05000458/LER-2017-001, Regarding Operations Prohibited by Technical Specifications (Conduct of Operations with a Potential to Drain the Reactor Vessel with Primary Containment Open)

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Regarding Operations Prohibited by Technical Specifications (Conduct of Operations with a Potential to Drain the Reactor Vessel with Primary Containment Open)
ML17101A614
Person / Time
Site: River Bend 
Issue date: 04/03/2017
From: Maguire W
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RBF1-17-0036, RBG-47745 LER 17-001-00
Download: ML17101A614 (5)


LER-2017-001, Regarding Operations Prohibited by Technical Specifications (Conduct of Operations with a Potential to Drain the Reactor Vessel with Primary Containment Open)
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

10 CFR 50.73(a)(2)(viii)(A)

10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(viii)(B)

10 CFR 50.73(a)(2)(ix)(A)

10 CFR 50.73(a)(2)(iv)(A), System Actuation

10 CFR 50.73(a)(2)(x)

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(i)
4582017001R00 - NRC Website

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\\1 RBG-47745 April 3, 2017

  • U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Licensee Event Report 50-458 I 2017-001-00 River Bend Station - Unit 1 Docket No. 50-458

.License No. NPF-47 RBF1-17-0036

Dear Sir or Madam:

Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225-381-4157 William F. Maguire Site Vice President In accordance with 1 O CFR 50. 73, enclosed is the subject Licensee Event Report. This document contains no commitments. If you have any questions, please contact Mr. Tim Schenk at 225-381-4177.

Sincerely, WFM/dhw Enclosure cc:

U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.

Arlington, TX 76011-4511 NRC Sr. Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 INPO (via ICES reporting)

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Licensee Event Report 50-458 I 2017-001-00 April 3, 2017 RBG-47745 Page 2 of 2 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.

Austin, TX 78711-;3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312

I i NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY,_OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

Estimated burden per response to comply with this mandatory collection requesl: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

. f>'J<Toll't<l(/<.-...

Reported lessons learned are incorporated into the licensing process and fed back to industry.

LICENSEE EVENT REPORT (LER)

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections i

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail (See Page 2 for required number of digits/characters for each block) to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory

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Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC20503. lfa (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control htt!)://www.nrc.gov/reading-rm/dQc-cQlleQtions/nuregs/staff/~r1022/r3l) number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE River Bend Station - Unit 1 05000 458 1 OF 3
4. TITLE Operations Prohibited by Technical Specifications (Conduct of Operations With a Potential to Drain the Reactor Vessel With Primary Containment Open)
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED I

SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NO.

05000 FACILITY NAME DOCKET NUMBER 01 31 2017 2017 -

001 - 00 04 03 2017 05000

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

D 20.2201cb>

D 20.2203<a><3>

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A) 5 D 20.2201 <d>

D 20.2203<a><3>(ii)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B)

D 20.2203<a><1>

D 20.2203(a)(4)

D 50.73<a><2><iii)

D 50.73(a)(2)(ix)(A)

D 20.2203<a><2>

D 50.36(c)(1)(i)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

10. POWER LEVEL D 20.2203(a)(2)(ii)

D 50.36(c)(1)(ii)(A)

D 50.73(a)(2)(v)(A)

D 13.11ca><4>

D 20.2203<a><2>cm>

D so.36(c)(2)

D 50.73(a)(2)(v)(B)

D 13.11ca>

D 20.2203(a)(2)(iv)

D so.46(a)(3)(ii)

D 50.73(a)(2)(v)(C)

  • D 13.77(a><1>

0 D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(D)

D 73.77(a><2>

D 20:2203(a)(2)(vi)

[{] 50.73(a)(2)(i)(B)

D 50.73(a)(2)(vii)

D 13.11ca><2)(ii) f,;it'.?'. -.. : *:*:;~~~;:~.--

- c.

. ;~:

D 50.73(a)(2)(i)(C)

D OTHER Specify in Abstract below or in CORRECTIVE ACTION TO PREVENT RECURRENCE On December 20, 2016, NRG approved a generic Technical Specification amendment that can be used by licensees to reconcile this condition. It is required by the EGM that applicable licensees (including River Bend Station) must submit a request for this amendment by December 20, 2017.

SAFETY SIGNIFICANCE

During all OPDRVs, the following prerequisites were enforced:

1. Refueling cavity water level was maintained greater than 23 feet above the reactor pressure vessel flange.
2. The high pressure core spray system was maintained available for inventory makeup
3. The size of the allowable drainage path was minimized to maintain time-to-draindown at greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (to the RPV flange)
4. Two independent means of monitoring reactor cavity.water level were maintained.

All activities were completed with no transients in reactor cavity water level having occurred_ This event was, thus, of minimal safety significance with regard to the health and safety of the public. Page 3

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