ML14175A709
| ML14175A709 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/11/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A710 | List: |
| References | |
| DPR-23-A-065 NUDOCS 8204130013 | |
| Download: ML14175A709 (6) | |
Text
ASREGj O
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-23
- 1. The Nuclear Regulatory Commission Cthe Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (.the licensee) dated January 26, 1982, 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.
8204130013 820311 PDR ADOCK 05000261 P
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-23 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, 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 NUCLE REGULATORY COMMISSION evenA. Varga, ief
'Operating Reactor ranch 1l Division of Licens g
Attachment:
Changes to the Technical Specifications Date of Issuance: March 11, 1982
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 65 TO FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 4.1-4 4.1-4 4.1-6 4.1-6 4.1-6a 4.1-6a
TABLE 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Check Calibration Test Remarks
- 1. Nuclear Power Range S
D (1)
B/W (2)
(1) Thermal Power calculations M* (3) during power operations R* (4)
(2) Signal to AT; bistable action (permissive, rod stop, trips)
(3) Upper and lower chambers for symmetric offset:
monthly during power opera tions. When periods of re actor shutdown extend this interval beyond one month, the calibration shall be performed immediately fol lowing return to power.
(4) Calibration of excore de tectors.
- 2.
Nuclear Intermediate Range S
(1)
N.A.
S/U (2)
(1)
Once/shift when in service N(2)
Log level; bistable action (permissive, rod stop, trip)
- 3.
Nuclear Source Range S
(1)
N.A.
S/U (2)
(1) Once/shift when in service (2) Bistable action (alarm, to
- 4. Reactor Coolant Temperarure S
R B/W (1)
(1) Overtemperature-AT (2)
(2) Overpower-AT
- 5. Reactor Coolant Flow S
R M
- 0)
- 6. Pressurizer Water Level S
R M
- 7. Pressurizer Pressure S
R M
- 8. 4 kv Voltage N.A.
R M
Reactor Protection circuits only Ryi means of the movable in-core detector system
TABLE 4.1-1 (Continued)
Channel Description Check Calibrate Test Remarks
- 21. Containment Sump Level N.A.
R N.A.
- 22. Turbine Trip Set Point **
N.A.
R R
- 23. Accumulator Level and Pressure.
S R
N.A.
- 24. Steam Generator Pressure S
R M
- 25. Turbine First Stage Pressure S
R M
- 26. Emergency Plant Portable M
R M
Survey Instruments
- 27. LogIc Channel Testing N.A.
N.A.
M(1)
(1).
During hot shutdonw and power operations. When periods of reactor cold shutdown and re fueling extend this interval beyond one month, the test shall be performed prior to startup.
- 28. Turbine Overspeed Protection N.A.
R M
Trip Channel (Electrical)
- 29. 4 Kv Frequency N.A.
R R
- 30. Control Rod Drive Trip Breakers N.A.
N.A.
M
- 31. Overpressure Protection System N.A.
R M
- Stop valve closure or low Ell fluid pressure
TABLE 4.1-1 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibration Test Remarks
- 32. Loss of Power
- a.
480 Emerg. Bus N.A.
R R
Undervoltage (Loss of Voltage)
- b.
480 Emerg. Bus N.A.
R R
Undervoltage (Degraded Voltage)
- 33. Auxiliary Feedwater Flow****
Indication M
N.A.
R
- 34. Reactor Coolant System**
Subcooling Monitor N
R N.A.
- 35. PORV Position Indicator***
N.A.
N.A.
R
- 36. PORV Blocking Valve***
Position Indicator N.A.
N.A.
R
- 37. Safety Relief Valve Position***
Indicator N.A.
N.A.
R 0
Instrumentation for Detection of Inadequate Core Cooling -
NUREG 0578 Item 2.1.3.b.
Direct Indication of Power Operated Relief Valve and Safety Valve Position -
NUREG 0578 Item 2.1.3.a.
Auxiliary Feedwater Flow Indication to Steam Generator NUREG 0578 Item 2.1.7.b.
S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W
At least once per 7 days B/W At least once per 14 days M
At least once per 31 days Q
At least once per 92 days S/U Prior to each reactor startup R
At least once per 18 months N.A.
Not applicable