ML19317F728
| ML19317F728 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/08/1977 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317F721 | List: |
| References | |
| NUDOCS 8001230617 | |
| Download: ML19317F728 (13) | |
Text
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THE TOLEEC EDISGI CO2NTI A__N.D_
'IHC CIIVEIRID ELECTRIC ILLUMRiATING CCNPNiY D
D DOCKETlO_. 50-346 voE m
- g-C.WIS-GEUSC_'."_"_7_'2 WJnTR STATICI, (. NIT t:0. I k
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,Vic&.ec TO ?ACILITY OPERATDiG LICENSE v
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_.a AmenI*ent '.4c.
4 Licents :ic, tGF-3 1.
The Nuclear Pegulatory Cc::3ission (the Coe: mission) has fcurd that:
A.
The aaplication for amncrent by tne Toledo Edizen Ccmeany (the 1icensee) dated June 24, 1977, cceplles with the stcrdards ard racuirec:ents of the Atomic Energy Act of 1954, as amended (the Act) and the Ccer.ission's rulas and regu19 tens set forta in 10 CPR Chapter I; B.
The facility will ocerata in centerrif ty with the apclicatien, the provisions of tne Act, and the rules and regulations of the Ccaniccien; C.
There is reascnacle assurance (i) rnat the activities autheri:od by tnis amer 4 Tent can be cerducted without erdarrierinc the hoalth and safety of the puolic, and (ii) that such act ivitiec vill ce ccnducted in comcliance with the Ccenissicn'a rnaulations:
D.
The issuance of this cendmnt will not ce inimical to tne c=cen i
defence and security or to the health and safety of the puclic; and G.
The ic:uance of this awndaent is in accordance with 10 CFR Part 51 of the Cornission's regulations and all apclicacia racuira-ments nave been satistied.
2.
Accordirgly, the license is amended oy changes to the Technical Specifications as indicated in the attachant to this license amerd-ment, and paragraph 2.C.(2) of facility Cperating License tio. NPF-3 is nerecy a: ended to read as follows:
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- NRC FORM 318 (9 76) NRCM 0240 W un s. eovanmusw? painvene orrican,seve_. eeW,
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2-2.C(2) Technical Scecificatiens The Technical Scecifications contained in Acperxtices A and 3, as revised throtz;h icerd::ent No. 4, are herecy incarcorated in the license. Toledo Edison Comcany chall coerate the facility in accordance with the Technical Specifications.
3.
Ibis license amerdent is effective as of the date of its issuance.
FCil THE NUCIEAR REGJI/CCFi CCtE4ISSION Orignal sh;ned by John F. Stols, Chief Iight Water Reactors 3 ranch 3o.1 Division of Pro Mt :2nage& nt at t ach: rent :
Charges to the Technical Egecification Date of Issuance: ' M 0 8.a...
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ATTACHMZff 'IO LICDEE A".DiDMDTI' l0. 4 PACILITY CPEPATDf3 LICCEE ?O. :lPP-3 DOCKm7, No. 50-346 Peplace tne following pages of the Appendix "A" Technical Soecifications witn the enclosed pages. De revised pages are identified oy Amencment nurber and contains vertical lines indicating the area of changee ne corresconding overleaf pages are also provided to maintain c%..: ment cocpleteness.
Pages 3/4 3-25 3/4 3-26 3/4 3-23 3/4 3-30 3/4 4-1 3/4 4-2 Also enclosed are cages 3/4 4-1 anc 3/4 4-2 wnien were incorrectly nu::rered as 3/4 4-2 and 3/4 4-3 by Anendment No.1.
The reolacement pages submitted witn Amerm ent No. I sr.ould te destroyed.
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NRC PORM Sts t9 76) NRCM 0240 W u. s. oovsommeant reenvine orric as nove - eawa4 1
m THE 'IOLEDO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1
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AMENDMENT 'IO FACILITY OPERATING LICENSE Amendment No. 4 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application fot sendment by the Toledo Edison Comoany (the licensee) dated June 24, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (i) that the activities authorizM by this amendment can be conducted without endangering the heal * '.
