ML20235W827
| ML20235W827 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/09/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20235W830 | List: |
| References | |
| DPR-19-A-096, DPR-25-A-091 NUDOCS 8710190050 | |
| Download: ML20235W827 (16) | |
Text
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UNITED STATES 58 NUCLEAR REGULATORY COMMISSION I
(g; WASHINGTON, D. C. 20666 l
COMMONWEALTH EDIS0N COMPANY 1
DOCKET N0. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT NO. 2 j
AMENDMENT'TO PROVISIONAL OPERATING LICENSE Amendment No. 96 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (thelicensee)datedMay 14, 1986, 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 I
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 Commission; 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 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 j
been satisfied.
l 8710190050 871009 PDR ADOCK 05000237 P
PDR li
1 l
. 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 Provisional Operating License No. DPR-19.is hereby-amended to read as follows:
B.
' Technical Specifications:
The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, 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 COMMIS ION
/
t'
/ff J
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of-Issuance: October 9,1987 i
L -_-__-_ - -__ _ _ _ _ _ -
1
.3, l
J.
ATTACHMENT TO LICENSE AMENDMENT N0. 96 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 50-237 f-
- 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 3/4 9-1 3/4 9-1 3/4 9 3/4 9-2 3/4 9-3 3/4 9-3 3/4 9-4 3/4 9-4 B'3/4 9-7 B 3/4 9-7 l
I w____._-___--___.-_.-__-_.__
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DRESDEN II DFR-19 m
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Anindmint No. 7d, p'2, %f, 96 j
y 4-1 E
~3.9 ' LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT AUXILIARY ELECTRICAL SYSTEMS AUXILIARY ELECTRICAL SYSTEMS.
1 i
Applicability:
Agglicability:
l Applies'to the auxilinry Applies to the periodic testing l
electrical power systerv requirements ef,the'adxiliary
.i electrical systen.
I Objective:
Objective:
4 To assure an adequate supply
' Verify the opera'bility.of the.
of. electrical power during auxiliary electridal' system.
~
plant operation, Specification:
Specifiestjon:
A.
The reactor shall not be A.
Station Batteries made critical.unless all the following requirements are satisfied:
l.
1.
One 138 KV line, 1.
Every week the specific associated switchgear, gravity, voltage and and the reserve temperature of the auxiliary power pilot cell and transformer capable overall batte:ry of carrying power to voltage shall Unit 2 shq11 be be :neasured.
availabic.
2.
The Dresden 2 diesel 2.
Every three months the generator and the measurements shall be Unit 2/3 diesel
.made of voltage of each generator shall be cell to nearest 0.01 operable.
volt, specific gravity of each cell, and temperature of every fifth. cell.
7 3.
One 345 KV line from 3.
Every refueling outage, Unit 3 capable of the unit's batteries c
carrying auxiliary power shall b9 suhjected to a to an essential electrical rate.1 load discharge i
bus of Unit 2-through;the test' Determine 4160 volt hus Lie shall be specific gravity and available, voltage of each cell after the discharge.
3/4.9-1 3693a 3124A E _ _ _ _ _ _ _ _ _ _
DRESDEN II DPR-19 pd, f, 96 6
Amendment No.
3.9 LIMITING CONDITION FOR OPERATION, 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
If this specification has been complied with for a particular battery for Dresden Unit 3, it shall not be required for Dresden Unit 2.
4.
(a) 4160 volt buses 23-1 and 24-1 are energized.
(b) 480 volt buses 28 and 29 are energized.
5.
The unit 24/48 volt batteries, the two station 125 volt batteries and the two station 250 volt batteries and a battery charger for each required batteey are operable.
B.
Except when the reactor B.
N/A is in the Cold Shutdown or Refueling modes with the head off, the availability of electric power shall be as specified in 3.9.A. except as specified in 3.9.B.1, 3.9.B.2, and 3.9.B.3.
1.
