ML20083E974
| ML20083E974 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/19/1991 |
| 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 | |
| ML20083E975 | List: |
| References | |
| NPF-68-A-045, NPF-68-A-046, NPF-81-A-025 NUDOCS 9110030293 | |
| Download: ML20083E974 (16) | |
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NUCLC AR REGULATORY COMMISSION Af.A wAssi9atoN. o c tout.
GEORGIA POWER C0ftPA'iY OGLETHORPE POWER CORPORATION MttHICIPAL ELECTRIC AllTHOPITY Of GEORGIA ClTY OF DALTON, GEOPG1A
@CKETf40.504?4 V0GTLE ELECTRIC GEf4ERATif1G PLAf1T, UtilT 1 AMENDMENT 10 FACILITY OPERATif4G LICENSE Amendment flo. 45 License No. NPF-68 1.
The fluclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, linit 1 (the facility) Facility Operating License No. NPf-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo.
ration, finnicipal Electric Authority of Georoia, and City of Dalten, Georgia (the licensees) dated November ?9, 1990, as supplemented ilanuary 29 and March 6,1991, and as revised March 29, 1991, as supplemented August B, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended Ithe Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the apnlication, 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 set forth in 10 CFR Chapter I; l
0.
The issuance of this license amendment will not be inimical to the l
common defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in ac:ordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 9110030293 910919 PDR ADDCK 05000424 P
PDR i
. l 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. HPF.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. 45, 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 beginning with Vogtle Unit 1 Cycle 4 startup.
FOR THE NUCLEAR REGULATORY COMMIS$10N 4
fYh N. $lf4~f$r David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance; September 19, 1991 l-l-
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/ g,6* % gy, UNIT [D ST AT[S l$c //,g NUCLE AR REGULATORY COMMISSION 4.
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C[0RGI A POWER C0t!PAtiy OGLETHOPPE POWER CORPORAT10tl tilltllClPAt ELECTRIC AtlTHORITY OF GEOPG1 A CITY OF DAlT0tl, GEORGIA DOCKET f0. 60 474 V0GTLE ELECTRIC GEt1 ERAT 1tiG pt AtlT, tlfitT 1 At?Ef4Dt1Et4T TO FACit1TY OPERAT1t4G llCEHSE Amendment flo. 46 License tio, tiPF 68 1.
1 'e fluclear pequl6 tory Conmission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating plant, Unit 1 (the facility) Facility Operating License No. Npf-68 filed by the Georgia power Company, acting for itself, Oglethorpe power Corpo-ration,tiuoicipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated flovenber 29, 1990, as supplemented January 29 and fiarch 6,1991, and as revised liarch 79, 1991, as supplemented August 8, 1991, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CER Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commissient 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 1; D.
The issuance of this license 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 requlations and all applicable requirements have been satisfied.
.?-
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 ?.C.(2) of Facility Operating License No. flPf-68 is hereby anended to read as follows:
Technical Specifications and Environ'nental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment flo. 46, 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, 1
l 3.
This license amendment is ef fective beginning with Vogtle Unit ? Cycle 3 startup.
FOR THE NilCLEAR REGULATORY C0tmlSS10N
)$1kk-bl. JA Iynft David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
September 19. 1991 l
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UNITE D ST ATEs
!.$t, 'i NUCLE AR REGULATORY COMMISSION t
W ASHINGT ON, O C 20m c,, ' y j GEORGI A POWER C0?'PAftY OGtETHOPPE POWIR CORPORAT10tl Muti1CIPAL ELECTRIC ANTHORITY OF GEORGI A CITY OF DALT0tl, GEORGI A 00CKET tin. 50 4?S E'p CE_L _QD 'i Et1 ERAT 1t4G PL AtlT, Ut11T P, AKt10tKf4T,,TC FACILITY OPERATING LICEt1SE Amendment No. 25 License No, itPF-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 f acility) Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itse'.f, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated November 29 1990, as supplemented January 29 and liarch 6,1991, and as revised March 29, 1991, as supplemented August 8, 1991, 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 1; 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 endangerina the health and safety of the public, and (ii) that 'ach activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; D.
