View source for 2CAN040806, 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19

{{Adams
| number = ML081140085
| issue date = 04/22/2008
| title = 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19
| author name = James D
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000368
| license number = NPF-006
| contact person = 
| case reference number = 2CAN040806
| document type = Letter type:, Report, Miscellaneous
| page count = 7
}}

=Text=
{{#Wiki_filter:Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Nuclear Safety Assurance Arkansas Nuclear One 2CAN040806 April 22, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

==SUBJECT:==
60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

==REFERENCES:==
1     NRC letter dated February 20, 2004, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors, EA-03-009 (0CNA020404) 2     NRC letter to Entergy dated May 17, 2006, Arkansas Nuclear One, Unit 2 (ANO-2) - Relaxation Request from Nuclear Regulatory Commission (NRC) Order EA-03-009 for the Control Element Drive Mechanism (CEDM) Nozzles (2CNA050601)

==Dear Sir or Madam:==

On February 20, 2004, the Nuclear Regulatory Commission (NRC) issued the revised Order addressing inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactors (Reference 1). Section IV.E of the Order requires licensees to submit a report detailing the inspection results within sixty (60) days after returning the plant to operation.
Entergy has previously sought and was granted a relaxation from the Order for Arkansas Nuclear One, Unit 2 (ANO-2). The relaxation was for augmented examinations at the blind zones on the lower portion of the Control Element Drive Mechanism (CEDM) nozzles (Reference 2). As noted in Reference 2, Entergy is authorized to use the proposed alternative inspection for all CEDM RPV head nozzles for the remainder of the current, 10 year in-service inspection (ISI) interval. The current ANO-2 ISI interval expires on March 26, 2010. This relaxation was utilized during the spring 2008 2R19 refueling outage.

2CAN040806 Page 2 of 3 In addition, Entergy has sought and was granted a relaxation from the Order with regard to only performing a limited bare metal visual (BMV) inspection. This relaxation was not required for the 2R19 refueling outage. This is due to the fact that the new RPV head cooling shroud and insulation package was installed in the 2R19 outage. This shroud and insulation package has been described in several previous ANO-2 submittals. This new shroud and insulation package will allow ANO-2 to perform full BMV inspections of the RPV in the future.
ANO-2 resumed operation on April 10, 2008 from the 2R19 refueling outage. As a result of the inspections performed, Entergy did not identify any boric acid leakage or flaws associated with the RPV head inspections. The results of the RPV head inspections are summarized in the attachment to this letter.
This letter does not contain any NRC commitments. If you have any questions or require additional information, please contact me.
Sincerely, DEJ/rwc

==Attachment:==
60-Day Report for Reactor Vessel Head Inspection Results for ANO-2 Refueling Outage 2R18

2CAN040806 Page 3 of 3 cc:   Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437

Attachment 2CAN040806 60-Day Report for Reactor Vessel Head Inspection Results for ANO-2 Refueling Outage 2R19

Attachment to 2CAN040806 Page 1 of 3 60-Day RV Head Inspection Results for ANO-2 Refueling Outage 2R19 Arkansas Nuclear One, Unit 2 (ANO-2) is a CE designed unit with Alloy 600 reactor pressure vessel (RPV) head penetrations which is subject to NRC Order EA-03-009. For ANO refueling outage 2R19, Entergy either complied with the Order or was granted relaxation in accordance with the Order where necessary. In accordance with Section IV.E of the Order, licensees are required to submit a report detailing the inspection results within sixty (60) days after returning the plant to operation. The following provides the results of the 2R19 inspections performed on ANO-2.
Inspection Area    Inspection Method                Extent of Inspection                                   2R19 Findings Visual            BMV of ICI Nozzles      Perform a 360&deg; bare metal visual           A BMV inspection of the 8 ICI nozzles at the annulus was Inspection of                             inspection around the ICI nozzles from     conducted. No evidence of boric acid leakage was RPV Head                                  inside the cooling shroud.                 observed.
BMV of CEDM             Perform a 360&deg; bare metal visual           A visual inspection of all 81 CEDM nozzles was Nozzles                 inspection around the CEDM nozzles.        conducted. No evidence of boric acid leakage was observed.
BMV of Vent Line        Perform a 360&deg; bare metal visual           A visual inspection of the vent line nozzle was conducted.
Nozzle                  inspection around the vent line nozzle. No evidence of boric acid leakage was observed.
Visual Inspection of    Inspect the peripheral portion of the head A visual inspection of the external surface of the RPV RPV Head Flange         and flange external to the cooling         head flange was conducted. No evidence of boric acid shroud.                                    leakage was observed.
Pressure Retaining      Perform visual inspections of the          A visual inspection was performed to assess leakage from Components              pressure retaining components above        pressure retaining components above the head. No the RPV head to identify potential boric   evidence of leakage was observed.
acid deposits.

2CAN040806 Page 2 of 3 Inspection Area   Inspection Method             Extent of Inspection                                 2R19 Findings NDE of CEDM      UT of Nozzle Wall      Inspect 2 above the J-weld to the     The 81 CEDMs were scanned and analyzed from the ID Penetrations     including Triple Point blind zone of the CEDM nozzle.         using Westinghouse UT probes. No flaws were detected.
(81)             Augmented Exam Augmented NDE of       Perform augmented ECT inspection of    A manual ECT exam was conducted on the exterior Nozzle Blind Zone      the blind zone region on 57 of 81      surface of the nozzle by various delivery techniques. No CEDM nozzles.                          flaws were detected.
UT of Nozzle Annulus   Review interference fit in the nozzle  The open housing probe examination did not reveal any (Leak Path)            annulus above the J-weld for leakage   leak path present in the annulus region of the CEDM path.                                  nozzles.
NDE of ICI       UT of Nozzle Wall      Inspect 2 above the J-weld to the     The open housing probe UT examination did not reveal Penetrations (8)                        blind zone (nozzle end).               any flaws in the 8 ICI nozzles.
ECT/UT of Nozzle Face  Perform ECT and UT of ICI nozzle       An automated ECT/UT on the face of the ICI nozzles was face to cover blind zone region at the performed. No flaws were detected.
nozzle end.
UT of Nozzle Annulus   Review interference fit in nozzle      The open housing probe examination did not reveal any (Leak Path)            annulus above the J-weld for leakage   leak path present in the annulus region of the ICI nozzles.
path.

2CAN040806 Page 3 of 3 Inspection Area       Inspection Method            Extent of Inspection                                2R19 Findings NDE of Vent          ECT of Wetted Surface Perform ECT of wetted surface of vent     The ECT examination did not detect any flaws on the weld Line Penetration     Area                  line nozzle and J-weld.                   or nozzle.
(1)
Legend:
BMV = Bare Metal Visual                                  NDE = Non-Destructive Examination CEDM = Control Element Drive Mechanism                   PT = Dye Penetrant Testing ECT = Eddy Current Testing                               PWSCC = Primary Water Stress Corrosion Cracking ICI = Incore Instrument                                  UT = Ultrasonic Testing}}