ML20084E046
| ML20084E046 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/03/1975 |
| From: | Stephenson B COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 407-75, 7352, AO-50-237-75-22, NUDOCS 8304130550 | |
| Download: ML20084E046 (12) | |
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d Fr. Ja es G. cppler, Regional Director gi-' iJ7 ' Directorate of Re.ulatory ; Operation-Region III i' U. S. Nuclear Regulatory Co=ission ; 4 . 799 Rooseve't Road e f
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SU2 JECT: REPORT OF AINC yAL OCCU:RE CE PER SECTICN 6.6. A OF TUE TECE!! CAL SPEC:FIC '. TIC::3 C::T-2 LOCA*. LEAK-RATE TEST SE7ARY SUPPLE"E;TARY REPCRT (1c74 7=, ~ 3:5 2 2I3 CU~ASE)
References:
- 1) Regulatory Guide 1.16 Rev. 1 Appendix A -
- 2) Notification of Region III of U. S. Nucle'ar Regulatory Co=ission Telephone: Mr. Johnson, 1130 hours en May 6, 1975 Telegram: Fr. Keppler, 11h0 hours on May 3, 1975
- 3) Drawing Nu=ber: M-3h h) Letter dated May 9, 1975 from Mr. B. 3. Stephensen,to Mr. J. G. Keppler Report Number: 50-237/75-22 ,
Report Date: July 3, 1975 ;
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Occurrence Date May 7, 1975 Facility: Dresden Nuclear Power Station, Forris, Illinois IDE.IFICATICN CF OCCU:RE':CE During local leak-rate testing for the recent Unit-2 refuel.ing outage, the volume bounded by valves 2-301-98 & 99 exceeded the maximum allowable limits. (The enclosed appendix gives a complete listing of all penetrations and associated leakages for the cutage mentioned above. This appendix is included to supplement B. B. Stephenson's letter dated May 9, 1975 with the results of the leak tests which were still pending at that time. These results have been circled for identification). CCNDITIONS PRIOR TO OCCURRE CE Unit-2 was in the shutdown mode for a refueling outage. 8304130550 750703 . PDR ADOCK 05000237 S PDR
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Mr. James G. Kep, t July 3, 1975 DESCRIPTIC:: OF CCCUR3R:CE a ]- At 1900 hours on May 7, 1975 the two check valves in the CRD return line (2-301-95 & 93) were leak-rate tested by the pressure decay mothed at d 48 psig to deter:-ine the "as-found" leakage. The two check valves were tested i } independently by using the 301-99 manual valve as a cormen boundary. The manual valve was assu=ed to be leak-tight since a water head was present
- on the reactor side. Check valve 301-98 had a leakage of 66.788 SCE which l exceeded the limit of 29 38 SCE.
1 DESIONATIC!! OF APPARE:T CAUSE OF CCCURRE CE (Equi;r.ent Failure) An inspection of 3C1-98 following the leak-rate testinc revealed that the mating surfaces of the disc and seat were dirty. There were no apparent major i defects. A':ALYSIS OF OCC'.'RRE CE Since check valve 301-95 (in series with valve 301-98) had a leakage of 1.247 SCFH, the total leakace through the penetration would have been tell within the Technical Specification limit. Had a line break occurred between the two check valves, the high differential pressure created across valve 301-98 would have seated it adequately in comparison to the 48 psig used for leak testing. Plant personnel and the public were not jeopardized by this occurrence. CORRECTIVE ACTION - The seating surfaces of the valve were cleaned, and the valve was reassembled and
- returned to service. The volu=e was satisfactorily leak-rate tested with a j
leakage of 11.786 SCFH. FAILURE DATA Valve 301-98 is a 4" check valve, body type F-S 900, disc type CR-13, =anufactured by Henry Vogt. Earlier in the refueling outage a modification for installing a test connection between valves 301-98 & 99 was completed. Prior to this cddification, valve 301-98 could not be leak-rate tested; consequently, there are no previous failures. Sincere
" B. B. S cphenson
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l I j APPENDIX Dresden Unit-2 Final Local Leak-Rate Test Su :.ary for 1974-75 Refueling outage >j Type of Penetration Max. Allowable Through Actual 5 of Limit y Lenkare (SCF10 L l 57.12 ' P-1: ary Inol . Valve . 1.e8 ( i Eellow Sesis E1cetrical 178.24 Combined 3.'o
- 3IV's 11.5 c; valve bo.7c Xax 7.35
( 1 Deuble Gaskoted Sasis E8.76 Combined 3 S*JPFLOTCARY NCCE CO :CEF2:I':G LPCI C0!CA2 TC SFRAY VALVE MO-1501-27E (See Reference 4) Valve MO-1501-273 was found to have excessive disc-to-seat clearance during the "as found" local leak-rate test. The valve was disassembled and the disc and seat were both lapped. After reassembly, the valve again failed the leak test. Further investigation revealed that the torque switch on the Limitorque operator was out of calibration. After recalibration, once again the leak test failed. The valve was disassembled a second time and again was found to have excessive dise-to-seat clearance. The disc was " bottoming out" before seating completely. Repairs consisted of building up and then recrinding the disc to the proper size. Upon reassembly, the leak test yielded a satisfactory leakage of 0.664 SCFH C 46 PSIG. This leakage is for both valves 1501-273 & *28B cc=bined. . In an effort to dete:=ine the total through-leakage for the penetration, 1501-28B
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was independently leak-rate tested prior to the repair of 1501-27B. The individual leakage was found to be 2.462 SOFL This test was performed with an 60 PSIG water head present against the upstream side of the 1501-275 valve. k'ater leaking past 1501-27B reduced the test volume. This reduct, ion in the test volume caused a given leakage to drop the test pressure faster, indicating greater leakage in spite of the water being added to the test volume past 1501-273. Consequently, the leakage for 1501-263 appeared to be greater than the leakage for 1501-273 & 28B combined.- l e I
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