ML19345E441
| ML19345E441 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/30/1968 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345E439 | List: |
| References | |
| NUDOCS 8101190303 | |
| Download: ML19345E441 (13) | |
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h UNITED STATES ATOMIC ENERGY C0tEISSION DOCKET NO. 50-155 CONSUMERS POWER COMPAfE j
NOTICE OF PROPOSED ISSUANCE OF AMENDMDJT TO OPERATING LICENSE The Atomic Energy Comission is considering the issuance of an amndment to Opemting License' No. DPR-0 which authorizes the Consumers Ner Company to operate its Big Rock Pbint Nuclear Plant ("the reactor") located in Charlevoix County, Michigan. The amendment, set forth below, would modify the Technical Specifications appended to the license to pemit pcwer operation of the reactor with six' (6) high perfomance developmental fuel bundles in f
accordance with the application dated May 26, 1967, and supplements thereto dated May 29, August 15, November 10, and December 14, 1967.
Prior to the issuance of the amrxinent, the facility will be inspected by representatives of the Comission to detemine that the nodifications to the i
facility to assure pmmpt delivery of water fror. the fire pmtection system to the reactor. pressure vessel, in the event of rupture of the core spray 'line, have been completed.
Within thirty (30) days from the date of publication of this rotice in the j
Federal Register the applicant may file a request for a hearing, and any person whose interest may be affected by this proceeding may file a petition for leave to intervene. Requests for a hearing and petitions to intervene shall be filed in accordance with the Comission's " Rules of Practice",10 CFR Part 2.
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-request for a hearing or a' petition for leave to intervene is filed within the time prescribed in this' notice', the Conmission will. issue a notice of hearing or an appropriate order.
For further details with respect to this proposed amendment, see (1) the
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application dated May 26, 1967, and supplements themto, (2) the mport of the Advisory Conmittee on Reactor Safeguards dated December 20, 1967, (3) a related Safety Evaluation prepared by the Division of Reactor Licensing and (4)
Attachment A to Amendment No.1, all of which am available.for public inspection 3
at the Comrnission's Public Document Room,1717 H Street, N. W., Washington, D. C.
Copies of items (2) and'(3) above nay be obtained at the Conmission's Public Docunent Room, or upon mquest addmssed to the Atomic Energy Conmission, Washington, D. C.
20545, Attention: ' Director, Division of Reactor Licensing.
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l IOR illE ATOMIC ENERGY COMMISSION I
M M.
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Peter A. Morris, Director.-
Division of Reactor Licensing i
Dated at Bethesda, Maryland this 30th dayf of January,1968 4
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CONSUMEPS POWER COMPANY DOCKET N0. 50-=155 PROPOSED AMENDMDIT TO OPERATING LICD1SE License No. DPR-6 Amendment No. 1 Tae Atomic Energy Conmission having found that:
a.
The application for amend: rent dated May 26, 1967, as supplemented May 29, August 15, November 10, and December 14, 1967, complies with the requirenants of the Atomic Energy Act of 1954, as amended, and i
the Conmission's regulations set forth in Title 10, Dapter 1, CFR; b.
There is reasonable assurance (i) that tha reactor can be opemted in accordance with the license, as amended, without endangering the health and safety'of the public, and (ii) that such activities will
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i be conducted in compliance with the rules and regulations of the Conmission; c.
The issuance of this amendment will not be inimical to the common t
defense and security or to the health and safety of the public;.
Operating License ?b. DPR-6, as amended, issued to Consumers Power Company for opemtion~of its Big Rock Point Nuclear Plant ("the reactor") located in l
Charlevoix County, Michigan, is hereby further amended by adding the following I
subparagraph to Paragmph 3.B.
"The Technical Specifications contained in Appendix A are nodified by Attachment A, appended hereto (designated as Change Ib.13), to pemit power opemtion of the reactor with six (6) high perfonrance developmental 4
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fuel bundles in accoMance with the application for amen nent dated May 26, 1967 and supplements thereto."
This amendment is effective as of the date of issuance.
IDR THE ATOMIC D.'ERGY COM4ISSION Peter A. Fbrris, Director Division of Reactor Licensing Pate of Issuance:
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CONSUMEPS POWER COMPA?N j
DOCKET NO. 50-155
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PROPOSED AMENDMENT 'IO OPERATING LICENSE License No. DPR-6 Amendment tb. 1
'Ihe Atomic Energy Conmission having found that:
'Ihe application for amendment dated May 26, 1967, as supplemented a.
- May 29, August 15, November 10, and December 14, 1967, complies with the requirements of the Atomic Energy Act 'of 1954, as amended, and the Conmission's regulations set forth in Title 10, Chapter 1, CFR; b.
'Ihere is reasonable assurance (i) that the reactor can be opemted in accordance with the license, as amended, without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Conmission; c.
'Ihe issuance of this amendment will not be inimical to the comr:en defense and security or to the health and safety. of the public; Operating License No. DPR-6, as amended, issued to Consumers Power Company for opemtion of its Big Rock Point Nuclear Plant ("the reactor") locsted in Charlevoix County, Michigan, is hereby further amended by adding the following subparagraph to Paragraph 3.B.
