ML19261F325
| ML19261F325 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/20/1977 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19261F326 | List: |
| References | |
| GQL-0971, GQL-971, NUDOCS 7910250787 | |
| Download: ML19261F325 (4) | |
Text
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NRC PoRu 195 U.S. NUCLE A R REGULA TORY A4 MIS 31oN cock ' NUMBER de (2 76)
NRCplSTRIBUTION Pom PART 50 DOCKET MATERIAL INCIDENT 9FPAPT TO:
FROM:
DATE or cocVMENT B. H. Grier Metropolitan Edison Co.
7/20/77 Reading, PA cary RgCaivgo J. G. Herbein 7/28/77 ETTER ONOToRIZED PROP INPUT PoRM NUMBER OF COPIES RECEIVEo
[U NC LASSIFI E D I sig aed Ricin AL cc-oESCRIPT1oN ENCLOSURE Licensee Event Report (50-289/77-17/3L) on 6/24/77 concerning the inner door seal on the personnel access hatch leaking excessively causing the total of reactor building local leakage to exceed to 0.6 La criteria of section
- 4. 4.1. 2. 3 of the Tech Spec.
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RET 7/28/77 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION /INFORMATION nos='ru ruTev.
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METROPOLITAN EDISON COMPANY POST OFFICE BOX 542 RE ADING, PENNSYLV ANI A 19603 TELEPHONE 215 - 929-2001 July 20, 1977 GQL 0971
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- s. [A^ -dp/'# U Mr. B. H. Grier, Director Z C Office of Inspections and Enfcrce=ent, Region 1
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U.S. Nuclear Regulatory Co==ission
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x King of Prussia, PA 19h06 9
Dear Sir:
.j Docket No. 50-289 Operating License No. DPR-50 In accordance with the Technical Specifications of our Three Mile Island Nuclear Station Unit 1 (TMI-1), we are reporting the following reportable occurrence:
(1) Report Number: 77-1T/3L (22) Required Report Date: 7-22-77 (2b) Date of Occurrence: 6-2h-77 (3) Facility: Three Mile Island Nuclear Station - Unit 1 (h) Identification of Occurrence:
Title:
Reactor Building Local Leakage Exceeded 0.6 La Criteria Type:
A reportable occu rence as defined by Technical Specificatien 6.9 2.B (2) in that the inner door seal on the personnel access hatch leaked excessively, caucing the total of Reactor Building Local Leakage to exceed the 0.6 La criteria of section h.h.1.2.3 of the Technical Specification.
1482 050 772090355
3 H. drier, Director July 20, 1977 GQL 0971 (5) Ccnditions Prior to occurrence:
Fover: Core:
2351 MWt Elec:
838 MWe Gross RC Flow:
1ho x 10 lb/hr RC Pressure:
2155 psi 0
RC Temp.:
579 F FRER Level:
215 inches FR;R Temp.-
650 F
.)
Description of Occurrence:
During a semi-annual leak test, gross leakage was noted around the inner door seal of the personnel access hatch of the Reactor Building.
Through visual inspection, it was determined to be the result of improper streng-back installation. After hatch depressurization, the outer door was opened to gain entry to the hatch for strongback removal and inspection.
The total potential leakage was approximately 2h0,000 SCCM. (acceptance criteria is 111.899 SCCM which corresponds to the 0.6 La Technical Specification limit).
(7) Apparent Cause of Occurrence:
The cause of this occurrence has been determined to be due to procedural inadequacies causing improper installation of the door strengbacks in that it did not give sufficient guidance to prevent the improper strengback installation.
(S) Analysis of Occurrence:
It has been determined that this occurrence did not ecnstitute a threat to the health and safety of the public in that the total of pctential Reactor Building Local Leakage cnly m'ceeded the 0.6 La limit for several minutes during which the outer door was 'rened for strongback removal.
(9) Corrective Action:
Immediate:
One of the two concentric seals en the inner door, which popped out of its groove due to the improper installation of the strengback, was inserted and the door strongbacks were re-installed, and the hatch was retested with satisfactory results within the required forty-eight hours.
Long term:
A detailed standard procedure for strengback installation and removal vill be approved and used to prevent future occurrences of this nature.
O
S. H. Grier, Director July 20, 1977 GQL 0971 The Plant Operations Feview Cenmittee and Unit Superintendent have reviewed and approved the above corrective action and have taken steps to assure its cc=pletion.
(10) Failure Data: Ncne Similar Events: Ncne Sincerely, b NFL
/
. G. Hertein Vice President-Generation JGH:0GM:kl
Attachment:
Licensee Event Report 982 052