ML20238A662
| ML20238A662 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 08/28/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20238A649 | List: |
| References | |
| R-067-A-039, R-67-A-39, NUDOCS 8709090381 | |
| Download: ML20238A662 (11) | |
Text
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uq'o. UNITED STATES
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GA TECHNOLOGIES,'INC.
DOCKET NO. 50-163 MARK F REACTOR AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. R-67
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment filed by GA Technologies, Inc. (the licensee),datedMay 20, 1986, as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations as set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (1),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 compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; 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; and F. Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a licenseofthetypedescribedin10CFRSection2.106(a)(2). ;
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- 2. Accordingly,:the license is amended by changes to the Technical
' Specifications, as indicated in the enclosure to this license amendment, and paragraph 2.C.2. of License No. R-67-is hereby amended to read as _
, follows:
Technical Specifications The Technical Specifications contained in Appendix A,.as' revised through Amendment No. 39, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3._ This license amendment is effective upon its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
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Lester S. Rubenstein, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifi_ cations Changes Date of Issuance: .
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i ENCLOSURE TO LICENSE AMENDMENT NO. 39 FACILITY'0PERATING LICENSE NO. R-67 DOCKET NO. 50-163' Replace the following pages of the Appendix A Technical Specifications with .
the enclosed pages. The revised pages are identified by amendment number and contain vertical lines. indicating.the areas of change.
, Remove Page. Insert Page 4 4
.4(a) 4(a) 4(b) 5 5 5(a) 5(a) 5(b) 5(b) 9 9 9(a)
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-(a) StandNd cores shall be assemblies wherein all fuel li;
' ~e lements are standard fuel elements.
L .(b) ,Special cores:shall be all-cores which are not standard Cores.
-5,2 . Standard fuel elements shall have the characteristics listed below:
5.2.1 Standard low-enrichment fuel L(a) Maximum uranium-content in unirradiated fuel :9.0 wt%.
(b)- Maximum uranium enrichment in unirradiated fuel <20% l.
(c) -Hydrogen-to-zirconium ratio 0.9 to 1.54 H atoms to (in the ZrHn )' 1.0 Zr atom (low hydride) .
1.55 to 1.8 H atoms to 1.0 Zr atom (high hydride)
(d) Cladding material and 0.020 inch 304 Lor 304L minimum thickness stainless steel, Incoloy 800, Haste 11oy-X, or 0.030 inch-aluminum or Zircaloy 5.2.2 Standard FLIP fuel (a) Maximum uranium content in unirradiated fuel 9.0 wt%.
(b) Nominal uranium enrichment in unirradiated fuel 70%
f (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to (in the ZrHn ) 1.0 Zr atoms.
(d)~ Natural erbium content 1.0 to 1.8 wt%
(homogeneous distribution)
(e) Cladding material and 0.020 inch 304 or 304L minimum thickness stainless steel, Incoloy 800, or Haste 11oy-X 5.2.3 Standard low-enrichment fuel with high wt% uranium (a) Maximum uranium content in unirradiated fuel 30 wt%
(b) Maximum uranium enrichment in unirradiated fuel <20%
(c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to (in the ZrHn ) 1.0 Zr atoms Amendment No. 39
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- 4(a) - 4 (d) Natural erbium content (homogeneous distribution) 0.4 to 1.8 wt%*
(e) Cladding material and 0.020 inch 304 or 304L minimum thickness stainless steel, Incoloy 800, or Hastelloy-X 5.3 Special fuel elements shall be uranium zirconium hydride fuel elements, which are not standard fuel elements, having the charac-teristics listed below.
5.3.1 Special fuel elements with high-enrichment uranium (a) Maximum uranium content in unirradiated fuel 12.0 wt%
(b) Maximum uranium enrichment in unirradiated fuel 95%
(c) Cladding material and 0.020 inch 304 or 304L minimum thickness stainless steel, Incoloy 800 or Haste 11oy-X or 0.030 inch Zircaloy (d) Construction shall be such that calculated clad temperature shall not exceed 500 C at the planned operating level.
