ML060670463

Request for Additional Information Revision of Appendix B, Environmental Technical Specifications

ML060670463
Person / Time
Site:	Oyster Creek
Issue date:	03/09/2006
From:	Geoffrey Miller Plant Licensing Branch III-2
To:	Crane C AmerGen Energy Co
Miller G, NRR/DLPM, 415-2481
References
TAC MC6046
Download: ML060670463 (4)

Text

March 9, 2006 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RE: REVISION OF APPENDIX B, ENVIRONMENTAL TECHNICAL SPECIFICATIONS (TAC NO. MC6046)

Dear Mr. Crane:

By letter dated February 2, 2005, AmerGen Energy Company, LLC (AmerGen) submitted a license amendment request (LAR) for the Oyster Creek Nuclear Generating Station (Oyster Creek). The LAR requested to revise the Oyster Creek Technical Specifications to incorporate the isolation trip setting and the instrumentation surveillance requirements of the reactor water cleanup high energy line break detection and isolation equipment.

The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. These questions were discussed with Mr. David Robillard of your staff on February 9, 2006. A response to this request for additional information is requested to be provided within 30 days. If you need additional time to respond to these questions, please let me know.

Sincerely,

/RA/

G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosure:

Request for Additional Information cc w/encl: See next page

March 9, 2006 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 By letter dated February 2, 2005, AmerGen Energy Company, LLC (AmerGen) submitted a license amendment request (LAR) for the Oyster Creek Nuclear Generating Station (Oyster Creek). The LAR requested to revise the Oyster Creek Technical Specifications to incorporate the isolation trip setting and the instrumentation surveillance requirements of the reactor water cleanup high energy line break detection and isolation equipment.

The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. These questions were discussed with Mr. David Robillard of your staff on February 9, 2006. A response to this request for additional information is requested to be provided within 30 days. If you need additional time to respond to these questions, please let me know.

Sincerely,

/RA/

G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosure:

Request for Additional Information cc w/encl: See next page DISTRIBUTION:

PUBLIC RidsNrrDorlLplb RidsNrrPMGMiller RidsOgcMailCenter LPL1-2 R/F RidsNrrLACRaynor RidsAcrsAcnwMailCenter RYoung RidsNrrDssSbpb SMazumdar Accession Number: ML060670463 OFFICE NRR/LPL1-2/PM NRR/LPL1-2/LA NRR/DSS/SBPB/BC NRR/LPL1-2/BC NAME GEMiller CRaynor DSolorio DRoberts DATE 3/09/06 3/09/06 3/7/06 3/09/06 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 (TAC NO. MC6046)

By letter dated February 2, 2005, AmerGen Energy Company, LLC (AmerGen) submitted a license amendment request for a change to the Oyster Creek Nuclear Generating Station (Oyster Creek), Technical Specifications (TSs), requesting to incorporate the isolation trip setting and the instrumentation surveillance requirements of the reactor water cleanup (RWCU) system high energy line break (HELB) detection and isolation equipment to the TSs. The Nuclear Regulatory Commission staff requests the following additional information to complete its review:

1. Describe the HELB analysis utilized in postulating an RWCU system HELB downstream of the system isolation valves (e.g., computer codes used, location of the postulated break, reactor coolant mass and energy discharge, predicted temperature response, etc.).

2. Section 5 of Enclosure 1 to your submittal states the following:

This safety grade break detection/isolation equipment monitors RWCU pump room temperature and initiates a[n] RWCU system isolation when ambient temperature exceeds a preset limit, below the process safety limit of 180 EF. The system is designed to detect a line failure as small as a one-inch diameter pipe and as large as a full guillotine rupture of the largest system pipe (six-inch diameter). The small line break is the most difficult to detect, and such, is used to establish the location and actuation limit of the temperature monitor.

Define the terms preset limit, process safety limit, and temperature monitor actuation limit. Explain the HELB analysis utilized to determine the preset limit and how this limit relates to the process safety limit (180 EF) and the temperature monitor actuation limit.

