ML20035B388
| ML20035B388 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/24/1993 |
| From: | IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20035B379 | List: |
| References | |
| NUDOCS 9304010275 | |
| Download: ML20035B388 (22) | |
Text
_.
P RTS-243A to NG-93-0067 Page 1 of 6 I
PROPOSED CHANGE RTS-243A TO THE DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS The holders of license DPR-49 for the Duane Arnold Energy Center i
propose to amend Appendix A (Technical Specifications) to said license by deleting certain current pages and replacing them with the attached, new pages.
The List of Affected Pages is given below.
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List of Affected Pages i
111 3.8-6a (deleted) vii 3.8-7 3.5-10 3.8-8 3.8-1 3.8-9 3.8-2 3.8-10 3.8-3 3.8-11 i
3.8-4 3.8 14 (deleted) 3.8-5
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3.8-6 Summary of Changes.
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The following list of proposed changes is in the order that the l
changes appear in the Technical Specifications.
Page Description of Changes 111 The Table of Contents has been revised to reflect that Section 3.8 has been reorganized.
Subsections A-C have been replaced with A-E which correspond to the revision to TS Section 3.8.
The Surveillance Requirements and page numbers have also been revised accordingly.
i vii Figure 4.8.C-1 has been renumbered 4.8.E-1 to be f
consistent with the reorganization.
3 4
3.5-10 Section 4.5.G.1 has been revised to require OPERABILITY demonstration in accordance with 4.8.A.2.a.1.a.
3.8-1 Sections 3.8.A and 4.8.A have been renamed "AC Power i
Systems."
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The applicability conditions have been revised to more clearly state that the AC power sources are required to be OPERABLE when the reactor is in the RUN or STARTUP Modes.
This change makes this section consistent with the rest of DAEC TS.
1 9304010275 930324 PDR ADOCK 05000 1
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RTS-243A to l
NG-93-0067 Page 2 of 6 i.
Page Description of Changes 3.8-1 In general, systems listed have the initial letters (cont.)
capitalized.
This change occurs throughout Section 3/4.8 and is made to be consistent with other sections.
In the proposed Section 3.8.A.1, the word
" automatically" has been removed.
The automatic l
capability is still described in the Bases.
This change is consistent with Standard TS.
ii LCOs and required actions for AC Power Systems have been consolidated into this section for ease of use.
4 Section 3.8.A.2 has been revised to' incorporate actions i
and LCOs with inoperable components.
A requirement, 3.8.A.2.a, has been added to maintain both emergency diesel generators and one offsite power i
source OPERABLE when the other offsite power source or startup or standby transformer becomes inoperable.
.The proposed 3.8.A.2.b is the existing 3.8.B.3.a, and has been reworded for clarity and consistency.
l The proposed 3.8.A.2.c is the existing 3.8.B.3.b, and i
3 has been reworded and includes actions and a shutdown requirement (3.8.A.2.c.2) if at least one offsite power source cannot be restored.
Additionally, the allowed l
operating time has been reduced from 7 days to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> consistent with Standard TS.
Section 4.8.A.1 has been revised to incorporate Surveillance Requirements with inoperable components.
The proposed 4.8.A.1.a is the existing 4.8.B.3.a and l
has been revised to be consistent with 3.8.A.2.b.
The proposed 4.8.A.I.b is the existing 4.8.B.3.b and l
1 has been revised to reference the Surveillance Requirement of 4.5.G.1 and also to allow verification j
f of emergency diesel generator OPERABILITY through the fact that the diesel would be operating.
3.8-2 Emergency diesel generator OPERABILITY requirements have been moved to TS Section 3.8.A.3 from the existing a
3.8.A.2.
Also, the minimum required quantity of diesel fuel has been' revised based on a new engineering l
l calculation.
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RTS-243A to NG-93-0067 Page 3 of 6 Page Description of Changes 3.8-2 Surveillance Requirements for the diesels have (cont.)
also been moved to TS Section 4.8.A.2 from the existing 4.8.A.1, and renumbered and reworded for clarity and consistency with other TS and the FSAR.
4.8.A.1.a is now 4.8.A.2.a 4.8.A.1.b is now 4.8.A.2.b 1
4.8.A.l.e is now 4.8.A.2.c
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Section 4.8.A.2.a has been revised by itemizing the three parts of the monthly test:
start and increase speed to verify output voltage and frequency; manually l
load the generator and operate for at least.one hour at rated load; and check the starting air compressors for proper operation.
