ML19253C166
| ML19253C166 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/02/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19253C159 | List: |
| References | |
| FOIA-80-162 NUDOCS 7911300075 | |
| Download: ML19253C166 (6) | |
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UNITED STATES
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CONSUMERS POWER COMPANY DOCKET N0. 50-155 BIG ROCK POINT NUCLEAR PLANT AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 31 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 October 23, 1979, as supplemented October 31, 1979, complies with the standards and requirements of the Atomic 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 conducted 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.
1442 270 e o,i a o o ()1715 o
. 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 31, 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 h
k Dennis L. Ziemann[ hief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: November 2, 1979 1442 271
ATTACHMENT TO LICENSE AMENDMENT ~NO. 31 FACILITY OPERATING LICENSE N0. DPR-6 DOCKET N0. 50-155 t
Revise Appendix A Technical Specifications by removing pages 6.2,11-3 and 11-9 and inserting the enclosed pages 6-2, 11-3 and 11-9.
The revised pages include the captioned amendment number and contain vertical lines indicating the area of change.
1442 272
-y C3 ON, 6.1.2 Reactor Safety System Durinsr Power Operation The following tabulation gives the arrangement of the reactor safety system that shall be effective during power operation:
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=--
Trip p
Contacts Coincidence Scram Setting Warning
--===
Sensor and in Each in Each and Instrument Annunciation Z
Trio Device Channel Channel Tolerance Snecial Features Rances Trip Set Point p
High Reactor Pres-2 1 Out of 2 50 5 Psi Above 100-1700 Psig 25 5 Psi Above sure (h Pressure Reactor Oper-Reactor Operating Switebes) ating Pressure Pressure Low Reactor Water 2
1 Out of 2 y,3'1" Above Closes containment Fixed Level Level (4 Level Top of Active sphere isolation Trip Point Switches)
Fuel (Toler-valves.
If reactor No Range ance pressure is less than
-1")fqmit 200 psig, actuates core spray system.
(Note: Spray water will not enter reactor vessel until reactor pressure drops below fire header pressure.)
Above or Equal
-30" to +30" h" Below Steam Low Steam Drum 2
1 Out of 2 to 8.0" Below Water Drum Center Line Water Level (4 Steam Drum Level Switches)
Center Line
.(Tolerance Limit
-0. 5") (1)
1 Out of 2 5015 Percent of Position Switch Backup Isolation Full Closure Trains Adjustable Valve Closure (h Full Valve Travel g
Position Switches)
High Condenser 2
1 Out of 2 8.010.S" of Hg Bypassed by pressure 0 - 20" Hg Vac Pressure (k Pres-Absolute Pres-interlock as described sure Switches) sure in Section 6.1.3.
(1 Level instrument set points shall be as specified.
Level instrument calibration shall be based on normal operating temperature (582 F) and pressure (1350 psia) and instrument reference leg temperature of 250 F or lower as measured to maintain un actu11 trip level greater than that assumed in accident analyses (2'8 above top of active fuel for reactor vessel level trips, and 38,500 lbm inventory above active fuel for reactor protective system trip). Set point drift between calibration checks within the specified tolerace limit shall be corrected but need not be reported under Specification 6.9 2.
Change No. O,
6-2 Amendment No. 31
TABLES ll. 3.1.ha A?ID 11.h. l.ha Instrumentation That Initiates Core Spray ll.3.1.hn Limiting Conditions for Operation ll.h.1.ha Surveillance Requirements Conditions for Instrument Parameter Trip System Logic Limitine Set Point Operability Instrument Trip Test Calibration Open Core Spray Valves Low Reactor Water One of Two for
>3'1" Above Top of Power Operation Quarterly Each Major Level (a)
Each of Two Active Fuel (Tal-and Refueling Refueling Valves in Series erance Limit Operations (b)
-1")(c)
Primary Pressure One of Two for
>200 Psig Power Operation Quarterly Each Major Low (a)
Each of Two and Refuelin6 Refueling Valves in Series Operations (b)
Notes for Tables ll.3.1.ha and ll.h.l.ha
" Initiation of valve operation requires both low reactor water level coincident with low primary system pressure.
(b)The primary core spray system shall be available for use during refueling operations. The redundant core spray system shall be inoperable during refueling operations with the valves blocked or otherwise defeated (while the piping section from the valves to the reactor head is dismantled).
Level instrument set points shall be as specified.
Level instrument calibration shall be based on normal operating temperature (582 F) and pressure (1350 psia) and instrument reference leg temperature of 250 F or less as measured to maintain an actual trip level greater than that assumed in the accident analysis (2'8" above the top of active fuel for reactor vessel level trips). Set point drift between calibration checks within the specified tolerance limit shall be corrected but need not be reported under Specification 6.9 2.
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11-3 Amendment No. J0, J5, 31
Tables 3.5.2.h and h.5.2.h Instrumentation That Initiates RDS Operation 3.5.2.H - Limiting Conditions for Operation h.5.2.H - Surveillance Requirement Minimum Protective Operable Conditions for Instrument Instrument Channel Parameter Channels Limiting Set Point Operability Trip Test Calibration Trip i
Low Steam Drum 3
Above or Equal to At Power Levels Monthly Each Major Level 17" Below Center Whenever the Refueling Line (Tolerance Reactor Is Limit -5")(1)
Critical With the Head On or When in Hot Shutdown Fire Pump (s) 3 2100 Psig Ditto Monthly Each Major Discharge Pressure Refueling Lov Reactor 3
>3'1" Above Top Monthly Each Major Water Level of Active Fuel Refueling (Tolerance Limit
-1")(1) 120-Second 3
1,120 Seconds Fol-Monthly Each Major Time Delay loving Low Steam Refueling Drum Level Signal Input Channels 3
Monthly A Through D Output Channels 3
bbnthly I Through IV
- Fire Pump Start 1
Monthly Monthly
" Reference Specifications 3.1.h and 4.1.h for Bases.
(1) Level instrument set points shall be as specified.
Level instrument calibration shall be based on normal operating 41=
IN3 temperature (582 F) and pressure (1350 psia) and instrument reference leg temperature of 250 F or lower as measured to maintain an actual trip level greater than that assumed in accident analyses (2'8" above top of active fuel for rs reactor vessel level trips, and 25" below steam drum center line for RDS actuation). Set point drift between
[ calibration checks within the specified tolerance limit shall be corrected but need not be reported under Specification 6.9 2. 11-9 Amendment No.10,31 .}}