ML19257B990

LER 79-116/03L-0:on 791227,following Reactor Scram & During Plant Startup,Several Problems Occured w/source-range Monitors.Seven Instances Noted.Followup Rept Describing Corrective Action Will Be Submitted

ML19257B990
Person / Time
Site:	FitzPatrick
Issue date:	01/16/1980
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19257B985	List: ML19257B984 ML19257B990
References
LER-79-116-03L, LER-79-116-3L, NUDOCS 8001220507
Download: ML19257B990 (2)

Text

NRC FORM 246 U. b. NUCLt AH H kUULA IUH Y COMMibMUN (7 771 6 LICENSEE EVENT REPORT CONTROL BLOCK: l a

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

E lN lY J l A lF l1 to l @l 1S 0l 0l -l O! O!

LICENSE 0l NUMeER 0l -l ol ol ol iS @l 20 4l Il Il LICENSE 1l 1 TYPE J0@ l l 57 L A T Sd l@

i 8 3 LICENSEE CCOE CON'T

?

o i 8

ZRc! kl@l015 0lo10131313l@l1 l'l'I?

60 61 COCKET NUMBER b8 64 EVENT 17 DATElo l@l011 l 11 61 8l ol@

74 75 REPOR T CATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h I

o 2 i SEE ATTACHMENT O 3 I nl4 l 1

0t$ l 1

o 6 I OI7 l 1

0:4 1 ,a 7 9 3 COMP. VALVE SYSTE*A CAUSE CALSE CCCE COCE SUSCCCE COMPCNENT CCCE SUSCCCE SUSCODE 064 4

11lBl @ lE @

9 to 11 12 A l@ lIlNISiTlRlIllh l xlh 13 18 19 20

'l h 7

SEQUENTI AL CCOU R R E NCE REPORT AEV'SicN EVENT YEAR REPCR T NO. C00E TYPE *a C.

@ g(g.:,g a gg 7! 91 1-1 1111 61 26 1/l 2d oisi 29 LlJ JJ L-J 31 lol J2

_ 2' .2 23 24 27 A T CP C Pt.hN T HOURS S Sa IT FOR S. SU PLIE MA UFA T GER YA E IJJ x'@lx l@ Je 05 cl@ lJ6A l@ l o l o f a l"s l 31 40 l Ylh 41 42 Yl@ lNl@

43 44 cl0l810K 47 cAUSE CESCRIPTION AND CORRECTIVE ACTIONS h i 3l l SEE ATTACHMENT l l1 l i i 1 l l I

l1ll 30 7 3 3 s ac; _: TY YETMCO 05 Staru %3CnER OTHER STATUS CISC ON E" OfSCOVERY OESCRIPTION

' i5 Icl@ l0IoIol@l"

NA I i al@l*

'5 onoru nt observu ion

$3 I

A!Tivir, Co'iTENT ecC2T,cN o, RcLE SE @

NAAMouNr C, ACTiv,Tv @ l af u Asto C, EtEast 7

i ojIzl@ l zig 4 7 10 11 44 l

45 NA 30 l

PER;CNNEL EXPONRES Nur/ni a TYPE C E ;C AIP TIO N i i7i 10 10 10 :@l z j@l NA l

PERscNNE L5NrjdES '

l/83 7

NcM9ER OEsCniericNh 333 NA 1 7

4 1 1 10 3 3 0 10 l@l 11 12 90 LCSS OF CR D avage TO F ACILtTY TvPE OESCDIPTION 1 l) l zl 0 NA da l

7 s J issyg E CRIPTION o lN l NA ] lffIIIIIiIi!l 68 63 30

} 7 A 3 to

' ~

NAME OF PREPARER PHONE 4

~

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-ll6/03L-0 Page 1 of 1 Following a reactor scram and during the subsequent plant startup, a number of problems with SRM's were encountered. While some of these difficulties are not considered to be specific instances of operation in a degraded mode permitted by Technical Speci fications Appendix A, Table 3 2-3, they are included in this report in an effort to fully describe the series of problems encountered:

. 1) On December 6,1979 SRM Channel C was observed to be occasionally spiking upscale during normal operation of the plant in the RUN mode with SRM instrumentation fully withdrawn. Investigation did not reveal the cause of the occasional spikes.

The problem was not discovered as part of surveillance testing and did rot result in operation in a degraded mode.

2) On December 10, 1979 SRM Channel A failed upscale during normal operation of the plant in the RUN mode with SRM instrumentation fully withdrawn. Investigation revealed electrical breakdown of the detector, detector cable or cable connector inside primary containment at approximately 250 VDC compared to a normal detector high voltage of 650 VDC. SRM A was bypassed and normal operation continued.

3) Following a reactor scram on December 27, 1979, SRM Channel C remained upscale while the remaining SRM channels followed the decay in reactor power. Investigatico did not reveal any cause for the upscale reading. Following recalibration, the instrument responded normally.

4) On December 27, 1979 and during surveillance testing to permit reactor startup, SRM Channel D was discovered to have a failed 15 volt DC voltage regulator in the instruments power supply. Replacement of the power supply voltage regulator and recalibration restored the instrument to normal.

5) On December 28, 1979, following repair and/or testing of SRM C and D, and follow-Ing the completion of other surveillance testing required for startup, reactor startup was initiated with SRM B, C, and D operable and SRM A inoperable.

During the startup, prior to reaching the point where reactor became critical, SRM Channel C failed upscale. At this point reactor was fully shutdown and cooled down to allow repair of SRM instrumentation components within primary containnent. The detector connector for SRM Channel A was found to have some indication of exterior corrosion and the connector was replaced. SRM C detector connector revealed the presence of moisture inside the connector and both the detector and cable connectors wcre replaced. Following this work, calibration of the instruments restored all four (4) SRM Channels to an operable status.

6) Following a reactor startup on December 30, 1979 and during heat up of the plant, SRM Channel A again failed upscale. Corrective action has been deferred until the next primary containment entry.

7) Following the units return to service and at approximately 60% rated power, SRM Channel C failed upscale on January 1, 1980. Investigation and repair has been deferred until the next primary containment entry.

A followup report describing the corrective action required to restore SRM Channels A and C to operable status will be submitted at a later date.

1783 334

.