View source for 05000313/LER-1983-007, Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure

{{Adams
| number = ML20073Q088
| issue date = 04/19/1983
| title = Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure
| author name = Rogers P
| author affiliation = ARKANSAS POWER &amp; LIGHT CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION I)
| docket = 05000313
| license number = 
| contact person = 
| document report number = LER-83-007-03X, LER-83-7-3X, NUDOCS 8304280291
| package number = ML20073Q086
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000313
| LER year = 2083
| LER number = 7
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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     -o NRC FORM 366 J
(7-77)                                                                                                                       U.S. NUCLEAR REGULATCRY CCMMISSIC*4 LICENSEE EVENT REPORT EXHIBIT A
 ;                         CONTROL BLOCK:      l IT                  IA 1_l_i_l_i_l_ l 16                                     (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7~lTI8~~                                                   10                        0 l 0 l,0.,l_ ,,l,0,,l~~025l 3 14 9 ~ ITICDiiEE R I A l NCODT- I O l ~1I4 1215'--l11 - -l ITCER5E 0 1 0 1TiGMEER 2rlT.TCER5T TWE701 i    15 l 1 l 111 l4 57CATTS l       iO 7-~I 1 8i
              ~-                      REPORT I L 16      10                                              101310 8l8 1 3 18 10l4l119I8 SOURCE 6D~         6I- 1~5 TCKET 1 0 1 0IT01 0FIBER-13l1      1 3 17
                                                                                              - ~68      6 F ~~IvERTlDATE            74 7F 7ERTRTTTE~I -319              E0
'                            EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 10 11111              10n 3/8/83, while in refueling shutdown, Reactor Buildinq (RB) pressure switch PS-2403 was found to be out of                                        I l1111              l tolerance while performing the Reactor Protection System (RPS) channel "0" calibration.                              Also, on 3/21/83, R8 l l1l11              l pressure switch PS-2401 was found to be out of tolerance while performing the RPS channel "B" calibration.
l l111l              IPS-2401 and PS-2403 were found to open at 18.9 psia, above the maximum Technical Specification Value of 18.7                                       l 5
l1111               l psia.
Since the switches would have actuated at h pressure higher than required, this occurrence is reportablel j      l1l1l               lper Technical Specification (TS) 6.12.3.2.a. RB pressure switch PS-2400 for RPS channel "A"
^
and RB pressure          l l switch PS-2402 for RPS channel "C" were found to be set at less than or equal to the value specified in T.S.
!      7~lTl lT ~8              9                                                                                                                                                    t i                                       SYSTEM               CAUSE 80 CAUSE                                                      COMP CODE                                                                                                         VALVE CODE            SU8 CODE                 COMPONENT CODE I                                                                                                                                      SUBCODE      SUBCODE 11tli                          I_I I A 111            1E                 1E             lI                                         15115 7          8                  9      70               11~112             12~113         IT~f, N,,l,S,,_[_,T,,l_R__lU l 14                      lZ
.!                                                                                                                           ~I8          1F          2D~l16 SEQUENTIAL                              OCCURRENCE        REPORT
 !                    LER/R0       l' EVENT YEAR                                                                                                                     REVISICN R(PORT NO.                               CODE            TYPE                       NO i               17 REPORT               8 IlTI3l~22 l---
2T-l               l011 2F          7l
                                                                                       ,0,,,l76          l/               l0    3l          lX           1---          l11 j                     NUMBER       1,,2                                                                  2Fl              2 F l-~29         3D'- l       3Fl          3F ACTION FUTURE                    EFFECT          SHUTCOWN                                ATTACHMENT         NPRD-4     PRIME COMP.      COMPONENT TAKEN           ACTION         ON PLANT           METHOD                HOURS             SUBMITTED FORM SUB            SUPPLIER IE             1Z               I Z 120          1Z             10                             lY MANUFACTURER 33~(18 3 F l19                   3F                              37-~l_0_,1,0_l                             lN          lA         l_B__I   0 l_8,_l 0 126 35~121                         --'700 122 4Fl23           4T~{24 4T-l25          44 77 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 i      I_TIll            lThe pressure switches were reset to 18.5 psia per the RPS calibration procedure and returned to service. Thesel j
l1111             l pressure switches are snap action type manufactured by Barton.
t l1111             l I
l      11111             l I
i     11111             l 7           8 9                                                                                                                                                         I FACILITY                                                                                                                                             80 METHOD OF STATUS            % POWER                    OTHER STATUS            DISCOVERY I
11111              iH             10                    i N/A                        130 l B 131 i DISCOVERY DESCRIPTION Routine Surveillance 7          8       9 ~ 128 16 ~1 ~0          ""'I21 0 129 13                         44       45~      46-132 ACTIVITY CONTENT                                                                                                                                  80 RELEASED OF RELEASE                            AMOUNT OF ACTIVITY j     IT                                                                                                                          LOCATION OF RELEASE
      ?~ill      8 lZ 9 ~ 133 10~13411l IZ              NA 44 135 i 45 NA 80 l36 PERSONNEL EXPOSURES NUMBER             TYPE      DESCRIPTION 7_lli I T_
8 9 11l_0_l~0l37IZ138i Il    12-~       13 NA 139 80 PERSONNEL INJURIES NUMBER            DESCRIPTION 11111
     ?           8 1
9,0,,,l_0_,l" 0Il140 12 i NA
[41 LOSS OF OR DAMAGE TO FACILITY                                                                                                                    80 TYPE         DESCRIPTION-I T_ l T_,,1       l Z,,,,142 l       NA 143 PUBLICITY ISSUED DESCRIPTION 111118 7
1N 9- ~l4410i NA (45- l 1 NRC USE ONLY 68     63 ,1,1,1,1,1,1,1,1 ,1 ,lIQl NAME OF PREPARER                Patrick C. Rogers (501) 964-3100 PHONE:
8304200291 830419 PDR ADOCK 05000313 4
S                                  PM

r      V NRC FORM 366 (7-77)                                                                                       U.S. NUCLEA:t REGULATCRY CC"MISSICN LICENSEE EVENT REPORT E/HIBIT A LER No. 50-313/83-007/03X-1 Occurrence Date: 03/08/83 Event Description and Probable Consequences (Continued)
Table 2.3-1. Instrument drif t has been reported in LER's (50-313) 74-008, 76-003, 83-003, and 83-004.
L.                                                      ._
}}

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