ML20065H043
| ML20065H043 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Hatch |
| Issue date: | 09/16/1980 |
| From: | Moeller D Advisory Committee on Reactor Safeguards |
| To: | Mccreless T Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML082180533 | List:
|
| References | |
| FOIA-82-261 NUDOCS 8210040367 | |
| Download: ML20065H043 (2) | |
Text
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f.U.CiO.? SATLCUAFDS, U.S.itR C.
SEP'l n%0 A I.1 tY I O,,IO1112 l 2 }!.N J
3 ii September 16, 1980 if TO:
Dr. Thomas McCreless Advisory Committee on Reactor Safeguards Attached is a recent LER which I would like to have one of the ACRS Fellows check, if possible.
As noted, the LER pertains to the isolation of the HPCI system at Hatch, Unit 2, due to failure of the steam leak detection relay.
My questions are these:
They state that "This is a non-repetitive event."
Do they mean for Hatch, only?
And, if so, do they mean only for this specific type of failure? -- that is, someone bumpting the relay.
In our review of LERs pertaining to failures in air monitoring systems, we noted a number of cas a of isolation of HPCI systems due to failues of fans _:.
the compartments through which the steam lines to the system passed.
I would personally classify this event as one of a very similar nature and therefore would not say that "This is a non-repetitive event." since very similar problems appear to be commonplace in BWRs.
Please have someone check into this and let me know what they find out.
Sincerely yours, Dade W. Moellier ACRS Member j
i Al s-8210040367 820628 l
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9 A E r.:1L A T 3e INFhWMATION DISTRI6UTION
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,y ACCESSIC's N34: 400e2eou3s 00C.DATE: ap/od/19 NOTARIZED: NO DOC 4ET s FACIL:Sn-3^6 E1-in I.
watch duelear Plant, Unit 2, Georgia Power C 05000366 A ll T H..% A v E AUTMCQ AFFILIATION COGGIN,C.L.
Georata 8ower C o '.
e DECIP.NA*E RF.CIP1EvT AFFILIATION Reaion 2, Atlanta, Office G E Direct 57 %
SOHJECT: LER.50-111/03L-0:en S00724,while operatina at steaov state, HPCI stes= line inocard isolation valve 2E41-F002 isolated, makino HCPI inoceraole.Procably caused hv oersonnel buroing HPCI steam leak detection relay.
DISTWICuTInN C 3 )E: A002S C3 DIES DECEIVE 0:LTR h ENCL _b SIZE:__1__I.b__
TITLE: Inci,emt Reports M'
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3 INTEM.AL:.i / ? C 0 4P % S T R 0 6 6 1
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1 A/3 RAD P43T 11 1
1 a/a SFTY AS3E12 1
1 A/9 TECHN3LJG13 1
1 4CC EVAL 44 14 1
1 AEOC 1
1 4SL94/J 4440 1
1 Ailx SYS 64 15 1
1 CHEM ENG 94 to 1
1 CONT SYS 4R 17 1
1 CORE DEDF 90 la 1
1 9/0!P, HU 4 FAC19 1
1 JI4,EvGINEERI21 1
1 DI4,Nuv FAC S21 1
1 7IG,SYS INTEG22 1
1 EFF TR SYS 9R23 1
1 E*' ERG PWE' 2 'J 1
1 E30!P QUAL 9025 1
1 GEJSCIENCE3 25 1
1 Hi" FACT E9G 27 1
1 HYC/GE7 SR 2d 1
1 I%C SYS SR 29 1
1 I&E 05 2
2 JnRoan,E./IE 1
1 LIC GUIS BR 30 1
1 LIC QUAL 90 31 1
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A T L E N G 4 4 32 1
1 SFCH ENG '4R 33 1
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3 URC PD4 02 1
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1 PROC /TST REV 57 1
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h Georgia Power Edwin t. Hatch Nucicar Plant
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' August 19, 1980 PM-80-836 PLANT E.
I.
HATCll Licensee Event Report Docket No. 50-366 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 ATTENTION:
Mr. James P.
O'Reilly Pursuant to section 6.1.9.1.b of Hatch Unit II Technical Specifications, please find attached Reportable Occurrence Report No. 50-366/1980-111.
51 %
f M.
Hanry Plant Manager CLC/pebe xc:
J.
H.
Miller, Jr.
R.
J.
Kelly W.
A.
Widner C.
L.
Coggin R.
D.
Baker
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Control Room File r
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1 LICENSEE EVENT REPORT Co'NTROL BLOCK: l l
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S 9 LICEh5EE CODE 14 15 LICENSE NUMBLR 26 26 LICENSE TYPL JO 67 C A T b6 CON'T
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60 61 DOCKET NUV8ER 6 41 63 EVE NT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEcuENCES h 0121 Dn 7-24-80,' while operating steady state at 99% thermal power, the HPCI I
Isteam line inboard isolation valve 2E41-F002 isolated, making HPCI inop-l Oi3i 0141 brable (Tech Specs 3.5.1.a).
The isolation was reset, 2E41-F002 was op-I O isi kned. and HPCI was operable.
ADS, core spray, RCIC, and LPCI were oper-I
~
tOl61 bble.
There were no effects upon oublic health and safety due to this I
LO.J.y_l le v e n t.
There was no impact on Unit 1.
This is a non-repetitive event.
I iTm i
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CODE TYPE NO.
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l0l0101 l ug lN lg Wg lZ l9 l9 l9 Ig 33 34 Jb 36 37 40 el 42 43 44 47 CAUSE DESCRirTION AND CORRECTIVE ACTIONS 2) 8 lThe probable cause of the spurious HPCI isolation was plant personnel I
l bumpino an 'HPCI steam leak detection rel ay.
Personnel have been cau-I i i 7
'l tioned to avoid bumping relays when working in panels.
The unit is now l i 2
[T']T1 I i n f ul l compliance with the requirements and no further reporting is l
1 required.
I t 4 e 9 80 h
STA US
% POWER OTHER $7ATUS DISCO RY DISCOVERY DESCRIPTION
[.E j@ l Ol 9 l 91@l NA l
lAl@l Operator Observation l
is ACTIVITY CO TENT KELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RE LE ASE
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7 8 9 to C5 69 80 3 912-367-7781 NAt.if OF PREPAREn C. l.. COGGin. SUDt. Plt. Eno. Serv.
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.....a 50-366/1980-111 Company Georgia PowerEdwin 1. Hatch LER f:
Licensee: Name.
Facility 50-366 Docket
.i Narrative Report 50-366/1980-111 for LER at steady, stateinboard operating line isolation steam 2 was Unit system spurious valve was Hatch HPCI on a
while the isolated isolation
- reset, 8-24-80,
- wer, the was core po 2E41-F002 while isolation
- ADS, On thermal inoperable 3.5.1.a).again no The operable.
were 99%
valve There-vent.
isolation HPCI was e
was this non-repetitive signal.
(Tech opened, systems safety to were due closed is a
2E41-F002 was and LPCI and This health 1
- RCIC, public Unit Plant
- spray, upon impact on annunciated. instrumentation effects no was not The was There isolation detection occurred.
leak occurrence.
HPCI the leak isolation steam been HPCI have The of the in the cause working when was a
personnel panels.and no were room The personnel control isolationPlant in working in the of the bumped. while requirements, panel cause being relays with the probable relay bumping compliance detection againstfull required.
cautioned in is now is unit reporting further e