2CAN120302, 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R16

60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R16

ML033450335
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/08/2003
From:	Cotton S Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN120302, EA-03-009
Download: ML033450335 (6)

Text

Entergy Operations, Inc.

, Entergy 1448 S.R. 333 Russellville, AR 72802 Tel 501 858 5000 2CAN120302 December 8, 2003 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 2R16 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

REFERENCES:

1 NRC letter dated February 11, 2003, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors, EA-03-009 (OCNA020302) 2 NRC letter to Entergy dated October 3, 2003, Relaxation Request From NRC Order EA-03-009 for the Vessel Head Penetration Vent Line (CNRI-2003-0013) 3 NRC letter to Entergy dated October 9, 2003, Relaxation Request From NRC Order EA-03-009 Regarding the Bare Metal Visual Examination (2CNA1 00306) 4 NRC letter to Entergy dated October 9, 2003, Relaxation Request From NRC Order EA-03-009 for the Control Element Drive Mechanism Nozzles (CNRI-2003-0014) 5 NRC letter to Entergy dated October 9, 2003, Relaxation Request From NRC Order EA-03-009 for the Incore Instrument Nozzles (CNRI-2003-0015)

Dear Sir or Madam:

On February 11, 2003, the Nuclear Regulatory Commission (NRC) issued an Order addressing inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactors (Reference 1). The NRC stated that the actions in the Order are interim measures, necessary to ensure that licensees implement and maintain appropriate measures to inspect and, as necessary, repair RPV heads and associated penetration nozzles. Section

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2CAN120302 Page 2 of 2 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. Arkansas Nuclear One, Unit 2 (ANO-2) resumed operation on October 13, 2003. The attachment to this letter provides the details of the recent ANO-2 reactor vessel head inspection from refueling outage 2R1 6. In summary, Entergy did not identify any boric acid leakage or primary water stress corrosion cracking as a result of the ANO-2 RPV head inspections conducted during 2R16.

This letter contains no NRC commitments. If you have any questions or require additional information, please contact Steve Bennett at 479-858-4626.

Sincerely, Ag-~~~

Sherrie R. Cotton Director, Nuclear Safety Assurance SRC/sab

Attachment:

60-Day Response to Order EA-03-009 on ANO-2 RPV Head Inspection for Refueling Outage 2R16 cc: Dr. Bruce S. Mallett 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. Thomas W. Alexion MS O-7D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205

Attachment to 2CAN1 20302 60-Day Response to Order EA-03-009 on ANO-2 RPV Head Inspection for Refueling Outage 2R16

Attachment to 2CAN120302 Page 1 of 3 60-Day RV Head Inspection for ANO-2 Refueling Outage 2R1 6 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 (Reference 1). Entergy either complied with the Order or sought relaxation in accordance with the Order where necessary. NRC approvals of the 2R16 Order relaxations, including augmented inspection requirements, are documented in References 2 through 5. Entergy performed inspections of the ANO-2 RPV head during refueling outage 2R1 6 which was conducted in the fall of 2003. 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 2R16 inspections performed on ANO-2.

Inspection Area Inspection Method Extent of Inspection 2R16 Findings Visual Inspection Visual Inspection Inspect the CEDM, ICI and vent line Inspections of the RPV CEDM, ICI and vent line nozzles of RPV Head Above Cooling Shroud penetrations for boric acid from above above the cooling shroud were performed. Boroscopic the cooling shroud. inspections between certain nozzles were also conducted

[Ref. 1] to confirm cleanliness of the shroud. No boric acid deposits were identified.

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 boric acid deposits were shroud. identified.

[Ref. 1]

Visual Inspection Inspect the CEDM nozzles to the extent A visual inspection inside the cooling shroud was Inside the Cooling practical for boric acid deposits above conducted including the peripheral CEDM nozzles visible Shroud and around the insulation. This from the shroud access doors. No boric acid deposits

[Ref. I and 3] inspection was not a BMV inspection. were identified.

BMV of ICI Nozzles Perform a 3600 BMV inspection around A BMV inspection of the 8 1CI nozzles at the annulus was the ICI nozzles from inside the cooling conducted using visual and boroscopics techniques. No

[Ref. 1 and 3] shroud. boric acid deposits were identified.

Attachment to 2CAN1 20302 Page 2 of 3 NDE of CEDM UT of Nozzle Wall Inspect 2" above the J-weld to the A Westinghouse open housing UT probe was used to Penetrations (81) [Ref. I and 41 blind zone of the CEDM nozzle. perform the examinations. The exams did not reveal any PWSCC indications in the CEDM nozzles.

UT of J-Weld (Triple Examine extent of J-weld next to The open housing UT probe did not reveal any PWSCC Point Exam) nozzle to 0.060" depth. indications to be present in the 81 CEDM J-welds.

[Ref. 1 and 31 Manual ECT of Nozzle Examine blind zone outside diameter A manual ECT exam was conducted on the exterior Blind Zone on 75 of 81 nozzle ends near the surface of the nozzle by various delivery techniques. No

[Ref. 1 and 4] threaded region of the nozzles. indications of PWSCC were identified.

LF ECT of Nozzle Examine a minimum of 1.5" below the The LF ECT was conducted on each of the CEDM nozzles Annulus counter-bore using an acceptance using the open housing probe. The exam did not reveal

[Ref. 1 and 3] criterion of 0.060" wastage depth. any loss of carbon steel indicative of wastage.

UT of Nozzle Annulus Interrogate interference fit in the nozzle The open housing probe examination did not reveal any (Leakage Assessment) annulus above the J-weld for leak path leak path present in the annulus region of the CEDM

[Ref. 1] assessment. nozzles.

NDE of ICI UT of Nozzle Wall Inspect 2' above the J-weld (except for The open housing probe UT examination did not reveal Penetrations (8) counter-bore liftoff) to the blind zone of any PWSCC indications in the 8 ICI nozzles.

[Ref. I and 5] the ICI nozzle.

Manual PT of Nozzle Inspect lower extent of the blind zone Manual PT exams were conducted on the nozzles at the Blind Zone on the 8 ICI nozzles. blind zones. Two nozzles had initial indications that required further examination. The indications were

[Ref. 1 and 5] subsequently removed by grinding and PT cleared. The indications were determined to be weld inclusions and not PWSCC.

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

path.

[Ref. 1]

I .1. L

Attachment to 2CAN120302 Page 3 of 3 NDE of Vent Line ECT of Wetted Surface Perform ECT of wetted surface of vent The ECT examination did not reveal any indications of Penetration (1) Area line. PWSCC on the weld or nozzle.

[Ref. I and 21 LF ECT of Nozzle Examine a minimum of 1.5" below the The LF ECT did not reveal any leak path or loss of carbon Annulus (Leakage top of the head to 0.060" depth for steel indicative of wastage.

Assessment) wastage.

[Ref. 1]

Legend:

BMV = Bare Metal Visual NDE = Non-Destructive Examination CEDM = Control Element Drive Mechanism PT = Dye Penetrant Examination ECT = Eddy Current Examination PWSCC = Primary Water Stress Corrosion Cracking ICI = Incore Instrument UT = Ultrasonic Examination LF ECT = Low Frequency Eddy Current Examination