IR 05000336/2006013

IR 05000336-06-013, on 06/09/2006 - 11/28/2006; Millstone, Unit 2; Pressurizer Replacement. the Report Covered a 6-Month Period of Inspection by Regional Inspectors. No Findings of Significance Were Found

ML070160068
Person / Time
Site:	Millstone
Issue date:	01/12/2007
From:	Conte R Engineering Region 1 Branch 1
To:	Christian D Dominion Resources Services
References
IR-06-013
Download: ML070160068 (14)

Text

ary 12, 2007

SUBJECT:

MILLSTONE POWER STATION - PRESSURIZER INSPECTION REPORT 05000336/2006013

Dear Mr. Christian:

Over the period of June - November of 2006 the US Nuclear Regulatory Commission (NRC)

completed an inspection at your Millstone Power Station Unit 2 Pressurizer Replacement. The enclosed inspection report documents the inspection results, which were discussed on November 28, 2006, with Mr. Alan Price and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The replacement of your pressurizer was implemented in accordance with your planned activities in a safe manner in compliance with the applicable codes, specifications, and regulations.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Richard Conte, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos: 50-336 License Nos: DPR-65 Enclosure: Inspection Report 05000336/2006013 w/Attachment

Mr. David

SUMMARY OF FINDINGS

IR 05000336/2006013, 06/9/2006 - 11/28/2006; Millstone Power Station, Unit 2; Pressurizer

Replacement. The report covered a 6-month period of inspection by regional inspectors. No findings of significance were found.

ii

REPORT DETAILS

4OA5 Other Activities

.1 PRESSURIZER REPLACEMENT (IP 50003)

a. Inspection Scope

The pressurizer replacement at a Millstone Nuclear Power Station was a significant modification activity involving many different licensee disciplines with extensive contractor support. Because the replacement pressurizer was designed to be as close to the original pressurizer as possible, the replacement activity did not substantially affect the power plant safety analysis. The containment structure and plant operational characteristics were minimally impacted as well.

This inspection verified that engineering evaluations and design changes associated with the pressurizer replacement were completed in conformance with requirements in the facility license, the applicable codes and standards, licensing commitments, and the regulations. This inspection verified the pressurizer removal and replacement activities maintained adequate nuclear and radiological safety.

This inspection also verified the pressurizer post-installation test program was technically adequate and in conformance with requirements, and was satisfactorily implemented. Additionally, the shutdown risk was reviewed to ascertain it was minimized, as much as reasonably possible, for the pressurizer removal and replacement activities.

Design and Planning Inspections The inspector verified that selected design changes and modifications to systems, structures, and components described in the Final Safety Analysis Report were subjected to a review in accordance with 10 CFR 50.59. Key design aspects and modifications for the replacement pressurizer and other modifications associated with the pressurizer replacement were reviewed. Pressurizer modifications and the designs of other related significant modifications were reviewed. Replacement materials and components were reviewed to determine they meet the appropriate design technical requirements. Selected key procurement specifications for the pressurizer and its components were reviewed to determine that they met applicable industry codes and standards and regulatory requirements including 10 CFR 50, Appendix B quality assurance requirements and 10 CFR 50.49 environmental qualification requirements.

The inspector determined that the licensee confirmed that the replacement pressurizer conforms to design drawings, and that there are no fabrication deviations from design.

The inspector confirmed that this Class 1 vessel was hydrostatically tested and N-stamped and discussed the pre- and post- inservice inspection results with the responsible Dominion Level III individual.

Because the containment crane is not single-failure proof, the inspector conducted a comprehensive review of the engineering design, modification, and analysis associated with pressurizer lifting and rigging including:

(1) crane and rigging equipment,

(2) pressurizer component drop analysis,

(3) safe load paths, and

(4) load lay-down areas.

The inspector focused on the impact of load handling activities on reactor core or spent fuel and its cooling and plant support systems for the reactor unit and common systems for the other operating unit at the site. The inspector determined the reactor was fully de-fueled during the lifting process and all lift paths were planned to avoid critical equipment impact.

A regional health physics specialist reviewed the overall pressurizer radiation protection program with focus on controls, planning, and preparation. The As-Low-As-Reasonably-Achievable planning was reviewed to determine if all reasonable measures had been considered. These projections were compared with the planned and implemented exposure controls and the use of temporary shielding. Additional features reviewed were contamination controls, radioactive material management, radiological work plans, and control emergency contingencies. Prior to the outage project staffing and training plans.

In addition, security considerations associated with vital and protected area barriers that were to be affected during replacement activities were reviewed including the multiple perimeter breaches used to bring in the replacement pressurizer and remove the old pressurizer.

The licensees maintenance rule risk assessment was reviewed and found acceptable.

In addition, the inspector reviewed the risk assessment of planned modifications to ensure shutdown risk management objectives were acceptable.

Pressurizer Removal and Replacement Inspections The inspector reviewed the following welding and non-destructive examination activities:

(1) Procedures for welding and Nondestructive Evaluations.

(2) Qualifications of welding and Nondestructive test personnel.

(3) Radiography results and work packages for selected welds.

(4) Completion of any pre-service NDE requirements.

The inspector reviewed activities associated with lifting and rigging including preparations and procedures for rigging and heavy lifting. The inspector reviewed the extensive modification of the pressurizer concrete support structure used to facilitate pressurizer replacement. The post-cut structural modification was reviewed and compared against the original design standards. The inspector reviewed radiological safety plans for temporary storage or disposal of the retired pressurizer and components.

The inspector reviewed the following activities throughout the replacement process:

(1) The operating conditions including system isolation and safety tagging/blocking.

(2) Implementation of radiation protection controls.

(3) Controls for excluding foreign material.

(4) Installation, use, and removal of temporary services.

(5) Implementation of fire prevention and mitigation plans.

Post-installation Verification and Testing Inspections The replacement pressurizer was essentially a direct replacement that did not require modification of the containment. The inspector reviewed the:

(1) Containment testing.

(2) RCS leakage testing.

b. Findings

No findings of significance were identified.

4OA6 Meetings, Including Exit

On November 28, 2006, the inspector presented the overall inspection results to Mr. Alan Price and other members of the staff, who acknowledged the findings. The inspector asked Dominion whether any of the material examined during the inspection should be considered proprietary. No proprietary information was identified.

ATTACHMENT

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

S. Jordan Director, Operations and Maintenance

R. Griffin Director, Safety and Licensing

P. Grossman Manager, Design Engineering

S. Janes Manager, Pressurizer Project

D. Yapchanyk Lead Engineer, Pressurizer Replacement

M. Doucette Project Engineer, Pressurizer Replacement

H. Beeman ISI Engineer

R. Fuller Level III

M. Stark Steam Generator Project Engineer

D. Gerber Steam Generator Engineer

NRC

J. Benjamin Resident Inspector