ML14175A696
| ML14175A696 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/13/1981 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A697 | List: |
| References | |
| DPR-23-A-061 NUDOCS 8111250581 | |
| Download: ML14175A696 (9) | |
Text
E 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. 61 License Nlo.
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
the application for amendment by Carolina Power and Light Company (the licensee) dated November 11, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulat'ions set forth in 10 CFR Chapter I;*
B.
The facility will operate i~n 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 act-ivities 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.
0PDR CAOLN POEPNDLGT OPN
-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. 61, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. Revise paragraph 3.I.a of Facility Operating License No. DPR-23 to read as follows:
- a. A primary to secondary pressure test at approximately 1825 psi differential shall be performed after operation at power levels such that estimated corrosion is equivalent to that of 24 effective full power days operation as shown in figure 4.3.3 in Attachment B of CP&L's letter of August 27, 1981.
A period of seven additional calendar days is permitted for flexibility for scheduling the necessary test.
This test shall be repeated after each interval of operation such that the estimated corrosion is equivalent to that of 241 effective full power corrosion equivalent days operation until the end of cycle 8 operation.
- 4. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Marshall Grote uls, Acting Branch Chief Operating Reactors Branch No. 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 13, 1981
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 61 TO FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 2.3-1 2.3-1 2.3-2 2.3-2 2.3-3 2.3-3 3.5-7 3.5-7 3.5-7a 3.5-7a 3.5-10a 3.5-10a
2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION Applicability Applies to trip settings for instrments monitoring reactor power and reactor coolant pressure, temperature, and flow and pressurizer level.
Objective To provide for automatic protective action in the event that the principal process variables approach a safety limit.
Specification 2.3.1 Protective instrumentation settings for reactor trip shall be as follows:
2.3.1.1 Startup protection
- a.
High flux, power range (low set point)
<25% of rated power.
2.3.1.2 Core protection
- a.
High flux, power range (high set point)
<109% of rated power.-*
- b.
High pressurizer pressure <2385 psig.
- c.
Lov.pressurizer pressure >1835 psig.
AThks setting 1 imit shll be. less than or equal to 92 of rated power when operating under the reduced temperature condton,' descre d in the November 11, 1981 license submittal, 2.3-1 Amendment No.
61
- d.
Overtemperature AT
< AT {K1 -
K2 (T -
575.4) + K3 (P -2235) -
f(AI)}*
where:
AT -
Indicated AT at rated power, *F 0
T Average temperature, *F P
Pressurizer pressure, poig K1
- 1.1619 K = 0.01035 2
K3 = 0.0007978 and f(AI) is a function of the indicated difference between top and.bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instru ment response during plant startup tests such that:
(1) For (qt -
b) within +12% and -17% where qt and qb are percent power in the top and bottom halves of the cote respectively, and q+
b is total core power in per cent of rated power, f(AI) -
- 0. For every 2.4% below rated power level, the permissible positive flux difference range is extended by +1 percent. For every 2.4% below rated power level, the permissible negative flux difference range is extended by -1 percent.
(2) For each percent that the magnitude of (qt b
exceeds +12% in a positive direction, the AT trip set point shall be automatically reduced by 2.4% of the value of AT at rated power.
(3) For each percent that the magnitude of (qt -b) exceeds -17%, the AT trip setpoint shall be automatically reduced by 2.4% of the value of AT at rated power.
- When operating under the reduced temperature conditions described in the November 11, 1981 license submittal, replace the number 575.4 with 537.9 in the overtemperature AT calculation.
2.3-2 Amendment No.
61
<AT E dT T
K-dT K
(T T') -
f(&I) J 0
5 dt 6
where:
AT Indicated AT at rated power, a 0
T
= Average temperature, OF T'v Indicatcd average temperature at nominal conditions and rated power, K 4 1.07 for decreasing average temperature K
0.2 seconds per OF for increasing average temperature 5
K 0.002235for T';
K 0 for T<T' 6
-T-6 f(Ll)= as defined in d. above.
- f.
Low reactor coolant loop flow >90% of normal indicated flow
- g.
Low reactor coolant pump frequency >57.5 Ez
- h. -Under voltage >70% of normal voltage.
2.3.1.3 Other Reactor Trips
- a.
High pressurizer water level <92% of span
- b.
Low-low steam generator wa r level >14% of narrow range instrument span.
