ML20101B985
| ML20101B985 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/28/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20101B988 | List: |
| References | |
| NPF-68-A-051, NPF-81-A-030 NUDOCS 9206050284 | |
| Download: ML20101B985 (8) | |
Text
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- o UNITED STATES
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' NUCLEAR REGULATORY COMMISSION
.o WASHINGTON, D.C. 20066
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GEORGIA POWER COMPANY-OGLETHORPE POWER CORPORATION
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MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA t:
CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT _1 AMENDMENT TO FACILITY OPERATING LICENSE
~ Amendment No. 51 License No. NPF-68
- 1. -
- The Nuclear-Regulatory Commission (the Commissior.) has found that:
A.;
.The application for amendment to the Vogtle Electric Generating-Plant, Unit'l (the-facility). Facility Operating. License No.
.NPE-68: filed.by the Georgia Power Company,: acting for itself,
'~ Oglethorpe Power Corporation,-Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated November-12,-1991,. as supplemented April-21, 1992, 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-in110:CFR Chapter <I; B.
The facility will operate in conformity'with the application, the provisions of the - Act, cand the rules and regulations of the Commission;-
C, There is-reasonable assurance.(1):that the activities authorized-by :thi; ~ amendment can be conducted without' endangering-the health-and: safety of the public,1 and (ii) that such activities will be conducted in compliance with the Commission's regulations--set-
- forth-in 10 CFR. Chapter-I; t
= 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 Lhave been satisfied.
9206050284'920528
.PDR-ADOCK 05000424
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. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
NPF-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective upon issuance.
FOR THE NUCLEAR. REGULATORY COMMISSION J
David B.' Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: May 28, 1992
__________-______.-_________m
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UNITED STATES n
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ui NUCLEAR REGULATORY COMMISSION
'f WASHINoTON, D.C. 20556 o
,**o f GEORGIA POWER CQW.N_1 OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 30 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
'The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No.
NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of
. Georgia, and City of Dalton, Georgia (the licensees), dated November 12, 1991, as supplemented April 21, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules ana regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the prolisions cf tha Act, and the rules and regulations cf 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 set forth in 10 CFR Chapter I; 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 :.nd all applicable requirements have been satisfied.
I
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2.-
Accordingly,'the license;idLhereby amended-by page' changes 1to the
- Technical-Specifications-as-indicated intthe. attachment to this license amendment, and paragraph:2.C.(2)aof Facility:0perating License _No.
NPF-8111s hereby amended.to read as follows:
o
- Technical Specifications ~and-Environmental-Protection Plan The-Technical Specifications contained in Appendix A, as revised through Amendment No. 30, and 'he. Environmental-Protection Plan contained -in Appendix B, both of which:are attached hereto, are hereby incorporated-Linto -this license. :' GPC shall operate-the: facilityJ in accordance with-the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective upon issuance.
FOR THE NUCLEA'R REGULATORY COMMISSION.
1 David B. Matthews, Director Project Directorate-II-3 Division of Reactor Projects.- 1/II Office of Nuclear Reactor Regulation Attachmenti JTechnical-Specification-Changes; Datefof Issuance:' T4ayf28,.1992-e
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- ! ATTACHMENT TO LICENSE AMENDMENT N0i S1
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-FACILITY OPERATING LICENSE NO. NPF :
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00CKEI NO. 50-424-I TO LICENSE is':NDMENT No. 30 LFACILITY 0PERATING LICENSE NO. NPF.
-DOCKET NO. 50-425' Replace the following pages.of: the Appendix "A": Technical Specifications'with'
-the: enclosed pages. - The-revised pages are identified by Amendment 1 number and:
contain' ve'rticalElines' indicating the-areas of change.
Rem 3veLPaagi Insert Paaes 2-5' 2-5=
3/4 2-12 3/4 2 -_Bl3/4' 2-5_
B:3/4-2-5 T
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TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETP')INTS TOTAL SENSOR-ALLOWANCE ERROR E
FUNCTIONAL UNIT (TA)
Z_
(S)
TRIP SETPOINT.
ALLOWABLE VALUE d
9.
Pressurizer Pressure-Low 3.1 0.71 1.67
>1960 psig**
>1950 psig (PI-0455A,B&C, PI-0456 &
~
i PI-0456A, PI-0457 & PI-0457A, w
a-PI-0458 & PI-0458A) 10.
Pressurizer Pressure-high 3.1 0.71 1.67 (PI-0455A,8&C, PI-0456 &
-<2385 psig
-<2395 psig PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) 11.
Pressurizer Water Level-High 8.0 2.18 1.67
<92% of instrument
<93.9% of instrument (LI-0459A, LI-0460A, LI-0461) ipan span 12.
Reactor Coolant Flow-Low 2.5 1.87 0.60
>90% of loop
>89.4% of loop (LOOP 1 LOOP 2 LOOP 3 LOOP 4 Besign flow
- Fesign flow
- FI-0414 FI-0424 FI-0434 FI-0444, m
FI-0415 FI-0425 FI-0435 FI-0445 J.
