05000346/LER-2005-002, Regarding Mode Change - Inoperable Battery Due to Procedure Deficiency and Inadequate Reviews

Regarding Mode Change - Inoperable Battery Due to Procedure Deficiency and Inadequate Reviews

ML051870216
Person / Time
Site:	Davis Besse
Issue date:	07/01/2005
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NP-33-05-002-00 LER 05-002-00
Download: ML051870216 (11)

LER-2005-002, Regarding Mode Change - Inoperable Battery Due to Procedure Deficiency and Inadequate Reviews

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x)
3462005002R00 - NRC Website

text

FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 NP-33-05-002-00 I OCFR50.73 Docket Number 50-346 License Number NPF-3 July 1, 2005 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Ladies and Gentlemen:

Licensee Event Report Number 2005-002-00 Davis-Besse Nuclear Power Station, Unit Number I Date of Occurrence - December 28, 2003 Enclosed is Licensee Event Report Number 2005-002-00, which provides written notification of the operation of the Davis-Besse Nuclear Power Station (DBNPS) Unit Number I under a condition prohibited by the Operating License Technical Specifications. On December 28, 2003, the plant entered Mode 4 and all station batteries were required to be operable. However, one (1) of the station batteries had not been demonstrated to be operable due to a low voltage reading on one battery cell. This was not discovered until the surveillance test data taken on December 4, 2003, was being re-evaluated and on May 4, 2005, it was determined this condition rendered one (1) station battery inoperable. The battery was determined to be operable at its next surveillance test on March 4, 2004. This event occurred because the December 4, 2003, surveillance test acceptance criteria was signed off as acceptable when in actuality one of the cells of the battery had not passed its surveillance test acceptance criteria. This event is being reported pursuant to IOCFR50.73(a)(2)(i)(B) as a condition prohibited by the station's Technical Specifications.

Commitments associated with this Licensee Event Report are listed in the Attachment.

Very truly yours, JCS

Docket Number 50-346 License Number NPF-3 NP-33-05-002-00 Page 2 of 2 Attachment Enclosure cc:

Regional Administrator, USNRC Region III DB-1 Project Manager, USNRC DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board

Docket Number 50-346 License Number NPF-3 NP-33-05-002-00 Attachment Page I 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 Compliance (419-321-8585) at Davis-Besse of any questions regarding this document or associated regulatory commitments.

COMMITMENTS

DUE DATE

1. DB-ME-03001 will be further revised to improve its use and to make it more conducive for users and reviewers to identify data that does not meet the Acceptance Criteria. This change to DB-ME-03001 will be in effect until the new electronic data recording mechanism is completely in place.

2. The DBNPS will implement an in-field electronic data recording mechanism for DB-ME-03001. The technology should be capable of flagging data that does not meet acceptance criteria. Implementation is currently scheduled for use during performance of DB-ME-03001 by October 20, 2005.

1. October 20, 2005

2. October 20, 2005

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 613012007 (6-2004)

Estinated, the NRC may (See reverse for required number of not conduct or sponsor, and a person Is not required to respond to, the digits/characters for each block)

Information collection.

3. PAGE Davis-Besse Unit Number 1 05000346 1 OF 8

4. TITLE Mode Change -

Inoperable Battery Due to Procedure Deficiency and Inadequate Reviews

5. EVENT DATE

6. LER NUMBER I

7. REPORT DATE I

8. OTHER FACILITIES INVOLVED MONTH I DAY I YEAR YEAR ISEQUENTIAL YER NUMBER DOCKET NUMBER 05000 2

28 2003 2005

- 002

- 00 OCKET NUMBER 05000

9. OPERATING MODE 4

10. POWER LEVEL 000

11. THIS REPORT IS SUBMITTED PURSUANT TO THE hat apply)

El 20.2201(b)

D 20.2201(d)

[E 20.2203(a)(1)

Cl 20.2203(a)(2)(i)

Ea 20.2203(a)(2)(ii) al 20.2203(a)(2)(iii) a 20.2203(a)(2)(iv) a 20.2203(a)(2)(v)

Dl 20.2203(a)(2)(vi)

Dl 20.2203(a)(3)(i)