"Ihe Technical Specifications contained in Appendix A are nodified by Attachment A, appended hereto (designated as Change No.13), to permit I
power operation of the reactor with six (6) high perfornance developmental H
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fuel bundles in accordance with the application for amendmeht dated May 26, 1967 and supplements thereto."
'Ihis amendment is effective as of the date of issuance.
FOR 'IHE ATOMIC DERGY CO!f!ISSION Peter A. !brris, Director Division of Reactor Licensing Date of 1ssuance:
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4.
et ATTAWMENT A 'ID
- iENDMENT NO. 1 CONSUMERS POWER COMPR N LICENSE NO. DPR-6 QMNGE NO.13 TO APPENDIX A 1.
Delete parugraph 1 of section 5.1.5(c) in its entirety and replace with the following.
"The general dimensions and configuration of the types of fuel bundles shall be.as sh wn 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 Intermediate Advanced General Perforrance Perforrance Geometry, Fuel Rod Array 8x8 7x7
-Rod Pitch, Inches 0.807 0.921 Standard Fuel Rods per Bundle 36 29 Special Ibel Rods-per Bundle 28***
20***
Spacers per Bundle 5
5
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Material -~ Cladding Zr-2 Zr-2
. Standard Rod Tube Wall, Inches 0.035 0.040 Special Rod Tube Wall, Inches 0.035 0.040
- Special rods have depleted uranium.
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. Developmental In'ermediate ~ -
Advanced General Perforence Performnce 4
Standard Fod Diameter, Inches 0.570 0.700 Special Rod Diameter, Inches 0.570 0.700 UO Density, Percent 'Iheoretical 94 Pellet 94 Pellet 2
85 Pcwder 85 Powder Active Fuel Length, Inches 66-67.3 65-66.3 Fill Gas Helium Helium" 4.
Add a new section as follows:
5.1.9.Centermelt Test Fuel Bundles a.
Operating Limitations Six fuel bundles my be opemted at increased thermal output I
with various dnounts of center melting of the U0. 'Ihe fuel shell 2
l be specially designed for this operation and shall be permitted to exceed J._
the geneml core operating limitations of Section 5.2.1 (b) but shall be limited to the most conservative of the following values:
Ebel Type Intermediate Advanced Performance Performnce I
Number of Bundles Pellet U0 1
2 2
Powder UO 1
2 2
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MaximumSteadySjateHeat
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Flux, BTU /hr Ft 500,000 500,000 Maximum Steady State Fuel Pod Power, Kw/Ft 21.8 26.8 Minimum Core Burnout Ratio at Overpcuer of 1.22 1.5*
1.5*
- Based,upon Critical Heat Flux Correlation, APF3-5286.
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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 rate of power increase between 170 Mat and 240 IOt shall be limited to 1/2 Mat average per minute per notch of cont:cl 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.
Fuel Examinations Non-destructive examinations of each fuel red in the centermelt fuel bundles shall be performed during each core refueling period. Any rods displaying unexpected increases in diameter shall not be returned to the Core.
- Selected fuel rods shall be reroved during each refueling period for destructive examinations. When the first rods are removed for i
destructive examination at about 15% expected lifetime, the 4 advanced.
performance bundles shall be renoved from the core. These assemblies shall not be returned to the core until the results of the destructive 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.
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d.
Supplemental 03re Cooling During irradiation of centernelt fuel bundles, a supple: rental system for core cooling shall be provided. This system shall provide a neans of introducing fire water into the reactor pressure vessel independent of the com spray system.
5.
Revise paragraph 1 of Section 4.2.6 on Fire Protection System to read as follows:
In addition to fumishing water for conventional plant firefighting equipment, the fire protection system shall furnish water as follows:
Core Spray Cooling System, Alternate method of core cooling by flooding the reactor pressure vessel, Containment Sphere Ibst-Incident Spray System, and Backup Service Water System to the Containment Sphere.
6.
Add a new section as follows:
7.2.4 Administrative and Procedural Controls Relating to High Perfomance Puel In addition to nomal operating procedures, the following additional pre-cautions shall be observed during irradiation of the centernelt fuel assemblies -
a.
In the event of suspected coolant system leaks, reactor power will be irrediately reduced to pemit entry for inspection purposes and an evaluation of the suspected leak will be made. If the evaluation reveals leakage in the primary cooling system, the reactor shall be shut down inrediately, except when it has been established that the leaks are in valves, packing or pumps where some leakage can be tolerated.
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'b.
'Ihe Plant Superintendent or Assistant Plant Superintende'nt shall be notified immediately of all' reactor scrams. and shall approve subsequent t
k startups.
'Startup of the reactor follwing a scram shall not proceed 7
until the cause of the scram has been determined and the necessary corrective action taken. The evaluation and approval of the Consurers
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j Power Company General Office shall be required for all startups follwing
- an unexplained semm.
- c.. Technical specialists on site:
(1) 'Ihe General Electric Gampany shall have a physicist familiar with 4
~ the Big Rock Plant present' at the facility for each initial startup following refueling. He shall be present during the initial appInach to criticality and shall remain until at least 10 percent of rated-pwer is reached.
(2) Consumers Pwer Co:rpany sh'.ll have a Reactor Engineer or his designated alternate who shall be a licensed senior operator'in the control room j
for all startups, special tests or significant pwer changes, i
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