ML071560451: Difference between revisions

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{{#Wiki_filter:PDuke DrPowerA Duke Energy Company GARY R. PETERSON Vice President McGuire Nuclear Station Duke Power MG01 VP / 12700 Hagers Ferry Rd.Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.
{{#Wiki_filter:PDuke                                                         GARY R. PETERSON DrPower                                                    Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MG01 VP / 12700 Hagers Ferry Rd.
com May 24, 2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555  
Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.com May 24,     2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.       20555


==Subject:==
==Subject:==
McGuire Nuclear Station Docket No, 50-369 Security Event Report 369/2007-SO1 Problem Investigation Process (PIP) M-07-2237 I Pursuant to 10 CFR 73 Appendix G, paragraph I(b), attached is Security Event Report 369/2007-SO1.
McGuire Nuclear Station Docket No, 50-369 Security Event Report 369/2007-SO1 Problem Investigation Process (PIP) M-07-2237 I
This report documents the escort of an unauthorized individual into the protected area.This event was determined to be of no significance to the health and safety of the public. There are no regulatory cormi-entsn ita-eT-n this Event Report.G. R. Peterson Attachment www. dukepower.
Pursuant to 10 CFR 73 Appendix G, paragraph I(b), attached is Security Event Report 369/2007-SO1.       This report documents the escort of an unauthorized individual into the protected area.
com U. S. Nuclear 'Regulatory Commission May 24, 2007 Page 2 cc: W. D. Travers Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J. F. Stang (Addressee Only)NRC Project Manager U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Site U. S. Nuclear Regulatory Commission May 24, 2007 Page 3 bxc: David G. Black (MG01SC).Kay L. Crane (MG01RC)Lisa F. Vaughn (EClIX)Robert L. Gill .(EC05P)(NSRB Support Staff) (EC05N)Paper Distribution:
This event was determined to be of no significance to the health and safety of the public.       There are no regulatory cormi-entsn         ita-eT-n this Event Report.
Master File (3.3.7)ELL (EC050)RGC File NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 06-30-2007 (6-2004) COMMISSION Estimated burden per response to comply with this mandatory information collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry.
G. R. Peterson Attachment www. dukepower.com
Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects@nrc.gov, and to the Desk Officer, Office of Information and (See reverse for required number of Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, digits/characters for each block) DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to rpqnnnri tn thp infnrmptinn 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE McGuire Nuclear Station 05000 369I 1 OF 3 4. TITLE Unauthorized Individual Allowed Escorted Access in the Protected Area 5. EVENT DATE 6. LER NUMBER f 7. REPORT DATE T 8. OTHER FACILITIES INVOLVED I IFACILITY NAME DOCKET NUMBER 1TZ ISEQUENTIAL REV MONTH DY YEAR YEAR NUMBER NO MONTH DAY YEAR IMcGuire 5 0- 37 0 0o7 2007 -SOl -00 1 5FACILITY NAME DOCKET NUMBER 9. OPERATING
 
: 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: Check all that apply)MODE 6 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
U. S. Nuclear 'Regulatory Commission May 24, 2007 Page 2 cc: W. D. Travers Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J. F. Stang (Addressee Only)
: 10. POWER 20.2201(d) 20.2203(a)(4)  
NRC Project Manager U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Site
._50.73(a)(2)(iii) 50.73(a)(2)(x)
 
LEVEL 0 20.2203(a)(1) 50.36(c)(1  
U. S. Nuclear Regulatory Commission May 24, 2007 Page 3 bxc: David G. Black (MG01SC)
)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4)___. .20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5), __ 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(g)
    .Kay L. Crane (MG01RC)
OTHER...._ _ __ _ _ _ _Specify in Abstract below or 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Lisa F. Vaughn (EClIX)
X in_____Form_366A
Robert L. Gill .(EC05P)
____ 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D)
(NSRB Support Staff) (EC05N)
___. .20.2203(a)(2)(v) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii)
Paper Distribution:
__I 20.2203(a)(2)(vi) 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A)
Master File   (3.3.7)
_____________________________
ELL (EC050)
20.2203(a)(3)(i)  
RGC File
-50.73(a)(2)(ii)(A) 50.73 a)(2)(viii)(B)
 
