEE NUCLEAR POWER CORPORATION RD 5. Box 169, Ferry Road, Brattleboro, VT 05301 y,,,,
June 29, 1984 ENGINEERING OFFICE 1671 WORCESTER ROAD w
FVY 84-60 FRAMINGHAM, MASSACHUSETTS 01701 TELEPHONE 617-872-8100 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
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b) Letter, VYNPC to USNRC, FVY 84-45, dated May 15, 1984
Subject:
Vermont Yankee Recirculation and Residual Heat Removal (RHR)
Weld Joint Inspection Program for the 1984 Refueling Outage
Dear Sir:
By letter dated May 15, 1984, [ Reference (b)], we forwarded you supplemental information regarding the structural adequacy of weld joint overlays applied during our 1983 refueling outage for a second cycle of operation. The May 15 submittal included a reference to General Electric (GE)
Report No. 22A2615 entitled, " Design Report - Recirculation System - Vermont Yankee Nuclear Power Station ANSI B31.1 Calculations".
During recent conference calls with members of your staff, we were requested to forward you the pertinent pages of the report for your review.
These pages are provided as Enclosure 1.
It should be noted that results of the GE report were used as supporting documentation for the basis of Appendix C-2.6, " Recirculation Loop Piping" and Section 4.3.1, " Reactor Recirculation System" to the Vermont Yankee Final Safety Analysis Report (FSAR).
We trust that this information is deemed acceptable; however, should you have any questions regarding this matter, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION
.s. ps J. B. Sinclair l
Licensing Engineer JBS/kg Enclosure 8407030425 840629 PDR ADOCK 05000271 PDR 0
li'
t e
Enclosure I 4
1 j
y'o %.
- - - r*.
.St A2615 i l
==A_
.=ve ne se w - 9 '
1 1
t 1
l f
f i
DESIGN REFOsf,
i RECIRCUIATICII ST8 Tat 1
1 VluGI0ir! 1ANKEE NUCLEAa POWEa STATICII ANSI m31.1 CALCULATIONS i
I FREPARED BY 3"*?
@ /A*2D r
Engineering Assistant Cc. h =w 5-n-no -
t..
l b * /M* YO Oftb APPROVID BY l
earlso asstan smetussatus I
f a
{
t l
t k
Arome pousa aqutneurt asrAatusst l
causaAL stsctalC COMNNT 173 CIRImsa AVSNIE SAs J0st, calif 0ElitA l
l l
t I
^
j i
.vERnouf YANggg #'NEClkC
~
'O
- 8 L osAs 831.1 A'4ALy5 tl l
10 T
' INERTIA I
l 13 47 11.Su/ 70 939, 463.8 D7 *8M fg Sg
- i t.,.
I nA na MG l
1 yyggg[
MOHkNISs
- 34439, 53 e
4 SSAD(OAD MOMkNTSs 7g.
- 272000, 190300.
PRIMARY SEISMIC MOMtMT58 t
.439*
- getto,
/4174 i SECONDAMV SEllu1C MomkNT5s l
STHkSS RATIO s
72b4 H.503 PRIMAkV STMkSS thTENSti!LS
'DEADLOAD + PHESSUREDEADLOAD + PRESSURE
- SElsMIC'
. s
.14543.
c.!58 _
l
~'
t
!i s
19554.
u.$75 I
I S. SECONDARY SIRkSS RANGE THERnAL e
16835.
0.919 l
THERMAL
- hECO*.UARY sk!SMIC
- C. PRja9ANY PLUh SECON ARY STRESS N ANhE s
22788.
u.549 DEADLOAD + PRESSURE
- THERNAL e
33240.
u.444 DEADLOAD + PRESSURE
- SEISMIC
- THENHAL j
2
- 9. RARE EVENTS-PN! MARY STkSS LIMIT 17312.
~
i t
7 ALLOWAhLF'sTHE55 s SIMkSS NATIO ELFSilC FVFLUATED PRIMARY STNESSES AS SHOWN BELOW i
i 1 E 1)P40)10E-4 hf sieh 29924 0,998
- EMERGENCY CONDIT10NS0EADLOAD + PRESSURE + DOU 56si,sii 17439, cesst I...
