ML20147A723
| ML20147A723 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/19/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20147A729 | List: |
| References | |
| DPR-19-A-098, DPR-25-A-093 NUDOCS 8803010318 | |
| Download: ML20147A723 (23) | |
Text
r e
/
'o,,
UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20665
~s.,...../
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO PROVISIONAL-OPERATING LICENSE Amendment No. 98 License No. DPR-19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (thelicensee)datedAugust 26, 1986 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 i
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 8803010318 800219 PDR ADOCK 05000237 P
ppq i
2 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. OPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 98, 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, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
Daniel R. Muller, Director Project Directorate !!!-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: February 19, 1988
)
l t
i 1
j
ATTACHMENT TO LICENSE AMENDMENT NO. 98 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 50-237 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 anendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 5-2 3/4 5-2 3/4 5-3 3/4 5-3 3/4 5-4 3/4 5-4 3/4 5-6 3/4 5-6 8 3/4 5-33 B 3/4 5-33 3/4 9-3 3/4 9-3 3/4 9-4 3/4 9-4 3/4 9-5 3/4 9-5 3/4 9-6 3/4 9-6
DERSDEN II DPR-19 Amendment No. SI 98 i
3.5 LIMITING CONDITION FOR OFttATION' 4.5 gUtVIILZJyfet st0VittMENT (Cont'd.)
(Cont'd.)
to a reactor vessel pressure of 90 psig i
- c. Pump once/ month operability
- d. Notor once/ month Operated Yalve
- e. Core Spray header delta i
p instru-mentationt check once/ day calibrate once/3 months test once/3 months
- f. Logic toch Systen Refueltag Functional Outage Test
't 2.
From and after the 2.
When it is determined date that one of the that one core spray core spray subsystems subsystem is inoperable, i
is made or found to be the operable core spray inoperable for any subsystem and the LPCI reason, reactor subsystem shall be operation is demonstrated to be permissible only during operable lamediately.
i the succeeding 13133 The operable core spray
{
days unless such subsystem shall be subsystes !s sooner demonstrated to be made operable, provided operable daily there-l that during such 11133 after.
days all active components of the other core spray subsystes and the LPCI subsystem and the diesel generators required
]
for operation 3/4.5-2 I
4 I
DRESDEN II DPR-19 Amehdment no. pt 98 3.5 LIMITINC coNDITIoM FOR OPERATION 4.5 SVRYTTLLANCI RIOVIREMENT (Cont'd.)
(Coat'd.)
of such components if so esternal source of power wsre available shall be operable.
3.
Iscept as specified in 3.
LPCI subsysten Testing j
3.5.A.4. 3.5.A.5 and shall be as specified 3.5.F.3 below, the la 4.5.A.1.a. b, c d.
LPCI subsystaa shall and f. except that be operable whenever three LPCI pumps shall irradiated fuel is in deliver at least 14.500 the reactor vessel.
spe against a system head corresponding to a reactor vessel pressure of 20 psig.
4 From and after the date 4.
When it is determined that one of the LPCI that one of the LPCI
{
pumps is made or found Pumps is inoperable, to be inoperable for the remaining active any reason, reactor compone-ts of the LPCI operation is permissible tad containment cooling only during the succeeding subsystem, both core i
thirty days unless such spray subsystems shall
)
pump is sooner made be demonstrated to be operable, provided operable immediately that during such thirty and the operable days the remaining active LPCI pumps daily i
components of the LPCI thereafter.
i and containment cooling subsystem and all active I
components of both core spray subsystems and the diesel generators required for operation of such components if so esternal source of power were available shall be operable.
1 5.
From and after the 5.
When it is determined date that the LPCI that the LPCI subsystem subsystem is made or is !aopgrable, both found to be inoperable core spray subsystmas.
3/4.5-3 l
1
)
i DRESDEN II DPR-19 Amendment No. p 98 3.5 LIMITING CONDITION FOR OPr#ATION 4.5 IVIVEILLANCE HQUIREMENT (Cont'd.)
(Cont'd.)
{
for any reason, reactor the containment coollag
{
operation is permissible subsystem, shall only during the suc-be demonstrated to coeding Agy,,gg days un-be operable isonediately less it is sooner made and daily thereafter.
operable, provided that during such agig days all active com-ponents of both core spray subsystems, the contalament cooling subsystem (lacluding 2 LPCI pumps) and the
{
diesel generators required for operation of such components if no external source of power were available shall be operable.
6.
Contatsment coollag 4.