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common dcfense 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 Comission's regulations and all applicable regaire-ments have been satisfied.
2.
Accordi.yly, the license is amended by changes to the Technical Specifictulons as-indicated in the attschment to this license amend-ment, and wragraph 2.C.(2) of facility Operating License No. NPF-3 is hereby amended to read as follows:
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. 2.C(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 4, are hereby incorporated in the license. Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
R THE NUCLEAR REGUIMORY CCM4ISSION
( )r L.0 "
Joh F. Stolz,' Chief p ht Water Reactors Branch No. 1 Division of Project Management
Attachment:
Changes to the Technical Specifications Date of Issuance:
JUL 0 81977 I
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s ATTACHMDff TO LICENSE AMDF41Efr NO. 4 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Arendirent number and contains vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain do.cment empleteness.
Pages 3/4 3-25 3/4 3-26 3/4 3-2fs 3/4 3-30 3/4 4-1 3/4 4-2 Also enclosed are pages 3/4 4-1 and 3/4 4-2 which were incorrectly nutered as 3/4 4-2 and 3/4 4-3 by Amendment No.1.
The replacement pages su!:taitted with Amendment No. I should be destroyed.
1 i
TABLE 3.3-11(Continuedl
)
O
$TEAMAhoFltbWATERRUPTURtCONTROL$YSTEMINSTRtlHENTATION v>
as 01 MINIMUM M
TOTALNO.
CilANNELS CilANNELS
(
FUNCTIONAL UNIT _
M OF CllANNEL$
TO TRIP OPERABLE ACTION zG 2.
Feedwater/ Steam Generrdor Differential Pressure - liigh
)
Instrument Channels 2
1 2
13#
a.
PDS 2685A Feedwater/ Steam Generator 2 Channel 2 PDS 2685B Feeduater/ Steam Cenerator 2 Channel 2 b.
PDS 2685C Feedwater/Stean. Gener8 tor 2 Channel 1 PDS 26850 Feedwater/ Steam Generator 2 Channel 1 M
c.
PDS 2686A Feedwater/ Steam Generator 1 Channel 1 PDS 26868 Feedwater/ Steam Generator 1 Channel 1 O!
d.
PDS 2686C Feedwater/ Steam Generator 1 Channel 2 PDS 26860 feedwater/ Steam Generator 1 Channel 2 3.
Steam Generator Level - Low Instrument Channels 2
1 2
13#
a.
LSLL SP988 Steam Generator 1 Channel 1 LSLL SP9B9 Steam Generator 1 Channel I b.
LSLL SP9A6 Steam Generator 2 Channel 1 LSLL SP9A7 Steam Generator 2 Channel 1 5
c.
LSLL SP9A8 Steam Generator 2 Channel 2 g
LSLL SP9A9 Steam Generator 2 Channel 2 3
3
TABLE 3.3-11(Continued)_
O STEAM Aku FtEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION T
=0 MINIMUM N
TOTALNO.
CilANNELS CHANNELS 0F CilANNELS TO TRIP OPERABLE ACTION FUNCTIONAL UNIT cz 4
3.
Steam Generator Level - Low Instrument a
Channels (continued) d.
LSLL SP986 Steam Generator 1 Channel 2 LSLL SP987 Steam Geaerator 1 Channel 2 4.
Loss of RCP Channels 2
1 2
13#
5.
ManualInitiation(Pushbuttons) a.
Steam Pressure - low 4
2 4
14 Y
b.
Level Steam Generator - low 2
1 2
14 M
c.
Feedwater a P - liigh 2
1 2
14 d.
Loss of aCP's 2
1 2
14
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A TABLE 3.3-11 (Continued)
TABLE NOTATION
- May be bypassed when steam pressure is below 650 psig.
Bypass shall be automatically removed when the steam pressure exceeds 650 psig.