3.8-3 The diesel fuel surveillances have been revised and reorganized also.
The requirement for testing new fuel l
shipments (from 4.8.A.l.f) has been expanded to l
accurately reflect the DAEC commitment (Ref. letter, Franz (IELP) to Murley (NRC), NG-92-2216) and moved to l
4.8.A.2.d.
s The proposed 4.8.A.2.e is the existing 4.8.A.l.c.
The proposed 4.8.A.2.f is the existing 4.8.A.1.d.
The proposed Section 4.8.A.2.g contains a new I
Surveillance Requirement and has been added for testing j
the stored diesel fuel each quarter for particulate contamination (Ref. NG-92-2216).
l The proposed Sections 3.8.A.4 and 4.8.A.3 have been added to specify-LCOs and Surveillance Requirements for f
inoperable components.
These requirements have been moved from existing Sections 3.8.B.1 and 4.8.B.l.
The proposed Section 3.8.A.4.b contains a shutdown requirement and has been added for the case when both emergency diesel generators are inoperable.
This.is
_l the current practice-and is consistent with, Standard I
TS.
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RTS-243A to l
NG-93-0067 i
Page 4 of 6 l
.i Page Description of Changes j
i 3.8-3 The proposed Sections 3.8.B and 4.8.B have been
-i (cont.)
renamed "DC Power Systems" and all related specifications and Surveillance Requirements have been e
consolidated herein.
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i The proposed applicability statement in 3.8.B.1 is the i
same as the proposed TS 3.8.A.
The proposed 3.8.B.1 is existing 3.8.A.3.
l The proposed.4.8.B.1 is existing 4.8.A.2-i 3.8-4 The reference in the proposed 4.8.B.l.d has been revised to 4.8.B.l.c consistent with the reorganization.
i The proposed 3.8.B.2 is existing 3.8.B.2 The proposed 4.8.B.2 is existing 4.8.B.2 l
l The shutdown requirement in the proposed 3.8.B.2.b has been clarified, j
An additional reference has been added in the proposed j
3.8.B.2.c to Specification 3.7.D in the, event that a 250 Volt DC System is inoperable.
i A reference has been added in'the proposed'3.8.B.2.d to
[
Specifications 3.1 and 3.2 in the event that a +/- 24 l
Volt DC System is inoperable.
i 3.8-5 Proposed Sections 3.8.C and 4.8.C have been-renamed i
"Onsite Power Distribution Systems."
The proposed.
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3.8.C.1 contains OPERABILITY requirements.for the AC
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power distribution buses from the existing Section 3.8.A.4.
The proposed applicability statement-in j
3.8.C.1 is the same as the proposed TS 3.8.A.
l The proposed Section 4.8.C.1 contains Surveillance.
1 Requirements for the essential ACl power distribution l
equipment.
This surveillance is based on the equipment manufacturer's recommendations and is consistent ~with M
Standard TS.
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l RTS-243A to NG-93-0067 Page 5 of 6 i
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Page Description of Changes 3.8-5 The proposed Section 3.8.C.2.a contains an-LCO for (cont.)
either bus 1B9 or IB20 inoperable.
This LCO is consistent with that for River-Water Supply, which is l
powered by these buses (Section 3.5.J.2).
The proposed Section 3.8.C.2.b contains an LCO for any of the other essential buses inoperable consistent with j
the most limiting LCO for the components powered by those buses.
The proposed Section 3.8.D is the existing Section 3.8.B.4, consistent with the reorganization.
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3.8-6 The proposed Sections 3.8.E and 4.8.E are the existing i
Sections 3.8.C and 4.8.C consistent with the i
reorganization.
The shutdown requirement in the proposed Section j
3.8.E.3 (existing Section 3.8.C.3) has been reworded to be consistent with the rest of the DAEC TS'and Standard TS.
1 l
The Surveillance Requirement in the proposed Section
'j 4.8.E.2 (existing Section 4.8.C.2) has been revised j
from requiring demonstrated OPERABILITY'to verified
_j OPERABILITY consistent with the rest of DAEC TS and a1 Standard TS.
i 3.8-6a This page has been deleted.
