NG-75-1158, AO 50-261/75-14:on 750715,valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to Steam Generator B Failed to Open.Caused by Belleville Spring Being Filled W/Grease.Belleville Spring Packs & Shafts to Be Inspected

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AO 50-261/75-14:on 750715,valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to Steam Generator B Failed to Open.Caused by Belleville Spring Being Filled W/Grease.Belleville Spring Packs & Shafts to Be Inspected
ML20086F583
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 07/25/1975
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20086F594 List:
References
AO-50-261-75-14, NG-75-1158, NUDOCS 8401030420
Download: ML20086F583 (4)


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Carolina Power & Light Company July 25, 1975 FILE: NC-3513 (R) SERIAL: NG-75-ll58 50- G Mr. Norman C. Moseley, Director - 7K'/ /h)

U. S. Nuclear Regulatory Commission kegion II, Suite 818 4

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, 7 ,' l'j 230 Peachtree Street, N. W.

Atlanta, Georgia 30303 3 .2

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Dear Mr. Moseley:

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Nu H. B. ROBINSON UNIT No. 2 LICENSE NO. DPR-23 FAILURE OF AUXILIARY FEEDWATER PUMP DISCHARGE VALVE V2-14B

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In accordance with Section 6.6.2.a of the Technical Specifica-tion tor H. B. Robinson Unit No. 2, the attached Abnormal Occurrence Report is submitted for your information. This report fulfills the requirement for a written report within ten days cf an Abnornal Occurrenca and is in accordance with the format set forth in Regulatory Guideline 1.16, Revi-sion 1.

Yours very truly, l/.

yE.E.Utley' hl g Vice President Bulk Power Supply DBW:pn Attachment cc: Mr. N. B. Bessac Mr. P. W. Howe Mr. J. A. Jones Mr.

Mr.

R.

W.

E. Jones B. Kincaid [ 4[,

Mr. D. Knuth J l

Mr. J. B. McGirt V Mr. D. B. Waters 8401030420 750725 l PDR ADOCK 05000261 '

S PDR b, n 336 Fayette ville treet . P. O. Box 1551. Raleigh, N C. 27602

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Abnornal Occurrence Report

1. Report No. 50-261/75-14 2a. Report Date July 21, 1975 2b. Occurrence Date July 15, 1975
3. Facility H. B. Robinson Unit No. 2 Hartsville, South Carolina 29550
4. Identification of Occurrence Valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to "B" Steam Generator failed to open. This constitutes an abnormal occur-rence as defined in Technical Specification paragraph 1.8.d.
5. Conditions Prior to Occurrence The plant was operating at 100% reactor power with all conditions normal. PT-22 " Auxiliary Feedwater System" (monthly) was being performed.
6. Description of Occurrence On July 15,1975, at 2108 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02094e-4 months <br /> during the performance of PT-22 an attempt was made to open V2-14B. On the first attempt the valve failed to open and was found to be on its seat with the Limitorque operator relayed out on thermal overload.

The thermal overload was reset and the valve subsequently operated satisfactorily two times. On a fourth attempt the thermal overload on the operator was again tripped and the valve failed to open. The valve was then declared out of service, and an I&C Technician was called to investigate. The technician reset the thermal overload on the operator and adjusted the torque switch. The valve was then test operated satisfactorily several times and was declared back in service at 0005 on July 16, 1975.

7. Designation of Apparent Cause of Occurrence Investigation on July 15th revealed that the valve was on its seat; l the Limitorque operator was relayed out on thermal overload; and the torque switch (which deenergizes the motor after the valve closes) was still closed. This would . indicate that the valve motor had stalled and relayed out (therms)ly) on its previous closing because of an improperly adjusted torque switch. The torque switch was ad-justed and the valve was retested satisfactorily several times. On s

t O O the following day, July 16, 1975, at 1003, after satisfactorily testing the motor-driven auxiliary feed pumps and associated valves, V2-14B was taken out of service to attempt to discern the reason for the misadjusted torque switch.

Internal inspection of the Limitorque operator revealed that the Belleville spring, (which resists the torquing thrust when closing the valve) was filled with grease and the shaft on which the Belle-ville spring rides was marred by a small burr under the middle of the spring. The burr was apparently caused by wear from the action of the spring. Either, or both of these factors could have changed the " stiffness" of the Belleville spring, causing the torque switch to appear out of adjustment.

8. Analysis of Occurrence There were no personal injuries, nor was there n release of radio-active materials involved in the occurrence.

) The failure of this valve would have prevented the addition of water 4 to the "B" Steam Generator from the steam-driven auxiliary feedwater l purp. At this time (July 15), however, feedwater was being supplied l

to all steam generators by the main feedwater pumps. The motor-driven j auxiliary feedwater pumps and valves had just been verified operable

  • during PT-22. (On July 16, 1975, when V2-14B was removed from service i for further inspection, the motor-driven auxiliary feedwater pumps had I also been verified operational.)

! Technical Specifications Paragraph 3.4.1 requires two of the three I auxiliary feedwater pumps to be operable. Since this was always the case, no limiting conditions of operation were violated, and the plant was continually maintained in a safe condition.

9. Corrective Action 1

Initial (July 15) corrective action was to readjust the torque switch to ensure that the Limitorque motor cut-off prior to " jamming" the valve and subsequently tripping out on thermal overload.

Y When it was later (July 16) determined that the " stiffness" of the Belleville spring had apparently been affected by grease and/or_a I burr on its shaft, these conditions were' corrected. The burr was-removed by " dressing" the shaft to a smooth surface finish; the

! grease was cleaned from the spring pack; and the torque switch ad-justment was checked. V2-14B was reinstalled at.1359 on July 16, 1975, and satisfactorily test operated several times.

I As further corrective action,'it is our intention to inspect the Belle-ville spring packs and shafts of all model SMB-00 and SMB-000 Limitorque.

operators on safety related systems. -These inspections will be made as soon as practical, considering accessibility of the valve operators.

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10. Failure Data

,v A. On June 17, 1975, during the perf ormance of PT-22, V2-14B opened as required by the PT, but would not close. A faulty torque switch was replaced, and the valve was test operated satisfactorily several times.

This did not constitute an abnormal occurrence because the valve opened as required, and thus was capable of performing its required safety function.

B. Valve V2-14B is a Chapman 4", L-900 W.E.0.S. Pressure Seal Gate Valve with a SMB-00 Limitorque Operator.

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