The issuance of this license 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.
l
2-2.
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-81 is hereby smended to read as follows:
4 Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 25, 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 beginning with Vogtle Unit 2 Cycle 3 startup.
FOR THE NUCLEAR REGULATORY COMMISSION i
W[r
[s/4: Al-David B. Hatthews, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes
= Date of issuance: September 19. 1991 P
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ATTACHMENT TO LICENSE AMENDHENT NOS. 45 AND 46 FACILITY OPERATitlG t ICENSE NO. NPF-68 AND LICENSE AMEtlDMENT NO. ?$
FAClllTY OPERATING LICENSE fl0. NPT-81 DOCKET NOS 50-4?4 AtlD 50-4?$
Replace the following pages of the Appendix "A" Technical Specifications ith the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Phase 1 is effective beginning with Unit 1 Cycle 4 reload, and Phase 2 is effective beginning with Unit 2 Cycle 3 reload.
Remove Pages insert Pages Phase 1 2-8 2-8 2-10 2,10 3/4 3-14 3/4 3-14 Phase 2 2-8 2-8 2 10 2-10 3/4 3-9 3/4 3-9 3/4 3-14 3/4 3-14 9
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THIS PAGE APPLICABLE TO UNIT 1 ONLY J.
<g TABLE 2.2-1 (Continued) d TABLE NOTATIGNS - UNIT 1 NOTE 1: OVERIEMPERATURE AT d
aT (1 + 1 5) Il + 1 5) $ AT, N - K 1
(1 + t 5) 1 (1 + 1 3) U (1 + 1 5) - T'] + K (P - P') - f (aI)j 2
3 t
(1 + 1 5) 3 3
8 e
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=
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=
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=
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$ 1.12 (UNIT 1);
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HOz V0GTLE UNITS - 1 & 2 2*10 Amendment No 45 (Unit 1) 1
{.
j TABLE 4.3-1 (Continued) l TABLE NOTA 110NS (Continued)
(10) Setpoint verification is not applicable.
(11) The TRIP ACTUATING DEVICE OPERATIONAL TES1 shall include independent verification of the OPERABIL11Y of the Undervoltage and Shunt trip of the t
Reactor Trip Breaker.
i (12) for Unit 2, the CHANNEL CAllBRATION shall includt the RTO bypass loops flow rate.
(13) Not used.
(14) The TRIP ACTUATING DEVICE OPERA 110NAL 1ES1 shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual i
Reactor Tri? function.
The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).
l t
(15) local manual shunt trip prior to placing breaker in service.
(16) Automatic undervoltage trip.
(17) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.
(18) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.
i l
l L
V0GTLE' UNITS < 1-& 2 3/4 3-14 Amendment No. 45 (Unit 1).
