ML082970174

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Draft Request for Additional Information, Upcoming Conference Call
ML082970174
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 10/22/2008
From: Richard Ennis
Plant Licensing Branch 1
To: Chernoff H
Plant Licensing Branch 1
Ennis R, NRR/DORL, 415-1420
References
TAC MD9199, TAC MD9200, TAC MD9201
Download: ML082970174 (4)


Text

October 22, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD9199, MD9200, AND MD9201)

The attached draft request for information (RAI) was transmitted on October 22, 2008, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s submittal dated July 3, 2008, for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2. PSEGs submittal requested authorization, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 20, Section 20.1703(b) to: (1) use French-designed respiratory protection equipment that has not been tested and certified by the National Institute for Occupational Safety and Health; (2) take credit for an assigned protection factor of 2,000 for this equipment; and, (3) not provide standby rescue persons whenever this equipment is used.

This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees submittals.

Docket Nos. 50-354, 50-272 and 50-311

Attachment:

Draft RAI

October 22, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD9199, MD9200, AND MD9201)

The attached draft request for information (RAI) was transmitted on October 22, 2008, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s submittal dated July 3, 2008, for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2. PSEG's submittal requested authorization, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 20, Section 20.1703(b) to: (1) use French-designed respiratory protection equipment that has not been tested and certified by the National Institute for Occupational Safety and Health; (2) take credit for an assigned protection factor of 2,000 for this equipment; and, (3) not provide standby rescue persons whenever this equipment is used.

This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals.

Docket Nos. 50-354, 50-272 and 50-311

Attachment:

Draft RAI DISTRIBUTION PUBLIC R. Pedersen, NRR/DIRS LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMREnnis Resource ACCESSION NO.: ML082970174 OFFICE PDI-2/PM NAME REnnis DATE 10/22/05 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR AUTHORIZATION TO USE DELTA PROTECTION RESPIRATORY PROTECTION QUIPMENT FOR HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-354, 50-272 AND 50-311 By letter dated July 3, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081980090), PSEG Nuclear LLC (PSEG or the licensee) requested authorization, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 20, Section 20.1703(b), for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2, to: (1) use French-designed respiratory protection equipment that has not been tested and certified by the National Institute for Occupational Safety and Health; (2) take credit for an assigned protection factor of 2,000 for this equipment; and, (3) not provide standby rescue persons whenever this equipment is used.

The Nuclear Regulatory Commission (NRC) staff has reviewed your request and would like to discuss the following to clarify the submittal.

1) Page 2 of the cover letter states that PSEG will implement the following controls for use of the Mururoa V4 F1 and V4 MTH2 single use respiratory protection suits:
1. The Mururoa V4 F1 and V4 MTH2 single use suit will be integrated into the PSEG respiratory protection programs using the information provided by the manufacturer.
2. New lesson plans will be developed to train workers on Mururoa's features, donning, use and removal, cautions and use of mouth strip and tear off strips for routine and emergency egress.
3. Radiation Protection personnel will be provided additional training for selection, approval, issue, equipment set-up, operation and maintenance instructions for the Mururoa suit.

Although Enclosure 1 to your submittal addressed some of the following issues, the cover letter did not specifically include the following controls in the above list of controls.

Please address whether the following controls will also be implemented and, if not, provide justification:

Attachment

1. The manufacturers instructions for use and storage of the Delta Protection Mururoa V4F1 and V4 MTH2 suits will be integrated into the respiratory protection programs.
2. The Mururoa V4F1 and V4 MTH2 suits will be discarded after a single use and will not be used in atmospheres that are immediately dangerous to life and health (IDLH).
3. Any defects discovered will be entered into the Corrective Action Program and reported to the manufacturer, as necessary. Industry notifications, when required, will be made through the Operating Experience Program.
2) As required by 10 CFR 50.34(b)(3), the Updated Final Safety Analysis Report (UFSAR) shall include information describing the means for controlling and limiting radiation exposures within the limits set forth in 10 CFR Part 20. Please provide a regulatory commitment to include the controls discussed in question 1 in the Hope Creek and Salem UFSARs upon implementation of the requested authorization.