ML083040278
| ML083040278 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/06/2008 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Polson K Nine Mile Point |
| Guzman R, NRR/DORL, 415-1030 | |
| References | |
| TAC MD9453 | |
| Download: ML083040278 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 6, 2008 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ONE-TIME EXTENSION OF THE PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST INTERVAL (TAC NO.
MD9453)
Dear Mr. Polson:
By letter dated August 15, 2008, Nine Mile Point Nuclear Station, LLC requested an amendment to the Nine Mile Point Nuclear Station, Unit NO.1 (NMP1) Renewed Facility Operating License.
The requested license amendment would revise NMP1 Technical Specification Section 6.5.7, "10 CFR 50 Appendix J Testing Program Plan," to allow a one-time extension of the Integrated Leak Rate Test (ILRT) interval for no more than 5 years. The next ILRT for NMP1 would be performed within 15 years from the last ILRT as opposed to the current 1O-yearinterval.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review.
Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on October 15 and 28, 2008, and it was agreed that your response would be provided within 30 days from the date of this letter.
Sincerely, 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
REQUEST FOR ADDITIONAL INFORMATION (RAI)
NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (NMP1)
ONE-TIME 5-YEAR EXTENSION TO INTEGRATED LEAK RATE TEST (ILRT) INTERVAL The Nuclear Regulatory Commission (NRC) staff has reviewed the Nine Mile Point Nuclear Station (NMPNS) submittal dated August 15, 2008. The NRC staff has determined that additional information requested below will be needed to complete its review.
Containment Integrity RAI-1.
Please discuss and provide the following:
- a.
A summary list of those containment penetrations (including their test schedule intervals) that have not demonstrated acceptable performance history in accordance with the primary containment leakage rate program.
- b.
A summary table for Type B and Type C tests, including the interval schedule dates, that are planned to be performed prior to and during the requested 5-year extension period of the ILRT interval.
- c.
Type B and Type C test results and their comparison with the allowable leakage rate specified in the plant Technical Specifications.
- d.
Testing and schedule of those penetrations with seals and gaskets, and bolted connections that are frequently disassembled or are not routinely disassembled.
RAI-2.
Regulatory Position C.3 of Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," recommends that visual examinations should be conducted prior to initiating a Type A test, and during two other refueling outages before the next Type A test based on a 1O-year ILRT interval. Please describe, with a schedule, how you would supplement this 10-year interval-based visual inspection requirement for the requested 15-year ILRT interval.
RAI-3.
Section 3.1.2.4 of the enclosure to your August 15, 2008, submittal, discusses IWE-1240 augmented inspection of the interior surface of the drywell shell. Please discuss whether there are other areas requiring augmented examination.
RAI-4.
As part of the NMP1 drywell augmented inspection/monitoring program, Section 3.1.2.4 of the enclosure to your submittal describes the volumetric and visual examinations of the drywell shell during the 2003 and 2007 refueling outages. Please provide further discussion relative to the followlnq:
- a.
General description and correlation between the 2003 and 2007 examination results.
- b.
General corrosion condition in the monitored areas.
- c.
Based on the results of 2007 examinations and anticipated corrosion rate, please discuss the schedule for the next ultrasonic testing measurements, root cause determination, and any planned or already implemented corrective actions.
Enclosure
- 2 Probabilistic Risk Assessment (PRA)
RAI-5.
The core damage frequency and total population dose in the ILRT analysis (based on the 2007 PRA) are about a decade lower than in the severe accident mitigation alternative analysis (based on the 2003 PRA). Provide a description of the major changes to PRA models and assumptions that account for these changes. Provide a description of the peer review comments in areas related to these reductions, the resolution of these comments, and the impact of any unresolved comments on the risk results for the requested change.
RAI-6.
Explain how the population dose of 1.05E6 person rem per event was derived for Electric Power Research Institute (EPRI) Class 7 releases (as reported in Tables 10-2 through 10-4 of Attachment 2 to the August 15, 2008, submittal). Table 6-7 indicates that the population dose for EPRI Class 7 would be a combination of releases from collapsed accident progression bins (APBs) 3, 4, and 5. However, the NMPNS adjusted population dose for each of these APBs (last column of Table 6-3) is well below 1E6 person rem per event. It appears that the population dose for EPRI Class 7 was calculated based on the sum of the population dose values for APBs 3, 4, and 5 rather than the frequency-weighted sum. Reconcile the population dose values and update the risk assessment as appropriate.
RAI-7.
The large early release frequency (LERF) is reported to be 3.00E-7 per year for internal events (on page 44 of Attachment 2) and 8.67E-7 per year for external events (on page B-1 of Attachment 2). This results in a total LERF of 1.17E-6 per year.
However, on page B-3, it is stated that the total LERF from all hazards is 1.7E-6 per year. Address this inconsistency, and confirm the correct value for the total LERF for NMP1, with and without the requested change.
RAI-8. Table B-2 provides the external and internal event contributions to EPRI Class 3b frequency based on the results from the 2003 PRA. Explain how the Class 3b frequency value of 2.38E-9 per year for external events (first entry in column 2) was derived.
Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ONE-TIME EXTENSION OF THE PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST INTERVAL (TAC NO.
MD9453)
Dear Mr. Polson:
By letter dated AUgust 15, 2008, Nine Mile Point Nuclear Station, LLC requested an amendment to the Nine Mile Point Nuclear Station, Unit No.1 (NMP1) Renewed Facility Operating License.
The requested license amendment would revise NMP1 Technical Specification Section 6.5.7, "10 CFR 50 Appendix J Testing Program Plan," to allow a one-time extension of the Integrated Leak Rate Test (ILRT) interval for no more than 5 years. The next ILRT for NMP1 would be performed within 15 years from the last ILRT as opposed to the current 1O-year interval.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review.
Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on October 15 and 28, 2008, and it was agreed that your response would be provided within 30 days from the date of this letter.
Sincerely,
/RA/
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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