During each five year spray loops are required period an air test to be operable when shall be performed on the reactor water the drywell spray toeperature is greater headers and nozzles.
than 212*F except that i
a maximum of one dry-well spray loop may be looperable for thirty days when'the reactor
)
water temperature is greater thsn 212*F.
7.
If the requirements of ll 3.5.A cannot be met, an orderly shutdown of the reactor shall be initi-sted and the reactor shall be in the Cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Sub-seguently, the reactor may be placed in Refuel, i
for post maintenance testing of control rod drives only, provided 4
no work is being performed which has the potential to drain the reactor-vessel.
3/4.5-4 l
j
DRESDEN II DPR-19 Amendment No. pd 98 3.5 LIMITIWC CoWDITIoM FOR opt 1ATI0li 4.5 gy3VIILLANCE REQUIRIMENT (Cont'd.)
(Cont'd.)
3.
From and after the 3.
When one containment i
date that one cooltag subsystem contatement cooltag becomes taoperable, the subsystem is made or operable subsystem shall -
found to be Laoperable be demonstrated to be for may reason, operable immediately and reactor operation is the operable containment permissible only cooling subsystem daily during the succeedias thereafter.
ggy.gg days unless such subsystes is sooner made operable, provided that all active components of the other containment cooling subsystem, both core spray subsystems anti both diesel generators required f or operation of su'ch cokres nts if no esternal source of
' power were available, shall be operable.
4.
If the requirements of 3.5.3 cannot be set an orderly shutdown shall be laittated and the reactor shall be la a Cold thatdown condition withia 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
HPCI subsystem C.
Surveillance of KPCT Subsystes shall be performed as follows:
1.
Except as specified in 1.
EPCI subsystem Testing 3.5.C.2 below, the RPCI shall be as specified subsysten shall be la 4.5.A.1.a. b, e, d, operable whenever the and f except that the reactor pressure is EPCI pump shall deliver greater than to psig at least 5000 spa and irradiated fuel is agatast a system la the reactor vessel, head corresponding to a reactor vessel pressure of 1150 pois to 150 i
pels.
3/4.5-6
)
__ _ __ -.. ~..... _ _ _ _ _. _... _..
DRESDgN II DPR 19 AmendmentNo.9d,94,96 98 3.5 LIMITING CONDITION FOR OPERATION RASIS (Cont'd.)
systems will function, a daily test is called for. Although l
l it is recognized that the information given in reference 3 I
provides a quantitative method to estimate allowable repair times, the lack of operating data to support the analytical approach prevents complete acceptance of this method at this time. Therefore, the times stated in the specific items were established with due regard to judgement.
Should one core spray subsystem become inoperable, the remaining core spray and the entire LPCI system are available l
should the reactor core cooling acise. To assure that the i
remaining core spray and LPCI subsystems are available they are demonstrated to be operable immediately. This demonstration includes a manual initiation of the pumps and associated valves.
Based on judgements of the reliability of the remaining systems; i.e. the core spray and LPCI, a 7-day repair period was obtained.
Should the loss of one LPCI pump occur, a nearly full l
complement of core and containment cooling equipment is available. Three LPCI pumps in conjunction with the core spray subsystem will perform the core cooling function.
Because of the availability of the majority of the core cooling equipment, which will be demonstrated to be operable, a 30-day repair period is justified.
If the LPCI subsystem is not available, at least 2 LPCI pumps must be available to fulfill the containment cooling function.
The 7-day repair period is set on this basis.
B.
Containment Cooling Service Water - The containment heat removal portion of the LPCI/ containment cooling subsystem is provided to remove heat energy from the containment in the event of a loss of coolant accident.
For the flow specified, the containment long-term pressure is limited to less than 8 pois and, therefore, is more than ample to provide the required heat removal capability.
(Ref. Section 5.2.3.2 SAR).
The containment cooling subsystem consists of two sets of 2 service water pumps, I heat exchanger and 2 LPCI pumps.
Either set of equipment is capable of performing the containment cooling function.
Loss of one containment cooling l
service water pump does not ssriously jeopardize the containment cooling capability as any 2 of the remaining three pumps can satisfy the cooling requirements. Since there is some redundancy left a 30-day repair period is adequate. Loss 1
l B 3/4.5-33 1
I l
DRESDEN II DPR-19 Amendment No, y, yk, 94 98 3.9 LIMITING CONDITION FOR OPgAATION 4.9 SURVEILLANCE R30UIREMENT (Cont'd.)
(Cont'd.)
permissible only during the succeeding ggy g days unless the second line is sooner placed in vervice providing both the Unit 2 and Unit 2/3
(
emergency diesel generators are operable. From and after the date that incoming power is not evallable 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.
l 2.
a.
