ML19261F211
| ML19261F211 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/07/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-1680, NUDOCS 7910250630 | |
| Download: ML19261F211 (4) | |
Text
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S NRCFORM 195 U.s. NUCLE AR REGULATORY cu JSION DOCKET NUM BE R A
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FILE NUMRE R NRC DISTRIBUTION FOR PART 50 DOCKET MATERI Al-INCIDENT REPORT TO:
FROM:
DATE OF DCCUMENT Ie tro?cli tan Cd' son Compan-12/-' :
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Reading, Pa.
DATE RECEIVED
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[O R IGIN AL MNC LASSIFIE D C"'
S i ?-.c 3 OcOPY DESCRIPTION ENCLOSuhE Ltr. trans the follo rin;:
Licens ae vent 7.c art (R0 59-2M/76 '.1/?L) on 11/7/70 concernin; an emoty fluti rescrcoir o f t'.:e ' audraulic s::ock & s. a:- su,,rassar located at oosition RCJi 6 t._P T W ol,i,TT S T m p ;
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PLANT NAME:
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'.ile Island Unit :;o. 1 NOIE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION /INFORMATION 12/ 23/ N OL iKi BRANCH CHIEF:
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Mr. J. P. O'Reilly, Directer Office of Inspections and Enforcement, Region I U. S. Iluelear Regulater/ Cer issien
\\-n 631 Park Avenue M f-King of Prussia, PA 19hC6 ni
Dear Sir:
1 Docket :io. 50-289 Cperating License No. DPR-50 In accordance with the Technical Specifications of cur Three Mile Island nuclear Station Unit 1 (TMI-1), we are reperting the folicving reportable occurrence:
(1) Report Number: 76 kl/3L (2a) Required Report Date: 12/07/76 (2b) Date of Occurrence :
11/07/76 (3) Facility: Three Mile Island Nuclear Statien - Unit 1 (h) Identification of Occurrence:
Title:
Empty Fluid Reservcir of the hydraulic Sheck & Sway Suppresscr Located at Position RC-14 Type:
A reportable occurrence as defined by Technical Specification 6.9.2.3 (2) in that one (1) hydraulic shcck a sway suppresser (snubber), located at RC-lh, was found inoperative due to less cf fluid thus leading to cperation in a degraded =cde permitted by a limiting condition for operation as defined by Technical Specification 3.16.h.*
(5) Conditions Prior to Cecurrence:
Power: Core 0
E1ec C
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- Please note that Technical Specificatien 3.16.4 is included in Technical Specification Change Request (TSCR) 19 Amendment A.
Althcugh Met-Ed does not have to repcrt the snubber because section 3.16.h has net been approved, we feel it is appropriate to infer: ycu cf the cccurrence and after T.S.C.R. 19 A=endment A is approved vill report such Occurrences under the stated section.
1481 162
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J. P. O'Reilly CQL 1680 RC Flcv 75 x 106 lb/hr EC Pressure 300 psig RC Temperature 2330 F PR R Level 307 inches FRZR Temperature h220 F (6) Description of Occurrence:
Cn Ucvember 7, 197c, at 1hCC hours, during routine surveillance of the snubbers located inside the Reactor Building Secondary Shield vall, one (1) snubber located at position RC-lh en the pressurizer spray line was fcund with an empty fluid reservcir. When placed cn a test stand, the snubber failed to lock as specified.
I :ediately snubber RC-lk was rebuilt using ethylene propylene seals. All seals were installed and the unit was satisfactorily tested on a test stand and returned to service.
(7) Designation of Apparent Cause of Occurrence:
The cause of this cccurrence has been determined to be rersennel in that a close examinatien of the seals re=cved frc the inoperable snubber en UcVerber 13, revealed that the main pisten rod seal was damaged and could not have sealed properly. This seal damage was probably due to improper installation. Also, one (1) 0-Ring ms found to be missing.
Its absence could have centributed to the fluid 1c s.
(8) Analycis of Occurrence:
This occurrence did not constitute a thre?.t to the health & safety of the public in that:
1.
Two (2) snubbers are installed at this location (RC-13, RC-1k).
The f lilure of cne (1) snubber vould be of censequence only during a seismic event. Excessive vibration eculd cause overstressing and possible failure of the pressurizer spray line (PSL); however, the PSL is very conservatively designed and such breaking of the line is censidered extremely unlikely under any circumstances.
2.
Eight (8) snubbers are installed on the PSL and two (2) of these (RC-11, RC-12) are within sevan (7) feet of EC-1k.
As these snubbers vould have functioned properly during a seismic event it is unlikely that any failure cf the FSL cculd have resulted.
(9) Ccrrective Action:
In additien to the irrediate corrective action described above, this snubber vill continue to be checked in accordance with the present snubber surveillance prcgra for these snubbers inside the Reacter Euilding Secondary Shield vall at each convenient cutage.
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'Mr. J. P. O'?.eilly GQL 1680 (10) Failure Data:
Snubber Manufacturer: 3asic Engineers Cylinder '1'ype:
Easic Engineers Size: 3/L" Strcke:
5" Similar Events Th-lk, 20, 23, 25, 30 75-03, 08, 09, 3h 76-7 Sincerely, f'
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L R. C.' Arnold Vice President RCA:DGM:kl
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