ML042260374
| ML042260374 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/13/2004 |
| From: | Michelle Honcharik NRC/NRR/DLPM/LPD4 |
| To: | Edington R Nebraska Public Power District (NPPD) |
| Honcharik M, NRR/DLPM, 301-415-1774 | |
| References | |
| TAC MC3320 | |
| Download: ML042260374 (5) | |
Text
August 13, 2004 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: CONTAINMENT ISOLATION LOGIC CHANGE FOR REACTOR VESSEL WATER LEVEL (TAC NO. MC3320)
Dear Mr. Edington:
By letter dated May 27, 2004, Nebraska Public Power District (the licensee) requested the Nuclear Regulatory Commission (NRC) staff approve an amendment to revise the CNS Technical Specifications. The proposed amendment would lower the reactor vessel water level at which the reactor water cleanup system isolates, secondary containment isolates, and the control room emergency filter system starts, as recommended in General Electric Service Information Letter No. 131.
The NRC staff has reviewed the information provided in the submittal and determined that additional information is required in order to complete the review of the changes. As agreed upon in telephone call on August 11, 2004, with Ed McCutchen, the licensee will respond to the request for additional information (RAI) within 45 days. The RAI is enclosed.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
RAI cc w/encl: See next page
August 13, 2004 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: CONTAINMENT ISOLATION LOGIC CHANGE FOR REACTOR VESSEL WATER LEVEL (TAC NO. MC3320)
Dear Mr. Edington:
By letter dated May 27, 2004, Nebraska Public Power District (the licensee) requested the Nuclear Regulatory Commission (NRC) staff approve an amendment to revise the CNS Technical Specifications. The proposed amendment would lower the reactor vessel water level at which the reactor water cleanup system isolates, secondary containment isolates, and the control room emergency filter system starts, as recommended in General Electric Service Information Letter No. 131.
The NRC staff has reviewed the information provided in the submittal and determined that additional information is required in order to complete the review of the changes. As agreed upon in telephone call on August 11, 2004, with Ed McCutchen, the licensee will respond to the request for additional information (RAI) within 45 days. The RAI is enclosed.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
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RidsNrrDssaDpr RidsNrrDeDpr Hulbert Li Shanlai Lu Steve LaVie ACCESSION NO: ML042260374
- See Tad Marsh 7/1/04 deferral memo
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ISSUES RELATED CONTAINMENT ISOLATION LOGIC CHANGE FOR REACTOR VESSEL WATER LEVEL COOPER NUCLEAR STATION DOCKET NO. 50-298 1.
Discuss the instrument setpoint methodology used to calculate the reactor vessel water level allowable values.
2.
The licensee stated in the May 27, 2004, submittal that reactor vessel water level is one of the input parameters to the isolation logic. The NRC staff is concerned that the proposed change from Level 3 to Level 2 would delay the protective action of the primary containment isolation, the secondary containment isolation, and the control room emergency filter system initiation. Verify that these changes will not affect the safety analyses assumptions with respect to the response time requirements by the protective actions.
3.
In the General Electric Service Information Letter No. 131, Containment Isolation Logic Change, dated March 31, 1975, it was recommended to add an reactor water clean up (RWCU) break detection system for automatic isolation on a cleanup system line break if the RWCU system isolation logic is changed to initiate at reactor vessel water Level 2.
The purpose of the detection system is to meet the criteria for minimizing the radiological consequences of a pipe break outside the primary containment. In order to meet this requirement, The licensee stated in its submittal that CNS has a functional RWCU leak/break detection system. The system provides for automatic isolation upon detection of either high flow in the RWCU system or high temperature in the vicinity of high temperature RWCU piping. The high RWCU flow signals are initiated from differential pressure (DP) switches that are connected to an elbow flow tap on the inlet pump suction line of the RWCU System. Explain the system response to a RWCU line break located between the RWCU outbound isolation valve and the elbow flow tap.
Also, please indicate the number of temperature elements in the area (i.e. in the RWCU heat exchanger room) and explain the logic that would initiate the protective response.
4.
For a spectrum of breaks inside containment, will the set point switch from Level 3 to Level 2 cause the delay to the secondary containment isolation? If it does, what is the impact on the dose calculation?
5.
Has the existing RWCU break detection system been graded as a safety system so that rigorous equipment qualification program is used to maintain the system?
Cooper Nuclear Station cc:
Mr. William J. Fehrman President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. Clay C. Warren Vice President of Strategic Programs Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. John R. McPhail, General Counsel Nebraska Public Power District P. O. Box 499 Columbus, NE 68602-0499 Mr. Paul V. Fleming Licensing Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P. O. Box 98922 Lincoln, NE 68509-8922 Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305 Ms. Cheryl K. Rogers, Program Manager Nebraska Health & Human Services System Division of Public Health Assurance Consumer Services Section 301 Centennial Mall, South P. O. Box 95007 Lincoln, NE 68509-5007 Mr. Ronald A. Kucera, Director of Intergovernmental Cooperation Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 218 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Jerry Uhlmann, Director State Emergency Management Agency P. O. Box 116 Jefferson City, MO 65101 Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson Suite 310 Topeka, KS 66612-1366 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street Suite D Des Moines, IA 50309 Mr. Scott Clardy, Director Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570 June 2004 Jerry C. Roberts, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321