ML20062L353
| ML20062L353 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/19/1981 |
| From: | Rich Smith VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Rooney V Office of Nuclear Reactor Regulation |
| References | |
| FVY-81-12, NUDOCS 8101270682 | |
| Download: ML20062L353 (6) | |
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- VERMONT Y AN KEE NUCLEAR POWER CORPORATION 6~
8 SEVENTY SEVEN GROVE STREET
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RUTLAND, VERMONT 05701 EVY 81-12
-1 Ej ne,tv ro, ENGINEERING OFFICE g
. LJ 1671 WORCESTER ROAD FR A MINGH AM, M ASS ACH USETTS o17o f 1ELEPHONE 817 872-8100 January 19, 1981 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attentior :
Office of Nuclear Reactor Regulation Mr. V. L. Rooney Operating Reactors Branch #2 Division of Licensing
Reference:
a) License No. DPR-28 (Docket No. 50-271) b) Letter, VYNPC to USNRC dated September 5,1980; Supplement No.1 to VY Proposed Change 81,
" Reactor Vessel Pressure / Temperature Limitations"
Subject:
Supplemental Information in Support of Vermont Yankee Change No. 81, " Reactor Vessel Pressure / Temperature Limitations"
Dear Sir:
Reference (b) proposed new pressure / temperature limitation curves to allow station operation through 1.15E8 MWH(t).
In subsequent conversations with members of the NRC staff, Vermont Yankee was requested to supply additional information in support of Reference (b).
The information requested is provided in the attachments to this letter and the discussion below.
The initial RTNDT for the Vermont Yankee reactor vessel was established by reviewing the original CB&I/Lukens test data on vessel plate and forging materiale ( Attachment 1).
This data was limited in nature, so AEC Branch Technical Position MTEB 5-2 was evoked. Original tests indicated charpy V-notch energies of 30 ft-lbs at +40oF.
Paragraph 1.1. (4) of MTEB 5-2 0
requires an additional +20 F to be added to longitudinal results which fall below +45 F for a charpy V-notch energy of 30 ft-lbs.
Therefore, we added 0
+200F to our +40 F data to arrive at an original RTNDT for vessel materials of +600F.
No copper or other residual chemistry data is available lor the material of interest, so " worst case" "TNDT shift curves are being used.
Additicnal information describing the development of the curves submitted in Reference (b) are contained in Attachment 2.
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U01270 QQ
United States Nuclear Regulatory Commission January 19, 1980 Office of Nuclear Reactor Regulation Page 2 We trust this information will be satisfactory. Should you have any questions, please do not hesitate to contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION R. L. Smith Licensing Engineer RLS/ dis
Attache nt 1 Pg. 1 of 3
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TEST CERTIFICATE Mr. G.H. Putman, P.A.
uitt onoce no.
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Birmingham, Ala.
35202 52700-1 6201 Sheet 1 RG 21167 7.M SPECIFICATIONS:
A-533-65 Gr.B Class 1 Mod. per CB 2: I MS-1 DTD 8/25/66 Fbx. 8o000 O.K.
O.K.
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under 400*f. by holdinv tes pqr inci! or thickness., then tempefed 1260-125
- F., held 1 hr. per ingh mino and Ailirmed and subscribed bMore me o*
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I Wihereby certify the above figures are correct as contained in the records of the company.
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- Attachment 2 RTNDT Shift at Reactor Pressure Vessel l
'l/4T and 3/4T Positions for Vermont Yankee
.1.
Requested power level output = 1.15 E8 MWH(t) 2 2
3 33 E9 n/cm i
2.
K31L* = 8.0E13 n/cm
=
1000 MWD (t)
MWH(t) 3.83 E17 n/cm(2) 3 33 E9 n/cm(2) 1.15 E8 MWH(t) i 3
Fluence =
x
=
MWH(t) 4.
Vermont Yankee's Reactor Vessel is 5 312 inches thick (Dug. #5920-105, 5920-108 through 115 and CB & I Dwg. R-6, Rev.1, Contract No. 9-6201) 1 328" 5 312" x 1/4 5
1/4 T
=
=
3 984" 5 312" x 3/4 3/4 T
=
=
6.
Per NRL Report 7209##., the percent of vessel I.D. fluence at 1/4 T and 3/4 T positions are:
62% of vessel I.D. fluence 1/4 T
=
22% of vessel I.D. fluence 3/4 T
=
3.83 E17 n/cm(2) 7 From (3), neutrca fluence (Vessel I.D. )
=
.62 x 3.83 E17 n/cm(2) 2 37 E17 n/cm(2) t 1/4 T
=
=
.22 x 3.83 E17 n/cm(2) 8.43 E16 n/cm(2) 3/4 T
=
=
8.
Consulting Vermont Yankee FSAR Figure 4.2-3, "Chan6e in NDTT.Versus Neutron Exposure", using the " worst case" curve, the shifts in RTNDT at the 1/4 T and 3/4 T locations are:
RTNDT shift G 1/4 T - 30 F RTNDT shift @ 3/4 T 15 F
=
i-SIL No. 14, Sapplement 1, " Reactor Pressure Surveillance Program",
General Electric, June 9, 1980.
1 I
F. J. Loss, et. al. NRL-Report 7209, " Analysis of Radiation-Induced -
Embrittlement Gradients on Fracture Characteristics of Thick-Walled Pressure Vessel Steels", Maren 1,1971, Page ' 5 t
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