ML20210D085
| ML20210D085 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/03/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210D062 | List: |
| References | |
| TAC-61473, NUDOCS 8702100015 | |
| Download: ML20210D085 (7) | |
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UNITED STATES g j. *. g (
NUCLEAR REGULATORY COMMISSION t ' ! ?./, :;
. WASMNGTON, D. C. 70555
't,.....f SACPAPFNTO FUNICIPAL UTILITY DISTRICT DOCKFT NO.50-31P RANCHO SECO NUCLEAR GENERATING STATION AFENDMENT TO FACILITY OPERATING LICFNSE Amendment No.83 License No. nPF-54 1.
The Nuclear Pegulatory Commissinn (the Commission) has found that:
A.
The application for amendment b.v Sacranento Municipal Utility District (the licensee) dated January 24, 1986. as supplemented September 19, 1986, complies with the standards and reouirements of the Atomic Energy Act of 1954, as arended (the Act), and the C)mmission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will nperate in confonnity with the application, the the provisions of the Act, and the rules and reaulations of the Commission; C.
There is reasonable assurance (i) that the activities authorf7ed 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, l
and paragraph 2.C.(?) of Facility Operatina License No. DPR-54 is hereby amended to read as follows:
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i 8702100015 870203 PDR ADOCK 05000312 PDR p
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.2-Technical Specifications The Technical Specifications centained.in Apperdices A and B,'as revised through Amendment No. 83, are hereby incorporated in the license.' The licensee 7
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-shall operate ~the facility in accordance with the 4
t Technical Specifications.
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3.
This license amendment'is effective as of its date of issuance.
FDP THE NUCLEAP PFGilLAT PY COMMISSI0f:
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jo L.F. Stol z ', Directer
/PWP Pro,iect Directorate #6/
( Di ision of PWR Licensing'R
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Attachment:
Cheroes tn the Technical j.
Specifications
- s Date of Issuance: February 3, 1987
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r ATTACHMENT TO LICENSE AVENDMENT NO. 83 FACILITY OPEPATING LICENSE NO. OPR-54 DOCKET NO. 50-312
.Raplace the following pages of the AppeAdix "A" Technical Specifications
.with the attached pages. The revised pages are identified by Amen hent number and contain vertical. lir.es -indicating the area of chance.
Pemove Insert
.2-4 2-4 2-7' 2-7 2-9 2-9 2-10 2-10
2%
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Safety Limits and Limiting Safety System Settings 2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE Applicability Applies to the limit on reactor coolant system pressure.
Objective To maintain the integrity of the reactor coolant system and to prevent the release of significant amounts of fission product activity.
Specification 2.2.1 The reactor coolant system pressure shall not exceed 2750 psig when there are fuel assemblies in the reactor vessel.
2.2.2 The nominal setpoint of the pressurizer code safety valves shall be less than or equal to 2500 psig.
Bases The reactor coolant system (1) serves as a barrier to prevent radionuclides in the reactor coolant from reaching the atmosphere.
In the event of a fuel cladding failure, the reactor coolant system is a barrier against the release of fission products. Establishing a system pressure limit helps to assure the integrity of the reactor coolant system. The maximum transient pressure allowable in the reactor coolant system pressurp yessel under the ASME code,Section III, is 110 percent of design pressure.t2J The maximum transient pressure allowable in the reactor coolant system piping, valves, and fittings under ANSI Section B31.7 is 110 percent of design pressure. Thus, the safety limitof275y2jpsig (110 percent of the 2500 psig design pressure) has been established.
The settings for the reactor high l
and the pressurizer code safety valves (2500 psig) gssure trip (2355 psig) have be' n established e
to assure that the reactor coolant system pressure safety limit is not exceeded. The initial hydrostatic test was conducted at 3125 psig (125 percent of design pressure) to verify the integrity of the reactor coolant system. Additional assurance that the reactor coolant system pressure does not exceed the safety limit is provided by setting the pressurizer electromatic relief valve at 2450 psig. This setpoint is above normal transients limited by setting the reactor trip at <2355 psig and sufficiently l
low to assure limited dependence on safety valves operation.
1 REFERENCES (1) FSAR, section 4 (2) FSAR, paragraph 4.3.8.1 l
(3) FSAR, paragraph 4.2.4 l
l 2-4 Amendment No. M, 83 o
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Safety Limits and Limiting Safety System Settings a
8.
Pump Monitors
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The pump monitors prevent the minimum core DNBR from decreasing below
- the CHF correlation limit by tripping the reactor due to (a) the loss of two reactor coolant pumps in one reactor coolant loop, and (b) loss of one or two reactor coolant pumps during two-pump operation. The pump monitors also restrict the power level to 55 percent for one reactor coolant pump operation in each loop.
