ML20148D027

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LER 97-S01-00:on 970418,improperly Authorized Individuals Were Granted Access to Plant Protected Area.Caused by Inadequate Work Process.Keycard Badges Were Inactivated for All Individuals Not Fully Employed
ML20148D027
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/19/1997
From: Beckendorf E, Leonard T
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-97-S01, LER-97-S1, W3F1-97-0098, W3F1-97-98, NUDOCS 9705300036
Download: ML20148D027 (5)


Text

'

y Ent; gy Operati ns,Inc.

Kdlona. LA 700E60751 Tel 504 464 3120 de a Man ger O'2rt" W3F1-97-0098 A4.05 PR l

May 19,1997 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 j

License No. NPF-38 Reporting of Security Incident Report Gentlemen:

Attached is Security Incident Report (SIR) Number 97-S01-001 for Waterford Steam Electric Station Unit 3. This report documents an occurrence where 10 individuals i

were improperly authorized access to the Plant Protected Area.

This condition is being reported pursuant to Appendix G to 10CFR73.71(c).

Very truly yours, i

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,a J

T.R. Leonard 4

s General Manager

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Plant Operations TRL/GCS/tjs Attachment C90045 cc:

E.W. Merschoff (NRC Region IV), C.P. Patel (NRC-NRR),

A.L. Garibaldi, J.T. Wheelock - INPO Records Center, R.B. McGehee, N.S. Reynolds, NRC Resident inspectors Office, j

Administrator - LRPD s

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YRE FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150 0104 14e51 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THis MANDATORY hFORMATION COLLECTION REQUEST: 60.0 WRS. REPORTED LESSONS LEARNED ARE LICENSEE EVENT REPORT (LER)

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RECORDS MANAGEMENT BRMCH lT 6 F33). U.S. NUCLEAR REGULATORY COMMISSION, (see reverse for required number of WASHINGTON, DC 20!E0001. MD TO THE PAPERWORK REDUCTION PROJECT (3150-digits / characters for each block) 0% ECE OF MMAGEMENT MD BN, WASHmGTM OC 2m FAC MrY NAAE (1)

DOCKET NUMim (2)

Pact (3)

WATERFORD STEAM ELECTRIC STATION UNIT 3 05000 382 1 op 4 wam IMPROPERLY AUTHORIZED INDIVIDUALS GRANTED ACCESS TO THE PROTECTED AREA EVENT DATE (5)

LER NUMBER (6)

REPO I DATE (7)

OTHER FACIUTIES INVOLVED (8)

F ACluTY NAME DOCKET NUMBER SEQU IAL Ri S MONTH DAY YEAR YEAR MONTH DAY YEAR q

N/A m@

FACluTY NAME DOCKET NUMBER 04 18 97 97 - S01 00 05 19 97 N/A 05000

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OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)

MODE (9) 6 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(0 50.73(aH2Hvin) 20.2203(a)M )

20.2203(aH3HO 50.73(aH2Hu) 50.73(aH2Hx)

POWER LEVEL (10) 0 20.2203 aH2)c) 20.2203( H3)(id 50.73(aH2)Did y

73.71 20.2203(a)(2)00 20.2203(aH4) 50.73(aH2)0v)

OTHER 20.2203(a)(2Hud 50.36(c)M )

50.73(a)(2Hv)

Spgengin A ract elow p

8 20.2203(a)(210v) 50.36(c)(2) 50.73(a)(2)(vu)

LICENSEE CONTACT FOR THIS LER O2)

NCME YLLEPHONE NUMBER Hnciuoe Area Codel E.G. BECKEND0RF, SECURITY SUPERINTENDENT (504)739-6340 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIGED IN THIS REPORT (13)

R P0 TA E REPORTAB E CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER SUPPLEMENTAL REPORT EXPECTED 04)

MONTH DAY YEAR EXPECTED YES SUBMISSION NO (if yes, complete EXPECTED SUBMISSION DATE).

X DATE 05) y ABSTRACT (Linst to 1400 spaces,i.e., approximately 15 single-spaced typewritten lines) 06)

On April 18,1997, Waterford 3 security personnel determined initially that an unknown number of individuals had been improperly authorized access to the plant protected area (PA). All of the individuals had been issued active keycard badges. Security performed a controlled evacuation of all nonessential personnel from the PA to determine the extent of the problem. The cause of this event is an inadequate work process in that contractors were allowed to obtain unescorted access to the plant while they were conditionally employed prior to completing all requirements for full employment.

Following an investigation into this event, it was determined that none of the individuals entered the PA and there was no malevolent intent to gain entry by the parties involved.

This event did not compromise the health and safety of the public or plant personnel.

This Security incident Report is being submitted per 10CFR73.71 (c) requirements.

