ML20084L083

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Ao:On 740514,standby Liquid Control Relief Valve 1-1105A Operated Above Tech Spec Limit.Caused by Possible Crud Buildup Interfering W/Valve Operation.Two New Valves & Spare Parts Ordered
ML20084L083
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 05/24/1974
From: Kalivianakis N
COMMONWEALTH EDISON CO.
To: Oleary J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084L085 List:
References
NJK-74-90, NUDOCS 8305200228
Download: ML20084L083 (3)


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Mr. John F. O ' Leary, Director Directorate of Licensing Regulation U.S. Atomic Energy Com. mission Vashington, D.C.

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Reference:

Quad-Cities Nuclear Power Station Unit 1. Docket No. 50-254, DPR-29, Appendix A, Sections 1.0.A.4, 4.4.A.2, 6.6.B.1.A

Dear Mr. O' Leary:

The purpose of this letter is to inform you of the details concerning 1-1105A standby liquid control relief valve which test operated at 1600 and 1680 psig, thus exceeding Technical Specification 4.4.A.2.

This abnormal occurrence was previously reported to you by telegram, and to Region Ill, Directorate of Regulatory Operations personnel by telephone and telegram on May 15, 1974 PROBl.EM AND lHVESTICATION With Unit I locked in shutdown mode for the current refueling outage, a sur-

- veillance test was perforned on 1-1105A and B SSLC relief valves to determine the relief valve set points. The 1-1105A valve lif ted at 1600 psig and the 1-1105B valve lifted at 1470 psig. A calibration check of the SBLC pump out-let pressure indicator (PI-1-Il57) was performed and the surveillance test was repeated on May 14, 1974 The I-1105A valve then lifted at 1680 osig and

,the 1-1105B valve lifted at 1600 psig. Both valves were disassembled and in-spected. No worn or broken parts were found. The valve seats were removed, cleaned, replaced, and the valves were reassembled. Tne valves were set to relieve within the 1400 - 1490 psig range. On May 17,1974, the surveillance test was again reccated. The 1-Il05A valve lifted at 1460 psig and the 1-11053 valve lifted at 1490 psig. This test was immediately repeated and gave the same results.

EVALUATION AND CORRECTIVE ACTION Safety Imolientinns Surveillance testing was previously perforr:cd on April 10, 1974, and both valves lifted within the 1400 - 1490 psig range. The increases in SSLC relief valve set points were in the safe direction, allcwing for continued cumping of sodium pentaborate solution into the reactor if the SDLC system was required to be Thus, the safety irplications of these set point chang les are minitral.

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RO Inspection Report No.

Transmittal Date Distribution:

Distribution:

R0 Chief, FS&EB RO Chief, FS&EB RO:HQ (5)

RO:HQ (4)

DR Central Files L:D/D for Fuels & Materials Regulatory Standards (3)

DR Central Files Licensing (13)

RO Files R0 Files B.

R0 Inquiry Report No.

Transmittal Date Distribution:

Distribution:

RO Chief, FS&EB R0 Chief, FS&EB RO:HQ (5)

RO:HQ DR Central Files DR Central Files Regulatory Standards (3)

RO Files Licensing (13)

RO Files C.

Incident Notification From: Commonwealth Edison Company Docket No. 50-254 (Licensee & Docke,t No. (or License No.)

Transmittal Date

June 4, 1974 Distribution:

Distribution:

RO Chief, FS&EB R0 Chief, FS&EB RO:HQ (4)

RO:HQ (4)

Licensing (4)

L:D/D for Fuels & Materials DR Central Files DR Central Files R0 Files RO Files

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