H 12. LICENSEE CONTACT FOR THIS LER NAME 1 TELEPHONE NUMBER (Include Area Code)Kay L. Crane, Regulatory Compliance
NRC FORM 366                               U.S. NUCLEAR REGULATORY               APPROVED BY OMB NO. 3150-0104                                                   EXPIRES 06-30-2007 (6-2004)                                                       COMMISSION       Estimated burden per response to comply with this mandatory information collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects@nrc.gov, and to the Desk Officer, Office of Information and (See reverse for required number of                         Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, digits/characters for each block)                         DC                       usedNRCto impose     an information conduct or collection sponsor, does and anotperson display is anot currently validto OMB20503.
[ 704-875-4306
controlIfanumber, means the             may not                                               required rpqnnnri tn thp infnrmptinn rnl*krtnn
: 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU- REPORTABLE MANU- REPORTABLE CAUSE SYSTEM COMPONENT FACTURER TO EPIX CAUSE SYSTEM COMPONENT FA CTURER TO EPIX 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR II S-UBMISSION YES If yes, complete 15.EXPECTED SUBMISSION DATE). X NO DATE 16. ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 sinqle-spaced typewritten lines)Unit Status: At the time of the event, Unit 1 was in Mode 6 (Refueling) at 0 percent power and Unit 2 was in Mode 1 (Power Operation) at 100 percent power.Event
: 1. FACILITY NAME                                                                 2. DOCKET NUMBER                                         3. PAGE McGuire Nuclear Station                                                                         05000           369I                                             1 OF         3
: 4. TITLE Unauthorized Individual Allowed Escorted Access in                                                                             the Protected Area
: 5. EVENT DATE                               6. LER NUMBER                 f         7. REPORT DATE                   T           8. OTHER FACILITIES INVOLVED MONTH         DY 1TZ    YEAR 0o7        2007 YEAR           NUMBER ISEQUENTIAL
                                                      -SOl          -
I NO REV 00        1 MONTH 5FACILITY DAY           YEAR IFACILITY IMcGuire NAME NAME DOCKET NUMBER 5 0- 37 0 DOCKET NUMBER
: 9. OPERATING                                       11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: Check all that apply)
MODE                 6               20.2201 (b)                 20.2203(a)(3)(ii)                   50.73(a)(2)(ii)(B)                         50.73(a)(2)(ix)(A)
: 10. POWER                               20.2201(d)                 20.2203(a)(4) .                 _50.73(a)(2)(iii)                             50.73(a)(2)(x)
LEVEL                 0               20.2203(a)(1)               50.36(c)(1 )(i)(A)                 50.73(a)(2)(iv)(A)                         73.71 (a)(4)
___.   .20.2203(a)(2)(i)           50.36(c)(1)(ii)(A)                 50.73(a)(2)(v)(A)                         73.71 (a)(5)
                                ,       __     20.2203(a)(2)(ii)           50.36(c)(2)                         50.73(a)(2)(v)(g)                         OTHER
                                      ....                   _     _     __       _     _   _     _Specify                                                     in Abstract below or 50.46(a)(3)(ii)                     50.73(a)(2)(v)(C)                 X       in_____Form_366A 20.2203(a)(2)(iii)
____   20.2203(a)(2)(iv)           50.73(a)(2)(i)(A)                   50.73(a)(2)(v)(D)
___.   .20.2203(a)(2)(v)           50.73(a)(2)(i)(B)                   50.73(a)(2)(vii)
__I     20.2203(a)(2)(vi)           50.73(a)(2)(i)(C)                   50.73(a)(2)(viii)(A)
_____________________________     20.2203(a)(3)(i)       -50.73(a)(2)(ii)(A)                     50.73 a)(2)(viii)(B)H
: 12. LICENSEE CONTACT FOR THIS LER NAME                                                                                                   1TELEPHONE NUMBER (Include Area Code)
Kay L.           Crane,         Regulatory Compliance                                                 [                               704-875-4306
: 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU-     REPORTABLE                                                                               MANU-         REPORTABLE CAUSE       SYSTEM           COMPONENT             FACTURER       TO EPIX             CAUSE           SYSTEM                   COMPONENT             FA CTURER           TO EPIX
: 14. SUPPLEMENTAL REPORT EXPECTED                                                       15. EXPECTED                     MONTH             DAY           YEAR II                                                                                                           S-UBMISSION YES   If yes, complete 15.EXPECTED SUBMISSION DATE).                       X     NO                               DATE
: 16. ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 sinqle-spaced typewritten lines)
Unit Status:                     At the time of the event,                                       Unit 1 was in Mode 6 (Refueling) at 0 percent power and Unit 2 was in                                                             Mode 1 (Power Operation) at 100 percent power.
Event


