ML042670538

Review of Final Status Survey Report for the Main Steam Support Structure, Electrical Penetration Area and Steam Generator Blow/Down Building at the Trojan Nuclear Plant

ML042670538
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/23/2004
From:	Buckley J NRC/NMSS/DWM
To:	Quennoz S Portland General Electric Co
References
+sispmjr200507, -RFPFR
Download: ML042670538 (3)

Text

September 23, 2004 Mr. Stephen M. Quennoz, Vice President Power Supply/Generation Portland General Electric Company Trojan Nuclear Plant 71760 Columbia River Highway Rainier, Oregon 97048

SUBJECT:

REVIEW OF FINAL STATUS SURVEY REPORT FOR THE MAIN STEAM SUPPORT STRUCTURE, ELECTRICAL PENETRATION AREA AND STEAM GENERATOR BLOWDOWN BUILDING AT THE TROJAN NUCLEAR PLANT

Dear Mr. Quennoz:

On March 30, 2004, Portland General Electric Company (PGE) submitted the Final Status Survey Report (FSSR) for the Trojan Nuclear Plant (TNP) Main Steam Support Structure, Electrical Penetration Area and Steam Generator Blowdown Building. The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the FSSR and concludes that:

(1) the final status survey was conducted in accordance with the License Termination Plan (LTP); (2) the FSSR contains the information identified in NUREG-1757, Consolidated NMSS Decommissioning Guidance, Section 4.5; and (3) the final status survey results demonstrate that the Main Steam Support Structure, Electrical Penetration Area and Steam Generator Blowdown Building meet the radiological criteria for unrestricted release identified in the LTP.

However, the staff would like PGE to consider clarifying the FSSR to address the following review comments:

1. Section 2.1.1, page 2-1, paragraph 2, sentences 6 & 7 - The sentences, as currently written, can be misinterpreted to mean that some surfaces were remediated and characterized, and the resultant post-remediation characterization data was used for classifying an area, rather than reflecting the pre-remediation condition. Table 2-1 presented on page 2-12 does provide clarification in a footnote which states that pre-remediation data were used to classify areas.

However, the staff recommends that PGE consider rewording the sentences on page 2-1 to reflect that pre-remediaiton data served as the basis for survey unit classification only.

2. Appendix C, page C The maximum reported scan measurement value was 20,090 dpm/100 cm2 for survey unit S18059A, which is close to the 21,000 dpm/100cm2 investigation level. The investigation summary notes that no investigation was performed in the survey unit because of no anomalous data. The surface scan map provided on page C-23 of the Supplement to Appendix C has a notation for an instrument alarm for scan location 085, which corresponds to both the survey unit maximum value on page C-27 and the reported value of 20, 090 dpm/100 cm2 listed on page C-20 of the Supplement to Appendix C. Please provide clarification whether this location was investigated, including whether a static measurement was performed to quantify the residual radioactivity.

S. Quennoz In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, and your response (if any) will be made 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

If you have any questions concerning this evaluation, please contact me at (301) 415-6607.

Sincerely,

/RA/

John T. Buckley, Project Manager Decommissioning Directorate Division of Waste Management and Environmental Protection Office of Nuclear Material Safety and Safeguards Docket No.: 50-344 License No.: NPF-1

S. Quennoz In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, and your response (if any) will be made 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

If you have any questions concerning this evaluation, please contact me at (301) 415-6607.

Sincerely,

/RA/

John T. Buckley, Project Manager Decommissioning Directorate Division of Waste Management and Environmental Protection Office of Nuclear Material Safety and Safeguards Docket No.: 50-344 License No.: NPF-1 DISTRIBUTION:

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