ML110320611: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[2CAN011109, Response to Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years]]
| number = ML110320611
| issue date = 01/31/2011
| title = Response to Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years
| author name = Schwarz C J
| author affiliation = Entergy Operations, Inc
| addressee name =
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000368
| license number = NPF-006
| contact person =
| case reference number = 2CAN011109
| document type = Letter
| page count = 3
| project =
| stage = Request
}}
 
=Text=
{{#Wiki_filter:2CAN011109  
 
January 31, 2011
 
U.S. Nuclear Regulatory Commission
 
Attn: Document Control Desk Washington, DC  20555
 
==SUBJECT:==
Response to the Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years
 
Arkansas Nuclear One, Unit 2
 
Docket No. 50-368 License No. NPF-6
 
==REFERENCES:==
: 1. Entergy letter dated June 17, 2010, "License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years" (2CAN061003)
: 2. Entergy letter dated January 17, 2011, "Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years" (2CAN011102)
: 3. Entergy letter dated June 29, 2000, "Request for Exemption from 10 CFR 50, Appendix J" (2CAN060011)
: 4. NRC letter dated October 12, 2000, "Arkansas Nuclear One Unit 2 One-Time Exemption from the Requirements of 10 CFR Part 50, Appendix J, Option B (TAC MA9350)" (2CNA100002)
: 5. NRC email dated November 18, 2010, "Request for Additional Information (RAI) on License Amendment Request dated June 17, 2010, Technical Specification Change to Extend the Type A Test Frequency to 15 years -
REVISION 1" (TAC No. ME4090)
 
==Dear Sir or Madam:==
 
Entergy Operations, Inc. (Entergy) proposed a change to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TS) via Reference 1. Specifically, the change would allow for the extension of the ten-year frequency of the ANO-2 Type A or Integrated Leak Rate Test (ILRT) required by TS 6.5.16 to 15 years on a permanent basis.
 
Christopher J. Schwarz Vice President - Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR  72802 Tel 479-858-3110 2CAN011109 Page 2 of 3
 
In an email dated January 21, 2011, the NRC noted an apparent contradiction in the containment test pressure quoted in the Reference 1 application for the TS change and the responses to the Request for Additional Information (RAIs) provided in Reference 2.
Reference 1 states the November 30, 2000, test was "performed at the new higher design pressure of 58 psig."  Note 2 of Table 2.2-1 in Reference 2 provided the ILRT test results as "percent of containment air weight per day at Structural Integrity Test pressure (68 psig)."
 
In addition, it was noted that the NRC email referenced in Entergy's letter dated January 17, 2011 (Reference 2 of this submittal) is dated November 23, 2010. The NRC believes it should be an email dated November 18, 2010 (Reference 5 of this submittal). The NRC requested Entergy to review these potential contradictions and submit a supplement correcting these as necessary. This submittal provides the requested supplement.
 
Both of these apparent discrepancies are clarified below.
 
Test Pressure
 
10 CFR 50, Appendix J, Option B, Section III.A, for Type A tests states, "Type A tests to measure the containment system overall integrated leakage rate must be conducted under conditions representing design basis loss-of-coolant accident containment peak pressure."  The original design basis loss-of-coolant accident (LOCA) containment peak pressure for the ANO-2 containment was 54 psig.
 
The steam generators were replaced during the fall of 2000. This replacement required an access opening to be cut in the containment building structure. Upon closure of the containment structure, a Type A test was required (e.g., performed November 30, 2000). This test was performed at a higher pressure to encompass the new LOCA containment peak pressure required by the new steam generators. The new LOCA containment peak pressure was determined to be 58 psig with a design pressure of 59 psig.
 
As a result of this increase, a Structural Integrity Test (SIT) was performed to evaluate the ANO-2 containment structure for the change in design pressure. The purpose of this test was to verify that the containment structure could safely carry design loads and that the structural behavior was similar to that predicted by analysis. The test was performed at 68 psig
 
(1.15 times the revised design pressure).
 
Entergy desired to perform the Type A test concurrently with the SIT, at the SIT test pressure. Entergy submitted an exemption request (Reference 3) to perform the Type A test at this higher pressure. Reference 4 provided the NRC's approval of the one-time exemption to perform the Type A test at 68 psig. The results of this test are noted in Reference 2.
 
Based on the above, the discrepancy was that 58 psig was denoted as the new design pressure for the Type A test when it is actually the new design basis LOCA containment peak pressure at which the Type A test would normally be performed. The last Type A test performed to date was the one on November 30, 2000. It was performed at the SIT pressure of 68 psig.
 
2CAN011109 Page 3 of 3
 
Request for Additional Information
 
Reference 5 provided the original formal request for additional information related to the subject TS change. Based upon a review of the requests, it was believed that one of the requests (RAI 2.1(d)) should have been deleted from the formal RAIs based on previous discussions with the Staff. This was noted in Reference 2. This deletion was confirmed in a separate follow-up email. This follow-up email was the one (dated November 23, 2010) cited in Reference 2, not the original request (dated November 18, 2010), since it provided the clarification. Entergy concurs with the NRC with regard to the correct reference that should have been cited.
 
There are no new commitments in this letter.
 
If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.
 
I declare under penalty of perjury that the foregoing is true and correct. Executed on January 31, 2011.
 
Sincerely, Original signed by Christopher J. Schwarz CJS/rwc
 
cc: Mr. Elmo E. Collins  Regional Administrator  U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX  76011-4125
 
NRC Senior Resident Inspector  Arkansas Nuclear One P. O. Box 310
 
London, AR  72847
 
U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North
 
11555 Rockville Pike
 
Rockville, MD 20852 Mr. Bernard R. Bevill
 
Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 7220}}

Latest revision as of 00:43, 13 April 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML110320611&oldid=1457242"