ML19224A110
| ML19224A110 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/18/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TASK-AS, TASK-BN-79-05, TASK-BN-79-5 BN--79-05, BN--79-5, GQL-1398, NUDOCS 7809070177 | |
| Download: ML19224A110 (2) | |
Text
.
dah'
.i w
- x...
., =.
..-m
.x....
l
$.$+3.;f;'2 q/m.,
/
meu me reoansss i
/
METROPOLITAN EDISON COMPANY cuc:cw ce crunmcuc ur:unes c a?:n.:c
/
POST OFFICE BOX 542 READING. PENNSYLVANI A 1960s TELEPHONE 215 - 929-2601 GQL 1390 Director of Nuclear Reactor Regulaticn v...z e
m.
R...a.
n..e _< a, -u Operating Reacter 3 ranch No. k U. S. Nuclear Reculatory Ccs=issica
'4ashingten, D. C. 20555
Dear Sir:
2ree Mile Island '.u en Statien, Unit 2 (CC-2)
Operating icense No. UPa-73 Occket No. 50-320 In respcnse to your letter of August ik, 1978 (cencerning the pcssible use of veld filler wire which was atypical of the submerged are veld filler vires used by 3abecek & 'Jilcox (3&'J), in CC-2 Reactor Vessel velds), please be advised that 3&'4 has :leta 4-ad *kat the only pcssible uses of the atypical material in the CC-2 Eeactor vessel vere:
- 1) as filler esterial for the buildup of Icv areas en the D and CD of the Upper Shell (h" C: cct of sufficient depth to affect operating limits er structural integrity), and
- 2) as veld material en the Outek - to 'cver Head veld (lov flux, Icv stress locaticn).
3&*4 has analyced these pcssible applicatiens of the atypical veld material, and has found that; "Se structu 21 integrity cf the reactor vessel has not been ec premised by the possible presence of the atypical raterial".
3&*4 has also ccncluded, based en thM - " alysis that: " Sere is no effect en the reactor vessel operaticn fcr CC-2".
As you may be aware, the pcssible use of this atypical veld material (i.e.,
sterial having a greater percentage concentration of silicen(1.05 vs 0.5fA and a smaller percentage concentration of nickel (0.15 vs 0.6f.) than specified by 3F41in critical veld locations may require sene plants to operate under
- Ore stringent pressure-temperature heatup a.nd ccc1down rate limitations.
~nis is nct the case for 202.
3FJ has dete mined that the heatup and eccidown rate limitations are calculated fcr a " critical veld".
This critical veld is neinher Of the two velis mentioned abcVe in which the atypical veld sterial may have been used.
(All cther velds including the two velds sentioned above, require lecs stringent heatup and cccidown limitations than does the " critical weld".)
3FJ has reanalyced the velds in which the atypical material may have baan used, and has determined that the " critical vell" has net change?.
~he current heatup and cocidown liritaticns have been, therefore, fcund tc be ac-ceptable for all velds in the C C-2 reacter vessel (even for those velds in which the atypical veld ate ~'C may have been used).
(
S 1'0oo
~ &
6 DQn s
w p
-)
- c 78 1200.4,7
~
s p o,Ln
1, R. W. Reid, Chief August 18, 1978 GQL 1390 Theref ore, please be advised that Met-Ed is not conte = plating taking any interim ceasures to ensure reactor vessel integrity, f or TMI-2 because, as indicated above, such mea.sures are not necessary. We also believe trat, despite the possible use of atypical weld raterial, the continued safe operation of IMI-2 is assured. This is because the current heat up and cooldown ratas, as well as the structural integrity of the TMI-2 Reactor Vessel have been analyzed and found to be acceptable.
Sincerely,
/ J. G. Herbein
/ Vice President JGH:RAL:tas
/'
cc:
Mr. S. A. Varga Mr. H. Silver
~
1L.C)TI pm gre. u aw4