(
/,
DEADLOAD + MAN. PRhSSURE
- PRIMARY SEISMIC i
i i
rAULTED Cof401T10NS 1 E-3)P40>10E-6 DFAULOAD + HAX. PREShuRE e DOUBLE PHIHANY SEISMIC blsi.44 27201 CeWSE l
i
't I
f i
I t
4 2,2 k *d b I
/${
ff6 C.
t
~
1 as
W
..c.-
'1,p gr* yw{ CHAMEE,,WISEh8 LOOP Ae8
. ) f..: i
..tlT TkE'- NECIYC
~- -
. ~
.9
.. -usa b.,rqM4Lvss 4014T SQs.
IVFL 00 10 T
jNENT14 2
y 349 ~
1bL SML 12.56/. t&.59/
0 930 463.e 67.496
~14h
~
n "/-
Mk hG i
s MA THERMAL M0t*kHTSs 4643J.
3696J0.
4296 0 t,.
DEADLOAD MOMkNTSs
- 6015, 21740 41s1",
PRIMARY Sk15Mic HOMENTSs 2556e.
191000.
/ttne.
SEC040ANY hE18MIC MOMkNTSa-925u.
44120 71134 v,
STNtSS NATIO PR!t'ANY WTHkSS INTENSITIES s
7728.
4.534 MAK0AD
- PRESEURE'"~ADLOAD + PRESSURE + SEtsMIC
=
14201 0.763
- 9. Stf.ONDARY 51RE85 RANGE e
20544.
0 76e THERMAL a
22739.
0 701 r,
THERMAL * $ECONDARY SEISMIC i-S. PRIMANY PLub SECONARY STHESS MANGE
=
28269.
b.683 DEADLOAD e PRESSURE. THERMAL a
39131.
0.706 DE ADLOAD + PRESSURE
- SEISMIC
- THhMMAL
- f. RARF EVENTS-PRIMARY STkSS LIMIT 17312 ALLOWASLE STRESS :
SINkSS NAfl0 ELESf!C EVgLUATED PRIMARY STRESSES AS SHOWN BELOW EMER6kHCYiC0hD1T10rS 1.E-1)P4U)10h-3 g
DEADLOAD + PRESSURE + (J0UBLE PNIMAhY SklSMIC SF e i,ht-18939, C,739 f
DFADLOAD e MAX. PRESSURE
- PRIMARY SEISMIC W si,sa. 14474.
- . 649 i
FAULTED CONQlf!ONS 1..E-J)P40)10E-6 DEADLCAD + tlAN. PRESSURE
- 0008LE PHIMANY SEISt*1C SFs1.J6 80205.
9,797 3
l l
1
.O...
! u4
/77...
m.
O
7 t
vee ' e ganske v aktinc sticHa'nuEHI5kksL60eaAs 82A26I5 M
.4 494,vsle t.
.?
- r.S.L...n g Case on;
~' vee.
ou in i.
gukNt:4
. 14.212 t
4 EML 13.481 11 581 u.46/
49.e
. Sg$
8e 4
p 4451W58 t
let e,4_99 g na HM HC l
fageng
'n04Nfse 121991.
14249 Lativo:.
[
3843LS&g M0%N18e '
9151.
stres.
4136.
j pag 4AN9 SklSMIC MonkNYSe 17106.
65720.
1440#,
SEC0aga#v SElle!C N44ENT5s 1 J 5 0.'.
5860 J y14 t.,
5TRE55 RATIO I
painaevtramSSpdt=51:ss5 7011.
o.4s6 sta3 LOAD entsS t
=
v147.
o.52s aga3 LOAD + ##SSSURE. SE15MIC I
I SEC045Aav SfakSS R44GE a
4792.
U.177 TMgAN4
=
$565 c.171 feW Ast&L
- SEcotiOARY 55:5MIC 103a9.
0.251 PetwaWf rLuv *ECONARY 51RESS NANGE e
8640L0a9. PNE55 pat. fnERMAL" 1J511.
0.272 l
SEA 9 Leap. entssyRE. SE!5nte. THENNAL l
saRE EVf9 S-Pd8MakY Sfk55 LIMIT i
f 1
17312 4LLQdas,LE afR$$$ e STRESS NATIO ALE $flC EV4LLUA ED PRIMARY SfMESSES AS SHOWN SELOW l
T satees=cv conoittens nE-1>P4c> ton-J EF = 1. 5 81 11523.
0,444 j
98!ADLOAS
- PRE 55URk
rauLTED CO*vot f t0NS 1 E-3)P40)10E-6 DEAOLOAD e wax. Pak5suRE'. 0008LE PWIMANY SEISMIC SF81.36 12495 0.437 i
I l
t l
i
{
I l
JUN 161970 i
l l
-.