ML19261F226
| ML19261F226 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/13/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-0073, GQL-73, NUDOCS 7910250650 | |
| Download: ML19261F226 (4) | |
Text
AEC D' RIBUTIC'i FOR ? ART 50 DOC 1GT Fr 3
( E *TORAR'l FORM)
CONTROL NO:
5501 FILE:
F.RCM:
~ 5TL'0F DOC DATE REC'D LTR TWX RPT OTHER Metropelitan Edison Co.
Reading PA R. C. Arnold 6-13-74 6-13-74 X
T0*
ORIG CC l OTHER SENT AEC PDR XXX SENT LOCAL PDR XXX Directorate of Licensing 1 signed l
CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
XXX 1
50-289 OgE0% g'b@k$g'$ g$o 2
DESCRIFTION:
ENCLOSURES:
Ltr furn info re abnormal occurrence #AO 50-289/
74-6 of 6-3-74 re failure of socket weld in the Q
Water Supply Line from the reactor coolant make-up pump discharge header to the core f lood tanks.......
PLANT NAME: THREE MILE ISLAND UNIT #1 FOR ACTION /INFORMATICN 6-19-74 GMC
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h oc.en u nxms METROPOLITAN EDISON COMPANY POCT OFFICE BOX 542 RE ACING. PENNS'rLVANI A 13Cc3 TELEPHONE 215 - 029 CE01 June 13, 197L GC.L 0073
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Director
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//i U. S. Ato:ic Energy Cc==ission2 Washington, D. C.
20545 rc.,
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Cear Sir:
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Operati. License DPR-5g Decket'"'4 50-2&V In accordance with the Technical Specificatiens for the Three Mile Island
- Tuclear Station, Unit 1, we are reporting the folleving abnor=al cecur-rence:
(1)
Repcrt :iu=ber: A0 50-289/Th-6 (2a) Repcrt Date: June 13, 197h (2b) Cecurrence Date: June 3, 197h (3)
Facility: Three Mile Island Nuclear Generating Station, Unit 1 (L)
Identificaticn of Occurrence:
Title:
Failure of a Sceket Weld in the Water Supply Line frc=
the Reacter Ccolant Make-up Pu=p Discharge Header to the Core Flecd Tanks.
M e:
An abnor=al cecurrence as defined by the Technical Specifications, paragraphs 1.8d and 1.8e, in that the failure of the socket veld (a) may have threatened to cause an engineered safety feature to te incapable of perfer=ing its intended functicn, and (b) resulted in an abacr=al degradatien of cr.e of the several boundaries designed to centain the radicactive = ate-rials resulting frc= t.he fission process.
(5)
Ccnditions Prior to Occurrence: Partially eccled down for =ainte-nance prior to initial criticality with =ajor plant parameters as follevs:
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73ULATORY DOCKET FILE COPY
Directorate of Licensing June 13, 197L RC Flev:
80 X 10' lbs/hr RC Pressure: 1000 psig RC Temp.:
350 F PRZR Level:
100 in.
FRZR Te=p.:
550 F (6)
Description of Occurrence: At 1610 en June 3, 197L, an operator en a routine tcur discovered a leak to te cc=ing frc= a failed sccket veld in *.ce water supply line frc= the reacter ecolant
=ake-up p=p discharge header to the core flced tanks. Upon dis-covery of the leak, the system volu=e inventory and pressure were verified as acceptable, and the EP injection ESAS signal was bypassed. The steam generators were isclated en the secondary sides and the operating reacter coolant pu=ps (lA and 1D), and the operating =ake-up pu=p (13) were i==ediately secured. The affected pcrtien of the take-up syste= vas then isolated by valve closure for repair.
(7)
Designatien of Apparent Fause of Occurrence:
Installatien/Construc-tien in that insufficient reinforce =ent of the veld alleved a crack to propagate cutvard frc= the root of the veld.
(8)
Analysis of Occurrence: At the time cf the occurrence, the reactor had not yet achieved initial criticality, therefore, there were no actual er threatened safety related problems with regard to either (a) exceeding core protection pressure /te=perature limits, or (b) inadvertantly releasing radicactive =aterials frc= the reactor coolant system.
In the event initial criticality and pcuer operatiens had cecurred prier to the incident, it is believed there still vould have been no safety related proble=s in that (a) the leak wouli again have been isolated, (b) it would have been possible to have two =ake-up pumps 'ined up to provide take-up water to the reacter coolant syste=, and (c) there are check valves installed in the lines leading frc= the
=ake-up pu=p discharge header to the reactor ecolant system which would have prevented reacter ecclant system water frc= flowing to the point of the leak.
(9)
Corrective Action: I==ediate corrective acticns censisted ef:
(a) isolating the OTSG seccndary sides, (b) stepping the operating coclant pu=ps (lA and 1D),
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Directorate of Licensing June 13, 1974 (c) decreasing reacter ecclant pu=p seal injectien, (d) stopping the operating =ake-up pump (13), and (e) isclating the leaking secticn cf the =ake-up syste= by valve closure.
The Plant Operatiens Review Cc==ittee (FCRC) =et prc=ptly after the incident and recc== ended to the Staticn Superintendent that (a) the defective veld be repaired, and (b) that cther sLnilar velds en the make-up header be inspected and any noted deficiencies be corrected as seen as possible.
The Station Superintendent cencurred with PCRC's recc==endaticas, and the recc== ended corrective acticns have been ec=pleted.
(10)
Fa'. are Data:
(a) Previous Failures: Not Applicable.
(b) Equip =ent Identification: Not Applicable.
Sincerely, em
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1 R. C.'IIGOLD Vice President-Generatien RCA:DNG:sh ec: Directcrate of Regulatcry Operations, Region 1 U. S. Atc=ic Energy Cec =issicn 631 Park Avenue King of Prussia, Pennsylvard a 19LC6 File 7 7 3 5 1 20.1.1
.