ML19310F001

Ns Savannah, Correction to Amendment 17 Technical Specifications

ML19310F001
Person / Time
Site:	NS Savannah
Issue date:	11/20/2019
From:	Tanya Smith Division of Decommissioning, Uranium Recovery and Waste Programs
To:	Koehler E US Dept of Transportation, Maritime Admin
Smith T
References
Download: ML19310F001 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 20, 2019 Mr. Erhard W. Koehler Senior Technical Advisor, N.S. Savannah U.S. Department of Transportation Maritime Administration (MAR-640.2) 1200 New Jersey Avenue, SE W25-209/212 Washington, DC 20590-0001

SUBJECT:

NUCLEAR SHIP SAVANNAH - CORRECTION OF TYPOGRAPHICAL ERROR IN AMENDMENT 17 OF THE TECHNICAL SPECIFICATIONS

Dear Mr. Koehler:

This letter corrects a typographical error introduced into the Technical Specifications (TS) for the Nuclear Ship SAVANNAH (NSS). License number NS-1, during U.S. Nuclear Regulatory Commission (NRC) approval of an Amendment revising the NSS TS.

On June 18, 2018, (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML18109A578) NRC approved Amendment 16 to the NSS TS to modify section 3.7.1 to establish controls for all accesses to the Containment Vessel (CV) in support of two structural modifications to provide restored access via the C Deck and new access via the D Deck. These changes were requested, noticed and evaluated before being approved on June 18, 2018. The structural modifications have since been completed and access controls provided in accordance with the approved revised TS.

Subsequently, on June 11, 2019, (ADAMS Accession No. ML19085A482) NRC approved Amendment 17 of the NSS TS to revise the radioactive effluent controls to incorporate a Process Control Program, an Offsite Dose Calculation Manual, a Radioactive Effluent Controls Program and a Radiological Environmental Monitoring Program. As part of this approval action, the TS were reissued in their entirety for improved readability. However, when the TS was reissued, the TS erroneously excluded the approved changes made in Amendment 16. This exclusion was not requested, noticed or reviewed as part of Amendment 17. Therefore, this error meets criteria for amendment correction as a typographical error as described in the Office of Nuclear Reactor (NRR) Office Instruction LIC-101, Revision 4 (ADAMS Accession No. ML113200053), and the criteria in the January 16, 1997 NRR memo on License Amendment Corrections of Technical Specifications (ADAMS ML103260096).

The NRC staff has prepared and reviewed corrected pages to Amendment 17 of the NS-1 TS, which are provided in Enclosure 1.

E. Koehler In accordance with the Title 10 Code of Federal Regulation (10 CFR) 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.

If you have any questions, please contact me at 301-415-3017, or via e-mail at theodore.smith@nrc.gov.

Sincerely, Theodore B. Smith, Project Manager Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards Docket Nos. 50-238

Enclosure:

Corrected Pages 9 and 10 of Amendment No. 17 to the NS-1 Technical Specifications

ML19310F001

• Via Email OFFICE DUWP DUWP DUWP OGC/NLO DUWP DUWP NAME TSmith CHolston* BWatson* AGendelman* BWatson* TSmith*

DATE 11/5/2019 11/6/2019 11/7/2019 11/19/2019 11/20/2019 11/20/2019 ENCLOSURE CORRECTED PAGES 9 AND 10 OF TECHNICAL SPECFICATIONS AMENDMENT NO. 17 TO LICENSE NO. NS-1 UNITED STATES MARITIME ADMINISTRATION NUCLEAR SHIP SAVANNAH DOCKET NO. 50-238

CORRECTION TO LICENSE AMENDMENT NO. 17 TO FACILITY OPERATING LICENSE NO. NS-1 DOCKET NO. 50-238 Replace the following page of the Technical Specifications with the attached revised page.

Revised pages are identified by amendment number and contains marginal lines indicating the area of change.

Technical Specifications Remove Insert 9-10 9-10

3.6.4 These reviews may be accomplished and concurred with by members of the Committee without a formal meeting.

3.6.5 The Committee shall be convened by the Chairman and shall meet annually to review and discuss events of the preceding period. The Committee will meet when necessary to review evaluations of Reportable Events per Technical Specification 3.4.3.1.

3.6.6 Written minutes of all meetings shall be prepared and distributed to all Committee members.

3.7 Ship Access Control and Surveillance Applicability Applies to routine access control and surveillance of the ship.

Objective To prevent unauthorized entry into Radiological Controlled Areas by manning or securing their entrances and to determine change in radiation levels or integrity of the ship. An entrance is secured by bolting, welding, locking via a chain and/or hasp, or preventing access via an equivalent method.

3.7.1 Access Control 3.7.1.1 All containment vessel entrances shall be either manned or secured.

3.7.1.2 All Radiological Controlled Areas entrances will be manned or secured.

3.7.1.3 All Radiological Controlled Area entrances will be posted with appropriate caution and warning signs.

3.7.1.4 All entrances to the ship not in use will be secured at all times.

3.7.1.5 The B Deck Reactor Compartment entrance at Frame 122, the C Deck Door to the Cold Chemistry Laboratory and the D Deck Containment Vessel Door shall be either:

a) Manned or b) Locked from the outside and fitted with an intrusion alarm that alerts a security monitoring station.

3.7.1.6 MARAD trained personnel will patrol the vessel at least once during a twenty-four (24) hour period.

3.7.1.7 Deviations from the above access control conditions will be in accordance with appropriate parts of Section 3 of these Technical Specifications, Administrative Controls.

3.7.2 Surveillance 3.7.2.1 Periodically and at least once a quarter, MARAD's designated personnel will inspect the Radiological Controlled Area entrances to verify they are properly secured and test the intrusion alarm in Technical Specification 3.7.1.5.

Amendment 17 (Corrected)

November 20, 2019

3.7.2.2 Radiological surveys of the ship will be performed at least annually and as necessary to support ship activities in accordance with 10 CFR 20.

3.7.2.3 DELETED.

3.7.2.4 DELETED.

3.7.3 Vessel and System Maintenance 3.7.3.1 Two draft level stripes will be painted fore and aft (at the draft marks), one will be just above the water level and the upper stripe will be one foot above the lower. These will be observed daily to check if the draft has increased. Both stripes must always be visible. If the lower stripe is not visible, the ship shall be surveyed and the water leakage located. The source of leakage will be determined, the ship pumped out, and repairs made as may be required, including dry-docking if determined necessary, in order to assure that the integrity of the hull is maintained.

3.7.3.2 A cathodic protection system will be provided and properly maintained to protect the underwater areas of the vessel's hull to minimize corrosion damage to the hull.

3.7.3.3 An underwater inspection of the hull will be conducted at least every four (4) years. The vessel will be dry-docked if the inspection determines that such action is necessary due to localized severe pitting, underwater plate thinning in excess of 40 percent, or other damage that would require corrective action and/or removal of the vessel to an off-site ship repair facility.

3.7.3.4 An inspection will be conducted at least annually by MARAD's designated personnel to determine any degradation of the primary, auxiliary and secondary systems.

Amendment 17 (Corrected)

November 20, 2019