05000348/LER-2019-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift

Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift

ML19343B093
Person / Time
Site:	Farley
Issue date:	12/09/2019
From:	Kharrl C Southern Nuclear Company
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-19-1454 LER 2019-001-00
Download: ML19343B093 (4)

LER-2019-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift

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)(iii) 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)
3482019001R00 - NRC Website

text

A Southern Nuclear OEC 0 9 2019 Docket No_:

50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Charles Kharrl Vice President - Farley Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2019-001-00 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits due to Setpoint Drift Ladies and Gentlemen:

Joseph M. Farley Nuclear Plant 7388 No11h State Hwy 95 Columbi~. Alabama 363 19 334.8 14.45 1 I tel 334.814.4575 fax ckharrl @sou themco.com NL-19-1454 In accordance with the requirements of 10 CFR 50.73{a)(2)(i)(B), Southern Nuclear Company is submitting the enclosed Licensee Event Report for Unit 1.

This letter contains no NRC commitments. If you have any questions regarding this submittal, please contact Thomas Campbell at (334) 814-4587.

Respectfully submitted, Charles Kharrl Vice President - Farley CK!tec/scm Enclosure: Unit 1 Licensee Event Report 2019-001-00 Cc:

Regional Administrator, Region II NRR Project Manager-Farley Nuclear Plant Senior Resident Inspector-Farley Nuclear Plant RTYPE: CFA04.054

Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2019-001-00 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits due to Setpoint Drift Enclosure Unit 1 Licensee Event Report 2019-001-00

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

Estimated burden per response to comply with !his mandatoty collection request 8ll hoUis.

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LICENSEE EVENT REPORT (LER)

Reported lessons learned are incorporated Into !he licensing process and fed back to lnduslly. Send COIM1ants regilf<ing burden estinate 1o lha Information Services Branch

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(See Page 2 for required number of digits/characters for each block)

(T*2 F43), U.S. Nuclear Regulatory Comnission. Washington, DC 20555-0001, or by 1H11al

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to lnfocollects.Resource@rvc.gov, and to the Desk O!ficer, O!r~ee of Information and (See NUREG-1 022, R.3 for instruction and guidance for completing this form Regulatory AJ!airs, NEOB-10202, (3150.0104), Oftioa or Managemenl and Budge~

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an information collection does not

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.f' tlt!Q://www Q[Q, gQv((~i!diog - rrn/doc-coii~ Qtion~l!!Y~gs/sti!ff!~tl Q22/r~l) display a currenUy valid OMB conrol number, the NRC may not conduct or sponsor, and a person is not required to respond to, lhe information collection.

3.Page Joseph M. Farley Nuclear Plant, Unit 1 05000 348 1

OF 2

4. Title Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits due to Setpoint Drift

5. Event Date

6. LER Number

7. Report Date

8. Other Facilities Involved Month Day Year Year I Sequential I Rev Month Day Year Facility Name Docket Number Number No.

05000 I~ DCf OlDt9 Facility Name Docket Number 10 11 2019 2019 -

001 -

00 05000

9. Operating Mode 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)

D 20.2201(b)

D 20.2203(a)(3)(i)

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

D 50.73(a)(2)(viii)(A)

D 20.2201(d)

D 20.2203(a)(3)(ii)

D 50. 73(a)(2)(ii)(B)

D 50. 73(a)(2)(viii)(B)

N D

D D

D 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2Wx)(A)

D 20.2203(a)(2)(i)

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 73.71(a)(4)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

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

D 73.71(a)(5)

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

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

D 73.77(a)(1) 000 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)(i)

D 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

D 50.73(a)(2)(vii) 0 73.77(a)(2)0i)

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

D Other (Specify in Abstract below or in NRC Form 366A)

12. Licensee Contact for this LER Licensee Contact Telephone Number (Include Area Code)

Thomas Campbell, Licensing Engineer (334) 814-4587 Cause System I ComR~/"t I Manufacturer Reportable to ICES I N/ACause I System I Component Manufacturer I Reportable to ICES X

AB C710 y

14. Supplemental Report Expected Month Day Year 0

0

15. Expected Submission Date Yes (If yes, complete 15. Expected Submission Date)

No Abstract (Limit to 1400 spaces, i.e., approximately 14 single-spaced typewritten lines)

On October 11, 2019, while at 0% power level and defueled, it was discovered that a Unit 1 pressurizer safety valve (PSV),

which had been removed during the October 2019 refueling outage ( 1 R29) and shipped off-site for testing, failed its as-found lift pressure test. The PSV lifted below the Technical Specification (TS) 3.4.1 0 allowable lift setting value. Setpoint drift is the cause of the PSV failure.

It is likely that the PSV was outside of the TS limits longer than the allowable completion times for the associated Required Action Statements during the previous operating cycle in all applicable modes of operation. Therefore, this condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS.

The PSV was replaced during the October 2019 refueling outage.

NRC FORM 366 (04-2018)

EVENT DESCRIPTION

During the Unit 1 October 2019 refueling outage (1 R29), while at 0% power level and defueled, with the Reactor Coolant System (RCS) [EIIS:AB] at atmospheric pressure and 88 degrees Fahrenheit, a pressurizer safety valve (PSV) [EIIS:RV]

was removed as part of the routine In-Service Testing (1ST) program and sent to an off-site testing facility. On October 11, 2019 the site was notified that the as-found lift pressure was discovered to be 2444 psig which was outside of the Technical Specification (TS) 3.4.10 allowable lift pressure settings of>/= 2460 psig and</= 2510 psig. The tested valve was in the ASME code acceptance band of+/- 3% (2411-2559 psig). Based on the lift pressure meeting the 1ST program (ASME code) monitored requirements, there was no 1ST scope expansion for the PSV.

EVENT ANALYSIS

Setpoint Drift of the PSV (Manufacturer: Crosby, Model Number: HB-86-BP, Serial Number: N56963-01-0005) was determined to be the cause of the failure.

REPORTABILITY AND SAFETY ASSESSMENT

This failure constitutes a condition that is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications." There is no firm evidence, prior to the time of discovery at the test facility, of when the failure occurred. Since the as-found lift setpoint was lower than the allowed value in the TS, the condition did not have an adverse impact on its over-pressurization function. The as-found lift pressure was 2444 psig, and the valve re-closed following the lift. This is within the safety analysis assumptions that are credited for PSVs, and the plant remained bounded by the accident analyses in the Final Safety Analysis Report (FSAR). Therefore, this condition had no significant effect on the health and safety of the public. There was no release of radioactivity.

CORRECTIVE ACTIONS

The PSV was replaced during the October 2019 refueling outage. The as-left setpoints were within+/- 1% tolerance.

Additional corrective actions are being pursued to prevent reoccurrence.

PREVIOUS SIMILAR EVENTS

Similar events were reported for Unit 1 in LER 2016-003-00, and LER 2018-001-00.

OTHER SYSTEMS AFFECTED:

No other systems were affected by this event. Page 2

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