5.3.2 Special fuel elements with high wt% uranium.
(a) Uranium content in unirradiated fuel >30.0 to 45.0 wt%
(b) Maximum uranium enrichment in unirradiated fuel <20%
(c) Cladding material and minimum 0.020 inch 304 or 304L thickness stainless steel, Incoloy 800 or Haste 11oy-X or 0.030 inch Zircaloy for 1.5 inch nominal diameter, or 0.015 inch to 0.020 inch stainless steel, Incoloy 800 or Hastelloy-X for 0.5 inch nominal diameter.
- Scaled according to maximum U-235 content such that a core containing only these elements would require a critical loading of > 50 fuel elements.
Amendment No. 39
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-4(b) -
a (d) 1 Construction shall be such;that the' calculated clad temperature-shall not exceed 500"C at planned operating level.
(e) .Special fuel. elements with 0.5 inch nominal diameter shall be
. enclosed in a 0.020 inch metal shroud. The shroud, constructed from one of the above: listed cladding materials, shall have a
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nominal diameter of 1.5. inches.
5.4L Any burnable poison'used'shall be'an' integral part of the as-manufactured fuel. element. A burnableLpoison is defined as a '
. material used for the specific purpose of compensating for fuel burn-up and/or other long-term reactivity adjustments, i
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.i Amendment No. 39
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m 5.5 ' Fuel Element Inspection 5.5.1 Standard Fuel Elements (5.2) and Special Fuel Elements with High-Enrichment (5.3.1)
(a) All. fuel elements shall be inspected visually for damage or deterioration.at least annually, and all uninstrumented fuel elements shall be measured for length and bend at least annually. ,
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(b). Uninstrumented fuel elements shall be measured 'for length and bend after each group of power pulses as defined in 5.5.1(c) if:
(1) They are standard fuel elements (5.2.1) and are'in a core subjected to reactivity insertions in excess of 4.00$,
.(2) They are standard FLIP fuel elements (5.2.2) or standard LEU fuel elements (5.2.3) subjected'to pulsed reactivity insertions and their measured temperatures exceed the following values:
Fuel Element Location LEU (20-20) FLIP LEU (30-20)
In Compact Segment 680 C 680 C 600 C ]
i Adjacent to l One Water-Filled l Hole 580 C 500 C 425 C .
Adjacent to Two or More Adjacent Water-Filled Holes 535 C 430 C 350 C i
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(3) They are special fuel elements and are in a core subjected I to power' pulses which produced measured temperatures in ]'
excess of 700 C, as measured by a standard thermocouple, (c) Fuel elements specified.in 5.5.1(b) shall be inspected after
_each series of power pulses in accordance with the schedule .,
below. Should more than 5% of the elements be damaged as l defined in section 5.5.1(d), the frequency of inspection !
shall not decrease to the next level of the schedule until the '
level in question has been repeated without damage. When a 1 minimum of six elements of a given type have successfully )
completed the scheduled operations, that type of element shall '
be considered as proven for the purpose of annual inspection.
Amendment No. 39
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, - 5(a) -
(1) 'two groups of 25 pulses' )
(2) three groups of 50 pulses !
(3) three groups of 100 pulses
-(4) three groups of 500 pulses 3
- (5) one group of 1000 pulses j l
(d) A fuel element shall be considered'as damaged within the .;
meaning of this section:
(1) Due to transverse ben' ding, if-its sagitta exceeds 1/16 inch in a length of 28 inches. . ,
(2) Due to elongation, if its length exceeds its original length by 0.1 inch for stainless steel or equivalent clad elements or 0.5 inch for aluminum clad elements.
(3) If a clad defect exists as indicated by release of fission products.
(e) Any fuel element found to be damaged according to the above shall not be used in any further reactor operation. However, reactor operation may continue for the purpose of locating a suspected damaged fuel element.
5.5.2 Special Fuel Elements with High wt% Uranium (1.5 inch nominal l diameter)
(a) For normal operations, these fuel elemen'ts shall be I measured after each series of power cycles (>l MW) according '
to the schedule below. Should more than 5% of the elements be damaged as defined in 5.5.1(d), the frequency of inspection shall not decrease to the next level of the schedule until the level in question has been repeated without damage. When a minimum of six elements of a given type have successfully completed the' scheduled operations for 1000 cycles, that type of element shall be considered as proven for the purpose of power cycling. Proven elements will be inspected per 5.5.1(a). l (1) two groups of 100 i 25 cycles (2) two groups of 200 1 25 cycles (3) one group of 400 1 25 cycles (b) For pulsing operations, the surveillance schedule specified in Section 5.5.1(c) and the criteria for damage in Section 5.5.1(d) shall be employed.
