05000388/LER-2011-002, Regarding Condition Prohibited by Technical Specification Due to Unknown RCIC Inoperability

Regarding Condition Prohibited by Technical Specification Due to Unknown RCIC Inoperability

ML112380638
Person / Time
Site:	Susquehanna
Issue date:	08/26/2011
From:	Rausch T Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 11-002-00
Download: ML112380638 (4)

LER-2011-002, Regarding Condition Prohibited by Technical Specification Due to Unknown RCIC Inoperability

Event date:
Report date:
Reporting criterion:	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)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x)
3882011002R00 - NRC Website

text

Timothy S. Rausch Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570,542,3445 Fax 570.542.1504 tsrausch@pplweb corn AJG 6 211 1J. S. Nuclear Regulatory Commission ikttrr. Document Control Desk

'Mail. Stop OP1-17 NA'ashinp,ton. D(' 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388/2011-002-00 LICENSE NO. NPF-22 PEA-6755 Docket No 50-388 Attached is Licensee Event Report (LER.) 50-388/2011-002-00. The event involved an unknown inoperability of Unit 2 RCIC that resulted in a condition prohibited by Technical Specifications. As a result. this event is being reported under JO CFR 50.73(a)(2Ki)(B) as a condition prohibited by Technical Specification.

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

No regulatory commitments are associated with this 1.,1.:1 Mr. P. V., Sr,,Resikif;n1.-, trispector Mr, R. R.,.

Mr.. B.

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NRC FORM 1311.6 1 iii 2olo*.I U.S. NUCLEAR REGU1.ATOR'c COMMISSION

!APPROVED BY OMB: No.

EXHRES 1 0/3 Ei--r.lirriated burden por respcinsc:

comply with this manr:iatory coithction 11,-,,,quest 80 kr.tirs. Reported thrrsonsteair.:ed Marc tnrrorporaled into the proc;Ea.,s and fed

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LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block) 1 FACILITY NAME

'12. DOCKET NUMBER

h3. PAGE Susquehanna Steam Electric Station Unit 2

05000388

1 OF 3

4. TITLE Condition Prohibited by Technical Specification Due to Unknown RCIC Inoperability

5. EVENT DATE 6. LER NUMBER

1

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEQUENTIAL

FACILITY REV

'DOCKET NUMBER MONTH DAY

YEAR

YEAR f

EP DAY

YEAR

05000

! NUMBER I NO,

I

FACILITY NAME

DOCKET NUMBER I

I t

2

10. POWER LEVEL 0%

2201b K 20.2201(b) 0 20.2201(d)

K 20.2203(a)(1)

K 20.2203(a)(2)(i)

K 20.2203(a)(2)(ii) 0 20.2203(a)(2)(iii) 0 20.2203(a)(2)(iv)

K 20.2203(a)(2)(v) 0 20.2203(a)(2)(vi) 0 20 2203(a)(3)(i)

K 20,2203(a)(3)(ii)

K 20.2203(a)(4)

K 50.36(c)(1)(i)(A)

K 50.36(c)(1)(ii) (A)

K 50.36(c)(2) 50.46(a)(3)(ii)

K 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B)

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

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

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

D 50.73(a)(2)(iii)

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

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

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

D 50.73(a)(2)(v)(D) 0 50 73(a)(2)(vii)

K 50 73(a)(2)(viii)(A)

K 50.73(a)(2)(viii)(B) 0 50.73(a)(2)(ix)(A) 0 50.73(a)(2)(x) 0 73.71(a)(4)

K 73.71(a)(5) 0 OTHER Specify in Abstract below or in =

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CONTINUATION SHEET

. FACILITY NAME Susquehanna Steam Electric Station Unit 2

2. DOCKET

6. LEIR NUMBER

3. PAGE YEAR FiRit)f:1411AL.

fiEVI SIUN I Numr3E'R

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00 3 OF 3 05000388 L

NARRATIVE

Analysis of Event

Following the overspeed trip, the EGM and RGSC output data was reviewed. The review identified that the outputs became abnormal when the flow controller was returned to AUTO following RCIC Turbine Overspeed Testing on May 10, 2011. The output remained abnormal until the flow controller was placed in MANUAL prior to the starting the RCIC turbine to perform the 24 month RCIC Flow Verification Test on June 27, 2011. Following the testing, the outputs returned to the abnormal values and remained abnormal following the overspeed trip on June 29, 2011. RCIC was restored to OPERABLE status on July 2, 2011. A Root Cause Analysis is in progress.

Failure Analysis The failed component was a Woodward Model 8271-083 RGSC. The RGSC circuit board did not show any indications of heat damage. The RGSC has no age-sensitive components. Review of Operating Experience also supports that the RGSC components do not experience age-related failures. Additional analysis of the failed RGSC is planned.

CAUSE OF THE EVENT

The apparent cause of the condition is an unexpected, random failure of the RGSC since the RGSC contains no age sensitive components, The investigation of this event is continuing. Additional insight into the cause is expected based on sending the failed RGSC to the vendor to identify the failed component and completion of a root cause analysis.

ANALYSIS/SAFETY SIGNIFICANCE

Actual Consequences:

The failure rendered the RCIC system unavailable for 109.15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> from the time reactor pressure exceeded 150 psig until the system became available following RGSC replacement and quarterly flow surveillance retest.

Potential Consequences:

Even though the RCIC System is not an Engineered Safety Feature System and no credit is taken in the safety analyses rcot ROTC.; system operation RCIC woirkt h3NE'r".* been onat,r,as to perform its terrr,hd mission lFtiriA,r. F":(0 i ton) autorrratJo

Irtject 000 qpm co

I' 6.19.(,I;OT water IeveI, Fx

a.ppro.A..,",.;-:tte tow' hcur perPoirl Ixiitween

28, 2011 arT,'0

29, 20/ 'I, IC entorod

to 21,-.,,nriod

qt's RCIC,

In the PPA.,

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• expecteo irsendor report iLt.o None