ML14183A113
| ML14183A113 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/11/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A114 | List: |
| References | |
| DPR-23-A-116 NUDOCS 8804150123 | |
| Download: ML14183A113 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION Z
WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power & Light Company (the licensee), dated June 16, 1987, 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.
- 2. Accordingly, the license 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-23 is hereby amended to read as follows:
A 8OR4jO1 23OD 8041 P _
2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 116, are hereby incorporated in the license. Carolina Power &
& Light Company 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 Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/Il
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 11, 1988 LA DRPR PM:PD
- DRPR D J *DRPR PA RLo 8 EAdensam 3I 88
/88/
~8 8
/1L/88
ATTACHMENT TO LICENSE AMENDMENT NO. 116 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages, as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3.5-21 3.5-21 3.11-1 3.11-1 4.1-6 4.1-6 4.11-1 4.11-1 4.19-3 4.19-3
TABLE 3.5-6 (Continued)
RADIOACTIVE LIQUID EFFLUENT NMOITORINC INSTRUMENTATION Release Pathway/Instrumentation NCO*
Required Action
- 2.
Steam Generator Slowdown 9ffluent Line
- a.
onitor (RNS-19ab, and c) 1 per With the number of channels operable less than the NCO requirement:
- provides automatic 5/C
- a.
Exert best efforts to return the instruments to operable Status termination of blow-within 30 days and, if unsuccessful, explain in the next Semi down from the affected annual Radioactive Effluent Release Report why the inoperability Steam Generators upon was not corrected in a timely manner in accordance with exceeding alarm/trip Specification 6.9.1.d and,
- b. Effluent releases via this pathway may continue provided that grab samples are analyzed for gross radioactivity (beta or gamma) with a lower limit of detection of at least 1.OE-07 IaCi/ml or are analyzed for principle gamma emitters consistent with Table 4.10-1;
- 1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the.
secondary coolant is < 0.01 pCi/a Dose Equivalent 1-131, or;
- 2. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is,> 0.01 pCi/al Dose Equivalent 1-131.
- b. Flow rate measurement 1 per With the number of channels operable less than the NCO requirement:
devices -
each Steam S/C
- a. Exert best efforts to return the instruments to operable status Generator has its own within 30 days and, if unsuccessful, explain in the next Semi blowdoam flow rate annual Radioactive Effluent Release Report why the inoperability measuring device.
was not corrected in a timely manner in accordance with Specification 6.9.1.d and, 0
- b. Effluent releases via this pathway may continue provided that the flow rate for the affected blowdown line(s) is estimated at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- NCO-Hinimum Channels Operable
3.11 MOVABLE IN-CORE INSTRUMENTATION APPLICABILITY Applies to the operability of the movable detector instrumentation system.
OBJECTIVE To specify functional requirements on the use of the in-core instrumentation systems, for the calibration of the excore symmetrical offset detection system.
SPECIFICATION 3.11.1 A minimum of 15 total accessible thimbles and at least 2 per quadrant sufficient movable in-core detectors shall be operable during recalibration of the excore symmetrical offset detection system.
3.11.2 Power shall be limited to 90% of rated power if recalibration requirements for the excore symmetrical offset detection system identified in Table 4.1-1 are not met.
BASIS The Movable In-Core Instrumentation Systes(1 ) provides a method for acquiring core data via drives, detectors, and thimbles. Each detector can be routed to twenty or more thimbles. Consequently, the full system has a great deal more capability than would be needed for the calibration of the excore detectors.
To calibrate the excore detector system, it is only necessary that the Movable In-Core System be used to determine the gross power distribution in the core as indicated by the power balance between the top and bottom halves of the core. The thimbles shall be selected such that when'reflected into a single quadrant, no assembly is more than a "king's move" away from a measurement.
In other words, every assembly is either a measured assembly or touched by a 3.11-1 Amendment No. 87, 707, 116
TABLE 4.1-1 (Continued)
HININUM FREQUENCIES FOR CHECKS.
CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibrate Test Remarks
- 9. Analog Rod Position S (1,2) a N
(1)
With step counters (2)
Following rod motion in excess of six inches when the computer is out of service
- 10. Rod Position Bank Counters S (1,2)
N.A.
N.A.
(1)
Following rod motion in excess of six inches when the computer is out of service (2)
With analog rod position
- 11. Steam Generator Level S
a H
- 12. Charging Flow N.A.
R N.A.
- 13. Residual Heat Removal Pump Flow N.A.
R N.A.
- 14. Boric Acid Tank Level D (1)
R N.A.
(1)
Bubbler tube rodded weekly
- 15. Refueling Water Storage W
R N.A.
Tank Level
- 16. Deleted
- 17. Volume Control Tank Level N.A.
R N.A.
- 18. Containment Pressure D
R B/
(1)
(1)
Containment isolation valve signal
- 19. Deleted by Amendment No.
85
- 20. Boric Acid Nakeup Flow Channel N.A.
R N.A.
4.11 REACTOR CORE APPLICABILITY Applies to surveillance of the reactor core.
OBJECTIVE To ensure the integrity of the fuel cladding.
SPECIFICATION 4.11.1 APDNS OPERATION 4.11.1.1 Prior to establishing normal operation vith APDMS, at least six maps will be taken to determine applicable values of I and a for surveillance thimbles.
4.11.1.2 Plant operation up to raced power shall be permitted for the purposes of obtaining the initial maps of Specification 4.11.1.1, provided the APDMS is operational and hot channel factors are shown to be below the limiting values set forth in Specification 3.10.2. Suitably conservative values of I and a shall be derived from maps previously run during the current fuel cycle for use in the APDMS system during this initial period.
4.11.1.3 Subsequent updates of I and ashall employ the last six maps in accordance with Specification 4.11.1.1.
4.11.1.4 Each power distribution map will be based on flux traverses obtained from 36 or more of the incore thimbles.
4.11.2 Except during physics tests and excore calibrations, axial surveillance of F(Z)S(Z) shall consist of traverses 4ith the movable incore detectors in appropriate pairs of detector paths, taken every eight hours, or a frequency of approximately 0, 10, 4.11-1 Amendment No. $, 116
TABLE 4.19-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel Pathway/Instruments Check Check Calibration Functional Test
.1. Liquid Radwaste Effluent Line
- s.
Monitor (RS-18)
D P
R (Note 3)
Q (Note 4)
- b.
Flow rate measurement device (Note 1)
N.A.
R N.A.
- 2.
Steam Generator Blowdown Effluent Line
- a.
Monitor (RMS-19a)
D N
R (Note 3)
Q (Note 4)
(RMS-19b)
D H
R (Note 3)
Q (Note 4)
(RMS-19c)
D N
R (Note 3)
Q (Note 4) o
- b.
Flow rate measurement devices for measuring flow of sample to BMS-19 (Note 2)
N.A.
N.A.
N.A.
- c.
Flow rate measuring devices for each steam generator blowdown line (Note 2)
N.A.
R N.A.
- 3.
Containment Vn Cooling Water Monitor (Service Water Effluent Line)
- a.
Monitor (RMS-16)
D N
R (Note 3)
Q (Note 5)
- 4.
- Tank Level Indicating Devices
- a.
Refueling Water Storage Tank D*
N.A.
R Q
- b.
Monitor Tanks A & B D*
N.A.
R Q
- c.
Waste Condensate Tanks C D & E D*
N.A.
R Q
- During liquid additions to the tank