ML20126E700
| ML20126E700 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/07/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126E694 | List: |
| References | |
| NUDOCS 8506170185 | |
| Download: ML20126E700 (4) | |
Text
' oar k,
UNITED STATES 8
p, NUCLEAR REGULATORY COMMISSION Q
'j WASHINGTON, D. C. 20555
...../
CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-6 1.
The Nuclear Regulatory Comission (the Comission) has found that: -
A.
The application for amendment by Consumers Power Company (the licensee) dated November 14, 1984, complies with the standards 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 and regulations of the Comission; 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 Comission'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 s,
51 of the Comission's regulations and all applicable requirements have been satisfied.
8506170185 850607 PDR ADOCK 05000155 P
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraphs 2.C.(2) of Facility Operating License No. DPR-6 are hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 74, 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 Cl""'ISSION
.~
John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 7, 1985.
ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-6 1
DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contain marginal line indicating the area of change.
REMOVE INSERT 3-6 3-6 4
L D
ness. The sum of leakage rates from these valves and locks shall j
be less than 0.25% per day of the containment atmosphere (weight basis) at 20 psig.
l (b) Each reactor shutdown for refueling, but in no case at intervals greater than two years, the following valves shall be tested for operability from both the manual and automatic modes of oper-ation and, at the same time, shall be tested for leak tightness by means of a pressure test utilizing air or the nomal working j
fluid at a pressure not less than 20 psig:
I Main Steam Isolation (M0-7050)
- Main Steam Drain (MD-7065)
Cleanup System Resin Sluice (CV-4091, CV-4092, CV-4093)
Reactor and Fuel Pit Drain Isolation (CV-4027, CV-4117)
ReactorEnclosureCleanSumpIsolation(CV-4031,CV-4102)
Reactor Enclosure Dirty Sump Isolation (CV-4025, CV-4103) j Reactor Enclosure Treated Waste Valve (CV-4049) l All significant leaks (drops /second) revealed by these tests shall require repair of valve seals and retests.
Automatic controls and instrumentation associated with these valves shall be tested at approximately quarterly intervals; c
these tests may be conducted with a simulated signal or in such other manner as to obviate plant shutdown.
(c) Each reactor shutdown for refueling, but in no case at intervals greater than two years, the following shall be visually examined j
for evidence of corrosion, cracking or deterioration:
All Electrical and Accessible Piping Penetration Nipple Welds l
All Accessible Piping Welds to Nipples All Expansion Joints and Welds on Expansion hints Potting Compound in All Electrical Penetrations Insulation at piping penetration welds shall be removed to permit visual examination.
The probable cause of any significant corrosion, cracking or deterioration revealed by such visual examination shall be i
detemined, and evaluated in terms of likelihood of recurrence and probable effect upon other containment sphere penetration components. An individual component leak detection test shall be performed with air at a pressure not less than 11.5 psig on
[
the faulty component prior to its repair or modification. The faulty component, and other components if necessary, shall be repaired or modified, and an individual component leak detection test perfomed with air at a pressure not less than 11.5 psig upon each repaired or modified component. All components so repaired or modified shall be visually re-examined at appropriate intervals, I
but not less frequently than once every six months, until the adequacy of annual visual inspection is reestablished to the i
operator's satisfaction.
- 0perability, automatic controls, and instrumentation tests required only if valve is opened for use during operation.
AmendmentNo.g,g,74 3
3-6
_