ML19262C605
| ML19262C605 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/04/1980 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19262C604 | List: |
| References | |
| TASK-09-01, TASK-9-1, TASK-RR NUDOCS 8002140665 | |
| Download: ML19262C605 (11) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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DAIRYLAND POWER COOPERATIVE DOCKET WO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.18 License No. DPR-45 1.
lhe Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated April 20, 1978, as supported by letters dated June 7, July 11, August 7, September 25, October 4, October 26, November 20 and November 29, 1478; January 4, January 31, February 14, March 1, May 17, June 26, July 11 and August 6,1979, complies with the stand-ards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules ar.d regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conpliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, pursuant to the Atomic Safety and Licensing Board's Initial Decision dated January 10,1980,as modified January 17, 1980, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Provisional Operating License No. DPR-45 is hereby amended to read as follows:
80Od
. (2)
Technical Specifications The Technical Specifications contained in Appendix A issued October 21, 1969, with Authorization No. DPRA-6, as revised through Amendment No.
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Replace the existing Paragraphs 2.B(2), 2.B(3)a-f, and 2.B(4) of Provisional Operating License No. DPR-45 with tiie following Paragraphs ?.B(2) through 2.B(6)* to reau as follows:
2.B(2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; 2.B(3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; 2.B(4)
Pursuant to the Act and 10 CFR Part 30, to receive, possess and use at any time:
(a) 100 millicuries each of any byproduct material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated radioactively contaminated apparatus and (b) up to 10 curies of Cesium-137 in the form of a sealed source for instrument calibration; 2.B(5)
Pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated radio-actively contaminated apparatus.
2.B(6) Pursuant to the Act and 10 CFR Parts 30 and 70, to receive, possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.**
For ease of reference, enclosed is a revised page 3 to License No. DPR-45 This paragraph has merely been renumbered from (4) to (6), in-addition, the last word in the paragraph has been changed from reactor to facility
. 4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0411SS10N Richard H. Yo11mer, Acting Assistant Director Systematic Evaluation Program Division of Operating Reactors
Attachment:
1.
Changes to the Technical Specifications 2.
New page 3 to License No.
DPR-45 Date of Issuance:
February 4, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 18 LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 Revise Appendix A by replacing the following pages with the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Pages 22 29a 37 37m(1)*
37m(2)*
37m(3)*
New pages approved in conjunction with flexible materials provisions, which are not within the purview cf the ASLB's Decision, but supported by our evaluation contained in the transmittal letter for this amendment.
. 2.11.2.5.
Removal of all other potentially radioactive gaseous waste and ventilation discharge from the restricted area shall be by monitored release through the stack.
air flow of 35,000 ft} be two stack blowers, each capable of discharging a minimum 2.11.2.6.
There shal per min. through a 350 ft high stack.
2.11.3 Solid Wastes Solid radioactive waste shall be collected, packaged in suitable containers, and shipped offsite for disposal.
2.12 FUEL STORAGE AND HANDLING 2.12.1 A fuel handling system shall be provided which is capable of remotely installing or removing fuel assemblies, one at a time, from the reactor core.
2.12.2 New fuel storage shall be provided in the new fuel storage racks located in pits in the biological shield. The pits shall have draining provisions and shall nonnally be covered within a sealed closure. The effective multiplication factor (Keff) for the new fuel storage racks, if the pits were flooded while filled with new fuel, shall be less than 0.95.
2.12.3 Spent fuel storage shall be provided in the spent fuel storage racks located at the bottom of the storage well within the containment vessel. The spent fuel storage racks are designed and shall be maintained with a nominal 7.0 inch center-to-center distance between fuel assemblies in each individual rack assembly and with a boron containing poison slab between each storage location to ensure Keff of < 0.95 when flooded with unborated water.
Fuel stored in the storage well shall be restricted to fuel with stainless steel cladding and it shall have a U-235 loading of $22.6 grams Der axial centimeter.
2.12.4 Water in the storagu nell shall be maintained at a temperature not exceeding 150 F by a storage well cooling system.