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, except as specified in Specifi-cation 3.9.B.2.b below, reactor opera-tion is permissible according to specifi-l l
cation 3.5/4.5.F and 3.9.D only during i
l the succeeding seven days unless such diesel generator and/or bus is sooner made 3/4.9-3 1
DRESDEN II DPR-19 Amendment No. yd, yt, 9, gl 98 3.9 klMITING CONDITION FOR OPERATI_0g 4.9 SURVEIL @ t 350UIREMENT (Cont'd.)
(Cont'd.)
operable, provided that during such givig days the operable diesel generator shall be i
demonstrated to be operable at least once each day and two off-site lines as l
specified in 3.9.A. are available, f-b.
Specification 3.9.B.2.a l
shall not apply when a l
diesel generator has i
l been made inoperable l
for a period not to l
exceed 1-1/2 hours for the purpose of conducting preventative maintenance.
Additionally, preventative maintenance shall not be undertaken unless two offsite lines are available and the alternate diesel I
generator has been demonstrated to be operable.
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.4a or b.
I Unit shutdown shall be j
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 t
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 l
can be sooner made operable, i
4.
a.
Each 125 or 250 volt battery may be inoperable for a maximum of 7 days per operating cycle for maintenance and testlng.
3/4.9-4
DRESDEN II DPR-19 f
Amendment No. P, pt 98
=
4 3.9 klMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
b.
If it is determined that a battery need be replaced as a j
result of maintenance or testing, a specific battery may be inoperable for an l
additiunal 7 days per operating cycle.
C.
Diesel Fuel C.
Diesel Fuel There shall be a minimum once a month the quantity j
of 10,000 gallons of of diesel fuel available diesel fuel supply on shall be logged.
site for each diesel.
Once a month a sample of diesel fuel shall be checked for quality.
D.
Diesel Generator D.
Diesel Generator Operability Operability Whenever the reactor is 1.
Each diesel generator in the Cold shutdown or shall be manually Refueling modes, a started and loaded once minimum of one diesel each month to generator (either the demonstrate optrational Dresden 2 diesel generator readinass. The test or the Unit 2/3 diesel sha11' continue until generator) shall be both the diesel engine operable whenever any work and the generator are is being done which has at equilibrium the potential for conditions of draining the vessel.
temperature while full secondary containment is load output is required, or a core or maintained.
containment cooling system is required.
2.
During the monthly generator test the diesel starting air compressor shall be checked for operation and its ability to 1
recharge air coceivers.
3.
During the monthly generator test the diesel fuel oil transfer pumps shall be operated.
3/4.9-5 l
l 1
DRESDEN !!
DPR-19 Amendment No. Pf. pd 98 i
3.9 LIMITING CONDITICW FOR OPERATION 4.9 SURYtILLANCE REQVIRENLNT (Cont'd.)
(Coat'd.)
4.
Additlesally, during each refueling outag*.
a simuisted loss of i
off-stte power la conjunctica with an RCCs lattlation signal test shall be performed on the 4160 volt energency bus by:
(a) verifylas de-energitation of the emergency buses sad load sheddtng l
from the emergency buses.
(b) Vertfying the diesel starts fron i
ambient condition on the auto-start signal, energites f
the energency buse, l
wlth permanently i
connected loads, energlaes the l
auto-connected energency loads through the load seguencer, and operates for j
greater than or i
equal to 5 minutes l
whlle its generator i
1: loaded with the emergency loads.
1 l
3/4.9-6
.a ns, UNITED STATES
[
NUCLEAR REGULATORY COMMISSION 5
W ASHINGTON, D. C. 20H6
....+
COMONWEALTH EDIS0N COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 93 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company I
(thelicensee)datedAugust 26, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, es amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; l
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 i
by this arendment 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 end security or to the health and safety of the public; and 1
l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1 l
2-2.
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 I
The Technical Specifications contair s' Appendix A, as revised through Amendnent No. 93,
<sreby incorporated i
in the license. The licensee shall
'a the facility l
in accordance with the Technical Spec t'i tations.
l 3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMIS'. ION 1
Daniel R. Nuller, Director Project Directorate !!!-2 Division of Reactor Projects - !!!,
IV, Y and Special Projects
Attachment:
Changes to the Technical l
Specifications Date of Issuance: February 19, 1988 l
l
ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 50-249 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 5-2 3/4 5-2 3/4 5-3 3/4 5-3 3/4 5-6 3/4 5-6 8 3/4 5-32 B 3/4 5-32 3/4 9-3 3/4 9-3 3/4 9-4 3/4 9-4 3/4 9-5 3/4 9-5 3/4 9-6 3/4 9-6
1 l
DRESDEN III DPR-25 i
Amendment N3. pf 93 I
3.5 LIMITINO CONDITION FOR OPERATION' 4.5
$UtvitLLANCE RgQUIREMgNT (Cont'd.)
