NRC-89-0185, LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr

LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr

ML19325C297
Person / Time
Site:	Fermi
Issue date:	10/06/1989
From:	Nader G, Orser W DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-89-0185, CON-NRC-89-185 LER-89-021, LER-89-21, NUDOCS 8910160031
Download: ML19325C297 (5)

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NRC-89-0185 ' U.~S.' Nuclear Regulatory Commission '^} Attention: Document Control Desk Washington. D.C. 20555 '

Reference:

Fermi'2 NRC Docket'No. 50-341

                                                               ~ Facility Operating License No. NPF-43

Subject:

Licensee Event Report (LER) No. 89-021-00 4

Please' find enclosed LER No. 89-021-00, dated October 6

                                   '1989, for a reportable. event that occurred on September 1989._ A-copy of this:LER is also being sent1to the 6,                                                                                                   ,

Regional Administrator. USNRC Region III.. - If you have any questions, please contact Gordon Nader at (313) 586-4513. Sincerely, o h Enclosures NRC. Forms 366 366A

• cc: A. B. Davis R. Eckert J.

R. C. Knop j W. G. Rogers J. F. Stang Wayne County Emergency Management Division 2

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f tTLE tes . - Local Leak Rate Testing Exceeds Tech. Speo. Limits EVENT DATE ISI

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Ni.Mg TELEPHONE NUM8ER Cordon,Nader, Licensing Engineer 3i l3 i S86 i i i -14 ;5 i l3 l COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRISED IN TH18 REPORT H31 M yORTA E CAUSE $YSTEM COMPONENT C- REPORTA E , p CAUSE SYSTEM COMPONE NT ,$C- qpq s s s 1 I I I I I I I I i l- 1 I I I I I I I I i I I I i 1 i i SUPPLEMENTAL REPORT EXPECTEO H41 MON 1 H DAY YEAR SU6M'58 SON

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1 vEs in r *-me exPrerro suewwou oAres --]NO 1 11 310 8I9 i AESTL ACT ILknot to 1400 spacer. In, sopronunserv rotwen smve soece typewerten knest Hti l l l Periodic leakage rate testing of Containment Isolation Valves and penetrations are being performed in accordance with the requirements contained in Technical Specification 3.6e1.2 and 10 CFR 50 Appendix J. During the performance of this testing, several valves have exceeded their administrative allowable leakage rate and their combined leakage exceeds the limits as defined in the subject Technical Specification Limiting Condition for Operation. All containment isolation valves that have exceeded their administrative in d i.v id u al allowable leakage rate have had work requests generated to disassemble the subject valves and repair or rework the valve (s) as conditions dictate. A full-report will be made in a supplement to this LER within 30 days after the completion of the Type Ae B and C testing / retesting. NRC ,e,. m. AnL - _ w

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       >          -             , operationallCondition:                               Sg (Refueling)                                                                                           l vgReactor. Powers-                    01      ,

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  ;                                , Reactor' Temperatures- 97 degrees' Fahrenheit-                                                                                                            3 Descriptionoof Event -

• 3

  ,'                Pp' OniSeptemberc6 1989. Local Leak Rate Testing (LLRT) of the                                                                                              ;'

(Primary Containment Isolation Valves (ISV) and Penetrations was

                                       ' initiated in accordanceJwith Technical Specification (TS).                                                                                             ;
                  .                '3/4.6.3.2j" Primary; Containment Leakage" and;10 CFR 50.' Appendix'J,                                                                                      l c
                                    - " Primary, Reactor: Containment Leakage = Testing for Water' Cooled                                                                                       ,

i . Power? Reactors". JAs of; September 28. 1989, approximately 35% of

                                                                                          '                                                                                                    1

thelpenetrationsz (Ty'pelB' tests)-and 77% of the isolation valves .

E (Type C. tests) have been< tested. Included in the above completed b 'testanare-the the TypenC tests on the Main Steam Isolation Valves [.

