LR-N04-0472, Letter from PSEG Outlining Actions in Response to the 10/10/2004 SCRAM

Letter from PSEG Outlining Actions in Response to the 10/10/2004 SCRAM

ML042990463
Person / Time
Site:	Hope Creek
Issue date:	10/17/2004
From:	Bakken A Public Service Enterprise Group
To:	Collins S Region 1 Administrator
References
LR-N04-0472
Download: ML042990463 (4)

Text

A. Christopher Bakken, I11 PSEG Nuclear LLC President and Chief Nuclear Officer P.O. Box 236, Hancocks Bridge, NJ 08038-1236 tel: 856.339.1100 fax: 856.339.1104 October 17, 2004 LR-N04-0472 Mr. Samuel J. Collins, Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 PSEG ACTIONS IN RESPONSE TO OCTOBER I O , 2004 SCRAM HOPE CREEK GENERATING STATION DOCKET NO. 50-354

Dear Mr. Collins,

The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) with an overview of our plans to respond to the Hope Creek steam leak of October I O , 2004.

As the NRC staff is aware, on October I O , 2004, Public Service Enterprise Group (PSEG) Nuclear personnel manually shutdown the Hope Creek Generating Station reactor in response to a steam leak in the turbine building. The steam leak was due to a failed eight (8) inch discharge line from the A Moisture Separator to the Main Condenser. Our preliminary investigation of the event has revealed equipment and personnel performance issues. PSEG is appropriately focused on maintaining the plant in a safe condition and continues to aggressively investigate this event. In light of the significance of this event, PSEG Nuclear is providing a summary of the actions planned and underway.

Hope Creek Generating Station is currently in cold shutdown. PSEG Nuclear does not plan to recommence power operation until completion of the Hope Creek refueling outage in December 2004. Prior to startup, we will complete the following actions:

1. Complete a root cause analysis of the event.

2. Address the adequacy of operator response and Technical Specification usage during the event.

3. Address the significant equipment issues surrounding this transient and the associated impact on plant operations.

Mr. Samuel J. Collins 2 LR-N04-0472

4. Complete the extent of condition review and inspections pertaining to the failed line and components.

5. Repair the failed moisture separator discharge line.

6. Complete necessary operations procedure changes and associated training due to issues identified in post trip review. These changes will include augmenting the procedural guidance for reactor level and pressure control.

7. Review our Operational Challenge Response (OCR) process for improvements.

PSEG Nuclear will keep the NRC staff informed about progress on these actions.

Should questions arise regarding this plan of action, please contact Ms. Christina Perino, Director, Licensing and Nuclear Safety, at (856) 339-1989.

Sincerely, n A. Christopher Bakken, Ill President & Chief Nuclear Officer Attachment

Mr. S. Collins 3 LR-N04-0472 C United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Mr. Daniel Collins, Salem & Hope Creek Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08C2 Washington, DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)

USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. 0. Box 415 Trenton, NJ 08625

COMMITMENTS The following table identifies those actions committed to by Public Service Enterprise Group (PSEG) Nuclear in this document. Any other actions discussed in this submittal represent intended or planned actions by PSEG. They are described to the Nuclear Regulatory Commission (NRC) for the NRCs information and are not regulatory commitments.

Commitment Condition PSEG Nuclear does not plan to recommence power operation until Mode 2 completion of the Hope Creek refueling outage in December 2004.

Prior to startup, we will complete the following actions:

1. Complete a root cause analysis of the event.

2. Address the adequacy of operator response and Technical Specification usage during the event.

3. Address the significant equipment issues surrounding this transient and the associated impact on plant operations.

4. Complete the extent of condition review and inspections pertaining to the failed line and components.

5. Repair the failed moisture separator discharge line.

6. Complete necessary operations procedure changes and associated training due to issues identified in post trip review. These changes will include augmenting the procedural guidance for reactor level and pressure control.

7. Review our Operational Challenge Response (OCR) process for improvements.