ML091810709
| ML091810709 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/01/2009 |
| From: | Lyon C Plant Licensing Branch IV |
| To: | Entergy Operations |
| Lyon C Fred, NRR/DORL/LPL4, 301-415-2296 | |
| References | |
| TAC ME1376, TAC ME1377, TAC ME1378, TAC ME1379, TAC ME1380, TAC ME1381, TAC ME1382, TAC ME1383 | |
| Download: ML091810709 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 1, 2009 Vice President, Operations Entergy Operations, Inc.
Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUESTS GG-ISI-005 THROUGH GG-1SI-012 (TAC NOS. ME1376-ME1383)
Dear Sir or Madam:
By application dated May 29, 2009,Entergy Operations, Inc. (Entergy, the licensee), submitted requests for relief GG-ISI-005 through GG-ISI-012 from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for the second 10-year inservice inspection interval at Grand Gulf Nuclear Station, Unit 1 (GGNS). The relief requests are based on limitations that preclude full code examination coverage for ASME Code welds and components.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submittal and determined that additional information is required in order to complete its review. These questions were provided to Mr. M. Larson of your staff on June 30, 2009.
Please provide a response to the enclosed questions by August 6, 2009.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov.
Sincerely, Carl. F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416 By application dated May 29, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091490755), Entergy Operations, Inc. (Entergy, the licensee),
submitted requests for relief GG-ISI-005 throllgh GG-ISI-012 from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI, for the second 1O-year inservice inspection interval at Grand Gulf Nuclear Station, Unit 1 (GGNS). The relief requests are based on limitations that preclude full code examination coverage for ASME Code welds and components.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(5)(iii), the licensee submitted the subject requests for relief for limited examinations in multiple ASME Code Examination Categories. The ASME Code requires that 100 percent of the examination volumes, or surface areas, described in ASME Code,Section XI, Tables IWB-2500 and IWC-2500 be performed during each interval. The licensee stated that 100 percent of the ASME Code-required volumes, or surface areas, are impractical to obtain at GGNS.
Paragraph 50.55a(g)(5)(iii) of 10 CFR states that when licensees determine that conformance with ASME Code requirements are impractical at their facility, they shall submit information to support this determination. The Nuclear Regulatory Commission (NRC) will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to public safety and the burden imposed on the licensee. Based on the NRC staff's review, it determined that additional information was required in order to complete its evaluation of the relief requests.
In most cases, the licensee provided only general information regarding the impracticality of obtaining ASME Code-required volumetric examination, as applicable. Statements such as "scanning obstructions and geometric surface conditions," "design configurations," "nozzle-to head configuration," and "due to transition of the nozzle adjacent to the weld toe," are inadequate to explain the bases for not obtaining the ASME Code-required examination volumes. No sketches with dimensional information showing the causes of limited accessibility were provided in the submittal.
As requested below, please provide detailed and specific information to support the bases for limited examination in all requests for relief and, therefore, demonstrate impracticality.
a)
Include descriptions (written and/or sketches, as necessary) of the interferences to applied nondestructive examination (NDE) techniques.
b)
As applicable, describe NDE equipment (ultrasonic scanning apparatus) and details of the listed obstructions (size, shape, proximity to the weld, etc.) to Enclosure
- 2 demonstrate accessibility limitations, and discuss whether alternative methods or advanced technologies could be employed to maximize ASME Code coverage.
c)
Fully clarify the wave modality and insonification angles used for all ultrasonic examinations.
d)
Show cross-sectional coverage plots to describe ASME Code volumes examined.
e)
If surface examination is required by the ASME Code in addition to the vOlumetric examination, state whether surface examinations were performed on any of the subject components and state examination coverage that was obtained..
f)
If not included, state whether any indications were discovered as a result of Code-required examinations, and how these indications have been dispositioned.
July 1,2009 Vice President, Operations Entergy Operations, Inc.
Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUESTS GG-ISI-005 THROUGH GG-1SI-012 (TAC NOS. ME1376-IVIE1383)
Dear Sir or Madam:
By application dated May 29, 2009, Entergy Operations, Inc. (Entergy, the licensee), submitted requests for relief GG-ISI-005 through GG-ISI-012 from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for the second 1O-year inservice inspection interval at Grand Gulf Nuclear Station, Unit 1 (GGNS). The relief requests are based on limitations that preclude full code examination coverqge for ASME Code welds and components.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submittal and determined that additional information is required in order to complete its review. These questions were provided to Mr. M. Larson of your staff on June 30, 2009.
Please provide a response to the enclosed questions by August 6, 2009.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov.
Sincerely,
/RN Carl. F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDciCvib Resource RidsOgcRp Resource LPLIV r/f RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLAJBurKhardt Resource TMcLellan, NRR/DCI/CVIB RidsNrrDciCpnb Resource RidsNrrPMGrandGulf Resource CNove, NRR/DCI/CPNB ADAMS Accession No' ML091810709
- memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CVIB/BC NRR/LPL4/BC NRR/LPL4/PM NAME FLyon JBurkhardt MMitchell*
MMarkley FLyon DATE 7/1/09 7/1/09 6/26/09 7/1109 7/1/09 OFFICIAL AGENCY RECORD