(c) Any fuel element found to be damaged according to the above shall not be used in any further reactor operation. However.,
reactor operation may continue for the purpose of locating a suspected damaged fuel element.
5.5.3 Special Fuel Elements with High wt% Uranium (0.5 inch nominal l diameter)
(a) For normal operations, these fuel elements shall be l measured after each series of power cycles (>l MW)
Amendment No. 39
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-:5(b);-
according to the' schedule.below. Should more.than 5% of t'he elements be damaged as. defined in Section 5.5.3(c) the
. frequency of inspections shall not decrease to the next level' of the schedule until the level in question has been repeated without damage. When a minimum of six elements'of a given' type have successfully completed the scheduled operations for 1000' cycles, that type of element shall'be considered proven
- for the pLrpose of. power cycling. Proven elements will be inspected per 5.5.1(a).
(1) two groups of 300 1 25 cycles (2)' two groups'of 200 1 25 cycles
'(3)~ one group of.. 400 1 25 cycles (b) For pulsing operations the surveillance schedule specified .in Section 5.5.1(c) shall be employed.
-(c) A fuel element with 0.5 inch nominal diameter shall be considered damaged if: .;
(1) The transverse bending progresses to the point that the fuel pin touches its shroud; (2) .The elongation as measured.for noninstrumented fuel elements has increased above its original length by 0.1 inch; or (3) A~ clad defect exists as indicated by release of fission products.
(d) Any fuel element found to be damaged according to the above shall not be used in any further reactor operation. However, reactor operation may continue for the purpose of locating a suspected damaged fuel element.
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Amendment No. 39
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9.1. 2 ..The maximum available excess reactivity (cold with experiments, -
if any, in place) shall be: l (a) 7.50$ whenever the transient rod (s) are worth-3.00$ or ,
less, or 1 (b) 6.00$ whenever the transient rod (s) are worth more:than- ] .i 3.00$. i 9.2 Transient Operations 9.2.1 The maximum reactivity insertion during transient operations shall be 5.50$.
9.2.2. The maximum allowable fuel temperature using a standard thermocouple shall be:
(a) 800 C for standard low-enrichment high-hydride fuel elements, (b) 500 C for standard low-enrichment low-hydride fuel elements or- l aluminum-clad fuel elements, (c) 920 C for special fuel elements, (d) Values selected for the applicable long-lived fuel elements are as follows:
Fuel Element Location LEU (20-20) FLIP LEU (30-20)
In Compact Segment 780 C 780 C 690 C Adjacent to One Water-Filled Hole 670 C 575 C 490 C Adjacent to Two or More Adjacent Water-Filled Holes 615 C 500 C 405*C A thermocouple element shall be placed in the hottest fuel-element location next to each flux trap. A thermocouple element shall also be placed in the anticipated hottest fuel element location within the compact segment of the core unless the flux trap is located in the hottest section of the core. With no flux trap, the thermocouple element shall be located in the anticipated hottest core position.
Amendment No. 39
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9.2.3 -The: maximum reactivity worth of any transient. control rod shall be 5.50$. l
- 9. 3 - Low Power and Subcritical Reactivity Worth of Experiment's 9.3.1- Individual, experiments having a reactivity worth greater.
than.3.00$, or a combination.of experiments having:a total
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worth greater'than'.4.00$,~shall be subject to.the.following restrictions-during reactivity worth. measurements (these ,
restrictions do not apply during the calibration of control rods which are part of the reactor safety system):
(a) Reactor power shall not exceed 500 watts, (b) -Two power level scrams shall.be set to scram at no more than.1-kilowatt, (c) No other type of experiments shall be in the core, (d) The individual worth of a single movable part of an
- experiment shall not exceed 5.50$. .
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Amendment No. 39 L _ --_ - _ - - -