View source for L-05-164, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Visual Examination Requirements Associated with Third Ten-Year Interval Inservice Inspection Program

{{Adams
| number = ML053110146
| issue date = 10/31/2005
| title = Proposed Alternative to American Society of Mechanical Engineers Code Section XI Visual Examination Requirements Associated with Third Ten-Year Interval Inservice Inspection Program
| author name = Pearce L
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000334
| license number = DPR-066
| contact person = 
| case reference number = L-05-164
| document type = Inservice/Preservice Inspection and Test Report, Letter type:L
| page count = 4
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:FENOCI          _A"%                                                                     Beaver Valley Power Station FirstEnergyNuclearOperatingCompany                                                     Shippingpor. PA        B50770004 L. William Pearce                                                                                     724-682-5234 Vice President                                                                                   Fax: 724-643-8069 October 31,   2005 L-05-164 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

==Subject:==
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Proposed Alternative to American Society of Mechanical Engineers Code Section Xl Visual Examination Requirements Associated With Third Ten-Year Interval Inservice Inspection Program (Request No. BV3-IWVE1-4)
Approval to perform an alternative visual examination for the Beaver Valley Power Station (BVPS) Unit No. 1 third ten-year interval inservice inspection program was requested in a July 27, 2005 letter (number L-05-127) to the NRC. Additional information regarding the examination and test sequence related to the subject proposed alternative visual examination requirements was requested in an October 24, 2005 telephone call from Mr. Tim Colburn, NRC Project Manager for Beaver Valley Power Station (BVPS).
Enclosure I provides the requested information. Regulatory commitments are listed in Enclosure 2 of this submittal. If there are any questions concerning this matter, please contact Mr. Gregory A. Dunn, Manager, Fleet Licensing at 330-315-7243.
Sincerely, rove L. William Pearce

Beaver Valley Power Station, Unit No. 1 Proposed Alternative to ASME Code Section XI Visual Examination Requirements (Request No. BV3-IWE1-4)
L-05-164 Page 2

==Enclosures:==
: 1. Examination and Test Sequence
: 2. Commitments C:   Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

ENCLOSURE 1 L-05-164 EXAMINATION AND TEST SEQUENCE A summary list of examinations and tests to be performed for containment liner restoration welds is provided below. Examinations and tests listed in Items 1 through 4 will be performed to verify the integrity of the welds prior to restoration of concrete on the containment liner exterior surface and subsequent pressure testing.
Planned In-Process Examination and Testing Sequence
: 1. Perform Visual (VT) examinations and either Magnetic Particle (MT) or Dye Penetrant (PT) testing of the completed steel liner plate weld and attachment welds.
: 2. Perform spot Radiographic Testing (RT) examination of the completed full penetration steel liner plate weld.
: 3. Perform Vacuum-Box testing of the completed full penetration steel liner plate weld.
: 4. Perform VT- 1 examinations of the welds and surrounding areas of the restored containment liner plate interior and exterior surfaces.
: 5. Perform a General Visual or a VT-3 examination of the inside surface of the containment liner plate after coatings are applied.
: 6. Perform 10 CFR 50 Appendix J, Type A pneumatic leakage test of the containment pressure retaining boundary after restored reinforced concrete has attained proper strength.

ENCLOSURE 2 L-05-164 COMMITMENTS The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Beaver Valley Power Station (BVPS) Unit No. 1 in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC. These other actions are described only as information and are not regulatory commitments. Please notify Mr. Gregory A. Dunn, Manager, Fleet Licensing at 330-315-7243 of any questions regarding this document or associated regulatory commitments.
Commitment                        Implementation Date
: 1. Perform Visual (VT) examinations and either Magnetic Particle (MT) or Dye Penetrant (PT) testing of the completed steel liner plate weld   Items 1 through 4 are to be and attachment welds.                             implemented as described during the BVPS Unit No. 1
: 2. Perform spot Radiographic Testing (RT)            maintenance and refueling examination of the completed full penetration     outage scheduled for steel liner plate weld.                           February 2006 and prior to
: 3. Perform Vacuum-Box testing of the completed       restoration of concrete on full penetration steel liner plate weld.          the containment liner exterior surface and
: 4. Perform VT-I examinations of the welds and        subsequent pressure testing.
surrounding areas of the restored containment liner plate interior and exterior surfaces.
: 5. Perform a General Visual or a VT-3 examination    Items 5 and 6 are to be of the inside surface of the containment liner    implemented as described plate after coatings are applied.                 during the BVPS Unit No. 1
: 6. Perform 10 CFR 50 Appendix J, Type A              maintenance and refueling pneumatic leakage test of the containment         outage scheduled for pressure retaining boundary after restored        February 2006 and prior to reinforced concrete has attained proper strength. start-up from the outage.}}