View source for 05000424/LER-1997-004, Corrected Copy of Forwarding LER 97-004-00,re Condition Discovered to Exist on 970322

{{Adams
| number = ML20137Y801
| issue date = 04/16/1997
| title = Corrected Copy of Forwarding LER 97-004-00,re Condition Discovered to Exist on 970322
| author name = Mccoy C
| author affiliation = SOUTHERN NUCLEAR OPERATING CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000424
| license number = 
| contact person = 
| document report number = LCV-1003, NUDOCS 9704230237
| title reference date = 04-16-1997
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
}}
{{LER
| Title = Corrected Copy of Forwarding LER 97-004-00,re Condition Discovered to Exist on 970322
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000424
| LER year = 2097
| LER number = 4
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter:- ..                         .         . . . . . _ - . .
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l-  .         4                                                                                                                                             '
l-*         ,            C. K. McCoy                           Southera Nucl:ar
[                        Vice President                        Optrating C:mpany. Inc.
l                        Vogtle Project                        40 inverness Center Parkway P.O. Box 1295                                                                                l
                .                                              Birmingharn, Alabama 35201 l                                                              Tel 2059923122 I'                                                             Fax 205.992.0403 SOUTHERN                                 i
                  . April 16,1997                                                                                                     N
,                                                                      CORRECTED COPY                              Energy to Serve hurWorld" 1
LCV-1003                      l l
Docket No.           50-424 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:                                                                                                                    ;
VOGTLE ELECTRIC GENERATING PLANT                                                                            I LICENSEE EVENT REPORT l-97-04 i
UNQUALIFIED CABLING RENDERS                                                                         I l                                          ATMOSPHERIC RELIEF VALVES INOPERABLE l                                                                                                                                                           \
l                   In accordance with the requirements of 10 CFR 50.73, Georgia Power Company (GPC)                                                        i hereby submits a Vogtle Electric Generating Plant licensee event report concerning a                                                    !
condition which was discovered to exist on March 22,1997.                                                              l                 l 4
Sincere                                                      l
                                                                                             &pff}f C. K. McCoy l
l~                  CKM/AFS l
l                   

==Enclosure:==
LER l-97-04 l
i cc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr.
Mr. M. Sheibani                                                                                                                    l NORMS U. S. Nuclear Regulatory Commission                                                                                    j Mr. L. A. Reyes, Regional Administrator                                                                   > [h Mr. L. L. Wheeler, Licensing Project Manager, NRR                                                                                   i l
Mr. C. R. Ogle, Senior Resident Inspector, Vogtle L                                           f 3 004'i'                                                                                                     H 9704230237 970416 PDR      ADOCK 05000424                                                               151piplRNRE5, s                            PDR i