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TABLE 2.2-1 (Continued)'
I d
TABLE NOTATIONS E-NOTE 1: DVERTEMPERATURE AT Z
2 h
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AT
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T 5) $ AT (Kr - K 4
Ts3) - T 1 + K (P - P') - fs(AI))
3 3
g
~
l
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e-
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AT Measured ai
[
=
1 Lead-lag compensator on measured AT;
=
Ti, 12 Time constants utilized in lead-lag compensator for AT, ti >8s,
=
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=
1 + r35 4
13 Time constants utilized in the lag compensator for AT, 13 = 0 s; j
=
2 t
Indicated AT at RATED THERMAL POWER; l
AT
=
O K
< 1 12 i
2 i
0.0224/ F
[
K2
=
1 FE
((
f[I4 ne 'inction generated by the lead-lag compensator for T,,g l
=
gg dyna-c compensation; oo i
EE ts < 4 s;
- 28 s, T4, is Time constants utilized in the lead-lag compensator for Tavg,1
=
4 l
bb l
Average temperature, 'F; T
=
1[1 Lag compensator on measured Tyg;
=
T85 er f
Time constant utilized in the seasured T,yg lag compensator, Is = 0 s; i
=
Ts 2
T 2
I i
i
t 5
TABLE 2.2-1 (Continued) m g
TABLE NOTATIONS (Continued)
Z, v
i e
NOTE 3: OVERPOWER AT AT ((1 + r25) (1 + 1 5) $ AT, { K 1 + t 5) ( 1
)
- Ks ((1 (1 + r 5) T - 4 [T (T + 1 ) - T9 - f (aI t 5 ) ( 1 ) 1 m 4 1 5) e ( 55) 2 3 7 1 i a i Where: AT = Measured AT f 1[ 5 Lead-lag compensator on measured aT; = 1 5 ti, r2 Time constants utilized in lead-lag compensator = for AT, ty 18 5,12 $ 3 s; 1 Lag compensator on measured AT; = y. 3 13 Time constants utilized in the lag compensator for AT, i = ta=0s; } EE AT Indicated AT at RATED THERMAL POWER; i = aa 1 22 K < 1.08 4 Ea ?? - 0.02/*F for increasing average temperature and 3 0 for decreasing average 22 Ks temperature, Me 1P,5 The function generated by the rate-lag compensator for T dynamic = ,3 compensation, -EE 3? 17 Time constants utilized in the rate-lag compensator for T,yg, 17 3 10 s, = ms 7 1 Ts3 Lag compersator on measured T,yg; = l
TABLE 4.3-1
- REACTOR TRIP SYSTEM INSTRUMENTATION SURV"ILLANCE REQUIREMENTS TRIP
- d '
ANALOG ACTUATING MODES FOR m CHANNEL-DEVICE WHICH !E. CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE g FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED a a 1. -Manual Reactor Trip N. A. N. A. N.A. R(14) N.A. 1 2, 3, 4, 3 5 2. PowerRan5C,NI-0042B&C, ae, Neutron Flux (NI-0041B N NI-0043B&C,NI-0044B&C) a. High Setpoint 5 D(2,4), Q(17) 'N.A. N.A. 1, 2 M(3,4), Q(4,6), R(4,5) d b. Low Setpoint 5 R(4) S/U(1) N.A. N. A. 1,2 t' 3. Power Range, Neutron Flux, N.A. R(4) Q(17) N.A. N.A.
- 1. 2 High Positive Rate y-(NI-0041B&C, NI-0042B&C, NI-0043B&C,NI-0044B&C) e 4
Power Range, Neutron Flux, N.A. R(4) Q(17) N.A. N.A. 1, 2 High Negative Rate (NI-0041B&C,NI-0042B&C, yy NI-0043B&C,NI-00448&C)
- a d
@ g-5. Intemediate Range, S R(4,5) 5/U(1) N.A. N.A. I,2 Neutron Flux oo55 (NI-0035B,0&E,' _gy-NI-0036B,D&G) c 5. Source Range, Neutron Flux 5 R(4,5) 5/U(1),Q(9,17) N.A. N.A. 2, 3, 4, 5 ~u (NI-0031B,D&E, g NI-00328,D&G) 22 37'7. Overtemperature AT' S R Q(17) N.A. N.A. 1, 2 m (TDI-0411C,TDI-0421C, TDI-0431C,TDI-0441C)
1ABLE 4.3-1 (Continued) TABLENOTATIONS(Continued) 1 (10)Setpointverificationis,notapplicable. (11) The 1 RIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the OPERABIL11Y of the Undervoltage and Shunt trip of the ~ Reactor Trip Breaker. (12) Not used. l (13) Not used.. (14) The TRIP AC10ATING DEVICE OPERATIONAL 1ES1 shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits fo,- the Manual Reactor Trip function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s). (15) local-manual shunt trip-prior to placing breaker in service. (16) Automatic undervoltage trip. (17) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS. (18) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable. V0GTLE UNITS'- 1 & 2 3/4 3-14 Amendment.No. 46 Unit 1)- = Amendment No. 25 Unit 2)}}