C.
Reactor coolant system pressure During a startup accident from low power or a slow rod withdrawal from high power, the system high pressure trip set point is reached before the nuclear overpower trip set point. The trip setting limit shown in Figure 2.3-1 for high reactor coolant system pressure (2355 psig) has l
been established to maintain the system. pressure below the safety limit (2750 psig) for any design transient (1) and minimize the challenges to the EMOV and code safeties.
The low pressure (1900 psig) and variable low pressure (12.96 Tout - 5834) trip set point shown in Figure 2.3-1 have been established to maintain the DNB ratio greater than or equal to the CHF correlation limit for those design accidents that result in a pressure reduction.
(2,3)
Due to the calibration and instrumentation errors the safety analysis used a variable low reactor coolant system pressure trip value of (12.96 Tout - 5884).
D.
Coolant outlet temperature The high reactor coolant outlet temperature trip setting limit (618 F) l shown in Figure 2.3-1 has been established to prevent ~ excessive core l
coolant temperatures in the operating range. Due to calibration and instrumentation errors, the safety analysis used a trip set point of 620 F.
E.
Reactor Building pressure The high Reactor Building pressure trip setting limit (4 psig) provides positive assurance that a reactor trip will occur in the unlikely event of a steam line failure in the Reactor Building or a loss of coolant accident, even in the absence of a low reactor coolant system pressure j
trip.
F.
Shutdown bypass In order to provide for control rod drive tests, zero power physics
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testing, and startup procedures, there is provision for bypassing certain segments of the reactor protection system. The reactor protection system segments which can be bypassed are shown in Amendment No. U, 37, 37, M,83 2-7 t.-
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RANCHO SECO UNIT 1
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TECHNICAL SPECIFICATIONS Safety Limits and Limiting Table 2.3-1 Safety System Settings REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS One Reactor Coolant Pump Four Reactor Coolant Pumps Thr'ee Reactor Coolant Pumps Operating in Each Loop Operating (Nominal.
Operating (Nominal (Nominal Operating Shutdown Operating Power - 100%)
- Operating rower - 751)
- Power - 495)
Bypass
- 1. Nuclear Power, % of rated, max.
104.9 104.9 104.9 5.0I3I
- 2. Nuclear power based on floM 1.06 times flow minus 1.06 times flow minus 1.06 times flow minus Bypassed and 1mbalance,1 of rated, max.
reduction due to reduction due to reduction due to Imbalance (s)
Imbalance (s)
Imbalance (s)
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- 3. Nuclear power based on pump (5)
NA NA 55 Sypassed monttors, 1 of rated, max.
- 4. High reactor coolarit system 2355 2355 2355 1820I4) l pressure, psig max.
- 5. Low reactor coolant system pressure, psta min.
1900 1900 1900 Bypassed
- 6. Variable low reactor coolant 12.96 Tout-5834III 12.96 Tout-5834III 12.96 Tout-5834III
. Bypassed system pressure, psig min.
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- 7. Reactor coolant temp. F., max.
618 618 618 618 i
- 8. High Reactor Butiding 4
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4 pressure, pstg max.
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- 9. Anticipatory reactor trip (6)
Autostopb11 pressure Autostopp1 pressure Autostopg1 pressure 50 psig I 1
50 psig I 50 psig I
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MFP goverDer oli pressure MFP goverggr oil pressure MFP gove gr oli pressure 50 psig I 3 50 psig 3
50 psig LU3 (1) T is in degrees Fahrenheit (F).
oug (2) Reactor coolant system flow, %.
l (3) Administratively controlled reduction set only during reactor shutdown.
(4) Automatically set when other segments of the RPS (as specified) are bypassed.
- 15) The pump monitors also produce a trip on: (a) loss of two reactor coolant pumps in one reactor coolant loop, and (b) loss of one or two reactor coolant pumps during two-pump operation.
l (6) This trip is disabled below 451 power. (power Channel) l l
(7) Indicative of a Turbine Trip.
(8) Indicative of loss of both Main Feed pumps, i
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Amendment No. Jf, @@, JJ, JJ, M,83 2-9
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Safety Limits and Limiting Safety System Settings Figure 2.3-1 Protective Systems Maximum Allowable Setpoints, Pressure Vs Temperature 2600 en 2400 --
Pa 2355 psig T = 618 m.
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Acceptable Operation 5m
,E 2200--
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2000__
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P = 1900 psig d[
1800 l
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540 560 580 600 620 640 Reactor Outlet Temperature, F i
Amendment No. Jf, 37, 33, 83 2-10
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