ML19210A133

Event Rept 76-14/3L:on 760427,valve Stem for DH-V1 Placed on Operation While Released Only for Installation.Caused by Personnel Not Obtaining Proper Documentation.Personnel & Mgt Notified of Proper Procedures

ML19210A133
Person / Time
Site:	Three Mile Island
Issue date:	05/27/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
ER-76-14-3L, GQL-0780, GQL-780, NUDOCS 7910240852
Download: ML19210A133 (4)

Text

• U.S. NUCLE AR REGULATOR Y ' M MISSIO N DOCKCT NUMDER ditC FOnu IDS '

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50-299 rlLE NUMurn NRC DISTR!BUTION FOR PART 50 DOCKET MATERI AL INCIDE:;T REPORT TO: F R O.'.1: DATE OF DOCUMENT METROPOLITAN EDISON COMPANY 5/27/76 R. W. REID ,' READING, PA. DATE RECEIVED R. C. ARN R 6/1/76 MLETTER ONOTORIZED l'R OP INPUT FORM NUMBER OF COPIES RECEIVED

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' OESCRIPTION . , E N CLOSU RE LICENSEE EVENT RPT. (R0 50-289/76-14/3L) ON 4/27/76 CONCERNING THE VALVE STEM FOR DH-V1 oo y _

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Director of Nuclear Reacter Regulation  ;> .\

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U.S. Nuclear Regulatory Cc==ission 631 Park Avenue King of Prussia, PA 19h06 Gentlemen:

Docket No. 50-289 Operating License DPR-50 In accordance with the Technical Specificaticn of our Three Mile Island Nuclear Staticn Unit 1 (TMI-1), we are reporting the following reportable occurrence:

(1) Report Number: IR 76-lh/3L (2a) Repor; Date: May 27, 1976 (2b) Date of Occurrence: April 27, 1976 (3) Facility: Three Mile Island Nuclear Station Unit 1 (k) Identification of Occurrence:

Title:

The valve ste for DH-VI was placed in operaticn while it was released for installaticn only.

P Type: A reportable cecurrence as defined by Technical Specification 6 9 2.3.(3) in that administrative centrols vere improperly i=ple=ented, which could have threatened to cause a reduction of the degree of redundancy provided by the Decay Heat Removal System.

(5) Cenditiens Prior to Event:

Pover: core: 0,.

5401 Elec.: 0 MWe RC Temp.: 1100F 1490 019

RC Flow: 0 RC Pre.__.. O PEZR Level: 0 PRZR Temp.: Ambient (6) Descriptita vf Event:

The valve stem in DH-V1 was replaced with a new stem. The new sten was satisfactory; however sc=e of the documentation required by the purchase order was not received. Because the requirements of the purchase order were not fulfilled, the material was released for installation only. Contrary to che Release for Insta11atien Crly Agreement, the valve was placed in operation.

(T) Designatien of Apparent Cause of Event:

The cause of this event has been determined to be personnel error.

Although the Release for Installation Only Agreement was made kncvn to operations personnel, the valve was placed in use hefore the documentation question was resolved.

(S) Analysis of Event:

Due to plant conditions at the time of the cecurrence, the violation of the procedure did not ec=prc=ise nuclear safety. The existing docu=entati< n on the stem was later determined to be adequate; therefore, n. threat to the health and safety of the public was involved. However, such a violatien under different circu= stances could have caused a reduction in the Decay Heat Removal System redundancy.

(9) Corrective Action:

L=:ediate :

1. The Unit Superintendent was notified of the violation of the agreement.

2. PORC evaluated the consequences of this situation.

Long Ter=:

1. An engineering evaluation was obtained verifying that the docu=entation obtained is satisfactory for long tez= use of the valve ste= in a nuclear safety related applicaticn.

2. A meeting was held between the Superviser of Quality Centrol and Supervisor of Operatiens to assure understanding and future co=pliance with Generaticn Procedure GP hh09 " Acceptance of Nuclear Safety Related Equipment for Insta11atien Only".

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3. The above procedure was evaluated and deter ined to be adequate.

(10) Failure Data:

II/A (10a) Similar Occurrence:

ER 75-18 Sincerely, R. C. nold Vice President RCA:JJM:ilm 1490 021