W3F1-2005-0045, 60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage

60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage

ML052030163
Person / Time
Site:	Waterford
Issue date:	07/19/2005
From:	Harris A Entergy Nuclear South, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-03-009, W3F1-2005-0045
Download: ML052030163 (7)

Text

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-- Entergy Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504-739-6475 Fax 504-739-6698 aharris@entergy.com Alan J. Harris Director, Nuclear Safety Assurance Waterford 3 W3Fl-2005-0045 July 19, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

REFERENCES:

60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

1.

NRC letter dated February 20, 2004, Issuance of First Revised Order (EA-03-009) Establishing Interim inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors, (IN040024)

2.

NRC letter dated May 28, 2004 NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in The Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at PWRs (IN040068)

3.

NRC letter to Entergy dated March 22, 2005, Waterford Steam Electric Station, Unit 3 (Waterford 3) - Relaxation Request from U.S.

Nuclear Regulatory Commission (NRC) First Revised Order EA 009 for Control Element Drive Mechanism (CEDM) Nozzles (TAC No. MC2643) (IN050036)

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 (W3Fl-2004-0058)

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 requested relaxation from portions of the Order and was granted relaxation on March 22, 2005 (Reference 3). In addition, on May 28, 2004, the NRC issued Bulletin 2004-01 (Reference 2) requesting licensees to perform bare metal visual (BMV) inspections of the pressurizer penetrations. If leaking penetrations were discovered, additional non-destructive examinations of the penetrations were to be performed. Entergy Operations, Inc. (Entergy) 4x0\\

W3F11-2005-0045 Page 2 of 3 provided its response on July 27, 2004 (Reference 4) where Entergy committed to comply with the bulletin.

Waterford Steam Electric Station, Unit 3 (Waterford 3) resumed operation on June 11, 2005.

The results of both the RPV head Order and Bulletin 2004-01 inspections are summarized in the attachment.

In summary, Entergy did not identify any boric acid leakage or primary water stress corrosion cracking of the reactor vessel head during the inspections. However, two pressurizer heater sleeves were identified to be potentially leaking. NDE of the two heater sleeves revealed two axial flaws in one sleeve and no flaws in the second sleeve. Therefore, no NDE expansion to other heater sleeves was required.

Note that mid-wall repairs were performed on all but one of the 30 pressurizer heater sleeves.

The one heater sleeve not repaired had previously been plugged and remains plugged.

These repairs were proactive except for the one leaking pressurizer heater sleeve as discussed in the attachment. Proactive repairs/rework was also performed on the side shell temperature element and two steam space instrument nozzles. These proactive repairs are discussed in the attachment.

This letter contains no NRC commitments. If you have any questions or require additional information, please contact D. Bryan Miller at 504-739-6692.

Sincerely, AJH/DBM/ssf

Attachment:

60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2005 Refueling Outage

W3Fl-2005-0045 Page 3 of 3 cc:

Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Nageswaran Kalyanam MS O-7D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P.O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 2 9th S. Main Street West Hartford, CT 06107-2445 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004

Attachment To W3F1 -2005-0045 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2005 Refueling Outage

Attachment to W3F1-2005-0045 Page 1 of 3 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2005 Refueling Outage Waterford Steam Electric Station, Unit 3 (Waterford 3) is a Combustion Engineering (CE) designed unit with Alloy 600 reactor pressure vessel (RPV) head and pressurizer penetrations which are subject to NRC First Revised Order EA-03-009 and NRC Bulletin 2004-01 (References 1 and 2) respectively. Entergy either complied with the Order or sought relaxation in accordance with the Order and committed to perform NDE per NRC Bulletin 2004-01 (References 3 and 4). Entergy performed inspections of the Waterford 3 RPV head and pressurizer during refueling outage 13 (RF-13) (spring of 2005). The RPV head inspections were conducted in accordance with Section IV.C of the Order (with relaxation per Reference 3) and the pressurizer inspections were conducted in accordance with Response 1 (c) of Entergy's response to Bulletin 2004-01 (Reference 4). The following provides the results of the RF-13 inspections.