D 20.2203(a)(3)(ii) al 20.2203(a)(4) 5 50.36(c)(1)(i)(A) 5 50.36(c)(1)(ii)(A)

E 50.36(c)(2) 5 50.46(a)(3)(ii) a 50.73(a)(2)(ij(A) 3 50-73(a)(2)(i)(B) al 50.73(a)(2)(1)(C) 5 50.73(a)(2)(ii)(a) a 50.73(a)(2)(ii)(B)

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

Dl 50.73(a)(2)(v)(A) a 50.73(a)(2)(v)(B)

E 50.73(a)(2)(v)(C) 5 50.73(a)(2)(v)(D)

D 50.73(a)(2)(vii) a 50.73(a)(2)(viii)(A) a 50.73(a)(2)(viii)(B) a 50.73(a)(2)(ix)(A)

El 50.73(a)(2)(x) a 73.71(a)(4)

E 73.71(a)(5)

S OTHER Specify In Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Fomn 366A)

DESCRIPTION OF OCCURRENCE (continued):

On December 28, 2003, the plant entered Mode 4 requiring Station Battery 2N (Train B) to be operable.

The plant was in a mode requiring both trains (Train A and Train B, including Station Battery 2N) of Station Batteries to be operable. Because Station Battery 2N Cell 60 voltage was not demonstrated to have been restored to above the 2.13 vdc operating limit, Station Battery 2N (Train B) was inoperable.

Therefore, the plant should not have entered Mode 4 and was in a condition prohibited by TS 3.0.4.

Additionally, the plant was in a condition prohibited by TS Limiting Condition for Operation (LCO) 3.8.2.3.

The start date of this event is December 4, 2003 (Cell 60 reading of 2.114 vdc).

The event date of this condition is December 28, 2003 (entry into Mode 4, all Station Batteries required to be operable).

The discovery date is May 4, 2005, when the surveillance test Acceptance Criteria for Station Battery 2N Cell 60 voltage reading of 2.114 vdc was determined to be accurate and it was concluded that Station Battery 2N should have been declared inoperable.

This is a past inoperability issue.

DC System Configuration The Direct Current (DC) system [EJ] is described in the Updated Safety Analysis Report (USAR) Section 8.3.2, "DC Power System." The DC equipment consists of two 250/125 vdc motor control centers, four batteries (IN, 1P, 2N and 2P), six battery chargers, four essential distribution panels, four 480 vac /125 vdc rectifiers and four nonessential distribution panels.

The four station lead-acid batteries [EJ-BTRY] are 125 vdc, approximately 1500 ampere-hour, on an eight-hour discharge basis, and arranged to form two independent 250/125 vdc systems.

The batteries have one minute, 1-hour and 8-hour capacities of 1400, 750, and 187 amperes, respectively. Each battery is maintained in a fully charged condition and is normally float charged at approximately 132 volts from its associated battery charger. Battery discharge will occur either when the DC requirements temporarily exceed the charger capacity or during a loss of a battery charger supply. Each battery is connected to one 125 vdc bus of one of the two DC motor control centers.

DBNPS has a total of four (4) Station Batteries in two (2) trains: 1) Train "A" consists of batteries IN and IP; and 2) Train "B" consists of batteries 2N and 2P.

The batteries are sized to supply the anticipated DC and instrument AC supply for a period of one hour after the loss of the battery charger supply. This includes approximately 20% over capacity to compensate for the loss due to aging of the batteries over a 20-year period.

(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)

FAILURE DATE (continued):

There was one other occurrence identified in which Station Battery out of specification cell voltage data was recorded and not identified during the Maintenance review process. Condition Report (CR) 02-02758 involved a situation identical to the one described in this event.

The electric shop/supervision did not identify the condition and the procedure was signed off as acceptable.

The designated reviewer identified the condition.

Condition Report (CR) 02-02758 did not look at how the data was recorded and how the procedure was structured.

The batteries were determined to have successfully passed their surveillance test and the equipment was operable when required by the Technical Specifications.

Energy Industry Identification System (EIIS) codes are identified in the text as [xX].

NP-33-05-002-00 CR 2005-02415