3.8-7 The proposed Figure 4.8.E-1 (existing 4.8.C-1) has been j
renumbered consistent with the reorganization.
3.8-8 The Bases have been reworded for clarity and-l consistency.
A statement has been added to the second.
_l paragraph defining the "two offsite" AC power sources.
The minimum diesel fuel supply has been revised to.
j 36',317-gallons based on a new engineering calculation.
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3.8-9 The wording has been revised for clarity.and j
consistency.
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The Bases for the 250 Volt DC System LCO has been
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revised to include the fact that some primary l
containment isolation valves are powered by this i
system.
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RTS-243A to NG-93-0067 i
Page 6 of 6 Page Description of Changes i
3.8-10 The Bases for 4.8 have been reworded for clarity and i
consistency.
i The first paragraph has been added to. discuss the power-distribution system capability of detecting and alerting operators of problems.
This capability obviates the need for periodic breaker alignment verifications, such as those required by Standard TS.
This paragraph ~also discusses the added periodic distribution system preventive maintenance.
The Bases for the diesel fuel testing have been_ revised to discuss the modified DAEC diesel fuel testing.
This-modified testing program was communicated to the NRC in
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our letter from J.
Franz to Dr. Murley dated July 1,.
1992 (NG-92-2216).
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The footnote referring to a previous change (Amendment
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143) has been removed.
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3.8-11 The Basis for ESW surveillance has been revised to
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reflect that when one ESW loop is inoperable, the other
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is verified to be OPERABLE instead of demonstrated j
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DAEC-1
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SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS PAGE NO.
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3.7 Containment Systems' 4.7' 3.7-1 i
f A.
3.7-1
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B.
Standby Gas Treatment B
3.7-15 C.
3.7-17 j
D.
Primary containment Power D
3.7-18 l
Operated Isolation Valves 3.8 Auxiliary El'ectrical Systems 4.8 3.8-1 l
A.
AC Power Systems A
3.8-1 l
B.
DC Power Systems B.
3.8-3 j
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C.
Onsite Power Distribution Systems C
3.8-5 D.
Auxiliary Electrical' Equipment -
D 3.8-5 CORE ALTERATIONS l
'E.
Emergency Service Water System E
3.8-6
.j 3.9 Core Alterations 4.9 3.9-1 A.
Refueling Interlocks A
3.9-1 i
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B.
Core Monitoring B
3.9-5 i
i C.
Spent Fuel Pool Water Level C
3.9-6 D.
Auxiliary Electrical Equipment -
D 3.9-6
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J 3.10 Additional Safety Related Plant 4.10 3.10-1 l
Capabilities t
A.
Main Control Room Ventilation A
3.10-1 l
B.
Remote Shutdown Panels B
-3.10-2a 3.11 River Level Specification 4.11.
3.11-1
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3.12 Core Thermal-Limits
-4.12 3.12-1 A.
Maximum Average Planar Linear A.
3.12-l' Heat Generation Rate f
i B.
Linear Heat Generation Rate B-3.'12-2
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C.
Minimum Critical Power Ratio C
3.12 'l; t
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RTS-243A 111 03/93 1
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DAEC-1 I
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TECHNICAL SPECIFICATIONS f
'l LIST OF FIGURES
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t 1 FIGURE l'
l NUMBER TITLE I.1-1 Power / Flow Map 2.1-1 APRM Flow Biased Scram and Rod Blocks I
l 4.1-1 Instrument Test Interval Determination curves f
I 4.2-2 Probability of System Unavailability Vs. Test Interval
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t 3.3-1 Thermal Power vs Core Flow Limits for Thermal Hydraulic l
Stability Surveillance 3.4-1 Sodium Pentaborate Solution Volume Concentration
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Requirements 3.4-2 Minimum Temperature of Sodium Pentaborate Solution
'li 3<6-1 DAEC Operating Limits i
l 4.8.E-1 DAEC Emergency Service Water Flow Requirement f
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1 RTS-243A vilf 03/93
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DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
t G.
Minimum Low Pressure' cooling and
-G..
Minimum Low Pressure cooling and.
l Diesel Generator Availability Diesel Generator Availability' l
1.
During any' period when one diesel 1.
