0CAN042504, LER 2025-S01-00 for Arkansas Nuclear One, Units 1 and 2, Follow-up Report for a 10 CFR 73 Security Report on January 31, 2025
| ML25091A100 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/01/2025 |
| From: | Keele R Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 0CAN042504 LER 2025-S01-00 | |
| Download: ML25091A100 (1) | |
Text
entergy Manager, ReguatoryAssurance Arkansas Nuclear One Tel 479-858-7826 0CAN042504 1 0 CFR 73 April 1, 2025 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Follow-up Report for a 1 0 CFR 73 Security Report on January 31, 2025 Arkansas Nuclear One Units 1 and 2 NRC Docket Nos. 50-313 and 50-368 Renewed Facility Operating License Nos. DPR-51 and NPF-6 Entergy Operations, Inc. (Entergy) submits the enclosed Follow-up Report for a 1 0 CFR 73 Security Report on January 31, 2025, 2025-501 -00 for Arkansas Nuclear One, Units 1 and 2 (ANO). The events reported herein are reportable in accordance with 10 CFR 73 Appendix G, Reportable Safeguards Events.
By letter dated November 21, 2023 (ML23325A141 ), as supplemented on November 29, 2023 (ML23333A136), ANO requested an exemption from the January 8, 2024 compliance date for the Final Rule for 1 0 CFR 73 published in the Federal Register on March 1 4, 2023 (88 FR 15864). Entergy committed to continued compliance with Appendix G to 10 CFR 73, Reportable Safeguards Events and the security event reporting requirements for ANO as they existed prior to March 2023, consistent with the sites current NRC-approved security plan and its security procedures. The NRC granted that request by letter dated February 2, 2024 (ML24012A050).
This report is based on the continued reporting requirements of 10 CFR 73, Appendix G (now reserved) and guidance provided in Regulatory Guide 5.62, Generic Letter 91-03 and NUREG 1304.
This letter contains no new regulatory commitments.
Entergy Operations, Inc. 1448 S.R 333 Russellville, AR 72802
0CAN042504 Page 2 of 2 If you have any questions concerning this issue please contact me at 479-858-7826.
Sincerely LA RDKIahv cc:
NRC Region IV Regional Administrator NRC Senior Resident Inspector Arkansas Nuclear One NRC Project Manager Arkansas Nuclear One NRC Director, Office of Nuclear Security and Incident Response
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB:
NO. 3150-0104 EXPIRES:
0413012027 (04-02-2024)
Esmated burden per response to comply with this mandatory collecton request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden
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LICENSEE EVENT REPORT (LER) estmate to the
- FOIA, Library, and Informaton Collectons Branch (T-6 AtOM),
U.S.
Nuclear Regulatory 2
l Commission, Washington, DC 20555-0001, or by e-mail to lnfocollecto.Resourcenrc.gov, and the 0MB reviewer (See Page 2 for required number ofdigitslcharacters for each block) at 0MB Office oflnformaton and Regulatory Affairs, (3150-0104), Ath,: Desk Officer for the Nuclear Regulatory m t-ar Commission 725 17th Sheet NW Washington DC 20503 The NRC may not conduct or sponsor and a person is
-o (See NUREG-1022, R.3 for InstruCbon and guidance for Completing this form not required to respond to, a collecton of informaton unless the document requesting or requiring the collection https://www.nrC.qov/readinq-rm/doC-colleCtionslnureqs/staff/srl022/r31) displays a currently valid 0MB conbol number.
- 1. Facility Name 050
- 2. Docket Number
052
- 4. Title port for a 10 CFR 73 Securit
- 3. Operating Mode
- 10. Power Level 1
100
w--
This Reportis Submitted Pursuantto the Requirements of 10 CFR: (Check all that apply)
,o CFR Part 2O El 20 2203(a)(2)(vi) 10 FR Part E 50 73(a)(2)00A L
50 73(a)(2)(viiO(A)
El 73 1200(a) 20.2201(b)
El 20.2203(a)(3)(i) 1 50.36(c)(1)(i)(A) fl 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
El 73.1200(b) i: 20.2201(d) 20.2203(a)(3)(ii) j 50.36(c)(1)(ii)(A) 50.73(a)(2)(iii) 1 50.73(a)(2)(ix)(A) fl 73.1200(c) 20.2203(a)(1)
El 20.2203(a)(4)
E 50.36(c)(2)
El 50.73(a)(2)(iv)(A) 1 50.73(a)(2)(x) 73.1200(d) 20 2203(a)(2)(i)
%O CFR Part 21 El 50 46(a)(3)(ii)
E 50 73(a)(2)(v)(A)
CFR4 73 LI 73 1200(e) 20.2203(a)(2)(ii) 21.2(c)
LI 50.69(g) 50.73(a)(2)(v)(B) 1 73.77(a)(1) 1 73.1200(f) 20.2203(a)(2)(iii)
E 50.73(a)(2)(i)(A)
E 50.73(a)(2)(v)(C)
E 73.77(a)(2)(i) 73.1200(g) 1 20.2203(a)(2)(iv)
E 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Q 73.77(a)(2)(ii) 73.1200(h) 20.2203(a)(2)(v)
E 50.73(a)(2)(i)(C)
J 50.73(a)(2)(vii)
OTHER (Specify here, in abstract, or NRC 366A). 10 CFR 73
- 12. Licensee Contactforthis LER Licensee Contact Phone Number (Include Area Code)
Riley D. Keele Jr.
