ML19261F333
| ML19261F333 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/20/1977 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19261F334 | List: |
| References | |
| GQL-0854, GQL-854, NUDOCS 7910250793 | |
| Download: ML19261F333 (5) | |
Text
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NRC PORu 195 U.S. NUCLE AR REGULATORY COMMISSION 00 NU E
FILE NUMbSR NRC DISTRIBUTION poR PART 50 DCCKET MATERIAL INCIDENT REPORT TO *.
FROM:
OATE OF OCCUMENT J P 0'Reilly Metropolitan Edison Co 6-29-77 Reading, Pa DATE RECEIVt0 J G Herbein 6-28-77 L TTER O NOTO RIZ E D PRCP
- NPUT PCRM NUMBER OF CCPIES RECEIVEO MORIGIN AL MNC LAS$1FIE D cecFv I
5 I for)GD CESCRIPTION ENCLOSURE Licensee Event Report (RO# 77-14/3L) on 5-24-77 concerning failure of reactor building isolation valve to close on an engineering cafeguard signal..............
DO NOT RE110YE, Three Mile Island #1 '
ACKNOWLEDGED NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. CLLLINS 6-28-77 eljf FOR ACTION /INFORMATION BRANCH CHIEF:
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METROPOLIIAN EDISON COMPANY POST OFFICE BOX 542 READING, PENNSYLVANIA 19603 ELEPHONE 215 - 929CE01 June 20, 1977 GQL Oe5h K.
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Mr. J. F. O'Reilly, Director Office of Inspections and Enforcement, Region 1 C
U. S. IIuclear Regulatory Con =ission 631 Park Avenue King of Prussia, Pa.
19h06
Dear Sir:
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Docket IIo. 50-289 Operating License IIc. DPR-50 In acccrdance with the Technical Specifications of our Three Mile Island
?!uclear Station Unit 1 (TMI-1), we are reporting the folleving reportable occurrence.
(1) Report :Iumber: 77-lh/3L (2a) Required Report Date: 6/23/77 (2b) Date of Occurrence: 5/2h/77 (3) Facility: Three Mile Island :Tuclear Station - Unit I (h)
Identification of Occurrence:
Title:
Reactor Building Isolation Valve failed to close en an :ngineering Safeguards Tes'. Signal.
Type:
A reportable occurrence as defined by Technical Specification 6.9.2.E(2) in that the Reacter Building Isolaticn Valve, RB-V7, failed to close on an Engineering Safeguards Test Signal, leading to operation in a degraded mode permitted by a limiting condition for operation as defined by 3.6.6.
1482 066
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June 20, 1977 Mr. J. P. O'Reilly, Director GCL OS5h (5) Ccnditions Prior to occurrence:
Power:
Cor-2510 MWt Elec: 622 VWe RC Flow:
lh3 x 106 lbs/hr RC Pressure:
2150 psig C
RC Temp:
579 F PRZR Level:
220 in.
PRZR Temp:
650 F (6) Description of Occurrence:
While performing SP 1303-5 1, " Reactor Building Cooling and Isolation System Logic Channel and Compcnent Test", RB-V7, Reactor Building Cooling Return Isolation Valve, failed to close upon receipt of the Engineering Safeguards Actuation Signal.
(7) Apparent Cause of Occurrence:
The cause of this occurrence has been determined to be material in that, dirt was en the seat of the diaphragm assembly of the solenoid valve supplying air to RB-V7.
This dirt prevented the diaphragm disc from prcperly seating when the solencid valve was energized. Therefore, air would not vent frcm RB-V7's actuator.
(8) Analysis of Jecurrence:
It has been determined that this occurrence did not constitute a threat to the he11th and safety of the public in that-1)
R3-V7 was able to be closed by manually bleeding air frcm t'. e operator.
2)
The normal Reactor Building Cooling units vould have prevented any leakage from the Reactor Building during LOCA conditions.
\\h0.
June 20, 1977 Mr. J. P. O'Reilly, Director GQL 085h
'9) Correctiva Action:
Immediate:
1)
RB-77 was placed in its Engineering Safeguards position (closed) by bleeding off the air from the operator.
2)
Reactor Building 2:ergency Cooling was established through AH-E1A and 13.
Note: This valve is a Cloaed System Isolation Valve and according to 10CFR50, Appendix A, Criterion 57, a redundant valve on the pipe is net necessary.
Therefore, the section in Technical Specification 3.6.6 does not apply since the redundant 'ralve does not exist.
Long Term:
1)
The solenoid valve was elecned and its internal ccmponents replaced.
2)
The air supply line and in-line filter vere cluaned.
3)
R3-77 was tested satisfactorily.
h)
RB-V7 has been test cycled daily for approximately fc ar (h) days and will continue to be cycled weekly for three (3) veeks to assure proper operation.
The Plant Operations Review Ccnmittee and Unit Superintendent have reviewed and approved the above corrective action el have taken steps to assure its completion.
14Bi2068
- 4r. J. P. O'Reilly, Director h-June 20, 1977 GQL OS5h
- 10) Failure Lata:
ASCO 3 way Solenoid Valve 120V DC Solenoid Catalogue :Iumber 80173 Valve Catalogue IIurloer 8316Ch5 Serial iumber: h2h713 Similar Cecurrences:
- ione Sincerely,
/
/
lA J. G. Herbein Vice President JGH:DG1:rk
Attachment:
L.E.E.
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