05000388/LER-2011-001, Regarding Multiple Inoperable Main Steam Safety Relief Valves

Regarding Multiple Inoperable Main Steam Safety Relief Valves

ML111820767
Person / Time
Site:	Susquehanna
Issue date:	07/01/2011
From:	Rausch T Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6723 LER 11-001-00
Download: ML111820767 (4)

LER-2011-001, Regarding Multiple Inoperable Main Steam Safety Relief Valves

Event date:
Report date:
Reporting criterion:	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) 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)(iii) 10 CFR 50.73(a)(2)(ix)(A) 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)(x) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3882011001R00 - NRC Website

text

Timothy S. Rausch Sr: Vice President & Chief Nu leaf Officer PPL Susquehanna, LLC i

76 Salem Boulevard

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1.J. S. Nuclear..Regulatory Commission

.Attn: Document Control Desk Mail Stop OP I -17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATI(." -

.LICENSEE EVENT REPORT 50-388/2011-001-00 LICENSE NO. NPF-22 PL A.-672?

Docket. No 50-388 Attached is Licensee Event Report (LER) 50-38812011-001-00. This event was determined to be an Operation or Condition Prohibited by Technical Specifications and reportable under 10 CFR 50.73(a)(2)(i)(B) in that three (3) main safety relief valves (SRNirs) were inoperable during the past operating cycle which is not in accordance with Technical Specification 3.4.3.

This event is also reportable as a Common-Cause inoperability of Independent Trains or Channels in accordance with 10 CFR 50.73(a)(2)(vii).

There Were no actual consequences to the health and safety of the public as a result of this event.

No regulatory' coiMilittrICIAS are a, sociated. with. this UFR.

Attachtnent p'+'° NRC. Region Mr.. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEP/RRP Mi. B. K_ Vaidye., INIRC Projeet Manager

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U.S. NUCLEAR REGULATORY COMMISSION

11,01130 VED B1' OMB. NO '3150-0.104

EXPIRE-S:10/31 12013 (Estimated burden per respor150 to (:,oroply with this mandatory collection regt,,,,;t*. 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported Iessons lam-Fled are incorporated into the is ansr.:n proc:ess :;rid fed

In industry. Send comments regarding burden thcr.. f Secttion (r-f3 F53), U. S. Nuclear Regulatory

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24',F.55-0001, or by internet o-rnail to v. and to thin Lock' Officer. Office of InfOnnation

at i kl.'2Ul'A'S.ryAt',..,ir..s.Nr--. 06-10202., (.3150-0104), Office of Management and Wastlingtt.,n, It a means itsFtd to impose tan infOnmtion dor.. not tit.7,plEw to curfently valid OMB control Flo I Tibef, tho NRC nay not conduct or sponsor, 'end a person is not required to respond to, thin nformation collection.

2. DOCKET NUMBER

2. PAGE 05000388

1 OF 3 LICENSEE EVENT REPORT (LER)

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

1. FACILITY NAME Susquehanna Steam Electric Station Unit 2

4. TITLE Multiple Inoperable Main Steam Safety Relief Valves 5,. EVENT DATE

6. LER NUMBER

7. REPORT DATE ;

8. OTHER FACILITIES INVOLVED SE:GWEN-HA(,

REV

FACILITY NAME

'DOCKET NUMBER MONTH i DAY i

YEAR ;

YLAR

I

, NIONTI-DAY ! YEAR 1

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1 1 NUMBER ; NO. 1

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DOCKET NUMBER 05 ! 02

2011

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9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §

(Check all that apply) 5 D 20.2201(b)

K 20.2203(a)(3)(i)

K 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)

K 20.2201(0)

K 20.2203(03)(ii)

K 50.73(a)(2)(ii)(A)

K 50.73(a)(2)(viii)(A)

K 20.2203(01)

K 20,2203(a)14)

K 50.73(a)(2)(ii)(B)

K 50,73(a)(2)(viii)(B)

J10. POWER LEVEL K 20.2203(a)(2)(i)

K 50:36(c)( 1 )(I)(A)

K 50.73(a)(2)(iii)

K 50.73(a)(2)(ix)(A) 0 K 20,2203(a)(2)(ii)

K 20.2203(a)(2)(iii) 0 50.36(c)(1)(5)(A)

K 50.36(c)(2)

K 50.73(a)(2)(iv)(A)

K 50.73(a)(2)(v)(A)

K 50.73(a)(2)(x)

K 73.71(a)(4)

K 20.2203(a)(2)(iv)

K 50.46(a)(3)(ii)

K 50.73(a)(2)(v)(B)

K 73.71(a)(5)

K 20.2203(a)(2)(v)

K 50.73(a)(2)0)(A)

K 50.73(a)(2)(v)(C) o SpeOcTify"EinRAbstract K 20.2203(a)(2)( vi) 50.73(a)(2)(i)(B)

K 50.73(a)(2)(v)(D) below or in

CORRECTIVE ACTIONS

The following corrective actions have been completed:

One SRV was replaced with an SRV having a setpoint tolerance of +/- 1% of nameplate setpoint pressure, Two SRVs were refurbished and reinstalled with setpoint tolerances of +/- 1% of nameplate setpoint pressure.

The issue of setpoint drift has been entered into the Corrective Action Program.

The following corrective action is planned; The SRVs that failed their setpoint tolerance will be refurbished to have an actuation pressure within +1-1% of nameplate setpoint pressure.

No regulatory commitments are associated with this report.

ADDITIONAL INFORMATION

Failed Component Information: None

Previous Similar Events

I.....ER 2000-007-00, Docket No 387/i. 'cense No. NPF-14, 'Multiple Test Failures of Main..!_l'Aeoirn Safety Relief Valves"'

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2001-0°5-0a,

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est Farti...trerr:; of rOoi!..:

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