== Description:==
== Description:==
On April 5,                                                    2007,          it        was discovered that a vendor employee had erroneously been allowed escorted (visitor)                                                                                        access into the Protected Area (PA) (for approximately one hour) due to an incorrect Social Security Number (SSN) being entered into the Personnel Access Data System (PADS).          This event is                            reportable pursuant to 10 CFR 73 Appendix G, paragraph I(b).
Event Cause: The cause of the event has been                                                                            attributed                to human                error due to inadequate self checking and validation.
Corrective Action:                                  Implemented an enhanced method                                                        for checking                        and validation of PADS documentation against the information on the visitor badge paperwork.
NRC FORM 366 (6-2004)


On April 5, 2007, it was discovered that a vendor employee had erroneously been allowed escorted (visitor) access into the Protected Area (PA) (for approximately one hour) due to an incorrect Social Security Number (SSN) being entered into the Personnel Access Data System (PADS). This event is reportable pursuant to 10 CFR 73 Appendix G, paragraph I(b).Event Cause: The cause of the event has been attributed to human error due to inadequate self checking and validation.
NRC FORM 366A                                                                 U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
Corrective Action: Implemented an enhanced method for checking and validation of PADS documentation against the information on the visitor badge paperwork.
LICENSEE EVENT REPORT (LER)
NRC FORM 366 (6-2004)
: 1. FACILITY NAME         2. DOCKET       6. LER NUMBER                     3. PAGE YEAR SEQUENTIAL NUMBER I REVISION NUMBER McGuire Nuclear Station                         05000369   2007     -   S01     -     00     2   OF     3 EVENT DESCRIPTION The Personnel Access Database System (PADS) is an industry computer application used to record access authorization, training, and radiation protection information. A data search by Social Security Number (SSN) in the system results in one of two indicators: "ID Check OK" or "Contact Access."
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)LICENSEE EVENT REPORT (LER)1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE SEQUENTIAL I REVISION YEAR NUMBER NUMBER McGuire Nuclear Station 05000369 2007 -S01 -00 2 OF 3 EVENT DESCRIPTION The Personnel Access Database System (PADS) is an industry computer application used to record access authorization, training, and radiation protection information.
On April 5, 2007, it was discovered that a vendor employee had erroneously been allowed escorted (visitor)               access into the Protected Area (PA).                   A security employee incorrectly entered the vendor employee's SSN into the system. Since the PADS system did not recognize the SSN, it displayed "ID Check OK". A validation of the PADS screen (as displayed) by a second employee failed to recognize the incorrect SSN.
A data search by Social Security Number (SSN) in the system results in one of two indicators: "ID Check OK" or "Contact Access." On April 5, 2007, it was discovered that a vendor employee had erroneously been allowed escorted (visitor) access into the Protected Area (PA). A security employee incorrectly entered the vendor employee's SSN into the system. Since the PADS system did not recognize the SSN, it displayed "ID Check OK". A validation of the PADS screen (as displayed) by a second employee failed to recognize the incorrect SSN.The escorted vendor employee was delivering equipment in support of the Unit 1 End-of-Cycle 18 refueling outage. A review of badge transactions revealed that the individual did not access any vital areas of the plant.Reportable Occurrence This event is reportable pursuant to 10 CFR 73 Appendix G, paragraph I(b)which requires a one hour notification and a written report within sixty days following discovery of an actual entry of an unauthorized person into the PA. The individual was not authorized for PA access per the requirements of the Duke Energy Nuclear Security and Contingency Plan.CAUSAL FACTORS The cause of this event is attributed to human error due to inadequate self checking.
The escorted vendor employee was delivering equipment in support of the Unit 1 End-of-Cycle 18 refueling outage. A review of badge transactions revealed that the individual did not access any vital                         areas of the plant.
The incorrect SSN coupled with the failure to recognize the error by validation resulted in access being granted.CORRECTIVE ACTIONS 1. Revoked vendor employee's escorted access authorization.
Reportable Occurrence This event is reportable pursuant to 10 CFR 73 Appendix G, paragraph I(b) which requires a one hour notification and a written report within sixty days following discovery of an actual entry of an unauthorized person into the PA.             The individual was not authorized for PA access per the requirements of the Duke Energy Nuclear Security and Contingency Plan.
: 2. Implemented an enhanced method for checking and validation of PADS documentation against the information on the visitor badge paperwork.
CAUSAL FACTORS The cause of this event is attributed to human error due to inadequate self checking. The incorrect SSN coupled with the failure to recognize the error by validation resulted in access being granted.
CORRECTIVE ACTIONS
: 1. Revoked vendor employee's escorted access authorization.
: 2. Implemented an enhanced method for checking and validation of PADS documentation against the information on the visitor                         badge paperwork.
NRC FORM 366A (1-2001)
NRC FORM 366A (1-2001)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)LICENSEE EVENT REPORT (LER)1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE SEQUENTIAL.
 
