ML19210A145
| ML19210A145 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/19/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-0051, GQL-51, NUDOCS 7910240868 | |
| Download: ML19210A145 (5) | |
Text
_NR ISTnUTION FOR PART 50_ DOC T M ATERI AL (TEMPOR ARY FORM) l' M p@ddb{$!l%
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Met. Edison Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Reading, Pa.-
19603 Lc. A +
12-19-75 12-23-75 XX TO:
NRC 1 signeh SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
- ccx 1
50-2s9 DESCRIPTION:
Ltr trans the following:
ENCLOSU RES:
Abnormal.0ccurrence on 12.10.-75 re inop rable steam generator sa=ple line containment
.f. _n.
isolation valve..... -(AO-50-289 /75-42).
A G E N C V,1 w W DO NOT REMOVE
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Three Mile Island Unit 1 FOR ACTION /lNFORMATION DHL 12-31-75 BUTLER (L)
SCHWENCER (L) ZIEMANN (L)
REG AN (E)
W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)
STOLZ (L)
DICKER (E)
LEAR (L)
W/ Ccoies W/ Copies W/ Copies W/ Copies PARR (L)
VASSALLO (L)
KNIGHTON (E)
SPELS W/ Copies W/ Copies W/ Copics W/ Copies KN!EL (L)
PURPLE (L)
YOUNGB LOOD (E) 04tEID W/ Copies W/ Ccpies W/ Copics W/$opies INTERNAL DISTRIBUTION CFEG Fith TECH REVIEW DENTON LIC ASST A/T IND -
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)OGC RCOM P 506A pSCHROiDER% RIMES R. DIGGS (L)
BRAITElAN N H'., P U H A1ACCARY GAMMILL H. GEARIN (L)
SALTZMAN GOSS!CK/STAF F KNIGHT KASTNER E. GOU LBCUR NE (L)
MELTZ CASE PAWLICKl BALLARD P. KREUTZER (E) f SHAO SPANGLER J. LEE (L)
PLANS SOYD
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MCDONALD MOORE (L)
- fHOUSTON ENVIRO S. REED (E)
CHAPMAN DEYOUNG (L)
- NOVAK MULLER M. SERVICE (L)
DUBE (Ltr) f SKOVHOLT (L)
ROSS DICKER S. SHEPPARD (L)
E. COU PE GOLLER (L) (Ltr)
IPPOLITO KNIGHTON M. SLATER (E)
PETERSON f
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/TEDESCO YOUNGBLOOD H. SMITH (L)
HARTFIELD (2)
DENISE J. COLLINS REGAN S. TEETS (L)
KLECKER REG OPR LAIN AS PROJECT LDR G. WILLI AMS (E)
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Rm B 127 GT dl6 ACRS SE:r TO LIO l.SST R. Ingram 12-31-73 1 - J. D. RUN KLE'S, Rm E-2C' 1490 046
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Eceket No. 50-289 t-Operating License No. EPR-50 ggt
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In accordance with the Technical Specificatiens of our Three IL 7slan Nuclear Station Unit 1 (TMI-1), we are reporting the following al CCCurrence.
(1)
Report Nu=ber: A0 50-289/75 h2 (2a)
Report Date:
DEC 191975 (2b)
Occurrence Eate: Dece=ber 10, 1975 (3)
Facility: Three Mile Island nuclear Station Unit 1 (h)
Identification of Cccurrence:
Title:
Incperable Steam Generator Sample Line Centain=ent Isolation Valve Type:
An abnormal occurrence as defined by the Technical Specifications, paragraph 1.3d, in that a contain=ent isolation valve for the Steam Generator Sa=ple Line failed to close and thus threatened to cause an engineered safety feature cr syste= to be incapable of perfor=1ng its intended functien.
(5)
Conditions Prior to Occurrence:
Power: Core:
100".
Elec.: 85h !Ge 0
RC Flow:
139 x 10 lbs/hr RC Pressure: 2155 psig 1490 047
Page 2 RC Te=p.:
579 F PR2R Level: 250 inches PRZR Temp.: 650 F (6)
Descriptien of Occurrence:
Cn Dece=ber 10, 1975, and while conducting the Reactor Building Cooling and Isolatien Syste= Lcgic Channel and Cc=penent Surveil-lance Test, the cutside centain=ent isclatien valve for the Stea=
Generatcr sarple line, CA-V53, failed to elese. Upon checking the valve, it was found that the =anual cperater was not engaged in the neutral pcsitica but rather held the valve in the cpen position thereby preventing it frc= closing en an autc=atic signal.
The valve operator was i==ediately placed in the neutral position.
However, the valve still failed to fully strcke to the closed position due to apparent binding of the valve. It was apparent that the binding was caused by the ja-~4ng effect of the =anual operator holding the valve in the open position while the valve was called to be closed. The inside isclaticn valve, CA-VhB, was tested and locked closed, in accordance with Technical Specification 3.6.6.
A seccnd atte=pt was made to strcke CA-V53 and the valve beca=e unbound and stroked freely. The valve was subsequently stroked a number of ti=es with no further binding and was, therefere, declared operable.
(7)
Designatien of Apparent Cause of Occurrence:
The cause of this cecurrence has been deter =ined to be persennel in that an operator inadvertently left the valve manual cperator in the cpen position rather than in the neutral positien, thus preventing tae valve frc= autc=atically closing and setting up the condition whereby the valve was te=perarily j a==ed.
It is believed that the valve was left in this condition en er abcut Nove=ber 2h,1975, when the valve was backseated to =ini=1:e valve stem leak-off leakage.
(8)
Analysis of Occurrence:
It has been deter =ined that this oceprrence did not constitute a th eat to the health and safety of the public in that the inside J
isolation valve, CA-VhB, was cperable and would have c1csed aute-matically if required.
(9)
Corrective Action:
In addition to the i==ediate acticn deceribed abcVe, all operators vill be reinstructed as to the proper operaticn of.his type of valve with e=phasis placed en the i=pertance of properly positioning the =anual cperator in the neutral position to permit unrestricted automatic operation of the valve.
1490 048
Page 3 The Plant Operations 3eview Cor=ittee and Station Superintendent have reviewed and approved the above corrective action and have taken steps to assure its ec=pletien.
(10)
Failure Data:
.4. A.
Similar Occurrences: None Sincerely,
(( i R C mold RCA:JMC:pa ec: Office of Inspection & Enforcement, Regien 1 1490 049
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Prime f'cvers Coesittee J. J. Colitz Edison Elcetri
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R. S. Brown C. U. Scyth ptB
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1490 050
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