Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift
Person / Time
ML13323A521
Site:	Pilgrim
Issue date:	11/12/2013
From:	Jeffery Lynch Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 13-002-00
Download: ML13323A521 (2)
v • d • e

LER-2013-002, Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift

Event date:
Report date:
2932013002R00 - NRC Website
v • d • e

text

Entergy Nuclear Operations, Inc.

600 Rocky Hill Road Plymouth, MA 02360 Pilgrim Nuclear Power Station November 12, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35 Revised Submittal Schedule for Supplement to the LER 2013-002-00, SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift

REFERENCE:

1. LER 2013-002-00, "SRV-3B Safety Relief valve Declared Inoperable Due to Leakage and Setpoint Drift", dated March 31, 2013

10 CFR Part 21 Report, "Notification of a Defect, Bellows Failure",

Curtis Wright Flow Control Company (Target Rock) Letter NID #

13307, dated June 17, 2013 LETTER NUMBER: 2.13.089

Dear Sir or Madam:

Licensee Event Report (LER).2013-002-00, "SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift" was submitted on March 31, 2013 (Reference 1), with a target schedule of September 30, 2013 to submit a Supplement to the LER, after completing the root cause analysis.

Since then the vendor (Target Rock) has issued a 10 CFR Part 21 Notification, (Reference 2) confirming defects in safety relief valve bellows. Entergy is incorporating the information related to the reported defect into the root cause analysis. Due to the recent refueling outage, emergent plant events, and vendor 10 CFR, Part 21 Notification, Pilgrim resources were diverted to address the emergent work activities. As such, the review and approval of the SRV-3B root cause incorporating the vendor Part 21 Notification and the lessons learned from the events is taking longer time than expected. Accordingly, the LER Supplement is expected to be submitted by February 14, 2014.

The revised submittal schedule was discussed with the NRC/NRR Project Manager.

This letter contains no commitments.

PNPS Letter 2.13.089 Page 2 of 2 Please do not hesitate to contact me at (508) 830-8403, if there are any questions.

Sincerely, Joseph R. Lynch, Manager, Pilgrim Licensing cc:

Mr. William M. Dean Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 INPO Records 700 Galleria Parkway Atlanta, GA 30399-5957 Ms. Nadiyah Morgan, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North Mail Stop O-8-C2A 11555 Rockville Pike Rockville, MD. 20852-2738 USNRC Senior Resident Inspector Pilgrim Nuclear Power Station

Licensee Event Report

Pilgrim

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		Reporting criterion
05000293/LER-2013-001, Inadvertent Trip of Both Recirculation Pumps and Subsequent Manual Scram	Inadvertent Trip of Both Recirculation Pumps and Subsequent Manual Scram	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-002, Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift	Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift
05000293/LER-2013-003, Regarding Loss of Off-Site Power Events Due to Winter Storm Nemo	Regarding Loss of Off-Site Power Events Due to Winter Storm Nemo	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-004, Regarding Manual Scram Inserted During Reactor Shutdown	Regarding Manual Scram Inserted During Reactor Shutdown	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-006, And LER 13-006-00 for Pilgrim Regarding Primary Containment Declared Inoperable During HPCI Testing & HPCI Controller Failure to Achieve Rated Flow While in Auto Mode	And LER 13-006-00 for Pilgrim Regarding Primary Containment Declared Inoperable During HPCI Testing & HPCI Controller Failure to Achieve Rated Flow While in Auto Mode	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-007, Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable	Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-008, Manual Scram - Reactor Feed Pump Trip	Manual Scram - Reactor Feed Pump Trip	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-009, Regarding Loss of Offsite Power and Reactor Scram	Regarding Loss of Offsite Power and Reactor Scram	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000293/LER-2013-010, Regarding Automatic Group I Primary Containment Isolation Actuation During Plant Startup Due to Reactor High Water Level	Regarding Automatic Group I Primary Containment Isolation Actuation During Plant Startup Due to Reactor High Water Level	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000293/LER-2013-002, Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift

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05000293/LER-2013-002, Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift

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