From and after the date that incoming power is available from only one of the lines specified in 3.9.A reactor operation in 3/4.9-2 3693a 3124A J2 _
S DRESDEN II-'
. DPR-19
}d, 9, 96 6
Amendment N3.
~ '
3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
permissible only during the succeeding seven days unless the second line is sooner placed in service providing both the Unit 2 and Unit 2/3 emergency diesel generators are-operable. From and after the date that incoming power is not available from any line, reactor operation is permissible providing both the. Unit 2 and Unit 2/3 emergency diesel' generators are operating and all core and containment cooling systems are operable and 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 /> of the situation, the precautions to be taken during this situation, and the plans for prompt restoration of incoming power.
2.
.From and after the date that one of the diesel generators-and/or its associated bus is made or found to be inoperable for any reason, reactor operation is permissible according to Specification 3.5/4.5F and 3.9D only during the succeeding seven days unless such dicuel generator and/or bus'is sooner made 3/4.9-3 3693a 3124A t
w
m DRESDEN II-DPR-19 h
6
?"1 AmendmentNo.ps,.P.9,96 3.'9 ' LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT-(Cont'd.)
(Cont'd.)
operable..provided that during
'such seven days the operable diesel generator shall be demonstrated to be operable at least once each day and two off-site lines as specified in 3.9.A. are available.
The specified 7 day outage period will apply except for spring of 1986, at which time an additional 7 days (14 total) will be allowed, on a one' time only basis, to complete 10CFR 50 Appendix R modifications to the 2/3.
Diesel Generator.
3.
From and after the date that.
one of the two 125 or 250V battery systems is made or i
found to be inoperable, except as specified in 3.9.B.4a or b, Unit shutdown shall be initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the unit shall be in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the failed battery can be sooner made operable.
l 4.
a.
Each 125 or 250 volt battery may be inoperable for a maximum of 7 days per operating cycle for maintenance and testing.
b.
If it is determined that a battery need be replaced.
as a result of maintenance or testing, a specific l
battery may be inoperable for en additional 7 days per operating cycle.
i 3/4.9-4 l
3693a 3124A
DRESDEN II DpR-19 Amendment ND. yd,]pf,96.
3.9:
LIMITING CONDITION FOR OPERATION BASES
~
h A.
The general objective of this Specification'is to assure an J'
adequate source of electrical power to operate the auxiliaries.
O during plant operation, to operate facilities to cool and
' lubricate the plant during shutdown, and to operate the engineered safeguards.following an' accident. There are three sources of electrical energy available; namely, the 138 KV'
~
transmission system, the diesel generators, and the 345 KV transmission system through'the 4160 volt bus tie.
The d-c supply is required for control and motive power for switchgear and engineered safety' features.
The electrical.
power required provides for the maximum availability of power;
'l
'i.e.,'one active off-site source and a back-up source of off-site power and the maximum amount of on-site sources.
B.
Auxiliary power for Unit 2 is supplied from two sources, either the Unit 2 auxiliary transformer or the Unit 2 reserve auxiliary transformer.
Both of these transformers are sized to carry.100% of the auxiliary load.
If the reserve auxiliary
~
transformer is lost, the unit can continue to run for 7 days since the unit auxiliary transformer is available and both diesel generators are operational. A reduced period is pro-vided since if an accident occurs during this period, the unit would trip and power to the unit auxiliary transformer would c
be lost and the dies,is would be'the only source of power.
In the normal mode of operation the 138 KV system is operating and two diesel generators are operational.
One diesel gener-ator may be allowed out of service based on the availability of power to the 138 KV switchyard, a source of power available from the 345 KV system through a 4160 volt bus tie end the fact that one diesel carries sufficient engineered safeguards l
equipment to cover all breaks.
Off-site power is quite re-liable.
In the last 25 years there has only been one instance in which all off-site power was lost at a Commonwealth Edison generating station, Two battery chargers are supplied for each of the 125 volt batteries, while for the 250 volt system a battery charger is supplied for each battery and a third battery charger acts as a shared unit.
Thus, on loss of a battery charger, another battery charger is available.
