ML18127A611

Enclosed Is Florida Power & Light Co.S Response to IE Bulletin 77-06

ML18127A611
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: ML18127A611 (10)

Text

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It DISTRIBUTION AFTER ISSUANCE OPERATING LICENSE NRC FOAM 196 UA. NUCI.EAR REGULATORY C I2 76)

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NRC DISTRlBUTlON FQR PART'60 DOCKET MATERlAL ISS ION FILE NUM ER TO:.

Q! ETTER QOR IGINAI ClcoPY DESCRIPTION ONOTORIZED CIUNCLASSIFIED Mr. James P ~ O'Reilly FROM:

Florida Power 6 Light Company Miami, Florida Robert Eo Uhrig INPUT FORM ENCL QSURE DATE OF DOCUMENT'ot Dated OATS RECEIVED 12/12/77 NUMBER QF COPIES RECEIV'EO Consists of response to IE Bulletin No 77-06 concerning containment electrical penetrationsi

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(1-P)

(4-P)

'LANT'QK:

St+ Lucie 1-2/Turkey Point Units RJL 12/13/77

& 4 BRANCH CHIEF:

7 Ao'iS FOR ACTION/INFORMATION EG INTERNAL0 ISTRl BUTION MC

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II:IC SIC CRS 16 CYS SK"T CATE R

EXTERNAL OISTR IBUTION CONTROL NUMBER g

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Mr. James P. O'Reilly, Director, Region XX Office of Xnspection and Enforcement U.

S. Nuclear Regulatory Commission 230 Peachtree

Street, N. N., Suite 1217

Atlanta, Gh.

30303

Dear Mr. O'Reilly:

Re:

RXX:JPO 50-335, 50-389 50-250, 50-251 t'

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og ~Iffy 0 11 Cg Florida Power

'& Light Company has reviewed IE Bulletin 77-06 and a response is attached.

Very truly yours, Robert, E. Uhrig Vice President.

REU/MAS/lah Attachment cc:

Robert Lowenstein, Esauire: ItC.~

I 773470025

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ATTAC$!i1ZNT Re:

Rii:JPO 50-335, 50-3S9 50-250, 50-251 Question l. 0 Do..you. have containme'nt electrical penetrations that a e of'he G.E.

Series 100, o-are otherwise similar in that they depend.

upon an epoxy sealant a~d a dry nitrogen pressure environment to ensure that the electrical and pressure characteristics are maintained so as to ensure the, functional capability as required by the plant's safety analysis report; namely (1) to ensure adequate functioning of electrical safety related equipment and (2) to ensure containment leak tightness?

Response

1.0 The containment electrical penetrations for the Turkey Point and

-'ucie nuclear uni s are not of the G.E. Series 100 nor do they depend upon an epoxy sealant and a dry nitrogen pressure envi onment to en-sure that proper electrical. and pressure characteristics are maintained.

T¹ safety =elated penetrations at Turkey Point Units 3

s:;.nd 4 we e manu-factured bv Czouse-H'nds Co.

Those at St. Lucia, Unit 1 >;ere manufactured.

by Gulf Atomic Co;pany and Conax Corporation.

Question 1.1

'pave you. experienced any electrical failures with this type of pene-tration?

R s onse 1.1 This question is

. "-'irectly applicable=because the containment electrical penetrations for

=h=- Turkey Point and St. Lucie'nuclear-units are not of the type referenc=c in Question.l.0.

Nith respect to the safety related penetrations that are in use at Tur-key Poin Units 3 and 4 and St., Lucie Unit 1, there have been no elec-trical failures at turkey Point and only two electrical failures at St. Lucie.

The St Lucie failures were caused by solder joint fabrica-tion errors which v re not environmentally related..

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'~ P. O'Heilly PA g~ Two Ques'tion 2.0 For those penetrations referenced in Xtem 1 above, have you maintained the manufacturer '

prescribed nitrogen pressure at all times>

This question is not directly applicable because the containment electri-cal penetrations for the Turkey point.and St. tucie nuclear units are not o

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the type referenced in Question 1.0.

7 Question 2.1 Xf you. have operated-the pefletrations without maintaining a nitrogen

pressure, was any degradation. of insulation resistance or anomalous comp'onent'peration detected?

Response

2.1 Same as

Response

2.0.

Question 2.2 Xf no measurements were taken during periods when nitrogen pressure was no maintained, florT v7 re you assured that the insulation resistance was not degrading or degraded?

Response

2.2 Same as Respons

.2.0 Question 2.3 How do you determine that circuit insulati.on resistance values are satisfactorily. maintained?

Response

2. 3 Same as Response, 2.0.

J.

P O'Peilly, Quest'n 3- 0 Is there a need, as determined by eithe the vendor.or yourself to maintain penotxations pressurized during a LOCA?

~Res or.ss

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 ar d do not need to be pressurized..

Tney are designed to function without pressurization in the pressure and temperature environment of a LOCA.

Question 3.1 What ~;asures have you taken to ensure that penetrations of this type will perform'their design function under LOCA conditions?

(Design review, analyses o-tests) 3.1 He assw-.,e

tha, ihe wording "penetrations of this type" means penetra;=ons that are of the G.E. Series 100 or are other.~ise, similar in ti at they depena

'upon an epoxy sealant and a'ry nitrogen pressure environment. to ensure that proper electrical and pressure characteristics are maintain'ed.

Under this assump-tion, Question 3.1 is not directly applicable because the containm nt electrical penetrations for the Turkey Point and St.

Lucie nuclear units are not of that type.

Even though penetrations of the suspect, type are no~ used by

PPL, we have conducted a review of the design specific t'ons 'o the penetra io;s we do use and have confirmed, that they were des'gned to pe==o~~ unde-LOCA conditions.

The abilitv o the electrical penetrations used at Turkey Point

'Units 3

s 4 az:= St. Lucie Unit 1 to function under Design Basis Acc'dent (DBA) conditions has been verified bv prototype testing and-by testing each penetration before installation.

Quest-on 3.2 Ar the m asures that provide this a'ssurance adequate to sati fy the Commission's regulations (GDC 4, Appendix A to Part 50; QA criteria, Appendix B. to Part

50) ?

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J.

P. O'Beilly

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Response

3.2 Same as

Response

-3.1 with the folio'.ving additional information:

As stated in the Final Safety Analysis Reports for Turkey Point and St. Lurie, all systems vital to safe shutdo~m and isolation of the reactor or a)hose failure might cause or increase the severity of an accident or result. in an uncon'trolled release of excessive amounts. of radioacti'vity conform to GDC 4.

Such systems include electrical penetrations.

Qualitv 'assurance requirements in effect at the. time of issuance

, of the FSAR's frere applied t:o containment electrical penetrations.

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