ML18227D439
| ML18227D439 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Turkey Point |
| Issue date: | 12/12/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | O'Reilly J NRC/IE, NRC/RGN-II |
| References | |
| IEB-77-006 | |
| Download: ML18227D439 (8) | |
Text
DISTRlBUTION AFTER ISSUANCE OF OP TING LICENSE NRC FQRM 195 UA NUCI SAR RKQULATORYCOMMISS IZ Vdl
. NRC DISTRlBUTION FoR PART'50 DOCKET M4TERlAL aocxsT NuM s R
%-9H PILS NUM SR TO:
Mr. James Pi O'Reilly FROM:
Florida Power 6 Light Company Miami, Florida Robert Ei Uhrig oATK oF oocuMKNT'ot Dated OATS RSCKIVSO 12/12/77 I QiLKTTKR QORIQINAL QCOPY ClNoTQRfzso GUNCLAsslplso PROP INPUT FORM NUMSSR OF COPIKS RSCSIVSO
. OSSCRIPTION I
i I
I I
KNCLOSURS Consists of response to IE Bulletin No 77-06 concerning containment electrical penetrations~
~ ~ ~ ~
(1-P)
(4-P)
PLAÃZ'i: St+ Lucie 1-2/Turkey Point Units RJL 12/13/77
& 4 SAFETY i
BRANCH CHIEF.
7 FOR ACTION/INFORMAT)ON Aui> '
'IITI iNTERNALOISTRI BUTION I
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I MT RNAL OISTRIBUTION CONTROL NUMBER 7p~<~OOPS
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Nr. James P. O'Reilly, Director, Region II O fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree
- Street, N. N., Suite 1217
- Atlanta, Gh.
30303
Dear l1r. O'Reilly:
Re:
RII:JPO
~
50-335, 50-389 50-250, 50-251
>Pp "W
Jf
, W~/p Florida Power
& Light Company has reviewed IE Bulletin 77-06 and a response is attached.
Very truly yours, Robert E. Uhrig Vice President REU/HAS/lah Attachment CC:
Robert Lo~~enstein, Esauire
- .Q~c~~~XSpe~x~'@~5:uL~~.
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77~g700'25 PCOPLE... SBRVII'~Q PFGPL.
ATTACE!iL~.ZT Re:
RII:ZPO 50-335, 50-3S9 50-250, 50-251 Question, 1.0 Do...you h=- -
containment electrical penetrations tha-are of'the G.E.
Series 100, or. are otherwise similar in that they depend.
upon an epoxy sealant and a ary nitrogen pressure environment to ensure that th electrical and pressure characteristics are maintained so as to ensure the,functional capability as required by the plant's safety analysis report; nam ly (l) to ensure adequate functioning of electrical safety-related.equipment arid (2) to ensure containment leam tightness?
Resa'onse 1.0 Tne containment electrical penetrations for the Tu-key'oint and
'ucie nuclear uni s are not of the G.E. Series 100, nor do they depend u on an epoxy sealant and a cry nitrogen pressure environment to en, sure thai prope-. elecirica1 and pressure characteristics are maintained The safety =elated peneirations a" Turkey Point Uniis 3
c"nd 4 we e manu-factured bv Croute.-E nas Co.
Those't St. Lucie Unit 1 v; re manufactured bv Gulf Atomic Co.pany and Conan Corporation.
Ques ion 1.1-gave you experierced any. electrical failures -with this type of zen~-
tration?
Res on'se 1.1 This question --
=. "-'irectly applicable because the"containment-electrica>
pene rations for.re Tur'cey Po-'nt. and St. Lucie'nuclear units are not of the type reference= in Question. 1.0.
Nith res-~ct to the safety related penetrations ihat a
e in use at Tur-key Poi.".t Un'ts 3 a".a 4 and Si.. Lucie Unit 1, there have been no elec-trical fa. lures a-turkey Point. and only two electrical failures at St. Lucie:.
~ The
~ ucie failures were caused bv so'der joint fabrica-t,ion erro s -;hie'". v re not environmentally related.
'J.
P. O'Reillv Pa e Sro Qu stion 2.0 For those penetrations referenced in Item 1 above, h". ve you mai.tain the manufacturer's prescribed nitrogen pressu e at all times>
This ques"ion is not directly applicable because the containmen electri-cal penetrations for the Turkey point and St. Iucie nuclear units are not of the type referenced in Question 1.0.
Question 2.1 If you. have operated.the penetrations without maintaining a nitrogen+
- pressure, was any degradation of insulation resistance or anomalous component'peration cetectod?
Resnonse 2.1 Same as
Response
2.0.
Question 2.2
'f no measurements s" re taken during periods when nitrog n pressure was no maintained, ho~ vere you assured that the insulation resistance was not degrading or cegraded?
Response
2.2 Sane as Respons
.2.G Question 2.3 Ho r do you determi"e that circuit insulation resistance values are sat'sfactor'lv maintained?
Res-onse 2.3 Same as Response.
2 0-
J.
P O'Reilly Pa e Th ee Question 3.0 Is tnere a need, as determined by either the vendor.or yourself to m i..tain penetrations pressurized during a LOCA?
~
'fresno".
e
- 3. 0 The containment electrical penetrations for the Turkey Point and, St. Lucie nuclear units are not of the type referenced, in Question 1.0 and do not need to be pressurized.
They are designed to function without pressurization in tne pressure,and temperatu e
environ"..ent of a LOCA.
Question 3.1 What ~casu es 2.'ave you taken to ensure that penetration's of this type will perform'their design function unde LOCA conditions?
(Design review, analyses or tests)
Resaonse 3.2.
&le assw=..e tha the vording "penetra ions of this type" means penetra=='ons
=hat are of the G.E. Series 100 or are other:rise, similar in that they depend upon an epoxy sealant and a'ry nitrogen press"'e environment to ensure that proper electrical and pressure characteristics are mainta'ned.
Under this assump-tion, Question 3.1 is not directly applicable because the containm nt electrical penetrations for the Turkey Point hnd Lucie nuclear units are not of that type.
Even though penetrations of the suspect type are not used by PPL, ve have conducted a review of the design speci='c "'ons of the penetratio"s
.~e do use and have confirmed that they vere designed to pe==o 'nder LOCA conditions.
The ability o- ='e electrical penetrations used at Turkey Point
'Units 3
6 4 a;= St. Lucie Unit 1 to function under Design B sis Acciden" (DBA) conditions has been verified by prototype testing and. by testin-each penetration be ore installation.
Quest-on 3-2
'e meas"res that provide this assurance adequate to sati -v the Cc.-,;.iss'o-. 's regulations (GDC 4, Appendix A to Part 50; QA cr'teri A-. pe.".diz B to Part 50)?
- p. O'Reilly Page Fou-
Response
3.2 Sa~e as
Response
-3.1 with the following additional ir'fora~ation:
As stated in the Final Safety Analysis Repor s for Turkey ?oint and St. Lucie, a~1 systems vital to safe shutdown and 'solation of the reactor or whose failure might cause or increase the severity of an accident or result in an uncontrolled release of excessive amounts of rad'oac i;vity conform to GDC 4.
Such systems include electri al penetrations.
Quality 'assurance reguirez nts in effect at the time o issuance of the FSAB.'s were applied to containment electrical penetrations..