ML20002A330
| ML20002A330 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/11/1976 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-76-35, NUDOCS 8011110781 | |
| Download: ML20002A330 (6) | |
Text
,
Propas:d Chang 2 No. 135
(
- d [ Obij bbbdbl Teliphons 617 366-9011 TwK 7!O-390 0739 YANKEE ATOMIC
- El.ECTRIC COMPANY WrR,6-25
/N
[ 'j) \\ ~. '
k 2OJampke Road Westborough, Massachusetts 01581
.Ya"m=x-e.,
- ^ ;
s r5-r.a 6
. QY.F'i c.,
i r<x s
v" March 11, 1976
_. e <:. -
Y Ikl;.
.f 9
\\
!!f, j i l $i j
~~
- l&
{.
~
A 9
'$geg,g '-
United States Nuclear Regulatory Commission Washington, D. C.
20555 q
C)u,.j j y & '.:
Attention: Office of Nuclear Reactor Regulation
Reference:
(1) License No. DPR-3 (Docket No. 50-29)
(2)
License Amendment No. 15, dated July 31, 1975.
(3) NRC Inspection Report No. 75-08, August 6, 1975.
(4) URC I^spection No. 75-15, dated November 11, 1975.
Dear Sir:
Fursuant to Section 50.59 of the Commission's Rules and Regulations Yankee Atcmic Electric Company proposes the following modification to Appendix A to the Technical Specifications.
PROFCSID CHA';GE: We propose to revise our Inservice Inspection Program as descrihed in Table G-1 of Appendix A to our Technical Specifications.
REASCN FOR CHANGE: Revision of Table G-1 is required to align the Technical Specifications with the recently completed ISI Program.
With the changes listed below future inservice inspection may be compared to the haseline data of the completed program and radiation exposure will be kept at a minimum.
1.
Reacter vessel and closure Head, E2, Penetrations. Change the Method to read " Visual during hydro leak tests."
2.
Pressurizer, Add category G-1, Pressure retaining bolting two inches and larger in diameter, Method, Visual and Volumetric, Percent, 100%.
3.
Pressurizer, G-2, Change Components and Parts to be examined to read " Pressure retaining bolting below two inches in diameter."
4.
Steam Generators, Delete category D, Nozzle to vessel welds since they do not exist.
(Reference 4) 5.
Steam Generators, Add category F, Primary nor:le to safe end welds, "ethod, Visual and Volumetric and Surface, Percent, 100%.
O r-c u e-vv0 8012220 7 U p
t
(.
- i..
^
United States Nuclear Regulatory Commission March 11, 1976 Attn Office of Nuclear Reactor Regulation Page Two 6.'
' Steam denerators, Delete category I-2.
'This category-is not included in the latest code revision.
We have included in this submittal revised pages (3) of Table G-1 of Appendix A;to the reference license.
4 SAFETY CONSIDERATIONS: The proposed change does not present significant
~ hazard considerations not described in the reference license as amended.
This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
SCHEDULE OF CHANGE: The changes will be effected following Commission approval.
Very truly yours, t
YANKEE ATOMIC ELECTRIC COMPANY D. E. Vandenburgh Vice President COMMO N E TH OF MASSACHUSETTS)
)ss.
COUNTY OF WORCESTER
)
Then personally appeared before me, D. E. Vandenburgh, who being duly sworn did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his knowledge and belief.
4C 4 4.
Armand R. Soucy
" Notary Public My Commission Expires September 9, 1977 i
..(
,e Table'G-1
[
INSERVICE INSPECTION PROGRAM Section'XI
. Components and Parts Percent of h' elds or.
Examination Category (1) to be Examined Method Components to be Examinedi
~
4 Reactor Vessel and Closure IIcad C
Vessel-to-flange and head-to-flange Volumetric 100%
circumferential welds e
s E IIcad Penetrations Visual during 25%
hydrostatic test G-1 Closure studs and nuts Volumetric and 100%
Visual or Surface
{
G-1
. Ligaments between threaded stud Volumetric 100%:
.'g,
. holes-
) y y-e G-1 Closure washers, bushings Visual 100%
j, Ia t
G-2 Pressure retaining bolting Visual 100%
y - f.';
1M I-1 Closure head cladding Visual and Surface-6 Patches or Volumetric (36 sq. inches each)-
7.p,,H Pressurizer B
Longitudinal and Circumferential Visual and Volumetric 10*. of Longitudinal welds 5% of Circumferential D
Nozzle-to-Vessel welds Visual and Volumetric 100's W
E-1 I! cater nozzle to shell weld Visual and Volumetric 25%-
O 5
Table G-1 INSERVICE INSPECTION PROGRN.!
