ML003729220

From kanterella
Jump to navigation Jump to search
License - Attachment to Order & Safety Eval
ML003729220
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/2000
From:
NRC/NRR/DLPM
To:
References
-RFPFR
Download: ML003729220 (5)
v • d • e


Text

J3( Zt im¶ YIZ( )1( *L t*( 1L S*( 't( 'X( 't( kZ )t( t' 'Iti 'IIt( Yk? Y*iZ 'Iii 'iIY TIflETi iwiir Yk( 1( 'tRt 1( 'II! tL '1( 'Ik( I( 'Ii( 'IX( 'Ik( 'IX( 'Ik( 'III' 'Itt' 'Itt Y*7 YE Ti?

NRC FORM 588 PAGE 1

_____OF _ 4

____PAGES (3-96) U.S. NUCLEAR REGULATORY COMMISSION LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Part 72, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel and other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at the place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified herein.

Licensee

1. Calvert Cliffs Nuclear Power Plant, Inc. 3. License Number SNM-2505 Amendment No. 2
2. 39 W. Lexington Street Baltimore, Maryland 21201 4. Expiration Date November 30, 2012
5. Docket or Reference No. 72-8
6. Byproduct, Source, and/or 7. Chemical and/or Physical 8. Maximum Amount that Licensee Special Nuclear Material Form May Possess at Any One Time Under This License A. Spent fuel assemblies from A. As U0 2 clad with A. 1,111.68 TeU of spent Calvert Cliffs Nuclear zirconium or zirconium fuel assemblies Station Units 1 and 2 alloys reactor using natural water for cooling and enriched not greater than 4.5 percent U-235 and associated radioactive materials related to receipt, storage, and transfer of fuel assemblies
9. Authorized Use: For use in accordance with statements, representations, and the conditions of the license application dated December21, 1989, as supplemented April 26, June 29, November 1, and December 20, 1990; February 1, February 12, September 30, October 18, December 19, and December 27, 1991; August 18, and September 4, 1992; July 29, and October 20, 1994; March 31, 1995; and February 29, April 7, April 27, May 2, May 19, and June 20, 2000.

I The material identified in 6.A and 7.A above is authorized for receipt, possession, storage, and transfer.

10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the Calvert Cliffs ISFSI located on the Calvert Cliffs Nuclear Power Plant site in Calvert County, Maryland. This site is described in Chapter 2 of the licensee's Safety Analysis Report (SAR) for the Calvert Cliffs ISFSI.
11. The Technical Specifications contained in Appendix A attached hereto are incorporated into the license. The licensee shall operate the installation in accordance with the Technical Specifications in Appendix A.

251251251251251251251)51151251251251251251251W 251251251251251251251251251)51251251 251251251)51251251)51251251251251)51251251251251 251' Printed on recycled paper

WYWW TV TV NRC FORM 588A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 4 PAGES (3-96) License Number LICENSE FOR INDEPENDENT STORAGE SNM-2505, Amendm.nt No 2 OF SPENT NUCLEAR FUEL AND Docket or Reference Number HIGH-LEVEL RADIOACTIVE WASTE 72-8 SUPPLEMENTARY SHEET

12. The licensee shall fully implement and maintain in effect all provisions of the Independent Spent Fuel Storage Installation (ISFSI) physical security, guard training and qualification, and safeguards contingency plans previously approved by the Commission and all amendments made pursuant to the authority of 10 CFR 72.56, 10 CFR 72.44(e), and 72.186. The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled: "Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation Physical Security Plan" Revision 3, submitted by letter dated December 15, 1993; "Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation Training and Qualification Plan" Revision 2, submitted by letter dated September 30, 1994; and "Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation Safeguards Contingency Plan" Revision 1, submitted by letter dated February 1, 1991.
13. The Technical Specifications for Environmental Protection contained in Appendix A attached hereto are incorporated into the license.

Specifications required pursuant to. 10 CFR 72.44(d), stating limits on the release of radioactive materials for compliance with limits of 10 CFR Part 20 and "as low as is reasonably achievable objective" for effluents are not applicable. Dry Shielded Canister (DSC) external surface contamination within the limits of Technical Specification 3.2.3.1 ensures that the off site dose will be inconsequential.

In addition, there are no normal or off-normal releases or effluents expected from the double-sealed storage canisters of the ISFSI.

Specifications required pursuant to 10 CFR 72.44(d)(i) for operating procedures, for control of effluents, and for the maintenance and use of equipment in radioactive waste treatment systems to meet the requirements of 10 CFR 72.104 are not applicable. There are, by the design of the sealed storage canisters at the ISFSI, no effluent releases. Also, all Calvert Cliffs site DSC and Transfer Cask (TC) loading and unloading operations and waste treatment therefrom will occur at the Calvert Cliffs Nuclear Power Plant under the specifications of its operating licenses.

14. No spent nuclear fuel shall be allowed to be loaded until such time as the following preoperational license conditions are satisfied:

A. A training exercise (dry run) of all DSC, TC, and horizontal storage module (HSM) loading and handling activities shall be held and include but not be limited to, those listed below and need not be performed in the order listed:

1. Loading DSC in cask.
2. DSC (length may be truncated) drying, welding, and cover gas backfilling operations.
3. Moving cask to and aligning and docking with HSM on the storage pad.
4. Insertion of DSC in HSM.
5. Withdrawal of DSC from HSM.
6. Returning the cask to the decontamination pit.