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N%C FOXC9 36s                                                  U.S. NUCLEAR REGULATORY COMMISSION N                                   APPROVED OM2 NO 3 SSc 04                       $
gg,                                                                                                                                         EXP1RES: tw30/50 ESTIMATED SgRDEN PER DESPONSE TO OOMPLY NN NSI
    ,                                                                                                                          MANDATORY (N50RMATION CCLLECTION REQUEST             KC MRSI I                                         LICENSEE EVENT REPORT (LER)                                                         "COMMENTS uC EE NEEs:         $"E s*E 'T E "EIIv Ed$ N REGARDING BURDEN ESTfMATE TO THE INFORMATION AND4 RECORDS MANAGEMENT BRANCN 17 4 F33t US                NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20565 0001 AND TO THE PAPERWORK REDUCTION PROJECT (31SO410dL OFFICE OF MANAGEMENT AND BUDGET WASHINGTON. DC 20503 i       e to iACluTY NAME(1)                                                                                                          DOCKET NUMBER (2)
Voetle Electnc Generatina Plant - Unit 1                                                                                      l5l0l0l0l4l2l4l1                        l OF l l3l
       's'l s'LE (4)
UNOUALIFTED CABLING RENDERS ATMOSPHERIC RELIEF VALVES INOPER ABLE LER NUMBER (6)                       REPORT OATE (7)                             OTHER F ACILITIES INVOLVED I9I l              EVENT DATE (S)         !!                                         l                          1 McWTH          DAY       YEAR $ YEAR              Hgry         M  Apg        MONTHi       DAY    YEAR ; F ACluTY NAME                               DOCKET NUMBER (S) nislololol ! !
F ACluTY NAME 16     9l7
                                                 ~                 -
013 212 917                       9l7           Ol0l4            Ol0        314            1                                                       gl5jolglgl j ;
op,,y,yg                   l   TNis REPORT IS $UBMITTED PURSUANT TO THE REQUIREMENTS OF to CPR (: (Cneca one or morel (11)
MODE (9)            j l         20.2201(b)                             20.220 nam 2)(v)             lX    60 7AaH2Ma)                             50.73(aK2Xvm)
POWER                      l      20.220*sx1)                            20 2203(aM3MI)                     Su 7%s)(2XiG                            50.7&aM2Xx) 3220*aK2)(Q                            20.203*agJXu)                      60.7xa)(2Xm)                           yg LEVEL (10)         ] l Q l()
20 220$aK2XiG                          M203NcH1)                          50 TRAM 2)0v)                           OTHER ab.I #MR2 gg 50.36(cx1)                         50 7AaM2dv)                             Spec @ m Abseact beew gN,                                    20.220*ax2)(m)
M              .e   2     J.;b         20.220*ag2xsv)                         60.36(cM2)                         50.73(aK2Xvu)                         ar m AWC Fam Jd6A UCEN.1EE CONTACT FOR THIS LER (12)
NAME                                                                                                                               TELEPHONE NUMBER (mcauoe atos cuoel
                                                                                                                                           ^^*^'*
Mehdi Sheibani, Nuclear Safety and Compliance 7l0l6 812161 13l21019 COMPLETE ONE UNE FOR EACM COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE          SYSTEM        COMPONENT        MANUFACTURER          REK)RTABLE TO M S               W Z'    ,
CAUSE      SYSTEM      COMPONENT         MANUFACTVRER        REPORTABLE TO NPROS TO *
                                                                                                 ,,J   ['                                 l l l             l l l l          l l l             l l l
                                                       $UPPLEMENTAL REPORT EAPECTED(14) bbJ                              !        !l l EXPECTED l          l MONTH      DAY      YEAR SUBMISSION YES (if yes. compaele EXPECTED SUBMISSION DATE)                                 X    NO                                           DATE (15)               l      l         l ASSTRACT (Lamst to 1400 spaces. s e , apprammstery 15 sangae space typewntion imes) (16)
Two atmospheric relief valves (ARVs) were found to have cable splices that were not fully jacketed.
The use of this cabling meant that the ARVs involved may not have been able to perform their intended safety function in the harsh environment of accident conditions. Two other ARVs with environmentally qualified cabling had remained in service, except for brief periods of maintenance.
However, the unit operated in a condition prohibited by the Technical Specifications (TS), because TS 3.7.4 requires three ARVs to be operable when the unit is in Modes 1,2, or 3. This requirement went into affect in January 1997 with the institution of the improved TS.
The cause of this event was the installation of cable splices that were not environmentally qualified because the conductors were not fullyjacketed. Due to the length of time since the work was performed in 1993 and 1994, an investigation was unable to determine the reason (s) that the splices were improperly irstalled. The ARV splices were repaired. All remaining ARVs in both Unit I and Unit 2 were inspected with no unqualified splices found.
S h y ;1 ^ 3' 4 3pp.
NRC f orm 364 (445)

