ML20107G508
Text
,
cn.73.uia l! ~ vij Jersey Central Power'& Light Company l((f)h
- v. y.
s MADISON AvtilVE AT PUNCH DOWL ROAD
- MORRibiOWN.N.J. 07900 -
d '#
j' g'.l.
PvDhc Ut.hi.es corporahori General i
i October 31, 1975 1
l I
Mr. Georne 1. car, Chief i
Operating-lteactors Dranch If 3
'llivision of Reactor I.icensing linit ed St ates Nuclear itegulatory Conunission h'ashington, D. C. 20555
Dear Mr. Lear:
Subject:
Oyster Crcok Nuclear Generating Station 11ocket No. 50-219 lieller Valve Line ltestraints
'this is in response to your letter dated September 10, 1975, in l
which you retpiested an analysis of the relief valve line restraints at the Oyster Creek Nuclear Generating Station.
In the'past few years, we have been analyzing and improving the relief valve piping system oa our own accord. The following transmittals have been sent in connection with these changes and studies:
1.
Oyster Creek Station No. 1, Safety and Itclief Valve Piping liesign lleport, dated August 1972, from Mr. Ivan it.
l'inf rock, Jr. t o Mr. Donald J. Skovholt, with cover letter dated August 22, 1972.
2.
Semiannual' lleport No. 7 (July 1, 1972 to December 31, 1972),
Section Vil, item 1.A.
3.
!;emi.mnual Report No. 8 (January 1, 1973 to June 30, 1973),
Se c t i ten V ! !, i t em 1.11.
1.
I.e t t. r : o Mr. 1)enni s I., ~' i emann. d a t 'd.' ;' r i l 13, l A,
cont aining informat ion on reli~ f valve blu.sduwn:5.
c Ia addition tu the above mentloned t ransaittais, a soimnary of the dated October final analysis of the Main Steam Relief Valve Piping Systera, 1973, is attached. 'this summary refers to the design eriterip, analysis and i
i r
'9'604230259 960213
~
2 58
_~-
Mr. l.ca r installatinn of the lilectromatic Relief Valve (1;RV) discharge eductor restraint system which was installed during the Spring 1973 refueling outage.
This restraint system was installed te minimize imposed stresses under reactor blowdown conditions.
i An inspection of the !!RV restraint syst em that is located in the t urns was conilucted during the Spring 1974 refueling outage.
The results of the inspection indiented that the restraints were in the proper position and weldments were intact with no evidence of deformation or wear.
Items specif-ically examined were the 12" to 20" pipe weld, the canal fitting weldments for signs of distress, the canal fitting brackets for signs of shifting or looseness, shim placement and lock wire integrity. The inspection further inchided an e.samination of the support columns for signs of movement or looseness. These were observed to be in satisfactory condition.
It should he noted that in the one year period between installation and inspection of this rest raint nyntem, the 1:RV's actuated twice automatically at 1070 psi as pressure relief valves, and once manually for test purposes at 500 psi prior to the start of the April 1974 outage.
Since we have performed an inspection of the relief valve lines and their rest raint s inside the torus subsecluent to relief valve blowdown and have determined that no damago nor degradation has occurred, we plan no further inspections.
We consider the actions that we have taken sufficient in fui-filling the inspect ion rettuest of your September 10, 1975 1ctter.
Very truly yours, v ($}l!/(',
}.Y'.' 1 U Ivan R. Finfrock,,lr.
Vice presidelit es Attachmesit l
I