ML20086H900
| ML20086H900 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/15/1975 |
| From: | Meyer R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H903 | List: |
| References | |
| AO-75-32, NUDOCS 8401200325 | |
| Download: ML20086H900 (3) | |
Text
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gPHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET s
PHILADELPHIA. PA.19101 '
s 1215)841 4000
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May 15, 1975
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Mr. A. Giambusso, Director
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Division of Reactor Licensing y
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Office of Nuclear Reactor Regulations United States Nuclear. Regulatory Commission
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l' Washington; DC 20555
Dear Mr. Giambusso:
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Subject:
Abnormal Occurrence i~
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The following occurrence was reported to Mr. Walt Baunack, Regiok4, Of fice of Inspection and Enforcement, United States Nuclear Regulatory Commission on May 5, 1975 Written notification was made to Mr. %nies P. O'Reilly, Of fice of Inspection and Enforcement, Region 1, Unit.ed States Nuclear Regulatory Comtission on May 5,1975 In accordbnce with Section 6.7 2.A of the Technical Specifications,
-Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power. Station, the following report is being subniitted to the Directorate of Reactor 3
Licensing as an Abnormal Occurrence.
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Reference:
License Number DPR-44 Technical Specif.ication
Reference:
Par a. 4.7. A. 2.f Report No.:
50-277-75-32
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Report Date:
May 15, 1975 Occurrence Date: May 5, 1975 Facility:
Peach Bottom Atomic Power Station
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R. D. til, De l t a, PA -- 17314 Identification of Occurrence:
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Failure;;f'o complete the surveillance requirement for local
- teak ra'te testing'on certain containment penetratiohs wi thin 2 years.
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Conditions Prior to Occurrence:
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Unit 2 at approximately 100% powert e,
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Desefiption of Occurrence:
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As, of-- May 5, 1975, 30% of the local.
ibak rate tests raquired b the Tech 6ical Specifications which shr.~ald be performed within 2 years had'not been completed. A list of the penetrations.avolved,is
. attached.
.a B401200325 750515 PDR ADOCK 05000277 r; t y vvv6 S
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Mr. A. Giambusso 50-277-75-32 May 15, 1975 Page 2 Designation of Apparent Cause of Occurrence:
Local leak rate testing was initiated early in 1974.
Sig-nificant progress was made on canpleting tNis task between November 1974 and February 1975 during unit shutdown periods. Because of the plant load factor, leak testing of all penetrations could not be completed within the 2 year period.
Analysis of Occurrence:
Safety implications of deferring the local leak rate testing of these penetrations has been reviewed by the PORC and 0&SR and is minimal. A safety evaluation for each penetration not tested was sub-mitted to the Nuclear Regulatory Commission, as a part of a request to relax the testing period.
Corrective Action:
As of May 13, 1975, those penetrations marked with an asterisk
(*) on the Attachment had been tested.
Discussions were held with NRC l-Division of Reactor Licensing to permit, testing of the remaining pene-trations (except 9A and 98) using water as the testing fluid.
On May 15, 1975 notification was received fran the Division of Reactor Licensing, approving the use of water as.the testing fluid. The unit will be shutdown on May 16, 1975 and the remaining tests will be completed.
Failure Data:
Not applicable.
Very truly yours,
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R. D. Meyer l
General Superintendent Generation Division l
cc:
Mr. J. P. O'Reilly Director, Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 l
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ATTACHMENT Table 3.7.2 - With Double 0-rings Penet.
N-2 Personnel Lock *,'
N-35 A-G TIP Dri ves' Table 3 7.4 - Isolation Valves Penet. 8 Main Steam Line Drain 9A Feedwater 98 Feedwater 12
.RHR Pump Shutdown Cooling Supply 13A RHR Pump Pump Return 13B RHR Puxp Pump Return 17 RPV Head Spray, 22 In s t r umen t N 2,'l, 25 Drywell Purge' 210A Torus Cooling 210B Torus Coolinj 211A Torus Spray 211B Torus Spray 2i2 RCIC Turbine Exhaust" 214 HPCI Turbine Exhaust - Line Drain" 218A Inst. N2 to Vacuum Breaker *
.221 RCIC Vacuum Pump Discharge,'l,,
223 HPCI Turbine Exhaus,t, Drain" 225 Torus Water Cleanup" It should be noted that Containment Atmospheric Dilution (CAD)
System penetrations listed in Table 3 7.4 have not been in-stalled. Paragraph 3 7.A.6 of the Technical Specifications permits deferral of the CAD System until the end of the first refueling outage.
- These tests completed between May 5 and May 13, 1975
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