NRc roIM sesa                                                                            U.S. NUCLEAR REGULATORY COMMISSION 14.es)
LICENSEE EVENT R'iPORT (LER)
TEXT CONTINUATION PACIUTY NAME(1)                                             00CMET hvMSER (2)             LER NUMSER (6)              PAGE (3)
A ij@                ,"*$    gg, Vogtle Electric Generating Plant - Unit 1                                                                                               l 015l0101014l214 9l7       -
01014           -
0l0  12 oF      13 l i 1 xw - . ,                       - - ., nRc % mav a                                                                                     i I
A. REQUIREMENT FOR REPORT l
This report is required per 10 CFR 50.73 (a)(2)(i) because the unit operated in a condition prohibited                   l by the Technical Specifications (TS) when atmospheric relief valves were in service with unqualified                    l cabling.                                                                                                                l i>
('                                                                                                                                          !'
B. UNITSTATUS AT TIME OF EVENT At the time of the discovery of this condition, Unit I was operating in Mode 1 at 100 percent of rated thermal power. Other than that described herein, there was no inoperable equipment that contributed to the occurrence of this condition.
l l
l                   C. DESCREPTION OF EVENT On March 22,1997, atmospheric relief valve (ARV) 1PV-3000 was out of service for maintenance.
Electricians noticed that cabling running to an electrical box had a splice that was not fullyjacketed.
Specifically,, four individual conductors were not jacketed as required by design specifications. The splices were repaired, maintenance was completed and IPV-3000 was returned to service on March                              !
24,1997. As a result of a broadness review, on March 26,1997, an inspection of cabling associated                           I with ARY JPV-3030 found a similar condition. The splicing was repaired and ARV IPV-3030 was                                 j returned to service on March 28,1997.
The use a(the unjacketed cabling in the harsh environment following an accident meant that the ARVs involved may not have been able to perform their intended safety function. Two other ARVs with quahfied cabling had remained in service, except for brief periods of maintenance. However, the unit operated in a condition proMited by the TS, because TS 3.7.4 requires three ARVs to be operable when the unit is in Modes 1, 2, or 3. This requirement went into affect in January 1997
                   .with theimplementation of the improved TS.
i D. CAUSE OF EVENT The cause of this event was the installation of cable splices that were not environmentally qualified because the conductors were not fully jacketed. The IPV-3000 cabling was installed in November 1993 during rework of the valve and the IPV-3030 cabling was installed in May 1994 during rework

       . _ . _ . _ _ _ _ _ . _                        _ _     _ . _ _ _ _             .__. . _ _ _ _ __ . _ _ _ .._~_. _ ._ _ _ _ _
u.s. NUCLEAR REGULATORY COMMISSION
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LICENSEE EVENT REPORT (LER) 1                                                                              TEXT CONTINUATION
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                                                                                                                                                        ",%**"             l 1                  Vogtle Electric Generating Plant - Unit i                                                                                                              1
 !                                                                               0l5101010l41214 9l7                                 -
0l014    -
010    13 OF   13 of that valve. Due to the length of time since the work was performed, an investigation was unable
:                                   to determine the reason (s) that the splices were improperly installed.
)'
E. ANALYSIS OF EVENT I
The ARVs continued to perform their normal pressure relief function. However, in the event of a high energy line break, the unqualified cabling may have failed, rendering up to two of the ARVs i                                   non-functional. Nonetheless, at least one of the other two unaffected ARVs remained in service I                                  when required during the period involved, ensuring that adequate pressure relieving capability was 1
available for the main steam system. Furthennore, no event has occurred that would require these ARVs to function in the post accident mode. Based on these considerations, there was no adverse l                                  affect on plant safety or on the health and safety of the public as a result of this condition.
  !                                 F. CORRECTIVE ACTION
: 1) The cable splices for both ARVs were repaired.
: 2) The remaining Unit 1 ARVs and the Unit 2 ARVs were inspected and no additional unqualified j                                       splices were found.
1
:                                   3) A broadness review of cable splices utilized in harsh environments will be performed by l                                       June 12,1997.
i                                   4) Appropriate maintenance personnel will review this LER in continuing training with emphasis on i                                      environmentally qualified splices. The next cycle of continuing training will be completed prior to i                                       the Fall 1997 refueling outage.
 ,                                . G. ADDITIONAL INFORMATION 1
: 1) Failed Components:
j                                       ~None
{                                 2) Previous Similar Events:
:                                     None l                                 3) Energy Industry Identification System Code:
:                                       Main Steam System - SB i
J
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