ML20203N556

Amend 96 to License DPR-40,updating Snubber Table Listings to Reflect Removal & Addition of Snubbers & Changing Nuclear Detector Well Cooling Annulus Exit Air Temp Detectors

ML20203N556
Person / Time
Site:	Fort Calhoun
Issue date:	04/24/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20203N549	List: ML20203N548 ML20203N556 ML20203N610
References
TAC-60064, NUDOCS 8605050492
Download: ML20203N556 (6)

Text

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& 'o UNITED STATES g

P o NUCLEAR REGULATORY COMMISSION

$ WASHINGTON, D. C. 20555 4, . . . . . ,o OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.96 License No. DPR-40

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated October 31, 1985 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 l

l E. The issuance of this amendment is in accordance with 10 CFR Part l 51 of the Commission's regulations and all applicable requirements I have been satisfied.

86050S0492 860424 PDR ADOCK 05000285 p PDR

2. Accordingly, Facility Operating License No. OPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this

. license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. .This license amendment is effective within 30 days of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION A

.[ . ,

Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: April 24,1986 1

1

2 ATTACHMENT TO LICENSE AMENDMENT N0.96 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 2-80 2-80 2-88a 2-88a 3-16 3-16 Am _ _ _ _ _ _ _ _

o . .

.8 TABLE 2-6(a)

(Continued)

Located i Accessible in High Difficult to During Inaccessible Radiation Remove for

• Snubb er No rmal During Normal Areas During Functional No. Elevation Operation Operation Shutdown Testing RCS-21 1032' 0" X RCS-22 1037' 6" X RCS Bo ttom 1032' 0" X RCS-25 1033' 0" X RCS-27 1052' 9" X RCS-28 1052' 9" X RCS-30 1045' 6" X RCS-30A 1047' 0" X RCS-31 1052' 0" X RCS-32 1052' 0" X RCS-33 1052' 0" X RCS-34 1047' 0" X RCS-42 1007' 9" X RCS-44 1007' 9" X RCS Top 1009' 6" X RCS Bottom 1009' 6" X RCS-4 7-Top 1009' 6" X RCS-4 7-Bottom 1009' 6" X RCS-49 1009' 6" X RCS-51 1007' 9" X i

l l

l Amendment No. 27, /S,96 2-80 l

l l

i

T a 3

Table 2-6(b)

ACCESSIBILITY OF SAFETY-RELATED SYSTEM MECHANICAL SNUBBERS LOCATED ACCESSIBLE INACCESSIBLE IN HIGH DIFFICULT TO DURING DURING RADIATION REMOVE FOR SNUBBER NORMAL NORMAL AREAS DURING FUNCTIONAL NO. ELEVATION OPERATION OPERATION SHUTDOWN TESTING RCS-3A 996* X RCS-16 1015' X RCS-29 1047' X RCS-29A 1045' X RCS-39 1048' X RCS-41 1048' X RCS-61 1051'6" X RCS LOWER 1032' X RCS-65 10S1'6" X RCS-67 1032' X RCS-68 1031' X RCS-69 1032' X RCS-70 1032' X

! RCS-71 1032' X SIS-114-A 1074' X SIS-114-B 1074' X SIS-114-E 1074' X i

! SIS-114-F 1074' X s

Amendment No. //, 7/#,96 2-88a t

c> o .

TABLE 3-3 (Continued) k

=

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS k Surveillance 3 Channel Description Function Frequency Surveillance Method 2

P

14. Nuclear Detector Well a. Check S a. Comparison of independent w temperature readings.

w Cooling Annulus Exit

.N Air Temperature Detectors b. Calibrate R b. Calibrate with known temperature.

3 Pn 15. Reactor Coolant System a. Check M a. Calculation of reactor coolant Flow flow rate.

16. Pressurizer Pressure a. Check S a. Comparison of independent pressure readings.

17. Reactor Coolant Inlet a. Check S a. Comparison of independent temperature w ,

Temperature readings.

cn

18. Low-Temperature Set- a. Test PM a. Verify operability of actuation circuitry point Power-0perated for low-temperature setpoint power-Relief Valves operated relief valves by utilization of installed test switches.

b. Calibrate R b. Calibrate temperature and pressure channels.

l I'

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