2CAN060503, 60-Day Report for ANO-2 Reactor Pressure Vessel Head and Pressurizer Inspection for Refueling Outage 2R17, Arkansas Nuclear One, Unit 2

60-Day Report for ANO-2 Reactor Pressure Vessel Head and Pressurizer Inspection for Refueling Outage 2R17, Arkansas Nuclear One, Unit 2

ML051660411
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/07/2005
From:	James D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN060503, BL-04-001
Download: ML051660411 (6)

Text

Entergy Operations, Inc.

A Entergy 1448 S.R. 333 Russellville. AR 72802 Tel 479-858-4619 Dale E. James Acting, Director.

Nuclear Safety Assurance 2CAN060503 June 7, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

60-Day Report for ANO-2 Reactor Pressure Vessel Head and Pressurizer Inspection for Refueling Outage 2R17 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

REFERENCES:

I 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 (OCNA020404) 2 NRC letter to Entergy dated February 7, 2005, Arkansas Nuclear One, Unit 2 (ANO-2) - Relaxation Request from Nuclear Regulatory Commission (NRC) First Revised Order EA-03-009 for the Control Element Drive Mechanism (CEDM) Nozzles (CNRI-2005-002) 3 NRC letter dated May 28, 2004 NRC Bulletin 2004-01: Inspection ofAlloy 82/182/600 Materials Used in The Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at PWRs (OCNA050408) 4 Entergy letter dated July 27, 2004, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used In Pressurizer Penetrations and Steam Space Piping Connections (OCAN070404)

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. In addition on May 28, 2004, the NRC issued Bulletin 2004-01 (Reference 3) requesting licensees to perform bare metal visual (BMV) inspections of the pressurizer penetrations. If leaking penetrations are discovered additional non-destructive examination of the penetrations were to be performed. Entergyprovided its response on July 27, 2004 (Reference 4) where Entergy committed to comply with the bulletin.

b-fl

2CAN060503 Page 2 of 2 Arkansas Nuclear One, Unit 2 (ANO-2) resumed operation on April 11, 2005. In summary, Entergy did not identify any boric acid leakage or primary water stress corrosion cracking of the reactor vessel head during 2R17. However, nine pressurizer heater sleeves and one previously repaired pressurizer heater penetration were discovered to be leaking. NDE of the leaking heater sleeves revealed only axial flaws and NDE expansion to other heater sleeves was not required. The results of both the RPV head and pressurizer inspections are summarized in the attachment.

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

Sincerely, Dale ames DEJ/ ab Atta hment: 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for ANO-2 Refueling Outage 2R17 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. Drew Holland 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 2CAN060503 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for ANO-2 Refueling Outage 2R17

Attachment to !4 2CAN060503 Page 1 of 3

.A 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for ANO-2 Refueling Outage 2R17 Arkansas Nuclear One, Unit 2 (ANO-2) is a CE designed unit with Alloy 600 reactor pressure vessel (RPV) head and pressurizer penetrations which are subject to NRC Order EA-03-009 and NRC Bulletin 2004-01 (References I and 3). Entergy either complied with the Order or sought relaxation in accordance with the Order and committed to perform NDE per Bulletin 2004-01 (References 2 and 4). Entergy performed inspections of the ANO-2 RPV head and pressurizer during refueling outage 2R1 7 (spring of 2005). These inspections were conducted in accordance with Section IV.E of the Order and Bulletin 2004-01. The following provides the results of the 2R17 inspections.

Table I Summary of ANO-2 Outage Alloy 600 Inspections for 2R17 Inspection Area Inspection Method Extent of Inspection Status BMV Inspection RPV Head BMV Inspect the RPV head surface 3600 around BMV performed on 81 CEDM nozzles, 8 ICI of RPV Head each penetration for boric acid. Inspect the nozzles, vent line, and general head condition. No RPV head flange. penetrations were determined to be leaking. Rust

[NRC Order] staining was observed on the head but no wastage was present. No head degradation was observed.

Pressure Retaining Inspect the CEDM and ICI housings for Dry boric acid staining identified on several CEDM Components potential boric acid leakage housings was determined to result from CEDM venting during previous operating cycles. This resulted in the rust staining noted above.

NDE of CEDM UT of 81 CEDM Inspect 2"above the J-weld to the blind zone 81 CEDM nozzles were examined and analyzed Nozzles nozzles of the CEDM nozzle from the ID using Westinghouse UTIECT probes.