NRC FORM 308 (496) f

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NRC, FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 14 F.4 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME U)

DOCKET LER NUMBER (6)

PAGE (3)

NU R NUM WATERFORD STEAM ELECTRIC STATION UNIT 3 382 97 S01 00 TEXT (11 more space is required, use additional copies of NRC Form 366A} U 7)

REPORTABLE OCCURRENCE Due to errors in the process of completing the Area Access Request (AAR) forms, ten improperly authorized individuals could have gained access into the Protected Area (PA). This event is being reported pursuant to Appendix G to 10CFR 73.71(c) which i

states that any failure, degradation, or the discovered vulnerability in a safeguards system that could allow unauthorized access to the protected area is reportable. On April 18,1997, a one hour report of this event was issued per the same requirement.

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lNITIAL CONDITIONS During this occurrence, Waterford 3 was in Mode 5 (Cold Shutdown). No structures, systems or components were inoperable that contributed to this event.

EVENT DESCRIPTION On April 18,1997, Waterford 3 security personnel determined an unknown number of individuals had been improperly authorized to access the PA. All of the individuals had been issued active keycard badges. This condition was discovered when a contract individual informed an Entergy Director that she was in possession of an active keycard badge but was not actively working for a contract company. This information was provided to the Security department who began to investigate this matter. Security performed a controlled evacuation of all nonessential personnel from the PA to determine the extent of the problem. Further investigation determined that ten contract individuals had been improperly authorized to access the PA. None of the individuals entered the PA.

CAUSAL FACTORS A Root Cause Analysis (RCA) team has been formed to investigate this event.

Preliminary results indicate the cause of this event is an inadequate work process in that contractors were allowed to obtain unescorted access to the plant prior to CRC FORM 388A 14951

NHC, FORM 3J2A U.S. NUCLEAR REGULATORY COMMISSION 1499 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME 0)

DOCKET LEH NUMBER (6)

PAGE (3)

NU B R NUM 05 WATERFORD STEAM ELECTRIC STATION UNIT 3 3

97 - S01

- 00 l

TEXT (If more space os required, use additional copses of NRC Form 366A) (17) completing all requirements for full employment. Any significant changes to preliminary causal factors and or corrective actions will be submitted as a revision to this Security incident Report.

The requirements for obtaining unescorted access are completion of General Employee Training (GET) I, a background investigation, Fitness for Duty drug screening, and having a need for plant access. The need for access for an applicant is determined by their supervision and is communicated by the submittal of an AAR to in-processing personnel. The process that was in place encouraged the expeditious submittal of AARs to facilitate the granting of unescorted plant access. AARs were submitted prior to the individual being in a full employment status. Upon receipt of the AAR by in-processing personnel, it was understood that the individual had met the requirement for need for plant access.

All ten of the individuals were conditionally employed by the supervisors because their employment was contingent upon successful completion of GET ll training. Since these individuals were only conditionally employed, there was no need to gain access to the PA. In consequence, unescorted plant access was inappropriately provided to the ten individuals who had completed background checks, successfully completed Fitness for Duty drug screening, completed GET I training, and had AARs submitted without a true need for plant access.

CORRECTIVE MEASURES Keyct.rd badges were inactivated for all individuals identified as not fully employed.

An evacuation of the plant of non-essential personnel was performed and their current employment status and need for unescorted access was verified.

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Security performed a 100% verification of employment and need for unescorted access for all badged individuals.

NRC FudM 366A I499

NHC, FORM 366A U.S. NUCLEAR REGULATORY COMMISSION H 051 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACIUTY NAME (1)

DOCKET LER NUMBER (6) l PAGE (3)

YEAR SEQU IAL REV S 0

0 WATERFORD STEAM ELECTRIC STATION UNIT 3 97 -- S01

-- 00 TEXT (11 more space is required, use additional copies of NRC Form 366A) (17)

A letter was issued by the Manager, Materials, Purchasing and Contracts to all Contract Managers emphasizing the importance of not requesting unescorted access for an individual until all company required elements have been satisfied and the individualis fully employed by a contract company.

An interim checklist was created that requires verification of employment status prior to releasing a keycard to the primary access point (PAP).

A procedure will be issued providing guidance to plant personnel on the proper in-promssing and out-processing of individuals and the correct use of the AAR.

SAFETY SIGNIFICANCE This event did not compromise the health and safety of the public or plant personnel.

With the exception of the need for access due to individuals being conditionally employed, all requirements to gain unescorted access to the PA (i.e. background l

check, fingerprinting, alcohol and drug testing, and psychological evaluation) were completed.

SIMILAR EVENTS There have been no similar events reported as SIRS at Waterford 3.

CRC FORM 368A Mkil

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