ML20041C018

Amend 50 to License DPR-6,replacing Tech Spec Figure 4-1 w/810918 Proposed Table 4-1 Re Pressure Temp Limits Until Plant Is Shutdown for Refueling

ML20041C018
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	02/04/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20041C014	List: ML20041C018 ML20041C019 ML20041C022
References
NUDOCS 8202260031
Download: ML20041C018 (4)

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UNITED STATES F

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..f CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 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 8,1982, as supported by a portion of the application dated September 18, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regula-tions 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 s

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.

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2.

Accordingly, the license is amended by changes to the Technical l

Specifications as indicated in the attachment to this license l

amendment and Paragraph 2.C(2) of Facility Operating License 1

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. 50, are hereby incorporated in the license.

The licensee shall

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operate the facility in accordance with the l

Technical Specifications.

3.

This license amendmer.t is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Sarf.

Dennis M. Crutchfield hief Operating Reactors Branch #5 l

Division of Licensing

Attachment:

I Changes to the Technical f

Specifications Date of Issuance:

February 4,1982 4

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ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155

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Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page contains the captioned amendment number and a vertical line indicating the area of change.

Pa g'e 4-3a (Table 4-1) e e

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TABLE 4-1 HYDR,0 STATIC TEST PRESSURE / TEMPERATURE LIMITS-FLAlt GE BELTLINE PRESSURE LIMITS PRESSURE LIMIT (4)

BELTLIN E TEM PERATU RE TEMP.

RATE CH AN GE 0{F/HR)

I 50'F 100'F 150'F 200'F 250*F

< 120*F 7

0 8s8 950 1162 1600 300 20 805 904 1108 1529 40 761

.858 1054 1858 2294 6

60 721 812 1001 1390 2194 80 678 766 948 1322 2096 i

100 637 721 896 1256 1996 HEATUPPRESSURE/TEMPERATURELIMITS FLANGE BELTLINE PRESSURE L'IMITS PRESSURE LIMIT (4)-

s BELTLI N E TEMPERATURE (SEENOTE3WHENREACTORISCRITICAL)

TEM P.

RATE OF 0{F/HR)

CHANGE

(

50*F 100*F 150 F 200*F 250'F

< 150'F 0

632 709 868 1196 1875 300 20 598 670 818 1124 1755 40 56 4 631 769 1054 1642 60 531 593 722 987 1532 80 498 556 675 922 1432 100 46 5 l

519 631 860 1335 000LDOWN PRESSURE / TEMPERATURE LIMITS FLANGE BELTLINE PRES $URE LIMITS PRESSURE LIMIT (4)

S ELTLI N E (SEE NOTE 3 WHEN REACTOR IS CRITICAL)

TEM P E RATU RE RATE OF CgANGE

( F/HR) 0 50'F 100 F 150'F 200'F 250*F

< 150'F 0

632 709 868 1196 1875 300 l

20 600 674 827 1143 1795 5

40 568 640 787 1090 1717 60 537 605 747 1039 1642 80 505 571 707 988 1568 100 474 537 668 938 1495 CRITICALIIT TEMPERATURE LIMITS: THE MINIMUM TEMPERATURE AT WHICH A CRITICALITY (EXCEPT FOR LOW POWEP *HYSICS TESTING) CAN TAKE PLACE IS 90 F NOTES

1. DURING A NS$$ HYDROSTATIC TEST THE PRIMARY SYSTEM WATER TEMPERATURE CAN EXCEED 212*F WITHOUT ENTERING THE TECHNICAL SPECIFICATION POWER OPEL ATION DEFINITION FOUND IN SECTION 1.2.1.

MYOR0 STATIC TESTS ARE PERMISSIBLE ONLY WITH THE REACTOR SUBCRITICAL.

2. TABLES ARE' APPLICABLE FOR A FLUENCE LEVEL UP TO 4.5 X 10 ' NEUTRONS /CM2 1

g,g,,,,

3. HEATUP/C00LDOWN PRESSURE LIMITS ARE APPLICABLE AT TEMPEi ATURES 40 F HIGHER WHEN THE REACTOR IS CRITICAL.

4 FLANGE PRESSURE LIMITS ARE NOT DEPENDEllT UPON THE TEMPERATURE RATE OF CHANGE.

5. ALL PRESSURE LIMITS ARE lit PSIG.

4-3a Amendment No. M 50

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