ML20216D350
| ML20216D350 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/06/1998 |
| From: | Czarnecki R FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20216D340 | List: |
| References | |
| LER-98-S02, LER-98-S2, NUDOCS 9804150264 | |
| Download: ML20216D350 (3) | |
Text
NRC FORM 368 U.S. NUCLEAR RE2ULATORY COMMISSION APPROVED CV OMS NO. 31604104 (4.e6)e EXPIRES 04/30f00 i
S"O"^MYT&" RETT"4EggU!SNk"H R E E l l!&"'?O'Mshit"? "filene"Csu'u'slli*Re?Mle1"PRbl?
LICENSEE EVENT REPORT (LER) psgogggAgggg,oS y MANA,OgMem BRg
^
(See reverse for required number of EdOdE" AN T" T digits / characters for each block)
FACluTY NAME (1) DOCKET NUGASER(2) PAGE (3) l ST. LUCIE UNIT 1 05000335 1 OF 3 TITLE (4)
Suspension of Safeguards Under 10 CFR 50.54(x) During a Severe Storm Due tc Personnel Safety Concerns EVE WT DATl! 181 LER 8C""-- fill m h si DATF (71 OTHER FACu ITIES I MVOLVED ($1 F ACILfTY NAME uOurN day vEAR vEAR Tgg^' gg uCNTN DAv YEAR W
DOCKET NUMBER WU2 EMM FACILITY NAME DOCKET NUMBER 03 09 98 98 - S02 -
0 04 06 98 l OPERATING j THIS REPORT IS e'""TTEE PL88*9^h8T TO THE pena unpassadTS O F 10 CFR 8: (Check one r r mor n) (111 MODE (9) 20.2201(b) 20.2203(a)(2)(v) X so.73(a)(2)(1) 50.73(a)(2)(viii) 1 POWER 20 220stawn 20 mwav3vn 50 ntawm 50 ntav m l LEVEL (10) 100 20.2203(a)(2)(I) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) X 73 71 20 2203(av? vin 20 99mtaV4) 50.73(ait2Viv) OTHER
, l 1
20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) gi Absgbelowor 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) e ecsnaass CONTACT FOR THis LER (1'tl NAME TELEPHONE NUMBER (incbde Area Code)
R. W. Czarnecki, Plant Security Supervisor (561) 467-7002 COMPLETF ONE LINE FOR sAcH COnamn mast FAII IMtE neanosaan IN THIS REPORT !131 CAUSE SYSTEM COMPONENT MANUFACTURER R RTA E CAUSE COMPONENT SYSTEM MANUFACTURER R g TABLE C IA MPX X999 N/A SUPPLEMENTAL REPORT EXPECTED fiel " " * ## **
EXPECTED YES SUPMISSION (if yes, complete EXPECTED SUBMISSION DATE). X NO GATE (16)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (it)
On March 9,1998, with both Units 1 and 2 at 100% reactor power, a tornado warning was issued for the local area. At approximately 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, a heavy thunderstorm with severe lightning was in the vicinity of the plant. At 0404 hours0.00468 days <br />0.112 hours <br />6.679894e-4 weeks <br />1.53722e-4 months <br />, the Electronic Security System (ESS) failed. The abnormally severe storm was determined to be life threatening for persons exposed in compensatory positions. The Security Shift Specialist (SSS), a Florida Power & Light (FPL) employee, advised ths Nuclear Plant Supervisor (NPS), a utility licensed Senior Reactor Operator (SRO), that a deviation from the Physical Security Plan (PSP) should take place,i.e., temporary suspension of safepuards measures. Thia s'_:spension of safeguards
~
was implemert.ed under 10 CFR 50.54(x) due to personnelsafety concem during the severe weather condition. The deviation was to delay compensating for the loss of the ESS due to very sever # weather to pavide protection for securi'y personnel from the lightning, gusting winds, and possible tomado. The NPS PJthorized this action. As soon as the severe weather subsided, compensatory measures were fuly instituted and sweeps r F vital and protected areas were completed satisfactorily.
The Nuclear Regulatory Commission (NRC) Operations Center was notified of the suspension of safeguards at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> rnd of the actions taken pursuant to 10 CFR 50.54(x) and (y) at 1528 hours0.0177 days <br />0.424 hours <br />0.00253 weeks <br />5.81404e-4 months <br />.