- The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than the Total Number of Channels operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable section of the channel is placed in the tripped condition within i hour.
ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
DAVIS-BESSE, UNIT 1 3/4 3-27
TABLE 3.3-12 E
STEAMANDFEFDWATERRUPTURECONTROL$YSTEM
_INSTRUMENTAT10N TlilP Itii%INIS_
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TRIP stiPOINTS ALLOWAELE VALUES FUNCTIONAL UNITS E
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>591.hpstg
> 591.6 psig*
p 1.
Steam Line Pressure - Low E586.6psig**
g a
N
> 26"HO
> 20" H 0*
2.
Steam Generator level - Low 2
> 18.87 11 0**
2 197.6 pside Steam Generator Fer.dwater Differential Presrure - illgh(2) 4 197.6 psid 3.
4
{199.6psid**
< 1384.6 amps #
4.
Reactor Coolant Pumps - Loss of High < 13M.6 amps E106.5 amps #
Low E 106.5 amps "3
w (I) Measured above the lower steam generator tubesheet.
(2)Where differential pressure is steam generator minus feedwater pressure.
" Allowable Value for CllANNEL FUNCTIONAL TEST
[
" Allowable Value for CllANNCL CALIBRATION I 110wable Value for CllANNEL FUNCTIONAL TEST and CllANNEL CAllBhATION h
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rt 2*
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TABLE 3.3-13 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIMES ACTUATED EOUIPMENT RESPONSE TIME IN SECONDS 1.
Auxiliary Feed Pump
- E 40 2.
Main Steam Isolation Valves E 6 3.
Main Feedwater Valves a.
Main Control
- E 8 b.
Startup Control
- L 13 c.
Stop Valve dL 16 4.
Turbine Stop Valves E 6 DAVIS-BESSE, UNIT 1 3/4 3-29
TABLE 4.3-11 0
STEAM AND FEE 0 WATER RUPTURE CONTR0l 3YSTEM Y'
7NSTRUM[hTATl0N SilliVEllfANCE R[i}0lREMENTT E
"w CIIANNEL CllANNEL CilANNEL FUNCTIONAL c
h FUNCTIONAL UNIT CllECK CAllllRATION_
TEST 1.
Instrument Channel 3
a.
Steam Line Pressure - Low S
R H
b.
Steam Generator Level - Low S
R M
l c.
R H
Differential Pressure-liigh d.
' Reactor Coolant Pumps-Loss of R
H g
2.
Manual Actuation NA NA R
/
g a
.E h
o o
m 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.4.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.
APPLICABILITY: As noted below, but excluding MODE 6.*
ACTION:
MODES 1 and 2:
a.
With one reactor coolant pump not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 80.7% of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operating:
1.
High Flux 2.
Flux-aFlux-Flow b.
With one reactor cooiant pump in each loop not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 53.0% of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with one reactor coolant pump operating in each loop:
1.
High Flux 2.
Flux-aFlux-Flow
\\
- See Special Test Exception 3.10.3.
1 i
l DAVIS-BESSE, UNIT 1 3/4 4-1 1
m
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REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
MODES 3, 4 and 5:
Operation may proceed provided at least one reactor coolant loop a.
is in operation with an associated reactor coolant pump or decay I
heat removal pump
- b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
- All reactor coolant pumps and decay heat removal train pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to acconnodate decay heat removal pump switching operations, provided no operations are permitted which could cause dilution of the reactor coolant system boron concentration.
SURVEILLANCE REQUIREMENTS 4.4.1 The Reactor protective Instrumentation channels specified in the applicable ACTION statement above shall be verified to have had their trip setpoints changed to the values specified in Specification 2.2.1 for the applicable number of reactor coolant pumps operating either:
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after switching to a different pump combination a.
if the switch is made while operating, or b.
Prior to reactor criticality if the switch is made while shutdown.
l DAVIS-BESSE, UNIT 1 3/4 4-2 Amendment No. 1 l
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