ML20237J952
| ML20237J952 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/06/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20237J955 | List: |
| References | |
| DPR-29-A-102, DPR-30-A-099 NUDOCS 8708190027 | |
| Download: ML20237J952 (14) | |
Text
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UNITED STATES g
NUCLE AR REGULATORY COMMISSION
-E WASHINGTON, D. C. 20555 l
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COMMONWEALTH EDISON COMPANY
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l AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 l
QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 102 License No. DPR-29 l
l 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee)datedMay 14, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) l 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 (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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,
)
and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
kR ADO K 4
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2-B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as-revised through Amendment No.102, are hereby incorporated in the l
The licensee shall operate the facility in accordance with j
license.
the Technical Specifications.
f l
This license amendment is effective as of the date of its issuance.
i 3.
i FOR THE NUCLEAR REGULATORY COMMISSION V
A Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications l
1 Date of Issuance: August 6, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE N0. DPR-29 DOCA!.'T N0. 50-254 Revise the Appendix A Technical Specifications by removing the pages-identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.9/4.9 - 1*
3.9/4.9 - 1*
3.9/4.9 - 2 3.9/4.9 - 2 3.9/4.9 - 3 3.9/4.9 - 3 3.9/4.9 - 4 3.9/4.9 - 4 l
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- Page re-typed for editorial clarity only.
No changes made.
t QUAD-CITIES OPR-29 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Applicability:
Applicability
- Applies to the auxiliary electrical power Applies to the periodic testing system.
requirement of the auxiliary electrical system.
(
Objective; Objective:
To assure an adeouate supply of electri-To verify the operability of the auxil-cal power during plant operation.
tary electrical system
$ SPECIFICATIONS A.
hornal and Emergency A-C Auxiliary A.
Nornal and emergency A-C Auxiliary j
Power Power i
The reactor shall not be made criti-1.
a.
Each diesel generator shall cal unless all the following require-be manually started and ments are satisfied.
loaded once each nonth to demonstrate operational 1.
The Unit diesel generator and readiness. The test shall i
I the Unit 1/2 diesel generator continue until both the shall be operable.
diesel engine and the generator are at equilibrium conditions of temperature while full load output is reintained.
b.
During the nonthly generator test. the diesel-starting air compressor shall be checked for operation and its ability to recharge air receivert.
I t
c.
During the monthly generator test. the diesel fuel oil transfer pumps shall be operated.
2.
One 345-kV line. associated 2.
The status of the 345-kV lines, switchgear and the reserve associated switchgear, and the auxiliary power transformer reserve auxiliary power capable of carrying power transformer shall be l
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l 036aN 3.9/4.9-1 Amendnent No.102 1
j i
i OUAO-CITIES OPR-29 checked daily, to the unit shall be available.
3.
One other 345-kV line and unit 3.
The status of the additional source reserve aux transformer capable of power via the 4160-volt bus t1e l
shall be checked daily.
-l of carrying auxiliary power to an essential electrical bus of the unit through the 4160-volt bus tie shall be available.
4.
a.
The Unit engineered saf ety 4.
The Unit engineered safety.
features 4160-volt and 480-volt features 4160- volt buses buses shall be checked daily.
(13 1 and 14-1. Unit 1; 23-1 and 24-1. Unit 2) are energized, b.
The Unit engineered safety I
features 480- volt buses (18.
)
and 19. Unit 1 28 and 29.
Unit 2) are energized.
B.
Station Batteries 8.
Station Batteries 1.
Every week the specific gravity The unit 24/48-volt batteries, two and voltage of the pilot cell, j
station 125-volt batteries, the two the temperature of adjacent
)
station 250-volt batteries, and a
. cell. and overall battery 1
battery charger for each required voltage shall be seasured.
battery shall be operable before the J
reactor can be made critical.
2.
Every 3 months the measurement shall be made of the voltage of.
each cells to the nearest 0.01 volt. the specific gravity of l
each cells, and the temperature of every fifth cell.