9804150264 980406 ppq ADOCh 05000335 g PDR NRC FORM 366 (4-95)
r 1 NRc FORM 366A U.S. NUCLEAR REllulATORY COMMisslON LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME fil DOCKET LER NUMBER '61 PAGE (3) l
. YEAR Sl h^l R ST. LUCIE UNIT 1 05000335 2 OF 3 98 - S02 - 00 TEXT (11more space is required. use ad@onal coptes of NRc Form 366A) (17)
DESCRIPTION OF THE EVENT:
Or. March 9,1998, with both units at 100% reactor power, a tomado waming was issued for the local area. At approximately 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, a heavy thunderstorm with severe lightning was in the vicinity of the plant. At 0404 hours0.00468 days <br />0.112 hours <br />6.679894e-4 weeks <br />1.53722e-4 months <br />, the Electronic Security System (Ells:lA) (ESS) computer experienced multiple Intelligent Multiplexer (IMUX) (Ells:lA:MPX] failures. This was attributed to severe lightning that overpowered the installed surge protection devices. The Security Shift Specialist (SSS) advised the Nuclear Plant Supervisor (NPS), a licensed Senior Reactor Operat3r (SRO), that because of the severe weather, safeguards measures relating to the posting of security officers during an ESS failure should be suspended. This suspension of safeguards was implemented under 10 CFR 50.54(x).10 CFR 50.54(x) authorizes licensees to take actions that depart from a license condition in an emergency to protect the health and safety of the public and plant personnel when this cction is immediately needed. The NPS authorized this action. Access control to the ,)rotected and vital areas was not suspended.
By approximately 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, the severe weather had subsided sufficiently to reinstate safeguards measures.
Proper compensatory measures were in place at 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br />. At 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />, the SSS completed the notification call to the NRC Operations Center informing the NRC that a portion of safeguards measures had been suspended due to the severe weather and at 1528 hours0.0177 days <br />0.424 hours <br />0.00253 weeks <br />5.81404e-4 months <br />, FPL informed the NRC that the actions had been taken l
pursuant to 10 CFR 50.54(x) and (y). l By 0640 hours0.00741 days <br />0.178 hours <br />0.00106 weeks <br />2.4352e-4 months <br />, a sweep of all vital areas and the protected area was completed with no discrepancies noted. l The SSS contacted the NRC Operations Center at 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br /> and informed the NRC that safeguards measures !
l had been reinstated. l l
At 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />, the ESS system was retumed to operation with the exception of the alarm on the outer door to l the escape hatch of the reactor containment building that had failed and was unable to be tested. The alarm on the inner door to the escape hatch was noted as the valid alarm point for the escape hatch. At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, all r;:; quired tests were completed, and at 1034 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.93437e-4 months <br />, all vital areas, vital doors, perimeter zones, and gates were checked with no discrepancies noted. By 1041 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.961005e-4 months <br />, compensatory measures were secured.
CAUSE OF THE EVENT:
l l The cause of the event was severe weather including strong gusting winds, direct lightning strikes in the i
vicinity of St. Lucie Plant, and heavy rain. Additionally, a tomado warning was in effect in the vicinity of the plant.
ANALYSIS OF THE EVENT:
10 CFR 50.54(x) permits licensees to take reasonable action in an emergency even though the action departs from the license conditions or plant technical specifications if (1) the action is immediately needed to protect the public health and safety, including plant personnel, and (2) no action consistent with the license conditions and technical specifications is immediately apparent that can provide adequate or equivalent protection. Deviations authorized pursuant to 10 CFR 50.54(x) are reportable. The operating licenses for St. Lucie Units 1 and 2 include License Cond&n 2.D. which require that FPL fully implement and maintain in effect all provisions of the Commission approved Physical Security Plan. The suspension of safeguards constituted a departure from Ucense Condition 2.D. and was approved by a licensed Senior Reactor Operator prior to taking the action, as p rmitted by 10 CFR 50.54(y).
NRC FORM 366A (4-95)
l l NRC FORM 388A U.s. NUCLEAR REGULATORY COMMisslON l * (W
! LICENSEE EVENT REPORT (LER) l TEXT CONTINUATION j FACILITY NAME fil DOCKET LER NUMBER 81 PAGE f31
= $Wa^' "323 l ST. LUCIE UNIT 1 05000335 3 OF 3 98 - S02 - 00 TEKT (If more space is required. Use addbo.,al copres of NRc Form Z:6A) (17) l ANALYSIS OF THE EVENT (Cont.)
The severe lightning contributed to the failure of the installed surge protection devices within the IMUXs, I which performed their design function to prevent electrical fault propagation throughout the security computer system. These surge protection devices had routinely performed their intended function prior to March 9, 1998. Physical access control functions were not suspended.
CORRECTIVE ACTIONS:
l The abnormally severe storm was determined to be life threatening for persons exposed in compensatory positions. As soon as the severe weather subsided, compensatory measures were fully instituted and sweeps of vital and protected areas were completed. The failed surge protection was replaced prior to securing from compensatory measures. l l
l ADDITIONAL INFORMATION:
- a. Similar occurrence: x #94-S01 dated August 18,1994 and LER #93-S01 dated July 22,1993. l l b. St. Lucie has a contrac, tecurity force.
- c. No press release was made.
j d. No Local Law Enforcement Agency (LLEA) was notified.
- e. No unauthorized access was gained to the protected area or any vital area. l l
l l
FAILED COMPONENTS IDENTIFIED:
Component: E8S Multiplexer Manufacturer VT Technologies Model Number 52n4 NRC FORM 366A (4-95)