Table I Summary of Waterford 3 Spring 2005 Refueling Outage Alloy 600 Inspections Inspection Area Inspection Method Extent of Inspection Status BMV Inspection RPV Head BMV Inspect the RPV head surface 3600 around BMV performed on 91 CEDM nozzles, 10 ICI of RPV Head each penetration for boric acid.

nozzles, vent line, and general head condition. No boric acid deposits were identified.

[NRC Order]

Pressure Retaining Inspect the CEDM and ICI housings for No boric acid deposits were identified.

Components potential boric acid leakage NDE of CEDM UT/ECT of 91 CEDM Inspect 2" above the J-weld to the blind zone 91 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 UT of nozzle Annulus Review interference fit in nozzle annulus As part of the CEDM ID exams a zero degree UT Relaxation]

(leak path) above J-weld for leakage path probe was used to establish that there was no leak path (wastage) from the nozzle annuli.

NDE of ICI UT/ECT of ICI nozzles Inspect 2" above the J-weld to the end of the The 10 ICI nozzles were UT/ECT examined from Nozzles ICI nozzle the ID. No flaws were detected.

[NRC Order]

UT/ECT of ICI Nozzle Perform UT/ECT exam of ICI nozzle face An automated UT/ECT on the face of the ICI Face where ID delivered UT/ECT tooling does not nozzles was performed. No flaws were detected.

provide inspection coverage.

Attachment to W3FI-2005-0045 Page 2 of 3 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2005 Refueling Outage Inspection Area Inspection Method Extent of Inspection Status 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 area line flaws.

[NRC Order]

Pressurizer Inspections and Repair

[Bulletin 2004-01]

Heater Sleeve BMV Inspect all Pressurizer heater sleeves and MNSA-2 installations for potential leakage Thirty heater sleeves were visually inspected and two were identified that were potentially leaking.

No leakage was observed on either of the MNSA-2 seal assemblies which were previously installed during RF-12 (fall 2003).

Heater Sleeve NDE Perform NDE of heater sleeves that had been Eddy Current examination performed on heater identified to be potentially leaking sleeves C4 & D2 revealed two axial flaws only on sleeve C-4. NDE did not detect a flaw on the D-2 sleeve.

Heater Sleeve Repair N/A Proactively implemented mid-wall repairs on 29 of 30 heater sleeves that removed Alloy 600 materials from the pressure boundary. One previously plugged pressurizer heater sleeve (F4) remains plugged.

Side Shell, Steam Perform visual inspection of Alloy 600 side A BMV of the pressurizer side shell nozzles, steam Space, Bottom shell, steam space, and bottom instrument space nozzles, bottom instrument nozzles and Instrument Nozzles nozzles associated welds was performed.. No leakage was BMV detected.

Side Shell, Steam Space & Bottom Instrument Nozzle Repair N/A The Side Shell TE and the two (2) bottom instrument nozzles were proactively repaired using a partial nozzle design that replaced Alloy 600 pressure boundary materials. In addition two (2) steam space instrument nozzles were proactively reworked to remove Alloy 600 weld filler material.

Attachment to W3FI-2005-0045 Page 3 of 3 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2005 Refueling Outage Inspection Area Inspection Method Extent of Inspection Status Pressurizer nozzle to Removed insulation and reviewed butt weld BMV of large bore nozzles and safe ends did not safe end welds and configurations for future inservice inspection reveal any leakage.

large bore steam space and potential weld overlay in RF-14 (fall 2006) welds BMV Legend:

BMV = Bare Metal Visual CEDM = Control Element Drive Mechanism ECT = Eddy Current Examination ICI = Incore Instrument ID = Inside Diameter MNSA = Mechanical Nozzle Seal Assembly NDE = Non-Destructive Examination RPV = Reactor Pressure Vessel TE = Temperature Element UT = Ultrasonic Examination