3.
-Every refueling outage. the station batteries shall be subjected to a ratelload discharge test. Specific i
gravity and voltage of each cell shall be determined after the discharge.
C.
Electric Power Availability C.
Electrte Power Availability Whenever the reactor is in the Run The avatishtlity status of electric mode or for startup from a hot shut-power shall be checked daily.
j down condition, the availability of electric power shall be as specified in Specifications 3.9.A and 3.9.8 except as stated in Specifications l
3.9.C.1, 3.9.C.2. 3.9.C.2. and 3.9.E.
1.
From and after the date that incoming power is available f rom only one of the lines Specified l
in 3.9.A. cantinued reactor opeiation is permissible only during the succeeding 7 days,
3.9/4.9-2 Anendment No.
102 0364H
so QUAD-CITIES OPR-29 l
unless the second line is sooner l'
made available,providing both the Unit and unit 1/2 emergency diesel generators are operable.
2.
From and after the date the incoming power is not available i
f rom any line, continued reactor operatinn is permissible pro-viding both the Unit and Untt d
1/2 emergency diesel generators are operating, all core and containment cooling systems are
]
operable, reactor power level ts reduced to a0% of rated. and the J
NRC 15 notified within 2a hours of the situation. the precau -
tiens to be taken during this period.and the plans for prompt restoration of incoming power.
1 I
3.
From and after the date that one of the two 125/250-volt battery systems is made or f ound to be inoperable for any reason.
continued reactor operation is permissible only during the succeeding 3 days unless such battery system is sooner made operable.
D.
Diesel Fuel D.
Diesel Fuel Once a month the cuantity of diesel There shall be a minimum of 10.000 fuel available shall be logged.
gallons of diesel fuel supply on site
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for each diesel generator.
'Once a month a sample of diesel fuel shall be checked for cuality.
E.
Diesel-Generator Operability E.
Diesel-Generator Operability 1.
Whenever the reactor is in the 1,
When it is determined that either the unit or shared diesel
$tartup/ Hot Standby or Run mode and the unit or shared diesel generator is inoperable, all
. low-pressure core cooling generators and/or their respec-systems and all loops of the ttve associated buses are made or f ound to be inoperable for
. containment cooling modes of the-any reason. except as specified RHR system associated with the in Specification 3.9.E.2 below, operable diesel generator shall continued reactor operation is be demonstrated to be operable i
permissible only during the suc-immediately and daily ceeding 7 days provided that all thereafter. The operaole diesel of the low-pressure core cooling generator shall be 6 demonstrated and all loops of the containment to be operable immediately and cooling mode of the RHR system daily thereafter, associated with the operable j
2.
During each refueling outage, a diesel generttor shall be oper-able. and two offsite lines as simulated loss of of f-site power -
a specifted in 3.9.A are l
in conjunction with an ECCS initiation signal test shall be 3
available. If this requirement cannot be met, an orderly shut-performed on the 4160 volt emer.
gency bus by-down shall be ingtiated and the 4
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'i Amensment Wo. ' 102 3;9/4.9-3 036aN i
1
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QUAD-CITIES DPR-29 l
a.
Verifying de-energ12ation of reactor shall be in the cold the emergency buses, and shutdown condition within 24 load shedding from the emergency buses.
W.
Specification 3.9.E.1 shall not b.
Verifying the diesel starts apply when a diesel generator from ambient conditicr. on-j has been mace inoperable for a i
the auto-start signal,
' period not to exceed 1-1/2 hours energtzes the emergency j
for the purpose of conducting buses with permanently preventative maintenance. Addi-connected loads, energtres r
tionally, preventative mainten-the auto-connected emergency l
ance shall not be undertaken loads through the load unless two off-site lines as specified in 3.9.A are available l sequencer, and operates for greater than 5 minutes while and the alternate diesel its generator is loadtd with generator has been demon-the emergency loads.
strated to be operable.
l 3.