FI-0416 FI-0426 FI-0436 FI-0446) 13.
Steam Generator Water Level Low-18.5 17.18 1.67
>18.5% (37.8)***
>17.6% (35.9)***
Low
-(21.8)***
(18.21)***
5f narrow range 5f narrow range (LOOP 1 LOOP 2 LOOP 3 LOOP 4 instrument span instrument span LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 pB LI-0519 LI-0529 LI-0539 LI-0549 mRR LI-0551 LI-0552 LI-0553 LI-0554) as 14.
Undervoltage - Reactor Coolant 6.0 0.58 0
>9600 vt
>9481 volts
((
Pumps I70% bus voltage)
I69% bus voltage)
PP 15.
Underfrequency - Reactor Coolant 3.3 0.50 0
>57.3 Hz 157.1 Hz gg Pumps
" Loop design flow = 93,600 gpm
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- Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and 33 1 second for lag.
CHANNEL CALIBRATION shall ensure that these time cor.stants are adjusted to these values.
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- The value stated inside the. parenthesis is for instrument that has the Swer tap at elevation 333"; the value stated outside the parenthesis is for instrumentation that has the lower tap at elevation 438".
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POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS LIMITINGCONDITICfFOROPERATION 3.2.5 The following DNB-related parameters shall be maintained within the limits:
a.
Reactor Coolant System Tavg (TI-0412, TI-0422, TI-0432, TI-0442),
5 592.5 F b.-
Pressurizer Pressure (PI-0455A,B&C, PI-0456 & PI-0456A, PI-0457 &
PI-0457A, PI-0458 & PI-0458A), 1 2199 psig*
c.
Reactor Coolant System Flow (FI-0414, FI-0415, FI-0416, FI-0424, FI-0425, FI-0426, FI-0434, FI-0435, FI-0436, FI-0444, FI-0445, i
FI-0446) 1 384,509 gpm**
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APPLICABILITY:
MODE 1.
ACTION:
With any of-the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.5.1 Reactor Coolant System T and Pressurizer Pressure shall be avg verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />..In the event of flow degradation, RCS flow rate shall be determined by precision heat balance within 7 days of detection of flow degradation.
4.2,5.2 The RCS flow rate indicators shall be subjected to CHANNEL CALIBRATION at each fuel loading and at least once per 18 months.
4.2.5.3 After each fuel loading, the RCS flow rate shall be determined by precision heat balance within 7 days after exceeding 90% RATED THERMAL POWER.- The RCS flow rate shall also be determined by precision heat balance at least once per 18 months. Within 7 days prior to performing the precision heat balance flow measurement, the instru-mentation used for performing the precision heat balance shall be calibrated.
The provisions of 4.0.4 are not applicable for perform-ing the precision heat balance flow measurement.
- Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWFR.
- Includes a 2.7% i ow measurement uncertainty.
V0GTLE UNITS - 1 & 2 3/4 2-13 Amendment ilo. 51 (Unit 1)
Amendment No. 30 (Unit 2)
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' POWER DISTRIBUTION LIMITS BASES-3/4.2.5 DNB PARAMETERS (Continued)
The measurement uncertainty for the RCS total flow is basea upon perform-ing a precision heat balance flow neasurement above 90% RATED THERMAL PCWER and using the results tc correlate the ficw indication channels with the measureo flow.
If a precision heat balance flow measurement is performed below 90%
RATED THERMAL POWER, the effect on the measurcaent uncertainty shall be taken into account. Potential fouling of the feedwater venturis which might not be detected could bias the results from the precision heat balance in a cen-conservative manner. Theref ore, a penalty cf 0.1% for undetected feedwater venturi fouling is included in the measurement uncertainty. Any fouling which might bias the RCS flow rate measurement greater than 0.1% may be detected by monitoring cnd trending various plant performance parameters.
If detected, action shall be taken before performing subsequent precision heat balance flow measurements, i.e., either the effect of the fouling shall be quantified and accounted for in the RCS flow rate measurement or the affected venturis shall be cleaned to eliminete the fouling. The indicated RCS flow value of 384,509 gpm corresponds to an analytical value of 374,400 gpm with allowance for measurement and indication untertainties.
The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the percmeters are restored within their limits following load changes and other expected transient operation. The 18 n,onth periodic measurement of the RCS total flow rate is adequate to detect fluw degradatict end ensure correlation of the flow indication channels with measured ficw such that the indicated percent flow will provide sufficient verification of the flow rate degraoation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis. A change in indicated percent flow which is greater than the instrument channel inaccuracies and parallax errors is an appropriate indication of RCS flow cegradation.
V0GTLE UNITS - 1 & 2 B 3/4 2-5 Amendment No. 51
- 1) nit 1 Amendment No. 30 Jnit 2
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