05000348/LER-2013-003-01, Regarding 1C Steam Generator Flow Transmitter Inoperable Longer than Allowed by Technical Specifications: Difference between revisions

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#REDIRECT [[05000348/LER-2013-003, Regarding 1C Steam Generator Flow Transmitter Inoperable Longer than Allowed by Technical Specifications]]
| number = ML14052A438
| issue date = 02/21/2014
| title = Regarding 1C Steam Generator Flow Transmitter Inoperable Longer than Allowed by Technical Specifications
| author name = Gayheart C
| author affiliation = Southern Co, Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000348
| license number =
| contact person =
| case reference number = NL-14-0272
| document report number = LER 13-003-01
| document type = Letter, Licensee Event Report (LER)
| page count = 6
}}
{{LER
| Title = Regarding 1C Steam Generator Flow Transmitter Inoperable Longer than Allowed by Technical Specifications
| Plant =
| Reporting criterion = 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(vii), 10 CFR 50.73(a)(2)(ii)(A), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(ii)(B), 10 CFR 50.73(a)(2)(viii)(B), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(ix)(A), 10 CFR 50.73(a)(2)(iv)(A), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(v)(A), 10 CFR 50.73(a)(2)(v)(B), 10 CFR 50.73(a)(2)(i)(A), 10 CFR 50.73(a)(2)(v)
| Power level =
| Mode =
| Docket = 05000348
| LER year = 2013
| LER number = 3
| LER revision = 1
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:Cheryl A. Gaybeart v.re Pres*dent
* Far'ey February 21, 2014 Southern Nuclear Operating Company, Inc.
Farley Nuclear Plant Post Office Drawer 470 Ashford. Alabama 36312 Tel 334.814 4511 Fax 334.814.4575 Docket Nos.: 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Ucensee Event Report 2013-003-01 SOUTHERN <<\\
COMPANY NL~14~0272 1 C Steam Generator Flow Transmitter Inoperable Longer Than Allowed By Technical Specifications Ladies and Gentlemen:
This Ucensee Event Report, "1 C Steam Generator Row Transmitter Inoperable Longer Than Allowed By Technical Specifications," is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50.73(a)(2)(i)(B),
"Any operation or condition which was prohibited by the plant's Technical Specifications."
This letter contains no NRC commitments. If you have any questions regarding the submittal, please contact Mr. Bill Arens at (334) 81 ~4765.
Sincerely, Ms. C..
ayheart Vice President-Farley CAGIWNA Enclosure: Unit 1 Ucensee Event Report 2013-003-01
 
U. S. Nuclear Regulatory Commission NL-14-0272 Page 2 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. B. L. lvey, Vice President-Regulatory Affairs Mr. C. R. Pierce, Regulatory Affairs Director Mr. D. R. Madison, Vice President-Fleet Operations Mr. J. G. Horn, Regulatory Affairs Manager-Farley Mr. J. E. Purcell, Nuclear Technical Specialist-Farley Ms. K. A. Walker, Senior Engineer-Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. G.E. Miller, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley Mr. J. R. Sowa, Resident Inspector-Farley Mr. R. E. Martin, Senior Project Manager-Farley
 
Joseph M. Farley Nuclear Plant-Unit 1 NL-14-0272 1 C Steam Generator Flow Transmitter Inoperable Longer Than Allowed By Technical Specifications Enclosure Unit 1 Licensee Event Report 2013-003-01
 
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS: NO. 3150-0104 EXPIRES: 01/31/2017 (01-2014)
Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to indus!~ Send comments regarding burden LICENSEE EVENT REPORT (LEA) estimate to the FOINPrivacy Section ( -5 F53). U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects.resource@nrc.Bov, and to the Desk Officer, Office of Information and Regulatory Affairs, NE B-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMS control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
r*
PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000 348 1 OF 3
: 4. TITLE 1 C Steam Generator Flow Transmitter Inoperable Longer Than Allowed by Technical Specifications
: 5. EVENT DATE
: 6. LEA NUMBER
: 7. REPORT DATE
: 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 11 5
2013 2013 - 003 -
01 2
21 2014
: 9. OPERATING MODE
: 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR&sect;: (Check all that apply)
D 20.2201 (b) 0 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C)
D 50.73(a)(2)(vii) 1 D 20.2201 (d) 0 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(2)(i)
D 50.36(c)(1 )(i)(A)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
: 10. POWER LEVEL D 20.2203(a)(2)(ii) 0 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
D 20.2203(a)(2)(iii) 0 50.36(c)(2)
D 50.73(a)(2)(v)(A)
D 73.71(a)(4) 100 D 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(B)
D 73.71 (a)(S) 0 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(C) 0 OTHER 0 20.2203(a)(2)(vi) 181 50.73(a)(2)(i)(B)
D 50.73(a)(2)(v)(D)
Specify in Abstract below or in I
SEQUENTIAL
!REVISION NUMBER NUMBER 003 01 3
OF Prior to being rescaled, the high-steam flow bistable for FT-495 would have actuated at 111.62 percent steam flow as compared to a maximum Technical Specification allowable set point of 110.3 percent steam flow. During the time period of the FT-495 out-of-tolerance condition, the redundant steam flow transmitter remained capable of performing its safety function. Therefore, sufficient inputs to the main steam line isolation circuitry were available to actuate a main steam line isolation at the proper setpoint. At no time was there a loss of safety function.
Another means of providing a main steam line isolation in the event of a steam line break is the low-steam-pressure main steam line isolation signal. This function remained fully capable of performing the main steam line isolation function during the periods that FT-495 was known to be inoperable.
Based on the above considerations and on the FT -495 setpoint being outside the allowable tolerance but otherwise functional, this condition is considered to have low safety significance.
 
==Corrective Action==
An immediate corrective action of rescaling the FT-495 loop was performed. The loop was declared operable on November 6, 2013.
Several actions are being taken to address the recurring failures to meet normalization acceptance criteria. The steam flow instrument pre-normalization calibration will be modified to either lower the high steam flow bistable setpoint or to conservatively reduce the instrument gain settings so that potential normalization process inaccuracies do not result in a high steam flow bistable exceeding the maximum allowable setpoint. The feasibility of widening the normalization acceptance band will also be assessed.
To improve the timeliness of the normalization process, additional training has been provided to site engineering personnel and improved scaling methods will be investigated.
 
==Additional Information==
A review of previously submitted Licensee Event Reports identified two similar previous events on Unit 2, both were reported in Farley Unit 2 LEA 2013-001-00, in which the 2C Steam Generator Flow Transmitter FT-494 was inoperable longer than allowed by Technical Specifications. 3
}}
 
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