View source for 05000255/LER-1986-004, Forwards LER 86-004-01 Re Failure of Main Steam Safety Relief Valves to Meet as Found Acceptance Criteria

{{Adams
| number = ML20203Q100
| issue date = 04/30/1986
| title = Forwards LER 86-004-01 Re Failure of Main Steam Safety Relief Valves to Meet as Found Acceptance Criteria
| author name = Bordine T
| author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.),
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION (ADM)
| docket = 05000255
| license number = 
| contact person = 
| document report number = NUDOCS 8605080643
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
}}
{{LER
| Title = Forwards LER 86-004-01 Re Failure of Main Steam Safety Relief Valves to Meet as Found Acceptance Criteria
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000255
| LER year = 2086
| LER number = 4
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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     @rowsmne           Power M E NREn N'E D w M M M General offices: 1945 West Parnall Road. Jackson, MI 49201 * (517) 788-0550 April 30, 1986 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 86-004 - REV 1 - MAIN STEAM RELIEF VALVES FAIL TO MEET "AS FOUND" PRESSURE ACCEPTANCE CRITERIA (REPLACES SUBMITTAL OF APRIL 24, 1986)
Licensee Event Report (LER) 86-004, Rev 1, (Main Steam Relief Valves Fail to Meet "As Found" Pressure Acceptance Criteria) is attached. This event is reportable to the NRC per 10CFR50.73(a)(2)(1). This revision is being submitted to include the evaluation of the safety significance which was committed in the original LER. This corrected copy of the attachment includes only the addition of vertical bars in the right hand margins.
           'W Thomas C Bordine Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment 9605000643 860433                                                                    'V PDR    ADOCK 05000255                                                            e'l S                          PDR'                                                g,9 '
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                                                                                                                                              ] =o  , osi l2i                  31!    8;6 On January 13, 1986, with the plant shutdown for refueling, it was determined, after testing and evaluation, that fourteen of twenty-four Main Steam Safety Relief Valves were outside the Palisades Technical Specification Acceptance Criteria of !1% of set pressure.
All but one.of the valves were within 2% of set pressure, with that one being within 2.8% of set pressure. These valves were overhauled by a representative of the valve manufacturer and set within specifications. The valves were judged to be in good repair. The drift outside the acceptance criteria is                                                                                                                                                        ,
attributed to a combination of setting the valves near the fringes of the tolerance band during the last outage and to the normal corrosion deposit
!                                      buildup during operation.
An evaluation determined that there was no safety significance to this event.
Reference LER 83-074.
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0l1 0l2 or 0 l2 As required by Palisades Technical Specifications 3.1.7.c, the Palisades Main Steam Safety Relief Valve Numbers RV-0701 through RV-0724 [SB;RV} were tested for set pressure.
This test started with the seven valves scheduled for overhaul, being tested for "as found" set pressure, overhauled, retested and set to within specifications. Three of the seven valves failed the "as found" acceptance criteria of 11% of specified set pressure therefore requiring the additional seventeen valves to be tested. Eleven of those seventeen were found outside the acceptance criteria. All valves except one were within 2% of their set point. That one valve was within 2.8% of its set point. These valves were overhauled by a representative of the valve manufacturer and set to within specifications.
The valves were outside the acceptance criteria mainly because of the combination of setting the valves near the fringes of the tolerance band during the last outage and the normal corrosion deposit buildup during operation.
The evaluation of the safety significance of this event determined that there was no significant impact on the Palisades FSAR Chapter 14 Safety Analysis and the Palisades Plant was not in an unsafe condition due to lift points on the safety valves being out of specification.
Action to prevent recurrence of this event requires a change to the acceptance criteria on the "as found" set pressure in the technical specifications. We will submit this technical specification change request by the end of the year 1986. If we are unable to make this submittal, we will apprise the NRC at the time of our next update to this LER.
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