ML19345E433
| ML19345E433 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/12/1968 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345E432 | List: |
| References | |
| NUDOCS 8101190236 | |
| Download: ML19345E433 (8) | |
Text
[7 *+,
UNITED STATES ATOMIC ENERGY COMMISSION
- d WASHINGTON. D.C.
20545
% m,',,' o CONSUMERS PCWER COMPANY DOCKET NO. 50-155 AMDIDMENT 10 OPERATING LICENSE License 16. DPR-6 Amendment No. 1 The Atomic Energy Conmission having found that:
a.
The app ication for amendment dated &y 26, 1967, as supplemented my 29, August 15, Ibvember 10, and December 14, 1967, complies with the mquire-nents of the Atomic Energy Act of 1954, as amended, and the Commission's regulations set forth in Title 10, Chapter 1, CFR; b.
There is reasonable assumnce (i) that the mactor can be operated in accordance with the license, as amnded, without endangering the health and safety of the public, and (ii) that stch activities will be conducted in compliance with the rules and regulations of the Commission; The i~ suance of this amendment will not be inimical to the camton defense s
c.
and security or to the health and safety of the public; Operating License No. DPR-6, as anended, issued to Consumers Power Company fcr operation of its Big Rock Point Nuclear Plant ("the reactor") located in Charlevoix County, Michigan, is hereby further amended by adding the following subparagraph to Paragraph 3.B.
"The Technical Specifications contained in Appendix A are nodified by Attachment A, appended hereto (designated as Change No. 13), to permit power operation of the reactor with six (6) high perfornance develop-nental fuel bundles in accordance with the application for amendment dated May 26, 1967 and supplements thereto."
This amendment is effective as of the date of issuance.
EUR THE ATOMIC ENERGY COMMISSION Peter A. Ibrris, Director Division of Reactor Licensing Attachnent:
Change No. 13 to Appendix A Date of Issuance: March 12,1968 7/D//f6A34-
l 1
ATTNEimT A 'IO AMENDMENT.NO.1 CONSUMERS POWER (X)MPANY LICENSE NO. DPR-6 WANGE NO.13 'IO APPENDIX A DATE: March 12, 1968 r
1.
Delete paragraph 1 of section 5.1.5(c) in its entirety and replace with the following.
"'Ihe generel dimensions and configuration of the types of fuel bundles shall be as shown in Figures 5.2, 5.3, 5.4, 5.5, 5.6 and 8.1 of these specifications. Principal design features shall be essentially as follows:"
2.
Add Figures 5.5 and 5.6 (8 x 8 and 7 x 7 Fuel Drawings).
3.
Add a column to the table in Section 5.1.5(c) as follows:
/
Developmental Intermedi&te Advanced Generel Performance Performance Geometry, Wel Pod Array 8x8 7x7 Rod Pitch, Inches 0.807 0.921 Standard Fuel Rods per Bundle 36 29 Special N el Rods per Bundle 28***
20***
Spacers per Bundle 5
5 Material - Cladding Zr-2 Zr-2 Standard Rod 'Ibbe Wall, Inches 0.035 0.040 i
Special Rod Tube Wall, Inches 0.035 0.040 I
- Special reds have depleted uranium.
8
. Developmental
~
Intermediate Advanced f
' General Performance Performance Standard Rod Diameter, Inches 0.570-0.700 Special Rod Diameter, Inches 0.570 O.700 00 Density, Pert:ent Theomtical 94 Pellet 94 Pellet 2
85 Powder 85 Powder Active Nel length, Inches 66-67.3 65-66.3 Fill Gas Helium Helium" 4.
Add a new section as follcus:
5.1.9 Centermelt Test Nel Bundles a.
Operating Limitations Six fuel bundles may be opemted at increased thermal output with various anour.ts of center melting of the U0. The fuel shall 2
be specially designed for this opemtion and shall be permitted to exceed the geneml core operating limitations of Section 5.2.1 (b) but shall be
/
limited to the most conservative of the following values:
Nel Type Intermediate Advanced Performance Performance Number of Bundles Pellet U0 1
2 2
Powder UO 1
2 2
MaximumSteadySgateHeat Flux, BTU /hr-Ft 500,000 500,000 Maximum Steady State Fuel Rod Power, Kw/Ft 21.8 26.8 Mininum Core Burnout Ratio at Overpower of 1.22 1.5*
1.5*
- Based upon Critical Heat Flux Correlation, APED-5286.
b.
Rate of power level change Control rod withdrawal shall be limited as in Section 5.2.1.
In addition, when centermelt fuel is in the core, the rute of power ir> crease between 170 Nt and 240 Nt shall be limited to 1/2 Nt average per minute per notch of control rod withdrawal when any of the following conditions exist: (1) a centermelt fuel bundle is being brought to power for the first time, or (2) a scram recovery is being made at a time in the xenon transient when the peak of the axial power distribution is lower in the core than the peak existing at the time of the last shutdown.
c.
F_uel Exarrinations Non--destructive examinations of each fuel rod in the centermelt fuel bundles shall be perforned during each core refueling period. Any rods displaying unexpected increases in diameter shall not be returned to the core.
f Selected fuel rods shall be renoved during each refueling period for destructive examinations. When the first rods are renoved for destructive examination at about 15% expected lifetime, the 4 advanced performance bundles shall be renoved from the core. 'Ihese assemblies shall not be returned to the core until the results of the de.structive examinations have been evaluated and it is confirmed that'the design performance of the fuel has been met and continued irradiation can be safely accomplished.
1 1
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g.
l d.
Supplemental (bre Cooling During irradiation of centemelt fuel bundles, a supplemental system for core cooling shall be provided. This system shall provide a means of introducing fire water into the reactor pressure vessel independent of the core spmy system.
5.
Revise paragreph 1 of Section 4.2.6 on Fire Protection System to read as follows:
In addition to furnishing water for conventional plant firefighting equipment, the fire protection system shall furnish water as follows:
Core S~pmy Cooling System, Alternate method of core cooling by flooding the reactor pressure vessel, Containment Sphere Post-Incident Spmy System, and Backup Service Water System to the Oantainment Sphere.
f 6.
Add a new section as follows:
7.2.4 Administmtive and Procedural Controls Relating to High Perfornance Ibel In addition to normal opemting procedures, the following additional pre-cautions shall be observed during irradiation of the centennelt fuel assemblies -
a.
In the event of suspected coolant system leaks, reactor power will be inanediately reduced to pemit entry for inspection purposes and an evaltation of the suspected leak will be made. If the evaluation reveals leakage in the primary cooling system, the reactor shall be shut down immediately, except when it has been established that the leaks are in valves, packing or punps where some leakage can be tolerated.
)
--e
e b.
The Plant Superintendent or Assistant Plant Superintendent shall be notified inrediately of all reactor scrums and shall approve subsequent startups.
Startup of the reactor following a scram shall not proceed until the cause of the scram has been determined and the necessary corrective action taken. The evaluation and approval of the Consumers Power Company Geneml Office shall be required for all startups following an unexplained scrum.
c.
Technical specialists on site:
(1) The General Electric Cbmpany shall have a physicist familiar with
/
the Big Fock Plant present at the facility for each initial startup following refueling. He shall be present during the initial approach to criticality and shall remain until at least 10 percent of rated power is reached.
f (2) Consumers Power Cbmpany shall have a Reactor Engireer or his designated alternate who shall be a licensed senior operator in the control room for all startups, special tests or significant power changes.
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