05000388/LER-2013-002, Regarding Valve Internal Misalignment Resulting in Multiple Inoperable Main Steam Safety Relief Valves

Regarding Valve Internal Misalignment Resulting in Multiple Inoperable Main Steam Safety Relief Valves

ML13186A056
Person / Time
Site:	Susquehanna
Issue date:	07/03/2013
From:	Franke J Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 13-002-00
Download: ML13186A056 (4)

LER-2013-002, Regarding Valve Internal Misalignment Resulting in 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)(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), 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3882013002R00 - NRC Website

text

JUL@ 3 2013 Jon A. Franke Site Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

• PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388/2013-002-00 LICENSE NO. NPF-22 PLA-7035 Docket No. 50-388 Attached is Licensee Event Report (LER) 50-388/2013-002-00. This event was determined to be a Condition Prohibited by Technical Specifications and a Common-Cause Inoperability of Independent Trains or Channels and reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(vii) in that three (3) main safety relief valves (SRVs) were inoperable during the past operating cycle.

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 LER.

Attachment: LER 50-388/2013-002-00 Copy: NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES:1 0/31/2013 (10-2010)

, the NRC digits/characters for each block) may not conduct or sponsor, and a person is not required to respond to, the information collection.

~.PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 OF 3

4. TITLE Valve Internal Misalignment Resulting in Multiple Inoperable Main Steam Safety Relief Valves

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL l REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR MONTH DAY YEAR NUMBER NO.

()1 d3 FACILITY NAME DOCKET NUMBER 05 06 2013 2013

- 002

- 00 2013

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 5 D 20.2201 (b)

D 20.2203(a)(3)(i)

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

~ 50.73(a)(2)(vii)

D 20.2201 (d)

D 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)

10. POWER LEVEL 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) 000 D 20.2203(a)(2)(ii)

D 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)

D 50.36(c)(2)

D 50.73(a)(2)(v)(A)

D 73.71(a)(4)

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

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

D 73.71(a)(5)

D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(C) 0 OTHER D 20.2203(a)(2)(vi)

~ 50.73(a)(2)(i)(B)

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

Specify in Abstract below or in

CORRECTIVE ACTIONS

The following corrective actions have been completed:

U.S. NUCLEAR REGULATORY COMMISSION

6. LER NUMBER I

SEQUENTIAL NUMBER

- 002 I

REVISION NUMBER

- 00

3. PAGE 30F 3 The SRVs were replaced with SRVs having a setpoint tolerance of +I-1% of nameplate setpoint pressure.

The following corrective actions are planned:

The SRVs that failed their setpoint tolerance will be refurbished to have an actuation pressure within +/- 1 % of nameplate setpoint pressure.

Pending a license amendment and In-Service Testing (1ST) Relief Request, procedures for post-installation testing of SRVs will be modified to test the SRVs using an alternative method. Cycling the valves with their actuators attached can cause misalignment of the load bearing parts sufficient to lower the lift setpoint. Valve lift setpoint reliability can be improved by detaching the actuator prior to cycling.

No regulatory commitments are associated with this report.

ADDITIONAL INFORMATION

Component Information:

Component: Main Steam Safety Relief Valve Manufacturer: Crosby Valve and Gage Co.

Model Number: HB-65-BP-DF Size: 6R10

Previous Similar Events

LER 2000-007-00, Docket No. 387/License No. NPF-14, "Multiple Test Failures of Main Steam Safety Relief Valves" LER 2001-005-00, Docket No. 388/License No. NPF-22, "Multiple Test Failures of Main Steam Safety Relief Valves" LER 2009-001-00, Docket No. 388/License No. NPF-22, "Multiple Test Failures of Main Steam Safety Relief Valves" LER 2011-001-00, Docket No. 388/License No. NPF-22, "Multiple Test Failures of Main Steam Safety Relief Valves" LER 2012-005-00, Docket No. 387/License No. NPF-14, "Valve Internal Misalignment Resulting in Multiple Inoperable Main Steam Safety Relief Valves"