ML20031C257
| ML20031C257 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/23/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031C254 | List: |
| References | |
| NUDOCS 8110060672 | |
| Download: ML20031C257 (5) | |
Text
.
,8 UNITED STATES e*%
- 4 NUCLEAR REGULATORY COMMISslON 3.l f ),h WASHINGTON. D. C. 20555 g
5.
l CONSUMERS POWER COMPANY DOCKET N0. 50-155 BIG ROCK POINT NUCLEAR PLANT
,AMENDMEtlT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated January 26, 1979, complies with the star.dards and requirements of the Atonic Energy Act of 1954, as amended (the Act), and the Commission'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 and regulations of the Commission; 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 cor. ducted in compliance with the Commission's regulations; 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
81'10060672 790323 T PDR ADOCK 05000155l P
~
. 2.
Accordingly, 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 Facility Operating License No. DPR-6 is hereby amended to read as follows:
(2) Technical _Sz cifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24, are hereby incorporated in the license.
The licensee shall-operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION S'Q
/%]2mu.k V 2- > n Dennis L. Ziemannl! Chief Operating Reactors Branch 82 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 23,1979 5
- ATTACHMENT TO LICENSE AMENDMENT 'NO. 24 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing page 5-1 and inserting the enclosed page_5-1.
The revised page. includes the captioned amendment number and contains a vertical line indicating the area of change.
1 f
a
-- y-50 REACTOR CORE AND CONTROLS The reactor core and controls shall consist of all the co=ponents of the reactor core including the reactor reactitity control system and the liq-uid poison system. The expected configuratien of the core is shown in Figure 5 1.
51 DESIGN FEATJRES The dimensions for these design features are for the cold con-dition and are subject to nor=al =anufacturing tolerances.
5.1.1 Principal Core Materials Fuel (Sintered Pellets or UO r UO -PuO 2
2 2
Co= pressed Powder)
Moderator and Reflector Light Water Structural Components (Fuel Cladding Will, in Addition to 30h SS ard Incaloy-800, Include Zr-2, Incenc.1-600 and Zr-3Nb-lSn)
Flow Channels Zircalcy 2 and 304 SS Control Rods - Either 3 C Filled 30k SS Tubes and Solid 30k SS 3
Rods or B c Filled 30L SS Tubes With 304 SS Tubes in crucifor=-
h Shaped 304 SS Sheaths 5.1.2 Control Red Asse=blies The reactor core shall contain 32 control rod assemblies each cr n-sisting of a crucifor= array of e=pty or solid stainless steel tubes and stainless steel tubes containing approximately 68 inches of boren carbide, 3 C, powder surrounded by a crucifor=-
4 shaped stainless steel sheath.
Change Nos f, 77, 7S, 7E Amendment No. 24 5-1
~
5.1.3 Control Rod Drives The core shall be controlled by 32 control rods with a patch of approximately 10.466 inches, which shall be moved vertically within the core by 32 hydraulically operated drives. The hydraulic pressure for positioning the drives during normal rod movement shall be supplied by one of two positive displacement pumps, which shall discharge into the hydraulic system at about 200 psi above reactor pressure (Pr +200) for normal control movement.
The drive mechanism used for both nomal operation and scram shall be of the locking piston design. Only one rod at a time can be withdrawn from the core.
Rods may be inserted into the core singly or all may be scranrned together. To scram a control rod, high pressure water from one or two independent sources shall be apolied to the underside of the piston and water from the top side of the piston shall flor to the scram dump tank. The two independent sources of scram hydraulic pressure l
shall be:
5-4 Change No. 25, Amendment No. 24
.