2.3.2 Protective instrumentation settings for reactor trip interlocks shall be as follows:
7,3.2.1 The low pressurizer pressure trip, high pressurizer level trip, and the low reactor coolant flow trip (for two or more loops) may be bypassed below 10% of rated power.
2.3.2.2 The single-loop-loss-of-flow trip may bc bypaosed below 45% of rated power.
- The value of T' for nominal conditions and rated power is 575.4'F. When operating under the reduced temperature conditions described in the November 11, 1981 license submittal, replace the number 575.4 with 537.9 in the overpower AT calculation.
2.3-3 Amendment No. 61
TABLE 3.5-1 ENGINEERED SAFETY FEATURE SYSTEM INITIATION INSTRUMENT SETTING LIMITS NO.
FUNCTIONAL UNIT CHANNEL ACTION SETTING LIMIT
- 1.
High Containment Pressure (HI Level)
Safety Injection*
4 5 psig
- 2.
High Containment Pressure (HI-Il Level)
- a. Containment Spray**
< 25 psig
- b.
Steam Line Isolation
- 3.
Pressurizer Low Pressure Safety Injection*
> 1700 psig
- 4.
High Differential Pressure Between any Safety Injection*
< 150 psi Steam Line and the Steam Line Header
- 5.
High Steam Flow in.2/3 Steam Lines***
- a.
Safety Injection*
N 40% (at zeroload) of
- b. Steam Line Isolation full steam flow
-I
< 40% (at 20% load) of full steam flow
< 110% (at full load) of full steam flow Coincident with Low T or Low Steam
> 541 F T Line Pressure avg 600 paigVteam line pressure a
- 6.
Loss of Power
- a. 480V Emerg. Bus Undervoltage Trip Normal Supply Breaker 328 Volts + 1 Volt (Loss of Voltage) Time Delay
.75 +.25 sec.
TABLE 3.5-1 (Continued)
ENGINEERED SAFETY FEATURE SYSTEM INITIATION INSTRUMENT SETTING LIMITS NO.
FUNCTIONAL UNIT CHANNEL ACTION SETTING LIMIT
- 6.
- b. 480V Emerg. Bus Undervoltage Trip Normal Supply Breaker 412 Volts + 1 Volt (Cont'd)
(Degraded Voltage) Time Delay 10.0 Second Delay +
0.5 sec.
0
- 7.
Containment Radioactivity High Ventilation Isolation
< 2 X Reading at the Time the Alarm is Set with Known Plant Conditions
- Initiates also containment isolation (Phase A), feedwater line isolation and starting of all containment fans...
Initiates also containment isolation (Phase B).
Derived from equivalent AP measurements.
- These setting limits shall be greater than or equal to 524 0 F and 450 PSIG when operating under reduced temperature conditions described in the November 11, 1981 license submittal.
(rD O-I
TABLE 3.5-3 (Continued)
INSTRUMENTATION OPERATING CONDITIONS FOR ENGINEERED SAFETY FEATURES 3
1 2
OPERATOR ACTION MINIMUM MINIMUM IF CONDITIONS OF CHANNELS DEGREE OF COLUMN 1 OR 2 NO.
FUNCTIONAL UNIT OPERABLE REDUNDANCY CANNOT BE MET
- 2.
- a. Manual*
2 0**
Cold Shutdown
- b. High Containment Pressure*
2/set 1/set Cold Shutdown (Hi-Hi Level)
- 3.
LOSS OF POWER
'C
- a. 480V Emerg. Bus Undervoltage 2/bus (a) 1/bus(b)
Maintain Hot Shutdown (Lose of Voltage)
- b. 480V Emerg. Bus Undervoltage 2/bus 1/bus Maintain Hot Shutdown(c)
(Degraded Voltage)
- Also initiates a.Phase B containment isolation.
- Must actuate two switches simultaneously.
When primary pressure is less than 2000 psig, channels may be blocked.
When primary temperature is less than 547 0F, channels may be blocked.(d)
- In this case the 2/3 high steam flow is already in the trip mode.
(a) During testing and maintenance of one channel, may be reduced to 1/bus.
(b) During testing and maintenence of one channel, may be reduced to 0/bus.
(c) The reactor may remain critical below the power operating conditions with this feature inhibited for the purpose of starting reactor coolant pumps.
(d) When operating under the reduced temperature conditions described, in the November 11, 1981 license submi.ttal the channels may be blocked when primary temperature is less that 530 0 FI