REVISION YEAR NUMBER NUMBER McGuire Nuclear Station 05000369 2007 -S01 -00 3 OF 3 SAFETY ANALYSIS The. individual was escorted at all times, did not enter any vital areas and demonstrated no malevolent intent. This event is of no safety significance and resulted in no adverse consequences to the health and safety of the public.ADDITIONAL INFORMATION A three year search of the McGuire corrective action database (PIP) and LER database revealed a similar occurrence in 2006. Security Event Report 369/2006-SO1 was reported on November 30, 2006.NRC FORM 366A (1-2001)}}
NRC FORM 366A                                                                   U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
: 1. FACILITY NAME         2. DOCKET         6. LER NUMBER                     3. PAGE SEQUENTIAL. REVISION YEAR       NUMBER     NUMBER McGuire Nuclear Station                         05000369     2007     -   S01     -   00     3   OF     3 SAFETY ANALYSIS The. individual was escorted at all               times, did not enter any vital               areas and demonstrated no malevolent intent.                   This event is of no safety significance and resulted in no adverse consequences to the health and safety of the public.
ADDITIONAL INFORMATION A three year search of the McGuire corrective action database (PIP) and LER database revealed a similar occurrence in 2006. Security Event Report 369/2006-SO1 was reported on November 30, 2006.
NRC FORM 366A (1-2001)}}

Latest revision as of 05:37, 23 November 2019

LER 07-S01-00 for McGuire Nuclear Station Regarding Unauthorized Individual Allowed Escorted Access in the Protected Area
ML071560451
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 05/24/2007
From: Gordon Peterson
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 07-S01-00
Download: ML071560451 (6)


Text

PDuke GARY R. PETERSON DrPower Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MG01 VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.com May 24, 2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

McGuire Nuclear Station Docket No, 50-369 Security Event Report 369/2007-SO1 Problem Investigation Process (PIP) M-07-2237 I

Pursuant to 10 CFR 73 Appendix G, paragraph I(b), attached is Security Event Report 369/2007-SO1. This report documents the escort of an unauthorized individual into the protected area.

This event was determined to be of no significance to the health and safety of the public. There are no regulatory cormi-entsn ita-eT-n this Event Report.

G. R. Peterson Attachment www. dukepower.com

U. S. Nuclear 'Regulatory Commission May 24, 2007 Page 2 cc: W. D. Travers Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J. F. Stang (Addressee Only)

NRC Project Manager U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Site

U. S. Nuclear Regulatory Commission May 24, 2007 Page 3 bxc: David G. Black (MG01SC)

.Kay L. Crane (MG01RC)

Lisa F. Vaughn (EClIX)

Robert L. Gill .(EC05P)

(NSRB Support Staff) (EC05N)

Paper Distribution:

Master File (3.3.7)

ELL (EC050)

RGC File

NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 06-30-2007 (6-2004) COMMISSION Estimated burden per response to comply with this mandatory information collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects@nrc.gov, and to the Desk Officer, Office of Information and (See reverse for required number of Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, digits/characters for each block) DC usedNRCto impose an information conduct or collection sponsor, does and anotperson display is anot currently validto OMB20503.

controlIfanumber, means the may not required rpqnnnri tn thp infnrmptinn rnl*krtnn

1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE McGuire Nuclear Station 05000 369I 1 OF 3
4. TITLE Unauthorized Individual Allowed Escorted Access in the Protected Area
5. EVENT DATE 6. LER NUMBER f 7. REPORT DATE T 8. OTHER FACILITIES INVOLVED MONTH DY 1TZ YEAR 0o7 2007 YEAR NUMBER ISEQUENTIAL

-SOl -

I NO REV 00 1 MONTH 5FACILITY DAY YEAR IFACILITY IMcGuire NAME NAME DOCKET NUMBER 5 0- 37 0 DOCKET NUMBER

9. OPERATING 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: Check all that apply)

MODE 6 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)