When the reactor is in the Cold Shutdown or Refueling mode, a mininum of one diesel generator (either the Unit diesel genera-tor or the Unit 1/2 diesel generator.1 shall be operable whenever any work is being done which has the potential for draining the vessel, secondary centairment is required, or a q
core or containment cooling system is reqJ1 red.
F.
REACTOR PROTECTION BUS P0wfR F.
REACTOR PROTECTION BUS POWER MONITORING SYSTEM.
MONITORING SYSTEM 1.
The RPS Bus power monitoring-1.
Two RPS electric power monitor-system instrumentation shall be ing channels for each inservice determined DPERABLE:
RPS MG set or inservice alter-nate power source shall tt At least once per 6 months 4.
OPERABLE except when the reactor by performing a chans.e1 is in the 5HUTDOWN sede.
functional test, and 2.
a.
With one RPS electric power b.
At least once per operating.
monitoring channel fer an cycle by demonstrating the inservice RPS MG set or operability of overvoltage.
inservice alternate power undervoltage, ant underfre-i source incoerable, restore quency protective instru-l the inoperat.1e channel to mentation by performance of..
l OPPERABLE status within 72' a channel calibration hturs or remove the assoct-I a,ed RPS MG set or alteri
. including simulated auto-~
I matic activation of the.
nste power source from protective relays, tripping
'ervice.
logic, and output circuit breakers -and verifying the f
b.
With both RPS electric power following setpotnts:
monitortng channels for an inservice RP! MG set or l
(1) overvoltage 126.5 V = 2.5%
inservice alternate power' Min. 123.3 V' L
source inoperable. restore Max. 129.6 V l
at least one channel to I
OPERABLE status within 30 (2) undervoltage '108 V = 2.5%
l minutes, or rear,ve the Min. 105.3 V i
associated eP3 NG set or Max. 110.7 V
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alternate power source from l
service.
(3) underfrequency 56.0 H2 1 1%-
j of 60 H2.
Min. 55.4 Hz Max. 56.6 Hz I
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l Amendment No.
102 3.9/4.9-4 0364H l
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_ psnay%j UNITED STATES
[
NUCLEAR REGULATORY COMMISSION
.p WASHINGTON, D. C. 20555
...../
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1 i
COMMONWEALTH EDISON COMPANY I
AND l
IOWA-ILLINCIS GAS AND ELECTRIC COMPANY l
DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-30 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the l
licensee) dated May 14,.1986, complies with the standards and I
requirementsoftheAtomicEnergyActof1954,asamended(theAct) 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 4
Commission; C.
There is reasonable assurance (1) that the activities authorized 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 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 Comission's regulations and all aoplicable 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, and paragraph 3.8. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
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. B.-
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are hereby incorporated in the license. The. licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ' effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
bf V
I Daniel R. Muller, Director Project Directorate III Division of Reactor Projects - III, IV, V and Special Projects-
Attachment:
Changes to the Technical Specifications Date of Issuance: August 6, 1987 l
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l ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265' Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.9/4.9 - 1*
3.9/4.9 - 1*
f 3.9/4.9 - 2 3.9/4.9 - 2 3.9/4.9 - 3 3.9/4.9 - 3 3.9/4.9 - 4 3.9/4.9 - 4 l
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- Page re-typed for editorial clarity only.
No changes made, j
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4 QUAO-CI?!ES OPR-30 3.9/4.9 AUXIL!ARY ELECTRICAL SYSTEMS
. SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION Applicability:
Applicability:
Applies to the' auxiliary electrical power Applies to the periodic testing requirement of the auxiliary electrical
_l System.
system.
Objective:
Objective:
To assure an adequate supply of electri-To verify the operability of the aux 11-tary electrical system cal power during plant operation.
$PECIFICATIDNS A.
Norwul and emergency A-C Auxiltary A.
Normal and Emergency A-C Auxiliary Power Power 1.
a.