When it is determined that one j
generator is inoperable, diesel. generator is inoperable,:
continued reactor operation is-the remaining diesel generator permissible only'during the-shall be demonstrated to be succeeding seven days unless such l
OPERABLE'in accordance with
.i diesel generator is sooner made l
Specification 4.8.A.2.a.1.a'within
-l OPERABLE, provided that the
-the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and every remaining diesel generator and subsequent 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.'
.l all low pressure core and In addition, all low pressure core containment cooling subsystems cooling and containment cooling, l'
supported by the OPERABLE diesel subsystems supported by.the generator are OPERABLE.
If this OPERABLE diesel shall be verified requirement cannot be met, an to be OPERABLE.
3 orderly SHUTDOWN shall be initiated and the reactor shall r
be in at least HOT SHUTDOWN l
within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in i
COLD SHUTDOWN within the
- l following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Any combination of inoperable j
components in the core and containment cooling systems shall not defeat the capability of the remaining OPERABLE components to i
fulfill the cooling functions.
l 3.
When irradiated fuel is in the h
reactor vessel and the reactor is in the COLD SHUTDOWN Condition or REFUEL Mode:
a.
If no work is being performed which.has the potential for draining the reactor vessel, both core spray and RHR systems may be inoperable; or b.
If work is being performed which has the potential for i
draining the reactor vessel, at least two.of any combination of core spray and/or RHR (LPCI or j
shutdown cooling mode) l pumps shall be OPERABLE
.j (including the capability i
to inject water into the reactor vessel with suction t
from the suppression pool) except as i
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.RTS-243A 3.5-10 03/93
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n DAEC-1
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] LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS -
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AUXILIARY ELECTRICAL SYSTEMS l 4.8 AUXILIARY ELECTRICAL SYSTEMS
.l 3.8 Applicability:
Applicability:
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Applies to the auxiliary Applies to the periodic testing
?
l electrical power systems.
requirements of the auxiliary j
1 electrical power systems.
7 Objective:
Objective:
To assure an adequate supply of Verify the OPERABILITY of_the electrical power for operation of auxiliary electrical systems..
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those systems required for safety.
Specification:
Specification:
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A.
AC Power Systems l
A.
AC Iower Systems j
t At all times when the reactor is in the RUN 11 ode or STARTUP Mode l
and not in a COLD CONDITION, the
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following AC electrical power j
sources shall be OPERABLE.
[
L 1.
Both offsite sources and the
.l startup and standby transformers are available and capable of supplying power to the 4kV emergency buses.
9 2.
Operation with Inoperable 1.
Surveillance Requirements with f
Components.
Inoperable Components.
[
t a.
With one of the offsite sources t
or startup or standby j
transformers inoperable, maintain l
the other offsite source OPERABLE
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and both emergency diesel generators OPERABLE.
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f b.
With cne of the offsite sources a.
With one of the offsite sources or or the startup or standby the startup or standby transformers and one emergency transformers and one emergency diesel generator inoperable, the-diesel generator inoperable, the requirements of Specification requirements of Specification l
3.5.G.1 shall be satisfied.
4.5.G.1 shall be satisfied.
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b.
-With both the startup and standby
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c.
With both the startup and standby transformers inoperable, maintain transformers inoperable, verify t
both emergency diesel generators, that both emergency diesel associated buses and all Low generators.are either OPERABLE or Pressure Cooling Systems OPERABLE j
operating and the requirements of j
and either:
j specification 4.5.G.1 shall be l
satisfied.
l 1)
Restore one or both of the transformers to OPERABLE status, or i
i
]. 2)
Be in at least HOT SHUTDOWN
]
withi.1 the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in l
COLD SHUTDOWN within the-l following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l RTS-243A 3.8-1 03/93-t f
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DAEC-1 i
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j LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS -
j 3.
2.
' Emergency Diesel! Generators.
The two emergency diesel--
l.a.
Diesel Start' Test.
generators shall-be OPERABLE.
1)
Once each month both emergency j
with a minimum ofE36,317 gallons of diesel fuel in the diesel fuel diesel generators shall be:
oil tank.
l a)
-Manually started, the speed-
[
increased from idle to.
synchronous, and verified to.
delfver rated voltage and frequency.
i l b)
~ Manually loaded to rated' load.
l The test shall continue for at i
least a one-hour period at rated i
load.
c)
During the monthly start test.the
- f emergency diesel generator starting air compressors shall be j
checked for operation and their ability to recharge air receivers.