(Cont'd.)
I 1
I to a reactor vessel
)
pressure of 90 pois l
- c. Pump once/ month l
Operability
- d. Motor Once/ month
[
operated Valve
- e. Core Spray header delta l
p instru-l mentation:
check once/ day calibrate once/3 months test once/3 months l
l
- f. Logic Each System Refueling Functional Outage Test I
l 2.
From and after the 2.
When it is d9termined i
date that one of the that one core spray core spray subsystems subs) stem is inoperable.
I 1s made or found to be the operable core spray inoperable for any subsystem and the LPCI __
)
reason, reactor subsystem shall be demon-operation is strated to bc operable J
permissible only during immediately. The oper-l the succeeding igvig able core spray sub-days unless such system shall be demon-subsystem is sooner strated to be oper-made operable, provided able daily there-that during such seven after.
days all active components of the other core spray subsystem and the LPCI subsystem and the diesel generators required for operation 3/4.5-2
4 DEE3 DEN III DPR-25 Amendment No. pf 93 P
l
~
3.5 LIMITING CONDITION FOR OPttATION 4.5
- URVIILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
of such components Tr no external source of power were available shall be operable.
3.
Except as specified in 3.
LPCI subsystem Testing 3.5.A.4, 3.5.A.5 and shall be as specified 3.5.F.3 below, the in 4.5.A.1.a. b, c, d, j
LPCI subsystes shall and f, except that j
be operable whenever three LPCI pumps shall irradiated fuel is in deliver at least 14,500 the reactor vessel.
spa against a system head corresponding to a reactor vessel pressure of 20 psig.
4.
From and af ter the date 4.
When it is determined that one of the LPCI that one of the LPCI l
pumps is made or found pumps is inoperable, to be inoperable for the remaining active any reason, reactor components'of the LPCI operation'is permissible and containment cooling only during the succeeding subsystem, both core thirty days unless such spray subsystems shall l
pump is sooner made be demonstrated to be operable, provided operable immediately that during such thirty and the operable days the remaining active LPCI pumps datir components of the LPCI thereafter.
and containment cooling subsystem and all active components of both core spray subsystens and i
the diesel generators required for operation of such components if no external source of power were available shall be operable.
5.
From and after the 5.
When it is determined date that the LPCI that the LPCI subsystem subsystem is made or is inoporable, both found to be inoperable core spray subsystems, 3/4.5-3
1 i
l DRESDEN III DPR-25 AmendmentNo.7f 93 I
3.5 LIMITING CONDITION FOR OPERATION 4.5 SVRVIILLANCE REQUIREMENT
)
(Cont'd.)
(Cont'd.)
{
3.
From and after the 3.
When one containment l
date that one cooling subsysten containment cooling becomes inoperable, the subsystem is made or operable subsystem shall --
found to be inoperable be demonstrated to be for any reason, operable immediately and reactor operation is the operable containment permissible only cooling subsystem daily during the succeeding thereafter.
ung days unless such subsystem is sooner made operable, provided 1
that all active components of the other containment cooling subsystem, both core spray subsystems and both diesel generators required for operation of such components if no external source of power were available, shall be operable.
4 If the requiretants of 3.5.3 cannot be met an orderly shutdown shall be initiated and the reactor shall be in a Cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
HPCI Subsystem C.
Surveillance of RPCI Subsystem shall be performed as follows:
1 1.
Ezeept as specified in 1.
EPCI subsystem Iesting 3.5.C.2 below, the NPCI shall be as specified i
subsystaa shall be in 4.5.A.1.a. b, c d.
operable whenever the and f, except that the reactor pressure is RPCI pump sha'll deliver greater than 90 psig at least 5000 gPa and irradiated fuel is against a system in the reactor vessel.
head corresponding to a reactor vessel pressure of 1150 psig to 150 psig.
3/4.5-6
DRESDEN III DPR-25 Amindment No. 7d, pt-93 j
3.5 LIMITING CONDITION FOR OPERATION BASES (Cont'd )
systems will. function, a daily test'is called.for. Although' it is recognized that the information givon in reference 3 provides a quantitative method to estimata allowable. repair' times, the lack of operating data to' support the analytical-approach prevents complete acceptance of this method at this~-
time.