Since an alternate charger is available, one battery charger per unit for the 125 volt and i
one battery charger overall for the 250 volt battery system can be out of service for thirty days. The system becomes inoperable whenever there is a' loss of the battery or loss of both chargers for that system and a battery voltage of 105 volts for the 125 or 210 volts for the 250 volt batteries.
B 3/4.9-7 3693a 3124A
o nerg'o UNITED STATES.
g 8
NUCLEAR REGULATORY COMMISSION o
((
E WASHINGTON, D. C. 20555 s *****
1 COMMONWEALTH EDISON COMPANY DOCKET N0. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. DPR-25 l
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated May 14, 1986, 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 I; 8.
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 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 amendnent 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.
e K___-_.-_-.
.y
.4 i.
.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-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, are hereby incorporated O.
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 COMMISS 0 h
b s-w Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects Attachnent:
Changes to the Technical Specifications
-Date of Issuance: October 9. 1987 i
i i
1 1
1 lL-
= - - _ _ _ _ _ _ _
-: Revise the' Appendix' A Technical Specifications by removing the pages identified belowland. 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' 3/4 9-1 3/4 9-1
.3/4 9-2 3/4 9-2 3/4 9-3 3-4 9-3 3/4 9-4 3/4 9-4 B 3/4-'9-7 B 3/4 9-7 y
U____
DRESDEN III DPR-25
[
4, 7/, 9, 91 4
6 Amendment N2.
3.9 LIMITING CONDITION FOR OPERATION.
4.9 SURVEILLANCE REQUIREMENT AUXILIARY ELECTRICAL SYSTEMS AUXILIARY ELECTRICAL SYSTEMS Applicability:
Applicability:
A Applies to the auxiliary Applies to the periodic testing electrical power system, requirements of the auxiliary electrical system.
Objective:
Obj ective:
To assure an adequate supply Verify the operability of the of electrical power during auxiliary electrical system.
plant operation.
Specification:
Specification:
A.
The reactor shall not be A.
Station Batteries made critical unless all the following requirements are satisfied:
1.
One 345 KV line, 1.
Every week the specific associated switchgear, gravity, voltage and and the reserve temperature of the auxiliary power pilot cell transformer capable and overall of carrying power to battery voltage shall Unit 3 shall be be measured, available.
2.
The Dresden 3 diesel 2.
Every three months the generator and the measurements shall be Unit 2/3 diesel made of voltage of each generator shall be cell to nearest 0.01
- operable, volt, specific gravity of each cell, and temperature of every fifth cell.
3.
One 138 KV line from 3.
Every refueling outage, Unit 2 capable of the unit's batteries carrying auxiliary shall be subjected to a power to an essential rated load discharge electrical bus of Unit test.
Determine 3 through the 4160 volt specific gravity and bus tie shall be voltage of each cell available, after the discharge.
3/4.9-1 3901a 3124A A
DRESDEN III DPR-25' Am:ndmentNo.$,f$,91 4
-A.
3.9 ' LIMITING CONDITION FOR OPERATION 4.9.' SURVEILLANCE REQUIREMENT-(Cont'd.)'
(Cont'd.)
4.
(a) 4160 volt buses 33-1 and 34-1 are 1
ener5 sed.
(b) 480 volt buses 38 and 39 are energized.
5.
The unit 24/48 volt batteries, the-two station 125 volt batteries and the two station 250 volt' batteries and a battery charger for each required battery are operable.
B.
Except when the reactor B.
N/A is in the Cold Shutdown or Refueling modes with the head off, the availability of electric power shall be as specified in 3.9.A,
-l except as specified in.
3.9.B.1, 3.9.B.2, and
.3.9.B.3.
1.
From and after the date j
that incoming power is I
available from only one of the lines specified in 3.9.A.,
reactor operation is j
l i
3/4.9-2 3901a 3124A w.
_DPR DRESDEN III.