Each diesel generator shall The reactor shall not be made criti-be manually started and cal unless all the following requtre-loaded once each month to.
ments are satisfied.
demonstrate operational readiness. The test shall 1.
The Unit diesel generator and continue until both the -
1 the Unit 1/2 diesel generator diesel engine and the shall be operable.
generator are at ecutlibrium conditions of temperature while full load output is maintained.
b.
During the monthly generator test. the diesel-starting air compressor shall be checked for operation and its ability to recharge air -
receivers, c.
During the monthly generator test, the diesel fuel oil transfer pumps shall be operated.
2.
The status of the 345-kV lines.
2.
One 345-kV line, associated associated switchgear, and the switchgear, and the reserve reserve auxiliary power auxiliary power transformer transformer shall be j
capable of carrying power I
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Amendment No. 99 '
3.9/4.9-1 0364H
QUAC-CITIES OPR-30 checked daily.
to the unit shall be available.
3 The status of the additional source 3.
One other 345-kV line and unit of power via the 4160-volt bus tie l
reserve aux transformer capable shall be checked daily.
of carrying auxiliary power to an essent;al electrical bus of the unit through the 4160-volt bus tie shall be availatie.
4.
The Unit engineered safety 4.
a.
The Unit engineered safety features 4160-volt and 480-volt features 4160- volt buses buses shall be checked daily, (13-1 and 14-1, Unit 1: 23-1 and 24-1, Unit 2) are energized.
b.
The Unit engineered safety f
features 480- volt buses (18 and 19. Unit 1: 28 ar j 29, Unit 2) are energized.
B.
Station Batteries B.
Station Batteries 1.
Every week tt.e specific gravity The unit 24/48-volt batteries, two and voltage of the pilot cell, station 125-volt batteries, the two the temperature of adjacent station 250-volt battertes, and a cell, and overall battery battery charger for each required voltage shall be reasured.
battery shall be operable before the reactor can be made critical.
2.
Every 3 months the measurement shall be rude of the voltage of each cells to the nes-it 0.01 volt, the specific gt-ity of each cells, and the temperature of every fifth cell.
3.
Every refueling outage the station batteries shall be subjected to a ratedload discharge test. Spe:1fic gravity and voltage of each cell shall be determined after the discharge.
C.
Electric Power Availability C.
Electric Power Availability The availability status of electric Whe ever the reactor is in the Run power shall be checked daily.
mode ar for startup from a hot shut-own condition. the availability of electric power shall be as specified in Specifications 3.9.A and 3.9.8 except as stated in Specifications 3.9.C.1, 3.9.C.2, 3 9.C.3 and 3.9.E.
1.
From and af ter the date that inc9 ming power is available from only one of the lines specified l
in 3.9. A continued reactor operation is permissible only during the succeeding 7 (tys, Amenoment No. 99 3.9/4.9-2 036tH
1 i
OUAD-CI?!ES OPR-30 l
unless the second line is sooner l
made available,oroviding both the Unit and Unit 1/2 emergency diese) generators are l
l 2.
From and after the date the
-l
[
incoming power is not available j
from any Itne, continued reactor l
operation is permissible pro-i viding both the Unit and Unit 1/2 emergency diesel generators l
are operating, all core and i
containment cooling systems are l
operable, reactor power level is reduced to 40% of rated, aad the NRC is notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
of the situation, the precau-
.-tions to be taken during this period.and the plans for prompt restoration of incoming power.
l 3.
From and after the date that one of the two 125/250-volt battery systems is made or found to be s
inoperable for any reason, i
continued reactor operation is permissible only during the succeeding 3 days unless such battery system is sooner made operable.
J D.
Diesel Fuel D.
Diesel Fuel There sha*.i be a minimum of 10,000 Once a month the quantity of diesel gallons of diesel fuel supply on site fuel available shall be logged.
for each diesel generator.
Once a month a sample of diesel fuel shall be checked for quality.
E.
Diesel-Genei uer Operability E.
