ML19210A162
| ML19210A162 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/27/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A163 | List: |
| References | |
| GQL-1214, NUDOCS 7910240887 | |
| Download: ML19210A162 (4) | |
Text
/
N R C C' RIBUTION FOR PART SO DOC _K_E- " ATERI AL (TEMPORARY FORM)
CONTROL NO:
FILE: II: CIDE:Tr REPENT rI:.E FROM. Metr Politan idison Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Reading, Penna.
R.C. Arnold 6-27-75 7-1-75 xxx
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TO:
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tiRC 1 Signed SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
xxxx 1
50--2S9 DESCRIPTION:
ENCLOSURES:
A/O # 75-18, on 6-16-75, concerning Inadequate control of vendor performed work.......
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PLANT NAME:
Three Mile Island #1 FOR ACTION /lNFORfbATION VCR 7-3-75 BUTLER (L)
SCHWENCER (L) ZIEMANN (L)
REG AN (E)
W/ Copies W/ Copies W/ Cooies W/ Copies
[ LE AR (L)
CLARK (L)
STOLZ (L)
DICKER (E)
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PARR (L)
VASSALLO (L)
KNIGHTON (E)
SPELS W/ Copies W/ Copies W/ Copies W/ Copies KNIE L (L)
PURPLE (L)
YOUNGBLOOD (E)
W/ Copics W/ Copies W/ Copics W/ Copies INTERNAL DISTRIBUTION en -
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TECH REVIEW CENTON LIC ASST A/T IN D.
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BRAITh1AN NBCFun pSCHROEDER j
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SALTZMAN GOSSICK/STAF F KNIGHT KASTNER E. GOULBOURNE (L)
MELTZ CASE PAWLICKl BALLARD P. KREUTZER (E) f GIAMBUSSO SHAO SPANG LE R J. LEE (L)
PLANS BOYD
MCDONALD MOORE (L)
- fHOUSTON ENVIRO S. REED (E)
CHAPMAN DEYOUNG (L)
,,.NOVAK MULLER M. SERVICE (L)
DUBE (Ltr)
SKOVHOLT (L)
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E. COUPE GOLLER (L) (Ltr) lPPOLITO KNIGHTON M. SLATER (E)
PETERSON f
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/TEDESCO YOUNG B LOOD H. SMITH (L)
HARTFIELD (2)
DENISE J. COLLItiS REGAN A. TEETS (L)
KLECKER REG OPR LAIN AS PROJECT LDR / G. WILLI AMS (E)
EISENHUT
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BENAROYA V. WILSON (L)
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VOLLMER HAR LESS R. INGRAM (L)
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METROPOLITAN EDISON COMPANY r.
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PCST OFFICE BOX $42 RE ADING. PENNSYLVANI A 19603 TELEPHONE 215 - 929-38,01 June 27,1975 GQL 1214 Director s
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/U O' Directorate of Reactor Licensing
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U.S. Nuclear Regulatory Commission Washington, D.C.
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Dear Sir:
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Operating Licence DPR-50 Docket #50-289 t
In accordance with Technical Specifications for the Three Mile Island Nuclear Station Unit I, we are reporting the following abnormal occurrence:
(1) Report Number: A0 50-289/75-18 (2a) Report Date: June 27, 1975 (2b) Occurrence Date: June 16, 1975 (3)
Facility: Three Mile Island Nuclear Station Unit I
(')
Identification of Occurrence
Title:
Inadequate control of vendor performed work.
Type:
An abnormal occurrence as defined by Technical Specifications, paragraph 1.8g, in that the inadequate control of vendor performed work constituted an observed inadequacy in the implementation of administrative or procedural controls that threatened to cause an unsafe condition in the operation of the plant.
(5)
Conditions Prior to Occurrence:
Power:
Core: 99%
Elect.: 824 MRe (Gross) 0 RC Flow: 137 x 10 lbs/hr 1490 105 7020
. RC Pressure: 2155 psig RC Temp.: 579 F PRZR Level: 215 inches PRZR Temp.: 650 F (6)
Description of Occurrence:
The motor for Decay Heat River Water Pump DR-P-1B was received from a vendor repair facility following repairs made necessary by the motor's shaf t having failed (ref: A0 50-289/75-14). In that administrative / procedural controls were not adequate to ensure that a vendor received appropriate QA/QC requirements prior to commencement of work, adequate documentation fro
_he vendor, providing a detailed description of the repair work performed, did not accompany the motor upon its return to Three Mile Island Nuclear Station Unit 1.
Attempts were then made to obtain the necessary documentation, and when it was realized that the vendor would not supply the documentation due to the motor not having been repaired in accordance with original design specifications, an independent evaluation was conducted by the Met-Ed Technical Support Staf f.
Further, the result of this evaluation was that the repairs were in f act adequate for the pump to continue meeting the operability requirements of TMI-l Technical Specification 3.3.1.4.d.
(7) Designation of Apparent Cause of Occurrence:
The apparent cause of the occurrence has been determined to be procedure, in that for rush priority vendor work, administrative / procedural controls are not adequate to ensure that vendors receive appropriate QA/QC requirements prior to the commencement of work.
(8) Analysis of Occurrence:
It has been determined that this occurrence did not constitute a threat to the health and safety of the public in that a,
other vendor performed rush priority work has adequate documentation, in accordance with the Operational Quality Assurance Plan, to assure that this work was performed so as to meet appropriate QA/QC requirements, and b.
the capability of the decay heat river water system was not degraded during reactor operations.
Further, this later determination is based on the fact that a.
only one Decay Heat River Water Pump is required during accident conditions, and the redundant pump was at all times operable, and b.
based on the evaluation conducted by the Met-Ed Technical Support Staff, the "B" pump was also operable during reactor oper. ' ions.
1490 106
. (9), Corrective Actions:
With regard to Decay Heat River Water Pump DR-P-1B :
a.
as previously described, corrective actions were taken to ensure that the vendor performed work was acceptable, and b.
s ubs equent to this evaluation, the pump was taken out of service,
further up-graded, and put back into service so that it now exceeds the original design specifications.
With regard to the administrative / procedural control inadequacy with which this report is primarily concerned:
a, personnel placing orders for rush priority vendor work have been made aware of the need to ensure that appropriate QA/QC requirements are specified so as to better control these work activities, and b.
appropriate additional administrative / procedural measures will be instituted by July 11, 1975, so as to prevent a recurrence of this type of situation.
The Plant Operations Review Committee and S tation Superintendent reviewed this occurrence, but have yet to be made a party to all of the above stated, yet to be completed corrective actions. Following completion of their further review, appropriate steps will be taken to ensure completion of c11 the above stated corrective actions, and any other actions that may be deemed necessary.
(10) Failure Data:
Not applicable Sincerely,
R. C.
rnold Vice President RCA:CWS:pa File 23.1.1/7. 7.3.5.1 1490 107