,Iwww_ - - I VW 'WWWT m

NRC FORM 588A (3-96)

U.S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 4 PAGES 1i License Number LICENSE FOR INDEPENDENT STORAGE SNM-2505. Amendment No- 2 Docket or Reference Number OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE 72-8 SUPPLEMENTARY SHEET

7. Removing the cask lid and cutting open the DSC (length may be truncated) assuming fuel cladding failure.
8. Removing the DSC from the cask.
9. All dry run activities shall be done using written procedures.
10. The activities listed above shall be performed to show that each activity can be successfully executed: prior to actual fuel loading.

B. The Calvert Cliffs Nuclear Power Plant Emergency Plan shall be reviewed and modified as required to include the ISFSI.

C. A training module shallbe developed for the Calvert Cliffs Nuclear Power Plant Training an Program establishing *SFSI Training and Certification Program which will include the following:

1. DSO, TC, and HSM Design (overview)
2. ISESI Facility Design (overview)
3. ISF** Safety Analysis (overview)
4. Fuel loading and DSC, and TC handling procedures and abnormal procedures
5. ISFSI License (overview).

D. The Calvert Cliffs Nuclear Power Plant health physics procedures shall be reviewed and modified as required to include the, ISFSI.

E. The Calvert Cliffs Nuclear Power Plant Administrative Procedures shall be reviewed and modified as required to include the ISFSI.

F. A procedure shall be developed and implemented for the documentation of the characterizations performed to select spent fuel to be stored in the cani.sters and modules.

Such procedure shall include independent verification of fuel assembly selection by an individual other than the original individual making the selection.

G. A procedure shall be developed and implemented for two independent determinations (two samples analyzed by different individuals) of the boron concentration in the water used to fill the DSC cavity for fuel loading and unloading activities.

H. Written procedures shall be implemented to describe actions to be taken during operation and abnormal/emergency conditions.

mr my mr yr yr Tryrmy Sr my yr my V., my Sr Sr S 57 S7 57

  • V7 '7 ThY 'tt t/ ThY Xtt V*t t( NW?'SW?itt NW?

)*4( M1 Jif - i NRC FORM 588A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 4 PAGES (3-96) License Number SNM-2505, Amendment No. 2 LICENSE FOR INDEPENDENT STORAGE

. OF SPENT NUCLEAR FUEL AND Docket or Reference Number HIGH-LEVEL RADIOACTIVE WASTE 72-8 SUPPLEMENTARY SHEET

15. The design, construction, and operation of the ISFSI shall be accomplished in accordance with the NRC regulations specified in Title 10 of the U.S. Code of Federal Regulations. All commitments to the applicable NRC Regulatory Guides and to engineering and construction codes shall be carried out.
16. The double closure seal welds at the bottom end of the DSC shall satisfy the Liquid Penetrant Acceptance Standards of ASME B&PV Code Section III, Division 1, Subsection NB-5350 (1983).

Additionally, these seal welds at the bottom of the DSC shall be leak tested in accordance with ANSI N14.5 (1987). The leakage rate shall be quantified and shall not exceed the leak rate specified in Technical Specification 3.2.2.2 of Appendix A (i.e., standard helium leak rate shall not exceed 10-4 atm-cc/s). i

17. Fuel and TC movement and handling activities which are to be performed in the Calvert Cliffs Nuclear Power Plant Auxiliary Building will be governed by the requirements of the Calvert Cliffs Nuclear Power Plant Facility Operating Licenses (DRP-53 and -69) and associated Technical Specifications.
18. Pursuant to 10 CFR 72.7, the licensee is hereby exempted from the provisions of 10 CFR 72.122(i) with respect to providing instrumentation and control systems for the DSC and HSM during storage operations.
19. This license is effective as of the date of issuance shown below.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION E. William Brach, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date of Issuance: November 30, 1992 Amendment No. 2 dated June 30, 2000

Attachment:

Technical Specifications

-1V1 v VUI9 M-9 '14S 9' i V2 V 9414M M14ý)S)Ak

6.0 ADMINISTRATIVE CONTROLS 6.1 GENERAL The Calvert Cliffs ISFSI is located on the Calvert Cliffs Nuclear Power Plant site and will be managed and operated by the Calvert Cliffs Nuclear Power Plant, Inc., staff. The administrative controls shall be in accordance with the requirements of the Calvert Cliffs Nuclear Power Plant Facility Operating Licenses (DPR-53, and -69) and associated Technical Specifications as appropriate.

6.2 ENVIRONMENTAL MONITORING PROGRAM The licensee shall include the Calvert Cliffs ISFSI in the environmental monitoring for Calvert Cliffs Nuclear Power Plant. An environmental monitoring program is required pursuant to 10 CFR 72.44(d)(2).

6.3 ANNUAL ENVIRONMENTAL REPORT The semi-annual radioactive effluent release reports under 10 CFR 50.36(a)(2) license requirements for the Calvert Cliffs Nuclear Power Plant shall also specify the quantity, if any, of each of the principal radionuclides released to the environment in liquid and gaseous effluents during the ISFSI operation and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases. Copies of these reposts shall be submitted to the NRC Region I office and to the Director, Office of Nuclear Material Safety and Safeguards. The report under this specification is required pursuant to 10 CFR 72.44(d)(3).

6-1 Amendment 2

Retrieved from "https://kanterella.com/w/index.php?title=ML003729220&oldid=2716605"