k479) 858-7826
- 13. Complete One Lineforeach Component Failum DeSCilbed in this Report Cause System Component Manufacturer Reportable To IRIS Cause System Component Manufacturer Reportable To IRIS
- 14. Supplemental Report Expected Month Day Year
- 15. Expected Submission Date No D Yes (lfyes, complete 15. Expected Submission Date)
I 6. Abstract (Limitto 1326 spaces, i.e., approximately 13 single-spaced typewritten hnes)
On January 31
, 2025 at 1436 CST, Entergys Fleet Access Authorization department, in conjunction with the Training department, discovered and documented a programmatic issue which resulted in some individuals with expired training being allowed entry into the Protected Area at one or multiple Entergy sites. These individuals had Unescorted Access Authorization but were deficient in their periodic training. This issue was determined to involve a software deficiency between Entergys Learning Management System and the industrys Personnel Access Data System which created incorrect requalification dates for Plant Access Training and/or Fitness for Duty training. At the time the event notification was made, 3 individuals badged at ANO had been identified.
Access for the affected individuals was removed until appropriate training was completed.
Entergy made an event notification at 1524 CST on January 31, 2025 (EN 57525).
This event is being reported in accordance with 1 0 CFR 73.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 (o4-o2-2o24 fc ;\\
LICENSEE EVENT REPORT (LER) iJ CONTINUATION SHEET (See NUREG-1 022, R.3 for instruction and guidance for completing this form https:/twww.nrc.gov/readinq-rm/doc-collections/nureqs/staff/sr1022/r3/)
1.
FACILITY NAME Arkansas Nuclear One, Unit I
Background
By letter dated November 21
, 2023 (ML23325A141), as supplemented on November 29, 2023 (ML23333A136),
Arkansas Nuclear One, Units 1 and 2 (ANO) requested an exemption from the January 8, 2024 compliance date for the Final Rule for 10 CFR 73 published in the Federal Register on March 14, 2023 (88 FR 15864). Entergy committed to continued compliance with Appendix G to 10 CFR 73, Reportable Safeguards Events and the security event reporting requirements for ANO as they existed prior to March 2023, consistent with the sites current NRC-approved security plan and its security procedures. The NRC granted that request by letter dated February 2, 2024 (ML24012A050).
This report is based on the continued reporting requirements of 10 CFR 73, Appendix G (now reserved) and guidance provided in Regulatory Guide (RG) 5.62, Generic Letter 91-03 and NUREG-1 304.
Event Description On January 31
, 2025, at 1436 CST, Entergys Fleet Access Authorization department, in conjunction with the Training department, discovered and documented a programmatic issue which resulted in some individuals with expired training being allowed entry into the Protected Area at one or more Entergy sites. These individuals had Unescorted Access Authorization but were deficient in their periodic training. This issue was determined to involve a software deficiency between Entergys Learning Management System (LMS) and the industrys Personnel Access Data System (PADS) which created incorrect requalification dates for Plant Access Training and/or Fitness for Duty training. At the time the event notification was made, 3 individuals badged at ANO had been identified. No additional individuals were identified during the investigation.
Of the 3 affected individuals badged at ANO, 2 of those individuals entered the ANO Protected Area after their training had lapsed. The individuals remained in the Fitness-for-Duty Random Pool during this time and also remained in the Behavior Observation Program. Upon discovery, the badges for these individuals were terminated until such time that appropriate training could be completed and their badges be re-instated.
EN 57525 was promptly made on January 31, 2025 at 1524 CST.
As of March 6, 2025, ANO is now in compliance with the March 2023 Final Rule for 10 CFR 73 (88 FR 15864).
Event Cause The direct cause was a result of the integration of the new PADS software with Entergys LMS.
Safety Assessment This event had no impact of the health and safety of the public. The individuals whose training had lapsed had previously completed initial training; therefore, they were of no risk to plant safety.
Corrective Actions Affected individuals access to the Protected Area was removed until appropriate training was completed. The software deficiency has been corrected and automatic data transfer between LMS and PADS has been reinstated.
EXPIRE5: 04130/2027 Estmated burden per response to comply with this mandatory collecton request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden eshmate to the FOIA, Library, and Information Collectons Branch (T-6 A1OM), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Reuource@nrc gov, and the 0MB reviewer at. 0MB Office of Information and Regulatory Affairs, (3150-0104), Atm: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW.
Washington, DC 20503 The NRC may not conduct or sponsor, and a person is not required to respond to, a collecton of informahon unless the document requesting or requiring the collechon disolavo a currenflv valid 0MB control number NARRATIVE NRC FORM 366A (04-02-2024)
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (o4-o2-2o24 Esmated burden per response to comply with this mandatory collechon request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden eshmate to the FOIA, Library, and Information Collechons Branch (T-6 A1OM), U.S.
1 CONTINUATION SHEET Nuclear Regulatory Commission, Waohington, DC 20555-0001, or by e-mail to lnfocollects.Resourcenrc.gov, and the 0MB reviewer at: 0MB Office of Information and Regulatory
Affairs, (3150-0104), Attn. Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, (See NUREG-1 022, R.3 for instruction and guidance for completing this form Washington, DC 20503. The NRC may not conduct or sponsor, and a person is not required to https://www.nrc.qov/readinci-rm/doc-collections/nureqs/staff/sr1022/r3/)
respond to, a collection of information unless the document requesting or requiring the collection displays a currenfy valid 0MB control number.
I.
FACILITY NAME Arkansas Nuclear One, Unit I Previous Similar Occurrences None
- 2. DOCKET NUMBER NRC FORM 366A (04-02-2024)
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