ML20009D599

Forwards Updated LER 81-006/01X-1

ML20009D599
Person / Time
Site:	Dresden
Issue date:	06/16/1981
From:	Scott D COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20009D600	List: ML20009D599 ML20009D602
References
81-463, NUDOCS 8107240208
Download: ML20009D599 (2)

Text

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                        ), _lLR.#1 Morris, lihaois 60450
                       / Telephone 815/942-2920
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DJS LTR 81-463 p 4 - 6

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10:, James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III M f'l h(.[%a. U. S. Nuclear Regulatory Commission 799 Roosevelt Road b#

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f Clen Ellyn, IL 60137 An updated Reportable Occurrence Report #81-06/0lX-1, Docket #050-237 is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.l. (c), abnonnal degradation dis-covered in fuel cladding, reactor coolant pressure boundary, or primary containment. This supplemental report is provided to indicate the reason for the excessive leakage discovered on the feedwater check valves during local leak rate testing and update the action taken and future action por-tions of the Licensee Event Report. D. J Scott Station Superintendent Dresden Nuclear Power Station DJS:lg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control

                     .U.S.~NRC, Document Mgt. Branch                                           r       y File /NRC S
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8107240208 810616 v~ PDR ADOCK 05000237 S pon i T 190\ JUL 1

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l DEVIATION REPORT

                                                                                            """"                                                                Revision #1 Commonwealth Edison                                          -

STA UNIT YEAR N O. D 2 7 af Il Il TLE OF OEV1 ATION OCCU RRED Exceeding Tech St ec Limitation for LLRT 1-23-81 1000 g4TE nue SYSTEM AFFECTED 1600 Pt. ANT CONDITIONS TESTING Pressure Suppression ' ' MODE Shutdown p wn ,9w73 0 . OA O (MWE) 0 YES NO CESCAIPTION OF Evi!NI During LLRT on Feedwater check valves leakage exceeded single penetration limit of 29.38 SCFH. total penetration and isolation valve leakage linit of 176.29 SCFIL and total containment lenime .1 fmf t of 781 SCF17 DESCRIPTION OF CAUSE Unknown 6THER APPLICABLE IMFORMAfTON - Feedwater check valves 2-220-62A and 2-220-58A & B. EQUINENT M% YES {{3N, 1.1363 1-23-81 FA M RE R NO N/A 11362 _ Kenneth R. Zirvas

                                                                                                                                            *ESPONSIBt.E  9 $4ViSCR                           OATE PART ij OPERATING ENGINEERS COMMENTS Rai. airs will be initisted during the scheduled refueling outage.

SAFETY-TYPE OF CEVIATION EVENT OF POTE!iTI AL TECH SPEC NON-REPORTABLE l^ ANNUAL RELATED REPORTABLE OCCURRENCE PUBLIC INTEREST VIOLATION OCCURRENCE REPORTING WR ISSUED V 14 DAY 10CFR21 YES X YES X 30 DAY 6_6 N0TIFlC E, , ION _ NO NC

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REPORTABLE CCCURRENCE ACTION ITEM NO. PROMPT ON-$1 TE NOTI FICATICN N BG _ R. M. Ragan 1-23-81 1300 iEX 81-06/01X-1 TITLE DATE TIME TI TLE CATE 'iME 24-HOUR NRC NOTI FICATION PRCMPT OFF-SI TE NOTI FICATION h TPH T. Toncue REGION Ii1 1-23-81 2:1400 TIME

                                                                                                                             ,F. A. Palmer                             1-23 Al             2:47 OATE                                                  TITLE                           DATE                TIME

{ TGM J. Kenoler 1-21-81 2.58 REGION 111 & COL CATE TIME TI TLE DATE TIME RESPONSI SLE COMP ANY OFFI CER I N FO RMED O F 10CFR21 I'ONOfT'ONS AND NE! O CEDO AT 'O NQC TlTLE CAIA IN REVI EW AND CCMPLEYED John W. Wuiziea CP EP AT ! NG ENG I N t. .H CATE s CE BY STATION REVIEW y g, g g g - DATE See Supplemental DVR Cover /

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