Section XI Ccmponents and Parts Percent of WelIs or Examination Category (1) to be Examined Method Components to be Examined Pressurizer (cont'd. )
G-1 Pressure retaining bolting 2 inches Visual and Volumetric 100's and larger in diameter G-2 Pressure retaining bolting below Visual 100'e 2 inches in diameter 11 Integrally welded vessel supports Visual and Volumetric S 0*6 I-2 Vessel cladding Visual 1 Patch (36 sq. inches)
Steam cencrators B
Tube-shect-to-head wcld on the Visual S's of Circumferential primary side wcld cach unit F
Primary nozzle-to-safe end welds Visual, Volumetric 100'e and Surface G-2 Pressure retaining bolting Visual 100's Piping Pressure Boundary G-2 Pressure retaining bolting Visual 100*6 O
o Table G-1 INSERVICE INSPECTION PROGRAM Section XI Components and Parts Percent of h' elds or Examination Category (1) to be Examined Method Components to bc Examined
- Piping Pressure Boundary (cont'd.)
J Circumferential pipe welds Visual and Volumetric 4 Loops - 25% cach K-2 Piping Support and llanger Visual 100%
Pump Pressure Boundary G-2 Pressure retaining bolting Visual 100*$
K-2 Supports and llangers Visual 100%
L-2 Pump casing Visual one pump (if opened for maintenance)
Valve Pressure Iloundary G-2 Pressure retaining bolting Visual 100*.
K-2 Supports and llangers Visual 100*6 M-2 Valve bodies Visual 100% of one valve of each class (if opened for maintenance)
(1) Those examination categories not applicabic or accessible are not listed.
IL
U.S. NUCLE An HEGUL ATO3Y CoMl1133 ton l doc V.C T NUMC E M 7,; g,ny 195
(
f 50-29 au
.C DISTP.lBUTION >cn PART G0 DOCKET MATERI AL F HOM: Yankee Atomic Elec. Co.
oATE oF ooCUMENT
- 7
- NRC 3-11-76 Westborough, Mass. 01581 D.E. Vandenburgh oATC RECEIVCo 3-15-76
%} NO T oHl2 C D PROP I!dPUT F oRM NUMDER OF COPIES RECEIVED
.1 C T T E n P90niGif 4 AL 10 U NC L AS3t F s E D 40 Ocopy u;C m rTioN Ltr notarized 3-11-76 request for l CNCLoSURE Revised pages to Tech Spec Change Proposed Change No. 135 to Tech Specs in order Request No.
135.....
to revise the Inservice Inspection Program &
trans the following:
(40 cys enc 1 rec'd)
- -. ; ~; r. r n
~
.->.. ~ <> A $ 5.0
.. w..c U
PLANT MAME:
Yankee Atomic a.!
w8 S/JETY FOR ACTION /INFOR.1ATION ENVIRO DHL 3-16-76 j ASSIG:iED AD :
l ASSIG!~ED AD :
y HRANCll CriIEF :
(f) g PLer I;RANCli CHIEF :
URGER PROJECT I'ANAGER :
PROJECT l'A;;AGER:
p{d pp_ggp LIC. ASST. :
[j,
~
EYC. ASTT. :
~
__._l INTERNAL DISTRIBUTION 1
REG FIJ, D SY_SJMIS_ SAFETY PI.AUT SYSIEM FIEI'1 TECE
~ ;RC PDjl
_] 215EllAN TEDESCO ERt:ST 1
Tj I&Eh SC11302 DER.___
BE!!AROYA BAL1.ARD SPA';GLEP E'j _QT.J.D IAll?As I
GOSSiCE & STAFF l
E' GINEERIt (;
IPPOLITO SIT" TECH
._. __IIIEC MCCARV KNIG!iT OPER/. TING REACTORS GA?g11LL
~gj,S g STEPP 1
pjgtha SIl3.'EIL STELLO liULMAN
'~- ~_llA'il.ESS PAULICKI i
OPERATING TECH RE?.CTOR SAFETY Vl'EISENUttr l
SITE AIIALYSIS i
~
~fi10 JECT MANAGEME:'T l
~ ROSS
~ LOYD I
/ SH50 VOLIMR i
J
'~
P. COLLINS I;0VAK Vi BAER BUNCH J
110USTO:'
ROSZTOCEY N SCIE?ENCER y J. COLLINS j
PETERSON l CHECK W
GIIIMES KREGER j
~
~~,LC177 d
~~
t'
~
~ il'L'T;55'S AT & I SITE SAFETY & ENVIRC
~
1
~ F S'K6VI!OET SALTZMAN ANAL.YSIS T
RUTiif}!d II".IITE: & Mt'U.ER EXTERNAL DISTRIBUTION CONTROL NU.10E R
![LPDR16 tee #FieJ4IM51.fATGB
.] N IPAIE M OTL L^B
( L TIC REG. V-IE ULRIKS0304L) a/
h F
t; SIC LA PDR
/
- h.
CONSULTANTSV%
pk@N fNAh5p b bE fh TEE 35 tuer ASLn_((pfe 7 m[-8'
$'.M d d h b
TfS ACgS H-i/Sr.:
di J
a m atu m
e g=
7
- = = =
=
s m as g ~ _
,,,