The operation of the diesel fuel oil transfer pumps shall also be l
demonstrated during this test.
2)
Once each six months both
[
emergency diesel generators shall be manually-started and loaded to demonstrate that they will reach rated frequency and voltage within.
specified' time limits. 'This test j
l may be run in lieu of the regular monthly test.
)
During the semiannual test the l
same checks to the Air Start l
System and' fuel oil pumps performed during monthly testing-shall be performed. In addition, l
the emergency diesel generator-starting time to reach rated frequency and voltage shall be j
l recorded.
b.
Once per. OPERATING CYCLE the:
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condition under'which-the j
. emergency diesel-generator is required will be simulated - and ^a e
test conducted to demonstrate that it will start and accept the_
emergency load within the specified. time sequence. The j
l emergency' diesel generator shall-be operated loaded for a~ minimum-i of 5 minutes. :The'results shall-l be recorded.
l c.
Once'per OPERATING CYCLE, during-l shutdown, each emergency diesel.'
l generator shall be given an inspection in accordance with q
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l ~ RTS-243A.
3.8-2 03/93; m,
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DAEC-1 j ' LIMITING CONDITIONS FOR OPELATION SURVEILLANCE REQUIREMENTS 1;
1
. procedures based on the.
j manufacturer's recommendations.
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d.
A sample shall be drawn from each
-j diesel fuel delivery and tested.
for API gravity, viscosity, and I
water and. sediment prior to.
addition-to the storage. tank.
Once itLis determined that the fuel meets the criteria for these characteristics specified.in ASTM-D975-77, the fuel may be added to i
the tank, e.
The quantity of diesel fuel i
available shall be recorded.
monthly and after.each use of the-1 diesels.
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f.
Once per month a sample of. diesel fuel shall be checked for viscosity, water and sediment.
The values for viscosity, water and sediment shall be within the:
acceptable limits specified in Table 1 of ASTM D975-77 and l
recorded.
g.
Once each 3 months a sample of
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diesel fuel shall be checked for-particulate accumulation and the-amount recorded..The amount of, particulates.chall not exceed 10-
-mg/ liter when filtered through a l
0.8 micron filter.
- j 4.
Operation with Inoperable-
- 1. 3.
Surveillance Requirements with Components, j
Inoptrable components.
I a.
With one of the emergency diesel a.
When it is determined that one'of l
l generators inoperable, the the emergency diesel: generators is.
I requirements of specification inoperable, the requirements of
[
]
3.5.G.1 shall be met.
Specification 4.5.G.1 shall be' j
l met.
l b.
With both of the emergency diesel l
generators inoperable either 1)
Restore one or both emergency diesel generators to OPERABLE i
j status,-or 2)
Be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in
-f COLD SHUTDOWN within the t
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
f l
B.
DC Power-Systems l
B.
DC Power Systems I
i 1.
At all times when the reactor is l ' 1.
The DCEPower System surveillance l-in the'RUN Mode or STARTUP Mode ~
l-shall be as follows:
l and not in-a COLD CONDITION, the
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essential station 24, 125 and 250 J
a.
-Each week the specific-gravity,
-l
~ Volt DC Power Systems shall be.
the voltage and temperature of the j
l OPERABLE.
The associated battery pilot cell'and overall battery.
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-l RTS-243A.
3.B-3 03/93 i
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DAEC-1 l
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS I
ll chargers for the 24 Volt Systems, voltage shall be measured.and it two of the:three battery chargers l
- recorded, l
for the 125 Volt Systems, and one l
of the two battery chargers.for b.
Each three months the essential the 250 Volt System shall be batteries' voltage of each' cell to
~j OPERABLE.
the nearest'O.01. Volt, specific.
gravity of each cell,'and l
temperature of every fifth cell l
shall be measured and recorded.
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c.
Once each OPERATING' CYCLE,-the'
'{
essential batteries.shall.be j
subjected to a Service Discharge Test (Joad profile). The specific gravity and voltage of each cell.
j shall be determined after the-l discharge and recorded.
t l
d.
Once every five years, the j
l essential batteries shall be subjected to a Performance-i Discharge Test (capacity). This' I
test will'be performed in lieu of' l
the Service Test requirement of
'j l
4.8.B.1.c above.
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2.
Operation with Inoperable 2.