.4 9l-AmendmentNo.9,7/s 3.9,' LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
permissible only'during the succeeding seven days unless the second line is-sooner placed in service providing both the Unit 3 and Unit 2/3 emergency diesel generators are operable..From and after the date that incoming power is not la available from any r
line, reactor operation i
is permissible providing both the Unit 3 and Unit 2/3
~
emergency diesel generators are-operating and all core and' containment cooling systems are operable and 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 /> of the situation, the precautions to be taken-during this situation, and the plans for prompt restoration of incoming power.
2.
From and after the date that one of the diesel generators and/or its associated bus is made or found to be inoperable for any reason, reactor operation is permissible according to Specification 3.5/4.5F and 3.9D only during the succeeding seven days unless such diesel generator and/or bus is sooner made 3/4.9-3 3901a-3124A i
z__________-_
DRESDEN III DPR-25 d
Amendment ND,'7d, $, 91 j
l 3.9 -LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
operable, provided'that during such seven days the operable diesel generator shall be demonstrated to be operable at least once each day and two
.off-site lines-as specified in 3.9.A. are available.
3.
From and after the date that one of the two 125 or 250V battery systems is made or found to be inoperable, except as specified in 3.9.B.4.a or b,zUnit shutdown shall be initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the i
unit shall be in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the. failed battery can be sooner made operable.
4.
a.
Each 125 or 250 volt battery may be
-inoperable for a maximum of 7 days per operating cycle for maintenance and
- testing, b.
If it is determined that a battery need be replaced as a result of maintenance or testing, a specific battery may be inoperable for an additional 7 days per operating cycle.
3/4.9-4 3901a 3124A I
!L
Eisuw Lys unu=m t
1 jr Amendment No.l p, 91
< qf -
r
' I e.
'3.9
' LIMITING CONDITION FOR OPgRATION BASES F
A.- The-general' objective of this-Specification is to assure an-adequate. source of electrical power to operate the auxiliaries-during plant operation, to ob rate facilities to cool and lubricate the plant during shutdown, and'to operate the:
engineered--safeguards fo11owing an. accident. There.are three C
sources of electrical. energy available; namely, the 345 KV transmission system,:the diesel generators, and'the'138 KV transmission system through the 4160 volt bus tie.
The d-c. supply is, required for control land motive power for switchgear and engineered safety features..The electrical power required provides for the maximum availability of power;~
l l
1.e.,
one active off-site source and a back-up source of off-site power.and the maximum amount of on-site sources.
B.-
Auxiliary power for Unit 3 is' supplied from two sources..
either the Unit 3 auxiliary transformer or the Unit 3 reserve auxiliary transformer. Both of these transformers are' sized to carry 100% of the auxiliary load.
If the reserve auxiliary j
transformer is lost,'the unit can continue ~to run for 7 days since the unit auxiliary transformer is available'and both diesel generators are operational. A reduced period is pro-vided since if an accident occurs during this periodi the unit j
would trip and power to the unit auxiliary transformer would q
i be lost and the diesels would be the only source of power.
'l In the normal mode of operation the 345 KV system is operating and'two' diesel generators are operational..One diesel l
generator may be allowed out of service based on the availability'of power to the 345 KV switchyard, a source of power available from the 138 KV system through a 4160 volt bus tie.and the fact that one diesel carries sufficient engineered l
safeguards' equipment to cover all breaks. Off-site power is quite reliable..In the last 25 years there has only been one I
instance.in'which all off-site power was lost at a Commonwealth Edison generating station.
Two battery chargers are supplied for each of the 125 volt l
batteries, while for the 250 volt system a battery charger is-supplied for each battery and a third battery charger acts as a shared unit. Thus, on loss of a battery charger, another i
battery charger is available.
Since an alternate charger is available, one battery charger per unit for the 125 volt and one' battery charger overall for the 250 volt battery system can be out.of service for thirty days. The system becomes inoperable whenever there is a loss of the battery or loss of both chargers for that system and a battery voltage of 105 volts for the 125 or 210 volts for the 250 volt batteries.
B 3/4.9-7 3901a
'3124A DL-__
. _ - _ - _ _ - _