2.12.5 The fuel storage well water level shall be at least 16 feet
- above any fuel stored in the spent fuel storage racks.
- During core refueling operations, with the transfer canal flooded to allow movement of irradiated fuel elements from the reactor vessel to the FESW, the depth of water above the spent fuel stored in the upper level of the storage rack is about 23 feet.
During a typical refueling, the flooded conditions exists for three to four weeks and the radioactivity decontamination factor of the water is 100 in accordance with Reg. Guide 1.25.
Beyond this period the iodine decay offsets the reduced decontamination factor that results when the water level is restored to a depth of 16 feet above the stored fuel elements.
AmendmentNo.I,13
- 29a -
4.2.1.9 The containment building shall be isolated whenever the spent fuel storage well contains irradiated fuel which has decayed less than 43* days after l
exposure in a critical reactor and a shipping cask for irradiated fuel is being moved by the crane on the 701 foot level or located within one cask length of the top of the spent fuel storage well or is within the spent fuel storage well.
During cask movement near or at the FESW the water level in the FESW must be at least 16 f t above the top of the fuel storage rack (no more than 7 feet below the top of the FESW).
- 43 days for off loading less than one half of the core, i.e. less than 36 fuel el ements.
51 days for off loading more than 36 fuel elements.
Amendment No. /,18
4.2.8 Spent Fuel Storage and Handling 4.2.8.1 Fuel elements and control rods shall be inserted or removed from the reactor vessel one at a time.
4.2.8.2 Irradiated fuel elements shall be stored underwater in spent fuel storage racks that are positioned on the bottom of the spent fuel storage well, or in an approved shipping cask.
4.2.8.3 During the handling of irradiated fuel elements that have been operated at power levels greater than 1 Mwt the depth of water in the reactor upper cavity and/or the spent fuel storage well shall be at least 2 ft above the active fuel.
4.2.8.4 Irradiated fuel elements shall have decayed for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to placing them in the spent fuel storage well.
4.2.8.5 With the exception of a spent fuel shipping cask, the core spray bundle, the transfer canal shield plug and the other components and fixtures that are nonnally located and used within the spent fuel storage well, no objects heavier than a fuel assembly shall be handled over the spent fuel storage well.
Ancndment No. }d, 18
37m(l)
PLANT SYSTEMS 4/5.2.20 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 4.2.20 Each sealed source containing radioactive. material either in excess of 100 microcuries of beta and/or gamma emitting materials or 5 microcuries of alpha emitting material shall be free ofE 0.005 microcuries of removable contamination.
APPLICABILITY:
At all times.
ACTION:
a.
Each sealed source with removable contamination in excess of the above limits shall be immediately with-drawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations.
SURVEILLANCE REQUIREMENTS 5.2.20.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
5.2.20.2 Test Frequencies - Each category of sealed sources, ex-cluding startup sources and fission detectors previously subjected to core flux, shall be tested at the frequency described below,
- a. _ Sources in use - At least once per six months for all sealed sources containing radioactive materials; LACBWR Amendment No. 18
37' (;2) m PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
With a half-life greater than 30 days, excluding Hydrogen 3, and 2.
In any form other than gas.
b.
Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
c.
Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or mainten-ance to the source.
5.2.20.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of > 0.005 microcuries of removable contamin-ation.
LACBWR Amendment flo. 18
37m(3)
PLANT SYSTEMS EULSES 4/5.2.20 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Scaled sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
LACBWR Amendment No. la
3-(1)
Pursuant to Section 104b of the Act and 10 CFR Part 50 -
" Licensing of Production and Utilization Facilities",
to possess, use, and operate the facility at the location designated in the application in accordance with the pro-cedures and limitations described in the application and in this license; (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act'and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR part 30, to receive, possess and use at any time:
(a) 100 millicuries each of any byproduct material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated radioactively contaminated apparatus and (b) up to 10 curies of Cesium-137 in the form of a sealed source for instrument calibration; (5)
Pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated radio -
actively contaminated apparatus.
(6)
Pursuant to the Act and 10 CFR Parts 30 and 70, to receive, possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.
9 toendment No. 18