ML052850011
| ML052850011 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/11/2005 |
| From: | Lesser M Division of Reactor Safety II |
| To: | Stinson L Southern Nuclear Operating Co |
| References | |
| Download: ML052850011 (7) | |
Text
October 11, 2005 Southern Nuclear Operating Company, Inc.
ATTN: Mr. L. M. Stinson Vice President P. O. Box 1295 Birmingham, AL 35201
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Stinson:
On October 24, 2005, the NRC will begin the baseline inservice inspection (NRC Inspection Procedure 71111.08), for NRC Bulletin 2004-001 (NRC Temporary Instruction 2515/160), and reactor head replacement inspection (NRC Inspection Procedure 71007) at the Farley Nuclear Plant, Unit 2.
In order to minimize the impact to your on-site resources and to ensure a productive inspection we have enclosed a request for documents needed for this inspection. It is important that all of these documents are current and complete to minimize the number of additional documents requested during the inspection. The first set of documents is needed to support inspection preparation and we request that these be sent to the Region II office by October 17, 2005. The second set of documents are needed by the inspector upon arrival at the site on October 24, 2005.
We have discussed the schedule for these inspection activities with Mr. J. Kale of your staff. If there are any questions about this inspection or the material requested, please contact either Mr. Kim Van Doorn at (404) 562-4643 or Ms. Alex Vargas at (404) 562-4657.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Mark S. Lesser, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-364 License No. NPF-8
Enclosure:
(See next page)
2 SNC
Enclosure:
Inservice Inspection Document Request cc w/encl:
B. D. McKinney, Licensing Services Manager, B-031 Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution J. R. Johnson General Manager, Farley Plant Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution J. T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution State Health Officer Alabama Department of Public Health RSA Tower - Administration 201 Monroe St., Suite 700 P. O. Box 303017 Montgomery, AL 36130-3017 M. Stanford Blanton Balch and Bingham Law Firm P. O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 William D. Oldfield Quality Assurance Supervisor Southern Nuclear Operating Company Electronic Mail Distribution
OFFICE RII:DRS RII:DRS RII:DRS RII:DRP SIGNATURE
/RA/
/RA/
/RA/
RA By C. Rapp for/
NAME KVanDoorn:pmd AVargas MLesser MWidmann DATE 10/11/2005 10/11/2005 10/11/2005 October 13, 2005 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO
Enclosure INSERVICE INSPECTION DOCUMENT REQUEST Facility:
Joseph M. Farley, Unit 2 Inspection Dates:
October 24-28, 2005 Inspection Procedures:
IP 7111108, Inservice Inspection TI 2515/160, Pressurizer Penetration Nozzles and Steam Space Piping Connections in U.S. Pressurized Water Reactors (NRC Bulletin 2004-001)
IP 71007, Reactor Vessel Head Replacement Inspection Inspectors:
Kim Van Doorn (404) 562-4643) (PKV@nrc.gov)
Alex Vargas (404) 562-4657) (AAV@nrc.gov)
Accompanying Personnel:
Billy Crowley, Louis Lake A.
Information Requested for the In-Office Preparation Week The following information (electronic copy if practicable) is requested by October 17, 2005, to facilitate preparation for the onsite inspection week. The inspector will select specific items from the information requested below and request a list of additional documents needed on-site to your staff. We request that the specific items selected from the lists be available and ready for review on the first day of inspection. All information requests relate to Unit 2 unless otherwise stated. If you have any questions regarding this information, please call the inspector as soon as possible.
1)
A detailed schedule of:
(a) nondestructive examinations (NDE) planned for Class 1 and 2 systems and containment, performed as part of your ASME Code ISI Program during the scheduled inspection weeks; Note: An initial list, Outage Activities Report-7", was sent on September 9, 2005. From this list we have tentatively identified the NDE activities to be observed as follows:
ISI-SIS Hot Leg (APRI-4305-3,4)
ISI-SIS Cold Leg (APRI-4203-9,10)
ISI-B RHR (APRI-4101-5)
Pressurizer Visual Inspections for NRC Bulletin 2004-001 2)
A copy of the NDE procedures used to perform the examinations identified in A.1 (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with Appendix VIII, of Section XI of the ASME Code, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include
2 documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers).
3)
A copy of the ASME Section XI, Code Relief Requests applicable to the examinations identified in A(1);
4)
A list identifying NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual (VT-1, VT-2, VT-3)) which have identified relevant indications on Code Class 1 and 2 systems since the beginning of the last refueling outage.
5)
List with short description of the welds in Code Class 1 and 2 systems which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage and identify the system, weld number and reference applicable documentation.
6)
If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the inspection period, provide a detailed description of the welds to be examined, and the extent of the planned examination.
7)
List with description of ISI related issues entered into your corrective action system since the beginning of the last refueling outage.
8)
Copy of any 10 CFR Part 21 reports applicable to your structures systems or components within the scope of Section XI of the ASME Code, that have been identified since the beginning of the last refueling outage.
9)
Copy of the plant procedures used to perform inspections to identify reactor coolant system leaks or boric acid deposits and the procedures for resolution of leaks or boric acid deposits.
10)
Copy of the procedure(s) for conducting the pressurizer exams required by NRC Bulletin 2004-001 and detailed schedule for these exams.
11)
Copy of the Certified Design Specification document. If this document is classified as Proprietary, do not provide it, but please have it available for onsite review.
12)
Applicable ASME Code edition for the head fabrication 13)
General Description (Code Classification) of the fabrication materials used (i.e. castings, cladding, buttering, RVH nozzles and filler materials).
14)
Copy of the QA Package table of content 15)
Copy of the portion of the Refueling Outage schedule designated for RHV replacement
3 B.
Information to be provided on-site to the inspector 1)
For welds selected by the inspector from A.1)(a) above, provide copies of the following documents:
(a)
Document of the weld number and location (e.g., system, train, branch);
(b)
Document with a detail of the weld construction; (c)
Applicable Code Edition and Addenda for weldment; (d)
Applicable Code Edition and Addenda for welding procedures; (e)
Applicable weld procedures (WPS) used to fabricate the welds; (f)
Copies of procedure qualification records (PQRs) supporting the WPS on selected welds; (g)
Copies of mechanical test reports identified in the PQRs above; (h)
Copies of the nonconformance reports for the selected welds; (i)
Radiographs of the selected welds and access to equipment to allow viewing radiographs; and (j)
Copies of the preservice examination records for the selected welds.
2)
For the ISI related corrective action issues selected by the inspector from A.7 above, provide a copy of the corrective actions and supporting documentation.
3)
For the nondestructive examination reports with relevant indications on Code Class 1 and 2 systems selected by the inspector from A.4 above, provide a copy of the examination records and associated corrective action documents.
4)
Updated schedules for item A.1 5)
Copy of the previous completed ASME Code leakage test for the reactor coolant system, documenting the results of the VT-2 inspections.
6)
Copy of documentation of:
(a) engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety significant components; and (b) corrective actions for coolant leakage including boric acid deposits on safety related components identified since the beginning of the last refueling outage.
4 7)
Ready access to the Editions of the ASME Code (Sections V, IX and XI) applicable to the inservice inspection program and the repair/replacement program.
8)
RPVH QA Package provided by the manufacturer 9)
Hard Copy or Electronic Copy of the applicable edition of the ASME Code (Sections II, III, V, and XI) 10)
If applicable, access to RT films, densitometer, and viewer 11)
Access to the Engineering Change Document (including the 50.59 screening/evaluation)