ML082200279
| ML082200279 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/04/2008 |
| From: | Cowan P Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MD8296, TAC MD8297, TAC MD8308, TAC MD8309 | |
| Download: ML082200279 (7) | |
Text
Exelen.
Exelon Nuclear www.exeloncorp.com 200 Exelon Way Nuclear Kennett Square, PA 19348 10 CFR 50.55a August 4, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Relief Requests Associated with the Third and Fourth Inservice Inspection (ISI) Intervals and the First and Second Containment Inservice Inspection (CISI) Intervals - Response to Request for Additional Information Concerning Relief Request CRR-13
References:
- 1) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Submittal of Relief Requests Associated with the Third and Fourth Inservice Inspection (ISI) Intervals and the First and Second Containment Inservice Inspection (CISI) Intervals," dated February 29, 2008
- 2) Letter from J. D. Hughey (U. S. Nuclear Regulatory Commission) to C. G.
Pardee (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Supplemental Information Regarding Relief Request 14R-44 (TAC NOS. MD8296 and MD8297)," dated May 7, 2008
- 3) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Supplemental Information Associated with Relief Request 14R-44," dated May 13, 2008
- 4) Letter from J. D. Hughey (U. S. Nuclear Regulatory Commission) to C. G.
Pardee (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3: Request for Additional Information Regarding Relief Request CRR-1 3 Associated with the First and Second Containment Inservice Inspection Intervals (TAC NOS. MD8308 and MD8309)," dated July 9, 2008
Relief Requests Associated with Third and Fourth ISI Intervals and First and Second CISI Intervals August 4, 2008 Page 2 In the Reference 1 letter, Exelon Generation Company, LLC (EGC) submitted for your review and approval relief requests associated with the third and fourth Inservice Inspection (ISI) intervals for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. Also included for your review and approval were relief requests associated with the first and second Containment Inservice Inspection (CISI) intervals for PBAPS, Units 2 and 3.
References 2 and 3 concern previous requests for information associated with these relief requests.
In the Reference 4 letter, the U. S. Nuclear Regulatory Commission Staff requested additional information. Attached is our response to this request.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Respectfully, Pamela B. Cowan Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments:
- 1) Response to Request for Additional Information - Relief Request CRR-1 3
- 2) Drawing 6280-S-188 cc:
S. J. Collins, Regional Administrator, Region I, USNRC F. Bower, USNRC Senior Resident Inspector, PBAPS J. Hughey, Project Manager, USNRC S. T. Gray, State of Maryland R. R. Janati, Commonwealth of Pennsylvania Response to Request for Additional Information - Relief Request CRR-13
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST CRR-13 ASSOCIATED WITH THE FIRST AND SECOND CONTAINMENT INSERVICE INSPECTION INTERVALS PEACH BOTTOM ATOMIC POWER STATION. UNITS 2 AND 3 Question 1:
By letter dated February 29, 2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080640587), Exelon Generation Company, LLC, submitted Relief Request CRR-13 associated with the first and second Containment Inservice Inspection intervals for Peach Bottom Atomic Power Station, Units 2 and 3. The Nuclear Regulatory Commission (NRC) staff has reviewed the request for relief the licensee provided in the February 29, 2008, submittal. In order for the NRC staff to complete its evaluation, response to the following request for additional information (RAI) questions is requested.
RAI-1) To facilitate the NRC staff's understanding of the as-constructed configuration of the drywell with the embedded construction manway N-3, please provide a detail drawing of a vertical section of the drywell passing through the location of the N-3 manway.
Please provide a detail that shows the as-constructed structural configuration of the drywell including its concrete components (i.e., concrete floor, concrete foundation and concrete wall with important dimensions and elevations).
Response
Drawing 6280-S-188 is contained in Attachment 2. This drawing represents the as-constructed structural configuration of the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 drywells, including their concrete components.
Question 2:
RAI-2) Please confirm if the seal weld for the manway penetration was radiographed and tested for leak-tightness (indicate method used) prior to being covered with concrete.
Response
Relief Request CRR-13 is based on the drawings and the Specification for Reactor Drywell and Suppression Chamber Containment Vessels. Note 1 on drawing S-188 states that a pneumatic test was performed prior to the concrete pours and the weld was seal welded. A search of construction records could not confirm that radiograph was performed on the seal weld for the manway path.
On December 24, 1968, an initial overload and leak rate test was completed satisfactorily on the Unit 2 Containment Vessel. The highest pressure recorded was 71.3 psig and the leakage was determined to be.0072% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowable leakage rate per Bechtel Specification 6280-C-2, paragraph 8.2.4.3, is 0.2% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. As indicated in Specification 6280-C-2, the test was to be performed prior to the concrete pour.
Response To Request For Additional Information Regarding Relief Request CRR-13 Associated With The First And Second Containment Inservice Inspection Intervals Peach Bottom Atomic Power Station, Units 2 And 3 Page 2 of 2 On May 23, 1970, an initial leakage rate test was completed satisfactorily on the Unit 3 Containment Vessel. The highest pressure recorded was 74.3 psig and the leakage was determined to be 0.078% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowable leakage rate per Bechtel Specification 6280-C-2, paragraph 8.2.4.3, is 0.2% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. As also indicated in Specification 6280-C-2, the test was to be performed prior to the concrete pour.
Question 3:
RAI-3) Since the proposed alternative in Section 6 is the Appendix J Integrated Leak Rate Testing, please provide the results, with dates and acceptance criteria, of the most recent two Type A tests performed on the Primary Containment at Peach Bottom Atomic Power Station, Unit 2 and Unit 3.
Response
The results from the last two (2) Integrated Leak Rate Tests (ILRTs) at PBAPS, Units 2 and 3 are as follows:
PBAPS, Unit 2:
ILRT Total ILRT Date Calculation Method Weight Percent Per Day
(%/day)
March 1991 Total Time Analysis based on 0.2135 BN-TOP-1, Rev. 1, 1972 October 2000 Absolute Method Mass Point 0.3365 per 56.8-1994 PBAPS, Unit 3:
______________I LRT Total ILRT Date Calculation Method Weight Percent Per Day
(%/day)
December 1991 Absolute Method Mass Point 0.1386 per 56.8-1987 October 2005 Total Time Analysis based on 0.2781 BN-TOP-1, Rev. 1, 1972 Acceptance criteria: 0.375 Weight Percent Per Day (%/day)
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