ML20127P454

Responds to Technical Assistance Request Re Review of Proposed Change in Reactor Vessel Surveillance Program

ML20127P454
Person / Time
Site:	Monticello, Dresden
Issue date:	12/19/1974
From:	Maccary R US ATOMIC ENERGY COMMISSION (AEC)
To:	Goller K US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212020223
Download: ML20127P454 (2)

Text

_ _ _ - - _ _ . - _ _ _ . . . . _ _ . _ _ . _ _,

1. g ,

a, .

h l

Decket No. 50-263 HEC 1 9 W Earl R. Os11er, Assistaat Director for Operating Reactors i

Directorate of Licensing NOMTICEL1A NUCLEAR GENERATING PLAlff - RESPONSE 10 TECIGIICAL ASSISTANCE l REQUEST - REVIEW PROPOSED CHANGE IN REACTOR VESSEL SURVEIIJANCE PROGRAM, i (TAR-1276)

! Plant Name: Monticello i

Docket Number 50-263 l

Responsible Branch and Project Managert ORS-28 J. Shea Requested Completion Date December 20, 1974 Technical Review Branch Involved . Materials Ragineering Branch Description of Request: Review Proposed Change in Monticello's Reactor Vessel Surveillance Program

Review Status: Complete In :tesponse to your Technical Assistance Request, the Materials. Performance f Section of the Materials Engineertag Branch has reviewed the change to the Monticello reactor vessel surveillance program proposed by Northern States Power company on November 15, 1974 i

They propose to delete the requirement for removing the first reactor vessel material surveillance sample basket during the third refueltag 1

' outage. They state that the calculated fluence- (based on the results

' from the dostaster basket removed during the first refueling outage) will be too low at this. time to provide meaningful results. They recommend that the first sample basket be removed at 15 years, when the fluence will approach 1.x 101 e afe.2, >

i We agree that the removal of the first basket should be- delayed until it~

has received significantly higher fluence (on the order of 1 x 1018 n/cm2 ),

j but will require additional information before we can evaluate their proposed schedule. Specifically, we must review the results'obtained.

i from the dosimater capsule, and the flux calculations made_to support

! their-reconamndations.

In reviewing'the Technical Specifications we note that Technical Speci-

! fication 3.6.B.1 " Pressure-Temperature Limits for Inservice _Testina,-

.ve, 11catup.1 Cooldown and Core Operation" is-incomplete and does not conform

.I l.. 'P_ PDR;

-i.

_ _ . _ _ __._-_ _ -- __ _ . _ __._ _ _ . _ _ . . _ _ _ - . _ . . . _ - - -_ . . = _ . _ ___ - . _ _. .

i  !

', Karl R. Coller .2- f r

• 1 9 tV4 j ,

j l to current requirements. This specification should be revised along the

) i lines of the current specification for Dresden 2.

s  !

I I

i  ! R. R. Haccary, Assistant Director for Engineering I . Directorate of Licensing 1

cc: S. H. Hanauer DRTA F. Schroeder, L i

S. Varga, L A. Giambusso. L W. G. Mcdonald, L i D. L. Ziemann, L 4

J. J. Shea, L S. S. Pawlicki, L R. M. Gustafson, L 4 i I

V. S. Hasalton, L

{ K. G. Hoge L

?

. , DISTRIBUTION:

, i Docket File (50-263) l l L Reading File l MTEB Files 4

t i i t

i i

l

. 4 4

4

..) i 4

Ah

' 6"is s * .

L... . _ . .

LiKrEB , ,. .

$ ewa=a=s * .JG ogelemb. WSjizelton

. ., S SP_ eki_ . . . . . ,. ccary, _ , , _ _ _ .,,,,,,,,_,,,,,,_,,,,,,,,,,

} f onto w -.12 /1.8/ 74.,,.. _,12 /74 12[<f/74 12/jy74_ _

i Forsa A&C.)l3 (Rev. 9 S$1 AECM 0240 W u. s. nova am mtat Pa htime otracts 's.74. 4..i.e f

,m- ,,__,,..~m-- -m ,e ,. , , y - -,. . _ , - . _ , .,___,.__.,,___m,.,m-_c - ,. e.- ..y. ..,- .,