Address the radiological impact of an RWCU system HELB for a small pipe. In particular, consider a pipe break where the release of reactor coolant mass is very small in magnitude over a prolonged period of time (e.g., slow leak), making detection and timely closure of the RWCU isolation valves even more difficult.

3. Section 5 of Enclosure 1 to the submittal states the following:

Calculation C-1302-215-E610-060...determined that a detector located at the RWCU pump room exit will detect the failure of an instrument tube size break in one minute. This calculation established an actuation setpoint of 180 EF for the RWCU HELB detectors to be consistent with the Emergency Operating Precedures (EOPs) at the time of the modification... This is a conservative value that considers the maximum allowable environmental temperature for equipment and instrumentation Enclosure

installed in the affected area, systems operational values, and system interactions.

Summarize how the actuation setpoint of 180 EF is a conservative value when compared to the maximum allowable environmental temperature for equipment and instrumentation installed in the affected area, systems operational values, and system interactions. State how use of the 180 EF setpoint facilitates effective and timely detection and isolation of the RWCU system HELB described above (e.g., setpoint is high enough to prevent system isolation due to spurious actuation). Compare the predicted maximum temperature for the RWCU pump room with bounding temperature profiles used for equipment qualification. Consider the HELB results compared to the profiles of other equipment qualification parameters (e.g., steam, pressure, radiation).

Provide Calculation C-1302-215-E610-060, which supports the safety evaluation for the modification.

4. Section 5.4.8.2 of the final safety analysis report states that for the RWCU system, the supply line has a motor operated isolation valve inside the drywell and two parallel motor operated isolation valves outside the drywell, and the return line has one motor operated isolation valve outside the drywell. Section 5.4.8.2 refers to Table 6.2-12, Containment Isolation Valves/Mechanical Integrity, for isolation signals for each valve, however; Table 6.2-12, which lists the four RWCU system isolation valves (V-16-061, V-16-001, V-16-014, and V-16-002) does not show valve V-16-061 receiving a signal to isolate on RWCU HELB. Please explain this apparent discrepancy.

Oyster Creek Nuclear Generating Station Site Vice President - Oyster Creek Director - Licensing and Regulatory Affairs Nuclear Generating Station AmerGen Energy Company, LLC AmerGen Energy Company, LLC Correspondence Control P.O. Box 388 P.O. Box 160 Forked River, NJ 08731 Kennett Square, PA 19348 Senior Vice President of Manager Licensing - Oyster Creek Operations Exelon Generation Company, LLC AmerGen Energy Company, LLC Correspondence Control 200 Exelon Way, KSA 3-N P.O. Box 160 Kennett Square, PA 19348 Kennett Square, PA 19348 Kathryn M. Sutton, Esquire Regulatory Assurance Manager Morgan, Lewis, & Bockius LLP Oyster Creek 1111 Pennsylvania Avenue, NW AmerGen Energy Company, LLC Washington, DC 20004 P.O. Box 388 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of Assistant General Counsel Environmental Protection AmerGen Energy Company, LLC Bureau of Nuclear Engineering 200 Exelon Way CN 415 Kennett Square, PA 19348 Trenton, NJ 08625 Ron Bellamy, Region I Vice President - Licensing and U.S. Nuclear Regulatory Commission Regulatory Affairs 475 Allendale Road AmerGen Energy Company, LLC King of Prussia, PA 19406-1415 4300 Winfield Road Warrenville, IL 60555 Correspondence Control Desk AmerGen Energy Company, LLC Regional Administrator, Region I 200 Exelon Way, KSA 1--1 U.S. Nuclear Regulatory Commission Kennett Square, PA 19348 475 Allendale Road King of Prussia, PA 19406-1415 Oyster Creek Nuclear Generating Station Plant Manager Mayor of Lacey Township AmerGen Energy Company, LLC 818 West Lacey Road P.O. Box 388 Forked River, NJ 08731 Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731