ML20054B549: Difference between revisions

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{{Adams
#REDIRECT [[05000336/LER-1982-006]]
| number = ML20054B549
| issue date = 04/08/1982
| title = LER 82-006/03L-0:on 820310,during Type B & C Local Leak Rate Testing During Refueling,Excessive Combined Leakage Rate Discovered.Caused by Mechanical Deficiencies in Valves & Personnel Access Hatch.Deficiencies Corrected
| author name = Criscione J
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| docket = 05000336
| license number =
| contact person =
| document report number = LER-82-006-03L-01, LER-82-6-3L-1, NUDOCS 8204160589
| package number = ML20054B537
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 2
}}
 
=Text=
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                . .                                                        LICENSEE EVENT REPORT l    l                (PLE ASE PRIMT OR TYPE ALL REQUIRED INFORMATf0M)
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  ' ?        8 9          LICENSEE CODE          14    15                  LICENSE NUMBER COM* T lo    Li J          % "C I L l@l0 l 5 l0 l0 l013 l3 16 68l@l690 l 3LVENT                    l 1 DATE l 0 l 8 l 2 j@l0 l4 74    75 l0 l8181280]@
REPORT DATE 7        8                    60          61            DOCK ET NUY8ER EVENT DESCRIPilON AND PRODADLE CONSEQUENCES h lTg] g While performing Type B and C Local Leak Rate Test during refueling a combined leak- l Lo l 3 ) l age rate in excess of that allowed by Technical Specification 3.6.1.2.b was noted.                                                              1
[_o y l            Valves 2-AC-6, 2-RB-28.2A, 3A, 2C, 3C and the Personnel Access Hatch were found to                                                              1 lg l                have various mechanical deficiencies resulting in excessive leaka ~ rates. The                                                                  l i  [o jg l            plant was operated in accordance with Technical Specification Action Statement                                                                  1 i
gl                  3.6.1.2.            Similar Events: LER 80-32.                                                                                                  l l
ElO I                                                                                                                                                              60 C E              CODE      SU CO E              COMPONENT CODE                  SUBC dE        SU O E i
lol9]8                            l X l X l@ [E j@ [ X j @ l P l E l N l E l T l R l@ [19X_j@ l_Zj                                      20
  ! 7                                    9      10          11            12 _        13                          18 HEViblON SEQUENTIAL                    OCCUHRENCE          HCFORT CODE              1YPE                        N O.
g g p. no      LVENT YEAR                        HLPORT NO.
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_.,  l218l222l          23          24          26      27          28        29        30            31          32 HOURS 22      S B ITT          FOR bub.        5 P LI E            MAN FA TURER T KEN ACilVN                O PL    T        PJ T lAj@[Zj@ l Zl@                                l36Zl@        l 0l 0l 0l 0 40l        [Yj@
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43 l44 Xl 9l 919l@ 47 33        34                35                            37 CAUSE DESCHIPTION AND CORRECTIVE ACTIONS h li1o]l Mechanical deficiencies of components were as follows:                                                    2-AC-6, packina leak:                    2-RB-    1 I
li ji j l 28.2A, 3A, 2C, 3C, seat ring damage and misadjustment, Personnel Access Hatch.
1 i, i,j l door operator shaft leaks. All deficiencies were corrected and the Local Leak Rate j
(gl Test successfully completed.
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l i l 41 1 7      8 9 OTHER STATUS            ISC      RY                        DISCOVERY DESCRIPTION ST      S            N POWER I1 15 I [lij@ l0 l0 l0 l@l                                  NA                    l  [_B_J@l                Surveillance Test                                      l ACTIVITY CO TENT                                                                                          LOCATION OF RELEASE RELE ASED Or RE LE ASE                  AYOUNT OF ACTIVITY NA                                                          l
,      l1l6l [Zj @ [Z_j@l                                        NA                    l        l FEH50NNE L E XPOSU ES NuenE n            TvPE      oEsCsiPriON @                                                                                                      l NA t i        l0 l 0 l 0 ' l@@@l"                                                                                                                                "
                    ' eEnSONNe't iN3uViES NUV8ER              DESCRIPilON l
7 i a 8 9 l0l0l0l@l      11      12 NA 80
                    'TSPE        EsCUPt ON '''''' '
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h4MK g                  05000336                                                                                      l 68    l l l l l l l l l 1 l l80lh 69 7      8 9            eu                        PDR J. L. Cr1scione                                            pgoye(203) 447-1791                              f, NAME OF PREPAflER
 
4.
ATTACHMENT TO LER 82-06/3L-0 NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION - UNIT 2 PROVISIONAL LICENSE NUMBER DPR-65 DOCKET NUMBER 50-336 Event Description and Probable Consequences While shut down for refueling and performing a Type B and C Local Leak Rate Test in accordance with Surveillance Procedure 2605C and 2605D, respectively on containment penetrations, a combined leakage rate in excess of that allowed by Technical Specifications 3.6.1.2.b was noted. Investigation revealed that valve 2-AC-6 had a stem packing leak, valves 2-RB-28.2A, 3A, 2C, and 3C were leaking by the T-ring seats.                  The personnel access hatch had packing gland leakage on the door operator shafts. The plant was operated in accordance with Technical Specification Action Statement 3.6.1.2.                        Similar Events: LER 80-32.
Cause Description and Corrective Actions The packing was readjusted on valve 2-AC-6 to correct the stem leakage. Valves 2-RB-28.2A, 3A, 2C and 3C exhibited a combination of T-ring seat age hardening and overadjustment of the T-rings during initial installation preventing the T-ring from fully seating with the disc. New T-rings were installed and the seats / discs properly adjusted.                  The operator door shafts gland packing on the personnel access hatch was readjusted. The Local Leak Rate Test was successfully completed after the above repairs / adjustments were accomplished.
VALVE DATA 2-RB-28.2A - 6 inch butterfly, Fisher Type 9222 2-RB-28.2C - with a Bettis CB-525-SR-80 Robotarm Actuator 2-RB-28.3A - 10 inch butterfly, Fisher Type 9222 2-RB-28.3C - with a Bettis CB-735-SR-80 Robotarm Actuator
        ,    -,.n.-- -            - - , . - . .      ,          - - . - , . .
                                                                              .  ,    . . . -.  ,  - - - , . - . ,}}

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