ML19210A217
| ML19210A217 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/21/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A218 | List: |
| References | |
| NUDOCS 7910240932 | |
| Download: ML19210A217 (4) | |
Text
.
NRC _ STRIBUTION FOR PART 50 DOCK M ATERI AL (TEMPORARY FORM)
CONTROL NO:
7827 s
FILE: INCIDE:Tr REronT FI -
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- Met. Edison Co.
DATE OF DCC DATE REC'D LTR TWX RPT OTHER Rehding, Pa.
19603 7-21-75 7-23-75 XX o_c_ A-nMd TO:
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NRC 1 signed SENT LOCAL PDR XX CLASS UNCLASS PROPINFO
- NPUT NO CYS REC'D DOCKET NO
XXX 1
50-289 DESCRIPTION:
Ltr advising of Abnormal ENCLOSURES:
Occurrence A0-50-289/75-22 on 7-11-75 re socket weld joint leaks in the suction vent line for the Make-Up Pump (MU-PIA)..
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br a, b... m w J7 PLANT NAME:
Three Mile Island Unit 1
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FOR ACTION /INFORT.1ATION DHL 7-24-75 BUTLE P. (L)
SCHWENCER (L) ZlEMANN (L)
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W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)
STOLZ (L)
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DEAR (L)
W/ Coo;es W/ Cooies W/ Cocies W@opies PARR (L)
VASSALLO (L)
KNIGHTON (E)
SPELS W/ Copies W/ Copies W/ Copics W/ Copies KNIE L (L)
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YOUNGBLOOD (E)
W/ Copies V// Copies W/ Copics W/ Copies INTERNAL DISTRIBUTION 6< EG FI LD TECH REVIEW CENTON LIC ASST A/T IN D h run pSCHROEDER jGRi?.1ES R. DIGGS (L)
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SA LTZM AN GOSSICK/STAF F KNIGHT KASTNER E. GOULBOURNE (L)
MELTZ CASE PAWLICKi BALLARD P. KREUTZER (E) f GI AM BUSSO SHAO SPANG LE R J. LEE (L)
PLANS BOYD
MCDONALD MOORE (L)
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_E NVi R O S. REED (E)
CHADMAN DEYOUNG (L)
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DUBE (Ltr)
SKOVHOLT (L)
,.RCSS DICKER S. SHEPPARD (L)
E. COUPE GOLLER (L) (L:r)
IPPO LITO KNIGHTON M. SLATER (E)
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/TEDESCO YOUNGBLOOD H. SMITH (L)
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Director Division of Reactor Licensing
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20555
Dear Sir:
Docket No. 50-289 Operating License No. DPR-50 In accordance with the Technical Specificctions of our Three Mile Island Nuclear Station Unit 1 (TMI-1), we are reporting the following abnormal occurrence.
(1) Report Number: A0 50-289/75-22 (2a) Report Date: July 21, 1975 (2b) Occurrence Date: July 11, 1975 (3)
Facility: Three Mile Island Nuclear Station Unit 1 (4)
Identification of Occurrence:
Title:
Socket weld joint leaks in the suction vent line for the Make-Up Pump (MU-PlA).
Type:
An abnormal occurrence as defined by the Technical Specifications, paragraph 1.8e, in that leaks from this Make-Up Pump suction line constituted abnormal degradation of a system boundry designed to contain radioactive materials.
(5) Conditions Prior to Occurrence:
}4]h 2kb Power: Core: 100%
Elect.: 870 W e 7827 RC Flow: 140 x 106 lb/hr RC Pressure: 2155 psig RC Temp.: 579 F PRZP Level: 240 inches PRZR Temp.: 6500F (6) Description of Occurrence:
On July ll,1975, during a routine inspection of the Auxiliary Building, two leaks were discovered in socket weld joints of the Make-Up Pump (MU-PLA) suction vent line leading to valve MU-V156A.
One leak on this vent line was a crack in the weld joint adjacent to the 6 inch diameter Make-Up Pump suction line. The other leak was a pinhole crack in the weld joint of a 900 elbow fitting on this same vent line.
Immediately upon discovery, these leaks were isolated.
(7) Designation of Apparent Cause of Occurrence:
Installation procedures specify 80 inches to be the minimum space between a moving anchor and the first pipe restraint. This specification allows sufficient flexibility in the pipe between the moving anchor and the first pipe restraint to prevent cyclic f atigue failure. For the vent line only 23 inches of space between anchor and restraint existed allowing cyclic stresses to cause f atigue f ailure of the weld joints on this line. Therefore, the apparent cause of this occurrence is installation / construction.
(8) Analysis of Occurrence:
It has been determined that this occurrence did not represent a threat to the health or safety of the public, in that only two Make-Up Pumps are required for normal system operation, a.
b.
the effected pump was immediately isolated, and c.
no detectable increase in radiation levels were observed.
(9)
Corrective Actions:
In addition to the immediate corrective action listed above, long term corrective actions were to:
modify the restraints to conform to the instr.11ation specifi-a.
cations, and b.
inspect and verify that similar conditions did not exist on "B"
and "C" Make-Up Pumps.
1 A 7 6 'c) 4 o'
The Plant Operations Review Committee and Station Superintendent have reviewed and approved the above listed corrective actions.
(10) Failure Data:
Pipe:
3/4 inch diameter Schedule 40S ASTM A 312, type 304 Stainless C teel Socket Welds.
Similar Occurrences: None Since rely,
W R. C. Arnold Vice President RCA/CWS/cas cc: Of fice of Inspection and Enforcement, Region 1 File:
20.1.1/7.7.3.5.1 1,476 247