Diesel-Generator Operability 1.
Whenever the reactor is in the 1.
When it is determined that Startup/ Hot Standby or Run mode either the unit or shared diesel and the untt or shared diesel generator is inoperable. 411 generators and/or their respec.
1ow-pressure core coolin, tive associated buses are made systems and all loops of the or found to be inoperable f or containment cooling moces of the.
l any reason, except as specified RHR system associated with the in Specification 3.9.E.2 below, operable diesel generator shall continued reactor operation is be demonstrated to be operable permissible only during the suc-imediately and daily creding 7 days provided that all thereafter. The operable diesel of the low-pressure core cooling generator shall be demonstrated and all loops of the containment to be operable imedtately and cooling mode cf the RHR system daily thereafter, associated with the operable diesel generator shall be oper.
2.
During each refueling outage, a able and two offsite lines as l
simulated loss of of f-site power specified in 3.9.A are I
in conjunction with an ECCS available. If this requirement initiation signal test shall be cannot be met, an orderly shut-performed on the 4160 volt emer-down shall t.e initiated and the gency bus by:
Amenenent No. 99 3.9/4.9-3 0364H
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QU AD-CITIES j
OPR-30 a.
Verifying de-energization of l
reactor shall be in the cold the emergency buses, and j
chutdown condition within 24 load shedding from the l
hours.
j l
emergency buses, 2.
'5pecif ication 3.9.E.1 shall not b.
Verifying the diesel starts l
apply when a dicsel generator f rom ambient cond" ton on has been made inoperable for a the auto-start signal.
period not to exceed 1-1/2 hours energizes the emergency l
l for the purpose of conducting buses with permanently preventative maintenance. Addi-l connected loads, energizes tionally. preventative mainten-the auto-connected emergency ance shall not be undertaken loads through the load unless two off-51te lines as a
specified in 3.9. A are available
}
sequencer, and operates f or greater than 5 minutes while and the alternate diesel 1.5 generator 15 loaded with generator has been denon-the emergency loads.
strated to be operable.
l 3.
When the reactor is in the Cold Shutdown or Refueling mode, a l
minimum of one diesel generator (either the Unit diesel genera-ter or the Unit 1/2 diesel generator) shall be operable whenever any work is being done which has the potential for draining the vessel. secondary containment is required, or a core or containment cooling system is required.
F.
REACTOR PROTECTION BUS POWER F.
REACTOR PROTECTION BUS POWER MONITORING SYSTEM MONIT0k!NG SYSTEM 1.
The RPS Bus power monitoring 1.
Two RPS electric power monitor-system instrumentation shall be ing channels for each inservice determined OPERABLE:
RPS F1 set or inservice alter-nate power source shall be At least once per 6 months a.
OPERABLE except when the reactor by perf orming a channel is in the SHUTOOWN mode.
functional test, and 2.
a.
With one RPS electric power b.
At least once per operating monitoring channel for an cycle by demonstrating the inservice RPS HG set or operability of overvoltage, inservice alternate power undervoltage, and underfre-source inoperable, restore quency protective instru.
the inoperable channel to nentation by performance of OPPERABLE status within 72 a channel calibration hours or renove the associ-including simulated auto-ated RPS MG set or alter-matic activation of the nate power source from protective relays, tripping service.
logic, and output circutt breakers. and verifying the b.
With both RPS electric power following setpoints; monitoring channels for an intervice RPS MG set or (1) overvoltage 126.5 V = 2.5%
inservice alternate power Min.
123.3 V source inoperable, restore Max. 129.6 V at least one channel to OPERABLE status within 30 (2) undervoltage 108 V = 2.5%
minutes, or remove the
- Min, 105.3 V associated RPS HG set or Max, 110.7 V alternate power source from service.
(3) underfreQuency 56.0 Hz i 11 of 60 HZ Min. 55.4 Hz Max. 56.6 Hz Amensment No. 99 3.9/4.9-4 0364H