Therefore, the times stated in the1 specific items were established with due regard. to judgement.
Should one core spray subsystem become inoperable, the remaining core spray and the entire LPCI system are available should the reactor core cooling arlse. To assure that the remaining core spray and.LPCI subsystems are available they are demonstrated to be operable immediately.
This demonstration includes a manual initiation of.the pumps and associated valves. Based on judgements of the reliability of the remaining systems; 1.e. the-core spray and LPCI, a 7-day repair period-was obtained.
Should the loss of one LPCI pump occur, a nearly full i
complement of core and containment cooling equipment-is available. Three LPCI pumps in conjunction with the. core
~f spray subsystem will perform the core cooling function.
Because of the availability of the majority of the core cooling equipment, which will be demonstrated to be operable, a 30-day repair period is justified.
If the LPCI subsystem is not available, at least 2 LPCI pumps must be svallable to fulfill the containment cooling _ function. The 7-day repair i
period is set on this basis.
B.
Containment Cooling Service Water - The containment heat removal portion of the LPCI/ containment cooling subsystem is provided to remove heat energy from the containment in the event of a loss of coolant accident.
For the flow specified, j
the containment long-term pressure is limited to less than 8 psig and, therefore, is more than ample to provide the required heat removal capability.
(Ref. Section 5.2.3.2 SAR).
The containment cooling subsystem consists of two sets of 2 service water pumps, 1 heat exchanger and 2 LPCI pumps.
i Either set of equipment is capable of performing the-containment cooling function. Loss of one containment cooling service water pump does not seriously Jeopardize the containment cooling capability as any 2 of the remaining three pumps can satisfy the cooling requirements. Since there is some redundancy left a 30-day repair period is adequate.
Loss B 3/4.5-32
DRESDEN III DPR-25 Amendment N). $4, ps, 9 93 1
I 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 soonar 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 available from any line, reactor operation 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.
l 2.
a.
From and aftor the date that one of the diesel generators and/or its associated bus is made or found to be inoperable for any reason, except as specified in Specification 3.9.B.2.b below, reactor operation is permissible according to Specification l
3.5/4.5.F and 3.9.D only during the succeeding seven days unless such diesel generator and/or bus is sooner made 3/4.9-3
DRESDEN III DPR-25 Amendment No. ps, 9, p 93 6
4 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 offsite lines as specified in 3.9.A. are available.
b.
Specification 3.9.B.2.a shall not apply when a diesel generator has been made inoperable for a period not to exceed 1-1/2 hours for the purpose of conducting preventative maintenance.
Additionally, preventative maintenance shall not be undertaken unless two offsite lines are available and the alternate diesel generator has been demonstrated to be operable.
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, 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.
4.
a.
Each 125 or 250 volt battery may be inoperable for a maximum of 7 days per operating cycle for maintenance and testing.
3/4.9-4
DRgSDEN III DPR-25 6
Amendment N3. 34, 5 93 3.9 LIMITING CONDITION FOR OPERATION.
4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
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.
j C.
Diesel Fuel C.
Diesel Fuel There shall be a minimum once a month the quantity i
of 10,000 gallons of of diesel fuel available i
diesel fuel supply on shall be logged.
site for each diesel.
Once a month a sample of 1
diesel fuel shall be checked for quality.
D.
Diesel Generator D.
Diesel Generator operability operability Whenever the reactor is 1.
Each diesel generator in the Cold shutdown or shall be manually Refueling modes, a started and loaded once minimum of one diesel each month to generator (either the demonstrate operational i
Dresden 3 diesel generator readiness. The test or the Unit 2/3 diesel shall continue untti generator) shall be both the diesel engine operable whenever any work and the generator are I
is being done which has at equilibrium the potential for conditions of dealning the 'zessel, temperature while full secondary containment is load output is required, or a core or maintained.
containment cooling system is required.
2.
During the monthly generator test the diesel starting air compressor shall be checked for operation and its ability to recharge air receivers.
3.
During the monthly generator test the diesel fuel oil transfer pumps shall be operated.
3/4.9-5
DRESDEN III DPR-25 Amendment No. pf, 96 93 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
4.
Additionally, during each refueling outage, a simulated loss of off-site power in conjunction with an ECCS initiation signal test shall be performed on the 4160 volt emergency bus by:
(a) verifying de-energization of the emergency buses and load shedding from the emergency buses.
(b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the I
auto-connected emergency loads through the load sequencer, and operates for j
greater than or equal to 5 minutes while its generator is loaded with the energency loads.
f I
3/4.9-6
_, __. _