No flaws were detected.

[NRC Order and NRC approved Augmented NDE of Perform Augmented ECT inspection on 76 of Augmented CEDM ECT data on 76 nozzles was Relaxation] Nozzle End per NRC 81 nozzle ends performed. No flaws were detected.

Relaxation UT of nozzle Annulus Review interference fit in nozzle annulus As part of the CEDM ID exams a zero degree UT (leak path) above J-weld for leakage path probe was used to establish that there was no leak path (wastage) from the nozzle annuli.

Attachment to 2CAN060503 Page 2 of 3 NDE of ICI UT of ICI nozzles Inspect 2" above the J-weld to the end of the The eight ICI nozzles were UT examined from the Nozzles ICI nozzle ID. No flaws were detected.

[NRC Order]

ECT of Nozzle Face Perform ECT exam of ICI nozzle face where An automated ECT on the face of the ICI nozzles UT cannot detect flaws. was performed. No flaws were detected.

NDE of Vent ECT of wetted surface Perform ECT of entire wetted surface of vent The ECT exam of the vent line did not reveal any ..

Line [NRC Order] area line flaws.

Pressurizer Heater Sleeve BMV Inspect all Pzr heater nozzles and MNSA-2 Entergy visually identified nine (9) heater sleeves Inspections and installations for potential leakage and one previously plugged nozzle to be leaking.

Repair Six (6) previously installed MNSA-2s were inspected with no leakage identified.

[Bulletin 2004-01]

Heater Sleeve NDE Perform NDE of heater sleeves that have PT of X-1 plugged nozzle revealed axial flaws in . I,. .

been identified to be leaking weld. No nozzle ID exam could be performed (see ., -, :.I Note 1). ECT exams on 9 of 9 heater sleeves revealed only axial flaws (see Table 2).

Heater Sleeve Repair Install MNSA-2 on 9 heater sleeves. The 9 heater sleeves were repaired by use of MNSA-2 assemblies.

Perform mid-wall repair on nozzle X-1 The previously plugged Pzr heater penetration (X-1) was repaired by a mid-wall weld repair.

Side shell/Steam space Perform visual inspection of steam space and A BMV of the pressurizer side shell nozzles, steam penetration BMV butt welds on Alloy 600 pressurizer space nozzles and associated butt welds was penetrations performed. No leakage was detected.

Other Alloy 600 Hot Leg Nozzles Perform visual inspection of hot leg nozzles BMV inspections of the hot leg nozzles did not BMV reveal any leakage Inspections

[GL 2002-01] Cold Leg Nozzles Perform visual inspection of cold leg nozzles BMV inspections of the cold leg nozzles did not reveal any leakage

Attachment to 2CAN060503 Page 3 of 3 I

Legend:

BMV = Bare Metal Visual NDE = Non-Destructive Examination CEDM = Control Element Drive Mechanism PT = Dye Penetrant Examination ECT = Eddy Current Examination UT = Ultrasonic Examination ICI = Incore Instrument MNSA - Mechanical Nozzle Seal Assembly Note 1: Pressurizer penetration X-1 was plugged in the late 1980's using Alloy 600 nozzle and weld material. This penetration was determined to be leaking during 2R17. In preparation to perform NDE of the nozzle bore, a Go-No Go gauge was used to determine NDE examination capability.

The gauge could not be inserted to the extent necessary to perform a UT scan. The original weld repair was determined to have distorted the nozzle bore where no useful UT data could be acquired. The NRC staff was notified of this condition during the 2R17 outage. - -

Table 2 Eddy Current Examination Report of Nine ANO-2 Pressurizer Heater Sleeves Examined During 2R17 Outage Sleeve Orientation Flaw Length Location G3 Axial 0.46 ID Flaw Below Weld Axial 0.41 ID Flaw Below Weld X3 Axial 0.57 ID Flaw Below Weld VI Axial 0.37 ID Flaw Below Weld J2 Axial 1.19 ID Flaw Below Weld Axial 0.74 ID Flaw Below Weld P1 Axial 0.41 ID Flaw Below Weld P2 Axial 0.49 ID Flaw Below Weld U3 Axial 0.46 ID Flaw Below Weld H4 Axial 0.30 ID Flaw Below Weld C4 Axial 0.39 ID Flaw Below Weld