ML072710564
| ML072710564 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 10/13/2007 |
| From: | Milano P NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Christian D Dominion Energy Co |
| Milano P, NRR/DORL/LPLIII-1, 415-1457 | |
| References | |
| TAC MD5843 | |
| Download: ML072710564 (5) | |
Text
October 13, 2007 Mr. David A. Christian President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
KEWAUNEE POWER STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REACTOR TRIP PERMISSIVE SETPOINTS (TAC NO. MD5843)
Dear Mr. Christian:
By letter to the Nuclear Regulatory Commission (NRC) dated June 12, 2007, Dominion Energy Kewaunee Inc. submitted a request for an amendment to the Technical Specifications associated with instrument operation conditions for the reactor trip system at Kewaunee Power Station.
The NRC staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific information requested is addressed in the enclosure to this letter.
This request for additional information was discussed with members of your staff, and it was agreed that a response would be provided within 60 days of the date of this letter. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1457.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. David A. Christian President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
KEWAUNEE POWER STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REACTOR TRIP PERMISSIVE SETPOINTS (TAC NO. MD5843)
Dear Mr. Christian:
By letter to the Nuclear Regulatory Commission (NRC) dated June 12, 2007, Dominion Energy Kewaunee Inc. submitted a request for an amendment to the Technical Specifications associated with instrument operation conditions for the reactor trip system at Kewaunee Power Station.
The NRC staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific information requested is addressed in the enclosure to this letter.
This request for additional information was discussed with members of your staff, and it was agreed that a response would be provided within 60 days of the date of this letter. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1457.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDorlLpl3-1 RidsNrrPMPMilano RidsNrrLATHarris RidsNrrDeEicb B. Marcus RidsAcrsAcnwMailCenter RidsOgcRp RidRgn3MailCenter RidsNrrDorlDpr ADAMS Accession Number: ML072710564 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/(A)BC NAME PMilano THarris TTate DATE 10/09/07 10/9/07 10/13/07 OFFICIAL RECORD COPY
Kewaunee Power Station cc:
Resident Inspectors Office U.S. Nuclear Regulatory Commission N490 Hwy 42 Kewaunee, WI 54216-9510 Ms. Leslie N. Hartz Dominion Energy Kewaunee, Inc.
Kewaunee Power Station N 490 Highway 42 Kewaunee, WI 54216 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominion Energy Kewaunee, Inc.
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
120 Tredegar Street Riverside 2 Richmond, VA 23219
REQUEST FOR ADDITIONAL INFORMATION KEWUANEE POWER STATION DOCKET NO. 50-305 By letter dated June 12, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML071700257), Dominion Energy Kewaunee Inc. requested an amendment to the Technical Specifications associated with instrument operation conditions for the reactor trip system at Kewaunee Power Station (KPS). In reviewing the application, the Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:
- 1.
Setpoint Calculation Methodology Provide documentation (such as method type and sample calculations) of the methodology used for establishing the limiting setpoint (or nominal trip setpoint) and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing. Indicate the related Analytical Limits and other limiting design values (and the sources of these values) for each setpoint.
- 2.
Safety Limit (SL)-Related Determination Provide a statement as to whether or not the setpoint is a limiting safety system setting (LSSS) for a variable on which a SL has been placed as discussed in 10 CFR 50.36(c)(1)(ii)(A). Such setpoints are described as SL-Related in the discussions that follow.
In accordance with 10 CFR 50.36(c)(1)(ii)(A), the following guidance is provided for identifying a list of functions to be included in the subset of LSSS specified for variables on which SLs have been placed as defined in Standard Technical Specifications (STS)
Sections 2.1.1, Reactor Core SLs, and 2.1.2, Reactor Coolant System Pressure Boundary SLs. This subset includes automatic protective devices in TSs for specified variables on which SLs have been placed that: (1) initiate a reactor trip; or (2) actuate safety systems. As such, these variables provide protection against violating reactor core SLs or reactor coolant system pressure boundary SLs.
An example of instrument functions that might have an LSSS included in this subset, in accordance with the plant-specific licensing basis, is the pressurizer pressure reactor trip. For each setpoint, or related group of setpoints that you determined not to be SL-Related, explain the basis for this determination.
- 3.
For Setpoints Determined to be SL-Related NRC letter to the Nuclear Energy Institute Setpoint Methodology task Force (SMTF) dated September 7, 2005 (ADAMS No. ML052500004) describes Setpoint-Related TSs (SRTS) that are acceptable to the NRC for instrument settings associated with SL-Related setpoints. Specifically, Part A of the Enclosure to the letter provides ENCLOSURE
limiting condition for operation notes to be added to the TS, and Part B includes a check list of the information to be provided in the TS Bases related to the proposed TS changes.
- a.
Describe whether and how you plan to implement the SRTS suggested in the September 7, 2005, letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c, below.
- b.
As-Found Setpoint Evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system. Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be inoperable or operable but degraded. If the criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g., plant test procedure) explain how the requirements of 10 CFR 50.36 are met.
- c.
As-Left Setpoint Control: Describe the controls employed to ensure that the instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g., plant test procedure) explain how the requirements of 10 CFR 50.36 are met.
- 4.
For Setpoints that are not determined to be SL-Related:
Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the As-Left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. Also, discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be inoperable or operable but degraded. If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it is ensured that the controls will be implemented.