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

60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19

ML081140085
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/22/2008
From:	James D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN040806
Download: ML081140085 (7)

Text

2CAN040806

April 22, 2008

U.S. Nuclear Regulatory Commission

Attn: Document Control Desk Washington, DC 20555

SUBJECT:

60-Day Report for ANO-2 Reacto r 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. 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 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 2R 19, 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 Inspection of

RPV Head BMV of ICI Nozzles Perform a 360

° bare metal visual inspection around the ICI nozzles from inside the cooling shroud. A BMV inspection of the 8 ICI nozzles at the annulus was conducted. No evidence of boric acid leakage was

observed.

BMV of CEDM Nozzles Perform a 360

° bare metal visual inspection around the CEDM nozzles. A visual inspection of all 81 CEDM nozzles was conducted. No evidence of boric acid leakage was observed.

BMV of Vent Line Nozzle Perform a 360

° bare metal visual inspection around the vent line nozzle. A visual inspection of the vent line nozzle was conducted. No evidence of boric acid leakage was observed.

Visual Inspection of RPV Head Flange Inspect the peripheral portion of the head and flange external to the cooling shroud. A visual inspection of the external surface of the RPV head flange was conducted. No evidence of boric acid leakage was observed.

Pressure Retaining Components Perform visual inspections of the pressure retaining components above the RPV head to identify potential boric acid deposits. A visual inspection was performed to assess leakage from pressure retaining components above the head. No evidence of leakage was observed.

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Inspection Area Inspection Method Extent of Inspection 2R19 Findings NDE of CEDM Penetrations (81) UT of Nozzle Wall including Triple Point Augmented Exam Inspect 2" above the J-weld to the blind zone of the CEDM nozzle. The 81 CEDMs were scanned and analyzed from the ID using Westinghouse UT probes. No flaws were detected.

Augmented NDE of Nozzle Blind Zone Perform augmented ECT inspection of the blind zone region on 57 of 81 CEDM nozzles. A manual ECT exam was conducted on the exterior surface of the nozzle by various delivery techniques. No flaws were detected.

UT of Nozzle Annulus (Leak Path) Review interference fit in the nozzle annulus above the J-weld for leakage path. The open housing probe examination did not reveal any leak path present in the annulus region of the CEDM nozzles. NDE of ICI Penetrations (8) UT of Nozzle Wall Inspect 2" above the J-weld to the blind zone (nozzle end). The open housing probe UT examination did not reveal any flaws in the 8 ICI nozzles.

ECT/UT of Nozzle Face Perform ECT and UT of ICI nozzle face to cover blind zone region at the nozzle end. An automated ECT/UT on the face of the ICI nozzles was performed. No flaws were detected.

UT of Nozzle Annulus (Leak Path) Review interference fit in nozzle annulus above the J-weld for leakage path. The open housing probe examination did not reveal any leak path present in the annulus region of the ICI nozzles.

2CAN040806 Page 3 of 3

Inspection Area Inspection Method Extent of Inspection 2R19 Findings NDE of Vent Line Penetration

(1) ECT of Wetted Surface Area Perform ECT of wetted surface of vent line nozzle and J-weld. The ECT examination did not detect any flaws on the weld or nozzle.

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