                                      '(MSIVs).-                                                                                                                                                *
                                                    ~

TSL3.6;1.2.b requires that the combined leakage rate of Type B and-1 d [ I" Type C tests.1except for-leakage tests on the.MSIVs: and valves s which are hydrostatically' tested, shall be less than or equa; to 0.60'La. Not including MSIV leakage _in the' combined total (0.6La) i fis ancapproved exemptionTfrom 10 CFR; 50 Appendix J,. As of j J ' September 28.:1989. two. Type-B tests have failed their.LLRTs. The o o fleakage rates through;these penetrations were greater than their j" o

                                   ' individual administrative limits.                                             Administrative limits are established'forLType B and~C tests in accordance with the
                                             ~

Inservice Test Program- to provide ~ individual valve and penetration

                      ,u             ' acceptance, criteria.                       As of September-28 1989 29 Type C tested                                                                     :

[ valves-haveEexceeded their individual administrative leakage . , y rates. The combined Technical Specification leakage rate of 0.6 [ .La;has'been exceeded. TS-3.6.1.2.c requires.that the leakage rates for all four main D 'steamLlines. when tested at'25.0 psig, be less than or equal to s l100 Standard Cubic. Feet per Hour (sefh). LLRTs of the MSIVs  ; y indicate that these valves have exceeded their TS limit.

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Additionally. TS 3.6.1.2.d requires that a combined leakage rate for all, containment isolation valves in hydrostatically tested

                                   -lines-be less than or equal to 5 gallons per minutes (gpm) when                                                                                              ;
               <-                 Ltested--at 1.10 Pa.                         Combined local leakage rates of the hydrostatically tested valves have exceeded the 5 spm TS limit.                                                                                           ;

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   <     #$'                     Cause of the Events n:                                                                                                                                                                                 ,

Excessive containment' isolation valve leakage is generally caused by normel-degradation-of valve components and/or contaminants'on  ; W

                             .the.. valve seating; surfaces.                                 Since valve disassembly and analysis                                                 .
                             - of each condition is; ongoing. .the specific.cause(s) of the excessively leaking isolation valves vill be included in a later revision ~to this;LER.

Analysis of the Event: Type BJand\C LLRTois performed to detect degradation of , l penetration-and valve sealing characteristics which would

                               ' adversely effect primary-containment integrity. Any degradation discovered through, testing is corrected so that potential                                                                                        ,

degradation of containment or containment penetrations does not

occur'between the: Type A. B and C testing periods.

A, complete. analysis of the consequences - of' exceeding these

                          . Technical Specification Limits will be provided.in the revision of                                                                                    ?

a this LER.that-will be submitted 30 days after the conclusion of the. Type 1A. B and'C' testing /restesting. Analysis at this' time

           ,'            Ewould be preliminarys and incomplete because testing /rctesting is                                                                                      '

Latill in1 progress. ' Corrective' Actions: All containment 1 isolation valves that have exceeded their '

          ~'
                          ' administrative individual allowable leakage rate have had work requests generated to disassemble the subject valves and repair or rework- the valve as conditions dictate. These valves will be ratested to determine their leakage rates.

In addition to.the above specified work. four inboard MSIVs are

                         -scheduled to.be' modified during the enrrent refueling outage using the manufacturer's latest' design modification kit.                                            This MSIV ac
                         < modification has been endorsed by the BWR Owner's Group and the

NRC, and consists of changes that include an elongated poppet and pilot poppet' assembly (" nose cone"), additica of an anti-rotation g

device and a 2 inch diameter stem with associated nachining of the L . valve cover / bonnet. These modifications are intended to improve

                         'LLRT performance and valve reliability.

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r. E I F i Previous Similar Occurrences . 1

                                       ' Licensee Event. Report. 86 011-01 " Excessive Leakage from MSIV" ' and LLicensee Event-Report- 88-008-01 " Leakage In-Excess of'the                                                                                                                                  i Allowable Found During LLRT"..

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