ML19341C619
| ML19341C619 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/27/1981 |
| From: | Randazza J Maine Yankee |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19250C882 | List: |
| References | |
| FMY-81-24, NUDOCS 8103030839 | |
| Download: ML19341C619 (4) | |
Text
h'F d a
,a L
IRAIRE
'2"HARHEE Amml0POK'ER00mPA09 e Box 450, RFD 2 Wiscasset, Maine 04578 g4 h
2.c.2.1 d' 5 ?'/)(nct 81-24
- -Q February 27, 1981
(,(
0
[ k[_.
[
'"ko 7
Ko
'4 S
8/
United States Nuclear Regulatory Ccanission A
Washington, D.C.
20555 9
/
Attention: Director of Nuclear Reactor Regulations (o
N
References:
(a) License No. DPR 36 (Docket No. 50-309)
(b) Code of Federal Regulations, Title 10 Part 50 Appendix H (c) Perrin, J.S., et. al., " Maine Yankee Nuclear Plant Reactor Pressure Vessel Surveillance Program:
Capsule 263",
BCL-585-21, Battelle Colunbus Laboratories, Decanber 21, 1980 (d) Hawthorne, J.R., " Notch Ductility Degradation of Ina Alloy Steel With ine-To-Intermediate Neutron Fluence Exposures",
NUREG/CR-1053; NRL Report 8357, Naval Research Laboratory, Washington, D.C., January 14, 1980 (e) Hawthorne, J.R., et. al., " Evaluation of Conmercial Production A533-B Plates and Weld Deposits Tailored for Improved Radiation Embrittlenent Resistance", Properties of Reactor Structural Alloys Af ter Neutron or Particle Irradiation, ASIM STP 570, American society for Testing and Materials,1975, pp.83-102.
Subject:
Reactor Vessel Surveillance Capsule Analysis Report
Dear Sir:
Persuant to Reference (b), the Maine Yankee Atomic Power Company hereby submits the folla4ing report.
During the Maine Yankee Cycle 4/5 refueling outage in January / February, 1980, a reactor vessel wall surveillance capsule was raroved fran the vessel Reference (c) and sent to Battelle Columbus Laboratories for analysis.
-docunents the results of that Battelle analysis.
Of significance in this report was the finding of fluence values
'Ihe cause for this Espproximately 2.3 times areater than had been predicted. discrepa As stated in Reference p(c)grirns and/or errors in the original methodology., Battelle utilized th ro l
81osoyo J
United States Nuclear Regulatory Camission February 27, 1981 Page 2 to solve the Boltzman transport equation in two-dimensional geon try. We-DECAY caputer code was used to cmplete the fluence calculationq.
It is tielieved that the original predictions were calculated using a si le-dimensional code cabination of ANISN-SHADRAC verses the DDT 3.5 -
method.
Maine Yankee believes the Battelle results are correct based on a cmparison of the Battelle results with the results of material property changes exhibited by other actual Maine Yankee vessel material utilized in test reactor progres (References (d) and (e)).
Reference (c) provides the nnjority of the information required by Section IV of Reference (b). Table I provides a cmparison of predicted results to the test results. Figure I depicts the pressure and temperature 4
limitations resulting frm the original prediction and also the new limitations based on the test results. %e operating procedure used to 4.
generate the pressure /tmperature limitation curves has been revised.to incorporate the test results and the Fluence vs RTNUp Shift curves specified in Regulatory Guide 1.99, Rev.1, April 1977.
We trust this information will be satisfactory. Should additional information be required, please feel free to contact us.
Very truly yours, l
MAINE YANKEE ATG11C POWER COMPANY
$~bw GA fA'4.g.-
John B. Randazza Vice President Manager of Operations JBR/ps Attachments i
~.
L
2500
~
240C
_~~'
f g
e FIGUPE 1 2300 g
L-
. 4 t
CCfPARISON OF OPERATING 2200
~,.L PRESSb6PERATURE LIMITS
~
L"~
BE7IWEEN PREDICTED AND 5
2100 PCIUAL TEST RESULTS-T-
T A
E==
=
2000 55
=
i-
==
1900
&C
"~'~
-m
=
1800 w
ORIGINALLI PREDICTED CURVE g
1700 i
m N TS N 1600
~,
.=
1500
. -_m -.
+
e 1400 8
~
1300 go h
1200 E!
==-*
c.
g 1100
-/
=
h 1000
-+
y 8
- t-900
-._=~
-^ '- ~~ j_. _ _.
800
. _ '~~
MINDG1 SERVICE "T+E
. C::5 TEMPEPATURE (2060F)
~
700 r-600
..c
^-
' ~ ~ -
/-
MAXD121 PRESSURE BEHM THE 500 Ef=
' MDIDOi SERVICE TDPEPATURE (589 psig)_ _ c-
___i.
g
+
400 1._ _ _
3 300
, = _. _,. _ _.,.
l 3
g -. _ -_ p.- - -
r
'Z E ~*
+
200 5 ICIE: ALL VALUES D CLUDE PRESSURE AND L
E- _
TE-EERATURE INSTRUMENT ERFOR
~~
~~~T-
-i
- = ~ ~~~ ~ ' - '-~~r -- -
=--
TOLEPANCES OF 32 PSI AND 60F.
-100
- ~
_ _p: =- u - -"
-+-
--+
=.:
=:
- q..
f :=--+
._. _c
_ 120 160 200 240 280 320 360 400
'3 O'? W OPEPATHE TEPEPATURS (O )
L.
F 6e e
TABLE 1 MAINE YANREE REACTOR VESSEL IRRADIATION SURVEILI ANCE 5
5 COMPARISON OF. PREDICTED VERSES ACTUAL TEST RESULTS PREDICTED ACTUAL TEST RESULTS Neutron Fluence (n/cm2 E y 1 MEV) at end of Cycle 4 3.0 E18 6.9 E18 Maximum End-of-Life Fluence
+0.32 (n/cm2 E > 1 MEV) for the 1.63 E19 2.73 E19 vessel I.D.
-0.48 Shift of RTNDT for b' eld Material @ 1/4T at end 104 F 1640F of Cycle 4 l
l l
l l
m e
i