10. POWER 20.2201(d) 20.2203(a)(4) . _50.73(a)(2)(iii) 50.73(a)(2)(x)

LEVEL 0 20.2203(a)(1) 50.36(c)(1 )(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4)

___. .20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5)

, __ 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(g) OTHER

.... _ _ __ _ _ _ _Specify in Abstract below or 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) X in_____Form_366A 20.2203(a)(2)(iii)

____ 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D)

___. .20.2203(a)(2)(v) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii)

__I 20.2203(a)(2)(vi) 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A)

_____________________________ 20.2203(a)(3)(i) -50.73(a)(2)(ii)(A) 50.73 a)(2)(viii)(B)H

12. LICENSEE CONTACT FOR THIS LER NAME 1TELEPHONE NUMBER (Include Area Code)

Kay L. Crane, Regulatory Compliance [ 704-875-4306

13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU- REPORTABLE MANU- REPORTABLE CAUSE SYSTEM COMPONENT FACTURER TO EPIX CAUSE SYSTEM COMPONENT FA CTURER TO EPIX
14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR II S-UBMISSION YES If yes, complete 15.EXPECTED SUBMISSION DATE). X NO DATE
16. ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 sinqle-spaced typewritten lines)

Unit Status: At the time of the event, Unit 1 was in Mode 6 (Refueling) at 0 percent power and Unit 2 was in Mode 1 (Power Operation) at 100 percent power.

Event

Description:

On April 5, 2007, it was discovered that a vendor employee had erroneously been allowed escorted (visitor) access into the Protected Area (PA) (for approximately one hour) due to an incorrect Social Security Number (SSN) being entered into the Personnel Access Data System (PADS). This event is reportable pursuant to 10 CFR 73 Appendix G, paragraph I(b).

Event Cause: The cause of the event has been attributed to human error due to inadequate self checking and validation.

Corrective Action: Implemented an enhanced method for checking and validation of PADS documentation against the information on the visitor badge paperwork.

NRC FORM 366 (6-2004)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)

LICENSEE EVENT REPORT (LER)

1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE YEAR SEQUENTIAL NUMBER I REVISION NUMBER McGuire Nuclear Station 05000369 2007 - S01 - 00 2 OF 3 EVENT DESCRIPTION The Personnel Access Database System (PADS) is an industry computer application used to record access authorization, training, and radiation protection information. A data search by Social Security Number (SSN) in the system results in one of two indicators: "ID Check OK" or "Contact Access."

On April 5, 2007, it was discovered that a vendor employee had erroneously been allowed escorted (visitor) access into the Protected Area (PA). A security employee incorrectly entered the vendor employee's SSN into the system. Since the PADS system did not recognize the SSN, it displayed "ID Check OK". A validation of the PADS screen (as displayed) by a second employee failed to recognize the incorrect SSN.

The escorted vendor employee was delivering equipment in support of the Unit 1 End-of-Cycle 18 refueling outage. A review of badge transactions revealed that the individual did not access any vital areas of the plant.

Reportable Occurrence This event is reportable pursuant to 10 CFR 73 Appendix G, paragraph I(b) which requires a one hour notification and a written report within sixty days following discovery of an actual entry of an unauthorized person into the PA. The individual was not authorized for PA access per the requirements of the Duke Energy Nuclear Security and Contingency Plan.

CAUSAL FACTORS The cause of this event is attributed to human error due to inadequate self checking. The incorrect SSN coupled with the failure to recognize the error by validation resulted in access being granted.

CORRECTIVE ACTIONS

1. Revoked vendor employee's escorted access authorization.
2. Implemented an enhanced method for checking and validation of PADS documentation against the information on the visitor badge paperwork.

NRC FORM 366A (1-2001)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)

LICENSEE EVENT REPORT (LER)

1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE SEQUENTIAL. REVISION YEAR NUMBER NUMBER McGuire Nuclear Station 05000369 2007 - S01 - 00 3 OF 3 SAFETY ANALYSIS The. individual was escorted at all times, did not enter any vital areas and demonstrated no malevolent intent. This event is of no safety significance and resulted in no adverse consequences to the health and safety of the public.

ADDITIONAL INFORMATION A three year search of the McGuire corrective action database (PIP) and LER database revealed a similar occurrence in 2006. Security Event Report 369/2006-SO1 was reported on November 30, 2006.

NRC FORM 366A (1-2001)