ML090430255
| ML090430255 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/12/2009 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Polson K Nine Mile Point |
| Guzman R, NRR/DORL, 415-1030 | |
| References | |
| TAC MD9539 | |
| Download: ML090430255 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Fehmary 12, 2.('(R Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.1 - CORRECTION TO SAFETY EVALUATION SUPPORTING AMENDMENT NO. 200 RE: REVISION OF CONTROL ROD NOTCH SURVEILLANCE TEST FREQUENCY USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MD9539)
Dear Mr. Polson:
On February 11, 2009, the Nuclear Regulatory Commission (NRC) issued Amendment No. 200 to Renewed Facility Operating License No. DPR-63 for the Nine Mile Point Nuclear Station, Unit NO.1 (NMP1). This amendment changed the NMP1 TSs by revising TS Section 3/4.1.1, "Control Rod System," to increase the Surveillance Requirement frequency associated with control rod exercising.
Subsequent to the issuance, Mr. John Dosa of your staff pointed out that page 5 of the safety evaluation (SE) was not included in the issued license amendment. Enclosed please find page 5 of the SE.
The NRC regrets any inconvenience that this error may have caused. If there are any questions regarding this matter, please contact me at 301-415-1030.
Sincerely, ef2U-#r-Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
As stated cc w/encl: Distribution via Listserv
- 5 The BWR scram system has extremely high reliability. In addition to notch testing, scram time testing can identify failure of individual CRD operation resulting from IGSCC-initiated cracks and mechanical binding. Unlike the CRD notch tests, these single rod scram tests cover the other mechanical components such as scram pilot solenoid operated valves, the scram inlet and outlet air operated valves, and the scram accumulator, as well as operation of the control rods. Thus, the primary assurance of scram system reliability is provided by the scram time testing since it monitors the system scram operation and the complete travel of the control rod.
HCUs, CRD drives, and control rods are tested during refueling outages, approximately every 18-24 months. Based on the data collected during the preceding cycle of operation, selected CRDs, are inspected and, as required, their internal components are replaced. Therefore, increasing the CRD notch testing frequency to monthly would have very minimal impact on the reliability of the scram system.
3.0.1 NRC Staff Evaluation - Applicability of TSTF-475 to NMP1 NMP1 is a custom TSs plant. Therefore, the applicable TS and associated Bases sections are not identical in format to NUREG-1433. The result is that NMP1's application of TSTF-475, Revision 1 differs in format and structure from the model; however, these changes do not alter the technical intent of the changes proposed for control rod operability surveillance frequency requirements for SR 4.1.1a.(2).
The licensee stated in their application that they have reviewed the basis for the NRC staff's acceptance of TSTF-475, Revision 1, and concluded that the basis is applicable to NMP1, and supports their adoption of the TSTF-475 changes into its TSs. The NRC staff also reviewed the basis of TSTF-475, Revision 1, as applied to NMP1, and similarly concluded that the basis for the TSTF is applicable to the NMP1 operating license, and therefore, the TSTF is appropriate for adoption by the licensee. In addition, the NRC staff reviewed the licensee's proposed changes against the corresponding changes made to the STS by TSTF-475, Revision 1, which the staff has found to satisfy applicable regulatory requirements, as described above.
The proposed amendment would revise the TS SR frequency in SR 4.1.1a.(2), "Control Rod System" to require exercising each withdrawn control rod every 31 days after the control rod has been withdrawn at least one notch and the power level is greater than the low power setpoint of the RWM. As contained in TSTF-475, the revised notch testing frequency is specific to fuily withdrawn control rods, since partially withdrawn control rods already have a 31-day test frequency per the STS. Currently, NMP1 custom TS SR 4.1.1a.(2) requires partially withdrawn control rods to be exercised at least once each week. The proposed NMP1 amendment changes include "withdrawn control rods" (inclusive of fully and partially withdrawn rods).
Per this license amendment, the licensee commits to the following:
Regulatory Commitment: Nine Mile Point Nuclear Station will establish the Technlcal Specifications Bases for TS 3/4.1.1 consistent with those shown in TSTF-475,
February 12, 2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.1 - CORRECTION TO SAFETY EVALUATION SUPPORTING AMENDMENT NO. 200 RE: REVISION OF CONTROL ROD NOTCH SURVEILLANCE TEST FREQUENCY USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MD9539)
Dear Mr. Polson:
On February 11, 2009, the Nuclear Regulatory Commission (NRC) issued Amendment No. 200 to Renewed Facility Operating License No. DPR-63 for the Nine Mile Point Nuclear Station, Unit NO.1 (NMP1). This amendment changed the NMP1 TSs by revising TS Section 3/4.1.1, "Control Rod System," to increase the Surveillance Requirement frequency associated with control rod exercising.
Subsequent to the issuance, Mr. John Dosa of your staff pointed out that page 5 of the safety evaluation (SE) was not included in the issued license amendment. Enclosed please find page 5 of the SE.
The NRC regrets any inconvenience that this error may have caused. If there are any questions regarding this matter, please contact me at 301-415-1030.
Sincerely, IRA!
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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