05000346/LER-2002-005, From Davis-Besse Unit 1 Regarding Potential Clogging of Emergency Sump Due to Debris in Containment

From Davis-Besse Unit 1 Regarding Potential Clogging of Emergency Sump Due to Debris in Containment

ML023110138
Person / Time
Site:	Davis Besse
Issue date:	11/04/2002
From:	Myers L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NP-33-02-005-00 LER 02-005-00
Download: ML023110138 (4)

LER-2002-005, From Davis-Besse Unit 1 Regarding Potential Clogging of Emergency Sump Due to Debris in Containment

Event date:
Report date:
Reporting criterion:	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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3462002005R00 - NRC Website

text

FENOC FEIJoC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Low W. Myrs 419-321-7599 Chief Operating Officer Fax. 419-321-7582 NP-33-02-005-00 Docket No. 50-346 License No. NPF-3 November 4, 2002 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Ladies and Gentlemen:

LER 2002-005 Davis-Besse Nuclear Power Station, Unit No. 1 Date of Occurrence - September 4, 2002 Enclosed please find the abstract to Licensee Event Report 2002-005, which is being submitted to provide written notification of the subject occurrence. This abstract is being submitted in accordance with 10CFR50.73(a)(2)(v)(B), 10 CFR 50.73(a)(2)(v)(D) and IOCFR50.73(a)(2)(vii). The abstract contains the requested information in accordance with Section 5.2.6 of NUREG-1022, Revision 2.

FirstEnergy Nuclear Operating Company is currently performing a detailed review of this occurrence and the results of our evaluation will be reported in a supplement to this License Event Report prior to restart. The supplement will include: A clear, specific, narrative description of what occurred including the apparent cause of the event; an assessment of the safety consequences and implications of the event including availability of systems that could have performed the same function; a description of any corrective actions planned as a result of the event including those to reduce the probability of similar events occurring in the future; and references to any previous similar events at the plant that are known.

Submission of this abstract was discussed with the appropriate NRC Regional Office.

Very truly yours, AWB/s Enclosure

) E~7'~

Docket Number 50-346 License Number NPF-3 NP-33-02-005-00 Page 2 cc:

Mr. J. E. Dyer, Regional Administrator, USNRC Region III Mr. C. S. Thomas, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board

Docket Number 50-346 License Number NPF-3 NP-33-02-005-00 Attachment Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory

commitments

Please notify the Manager - Regulatory Affairs (419-321-8450) at Davis-Besse of any questions regarding this document or associated regulatory commitments.

COMMITMENTS

DUE DATE A supplement to this LER shall be submitted prior to Prior to Restart restart after the review of the emergency sump clogging issue is complete.

NNRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 06130/2001 (1-2D01)

Estimated burden per response to comply with this mandatory Information collection request 50 hrs Reported lessons learned are incorporated into the LIENEEEVN RPO T LE'licensing process and fed back to industry Forward comments regarding LICENSEE EVENT REPORT (LER) burden estimate to the Records Management Branch (T-6 F33), U S Nuclear Regulatory Commission, Washington, DC 20555-0001, and to the Paperwork (See reverse for required number of Reduction Project (3150-0104),

Office of Management and

Budget, for ech bock)Washington, DC 20503 If an Information collection does not display a currently digits/characters for each block) valid MB control number, the N RC may not conduct or sponsor, and a person is not required to respond to, the information collection FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

Davis-Besse Unit Number 1

[

05000346 1 OF 1 J

TrTLE (4)

Potential Clogging of the Emergency Sump Due to Debris in Containment EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7) ll OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR lENUMBER l NUMBER MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 09 04 2002 2002

-- 005 --

00 11 04 2002 lFACILITY NAME D 05000 OPERATING DF THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR E: (Check all that apply) (11)

MODE (9) 20 2201 (b) 20.2203(a)(3)(i)

_50.73(a)(2)(1)(C)

X 50.73(a)(2)(vii)

POWER 000 20 2201 (d)

_ 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(vm)(A)

LEVEL (10) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20 2203(a)(2)(i)

_ 50.36(c)(1)(i)(A)

_ 50 73(a)(2)(iii) 50 73(a)(2)(ix)(A) 20 2203(a)(2)(i 50.36(c)(1)(i)(A) 50.73(a)(2)(tv)(A) 50 73(a)(2)(x) 20 2203(a)(2)(uii 50.36(c)(2)

_ 50 73(a)(2)(v)(A) 73 71 (a)(4) 20 2203(a)(2)(v) 50.46(a)(3)(ii) 50 73(a)(2)(v)(B) l 73 71 (a)(5) 20 2203(a)(2)(v) 50.73(a)(2)(i)(A) 50 73(a)(2)(v)(C)

OTHER f

20 2203(a)(2)(vi)

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

Specify In Abstract below or in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Include Area Code)

Aaron W. Bless, Engineer - Licensing l(419) 321-8543 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANU-REPORTABLE I

MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT FACTURER T EPIX

CAUSE

SYSTEM COMPONENT FACTURER T

EPIX SUPPLEMENTAL REPORT EXPECTED (14) l EXPECTED lMON DAY YEAR X YES (if yes, complete EXPECTED SUBMISSION DATE)

NO L

SUBMISSION 02 l11 2003 1 1DATE (15IS)_

ABSTRACT (Limit to 1400 spaces, i e, approximately 15 single-spaced typewritten lines) (16)

On September 4, 2002, with the reactor defueled and the unit in mode 6, investigations determined that a gap existed in the sump screen that exceeds the existing design basis (greater than 1/4-inch openings) and the existing amount of unqualified paint used inside containment could potentially block the emergency sump intake screen, rendering the sump inoperable, following a loss of coolant accident. With the emergency sump inoperable, both independent Emergency Core Cooling Systems (ECCS) and both Containment Spray (CS) systems are inoperable due to both requiring suction from the emergency sump during the recirculation phase of operation. This could result in neither train of ECCS being able to remove residual heat from the reactor nor could CS remove heat and fission product iodine from the containment atmosphere. This condition is being submitted in accordance with 10 CFR 50.73(a)(2)(v)(B) and (D) as a condition that could have prevented fulfillment of a safety function, and in accordance with 10 CFR 50.73(a)(2)(vii) where a single cause or condition caused two independent trains or channels to become inoperable in a single system. Review of the emergency sump is ongoing and a supplement report will be submitted prior to restart. The emergency sump strainer has been removed and construction of a new strainer system with greater surface area is in progress.

NRC FORM 366 (1-2001)