ML19256D687
| ML19256D687 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/01/1977 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Herbein J METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19256D685 | List: |
| References | |
| NUDOCS 7910220606 | |
| Download: ML19256D687 (2) | |
Text
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UNITED STATES yg
't L JLEAR REGULATORY COMMisslON I
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Docket No. 50-289 Metropolitan Edison Company ATTN: Mr. J. G. Herbein Vice President P. O. Box 542 Reading, Pennsylvania 19603 y
Gentlemen:
Subject:
Decay Heat Removal Pumps This refers to the telephone conversation on September 1,1977, between Mr. A. B. Davis of this office and you, Mr. L. L. Lawyer, and others of your organization, in which you agreed to the following inspections /
actions regarding the Three Mile Island Unit 1 Decay Heat Removal Pumps.
These inspections / actions may be deemed to be unnecessary if you submit a safety evaluation which justifies that the pumps in their present condition can perform their functions as prescribed in the Safety Analysis. for Three Mile Island Unit 1, and this safety evaluation is reviewed and accepted by the Office of Nuclear Reactor Regulation.
1.
The pump with the longest operating history under those conditions specified by your Nuclear Steam System Supply (NSSS) vendor or Generation Engineering Department to most enhance a fatigue failure of the shaft, will first be inspected to determine the condition of the shaft. The pump shaft in the area under the impeller and at the keyway shall be examined by liquid penetrant test in accordance with Section XI of the ASME Code.
In addition, the radius of the keyway will be measured in accordance with instructions provided by your HSSS vendor or Generation Engineering Department.
If the shaft shows indications of fatigue failure or if the keyway radius is not within tolerances provided by the NSSS vendor or Generation Engineering Department, the pump shaft will be replaced or repaired.
2.
If.the pump examined under item 1 requires shaft replacement / repair, this replacement / repair shall be started icmediately.
After comple-tion of this replacement / repair, imediate inspection of the second pump will be initiated and necessary shaft replacement / repair made in accordance with item 1, above.
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3.
If the pump examined under item 1 does not require shaft replace-ment, the second pump will still be examined in accordance with item 1.
This examination will be completed by October 1,1977.
If the shaft shows indication of fatigue failure or if the keyway radius is not within tolerances provided by the NSSS vendor or Generation Engineering Department, the pump shaft will be replaced /
repaired.
4.
Disassembly of the first pump for examination will commence by 8:00 a.m., September 9,1977, unless this is deferred in writing by this office based on a safety analysis subaittal !by ydu.
If odr ' understanding of your planned actions as described above is act in accordance with the actual plans, please contact th,is office immediately.
Sincerely,
.y Grier
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L. L. Lawyer, Manager, Generation Operations - Nuclear G. P. Miller, Superintendent J. P. O'Hanlan, Unit 1 Superintendent R. W. Heward, Project Manager, GPUSC Miss Mary V. Southard, Chairman, Citizens for a Safe Environment bec:
IE Mail & Files (For Appropriate Distribution) ~-
Central Files Public Document Roca (POR)
Local Public Doc:: ment Rocm (LPDp)
Ruclear Safety Infort:ation Cantar Technical Infomation Center (TIC)(NSIC)
REG:I Reading Rocm f
C-m,alth of Pennsylvania L6na Cobb, IE:HQ W. P. Ellis, IE:HQ G. L. Snyder, R1 H. D. Thornburg, IE:HQ R. Woodruff, IE:HQ
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