Surveillance Requirements.with' f
l Components.
Inoperable Components.
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a.
With normal battery room l
a.
With the battery room ventilation f
ventilation unavailable, portable j
unavailable, samples-of-the ventilation equipment shall be battery room atmosphere shall be i
provided.
taken daily.for hydrogens.
'l, concentration determination.
b.
With one of the two 125 Volt DC Systems inoperable, verify that Specification 3.5.G is met, and
'l within 3 days either:
a 1)
Restore the inoperable 125 Volt
{
DC System to OPERABLE status, or t
2)
Be in at least HOT SHUTDOWN 1
within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in l'
COLD SHUTDOWN within the following 24-hours.
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c.
With the 250 Volt DC System inoperable, the HPCI System and
- j other affected primary containment isolation-valves shall be considered inoperable and the requirements of
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Specifications 3.5.D and 3.7.D t
respectively shall be met.
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d.
With one of the 24 Volt DC
.h Systems. inoperable, the j
requirements associated with the I
affected instruments of
)
Specifications 3.1 and 3.2 shall be met.
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i-)i j 'RTS-243A 3.8-4 03/93
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.DAEC-1 j LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
C.
Onsite-Power Distribution Systems l
C.
Onsite Power Distribution Systems 1.
At'all times when the~ reactor is 1.
Once each 4 OPERATING CYCLES each in the RUN Mode or STARTUP Mode circuit breaker shall be subjected l
and not'in a COLD CONDITION the to inspection and preventive j
essential AC 4160 volt buses lA3 maintenance in accordance with and 1A4, and 4BO volt buses 1B3,-
procedures based on the IB4, IB9. and 1820 shall be j
manufacturer's recommendations.
energized and OPERABLE.
l 2.
Operation with Inoperable l
Components.
a.
With one of the essential AC 480 volt buses, IB9 or IB20, inoperable, restore the bus to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the
]
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l b.
With one of the essential AC 4160 j
volt buses, IA3 or 1A4, or 480 volt buses IB3 or IB4 inoperable, be.in at least HOT SHUTDOWN within the next'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the U
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Auxiliary Electrical Equipment -
Refer to Specification 3.9.D.
.l RTS-243A 3.8-5 03/93;
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
E.
~ Emergency Service Water' System l
E.
Emergency' Service Water System.
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1.
Except as required in 1.
Emergency Service Water System l
Specification 3.8.E.2 below, both surveillance shall-be as follows:
l Emergency Service Water System loops shall be OPERABLE whenever a.
Simulated auto-Once/
irradiated fuel is in the reactor j
matic actuation
. OPERATING CYCLE i
vessel and reactor c; olant test.
l temperature is greater'than
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212'F.
b.
Pump and motor
_Once/3 mor,ths operated valve l
OPERABILITY i.
c.
Flow Rate Test l
Each Emergency-After major pump l
Service Water-maintenance
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a pump shall and once per deliver at least 3 months, except' that flow weekly during
. determined from periods of titne l
l Figure 4.8.E-1 the river water for the existing temperature
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river water exceeds 80*F.
temperature.
2.
With one of the Emergency Service 2.
With one Emergency Service Water Water System pumps or loops System pump or loop inoperable,.
i inoperable, REACTOR POWER the OPERABLE pump and. loop' thall i
l OPERATION must be limited to l
be verified to be OPERABLE.
In i
seven days unless OPERABILITY of addition, the requirements of.
that system is restored within l
Specification 4.5.G.1 shall be
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this period. _During such seven met.
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days all active components of the other Emergency Service Water i
System shall be OPERABLE, provided the requirements of
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l Specification 3.5.G are met.
'l 3.
If the requirements of l
Specification 3.8.E cannot be met, be in at least HOT SHUTDOWN j
within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in i
COLD SHUTDOWN within the i
l following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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t l RTS-243A 3.8-6 03/93 l
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1 c_e i
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600 bW 5
I 80 85 90 95 f
River Water Temperature - Degrees F Duane Arnold Energy Center Iowa Electric Light and Power Company Technical Specifications DAEC Emergency Service.
Water Flow Requirement I
Figure 4.8.E-1
- j. RTS-243A 3.8-7 03/93
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3.8 BASES
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l The objective of this specification is to assure that adequate power l
l will be available to operate essential equipment. Adequate AC power can be provided by any one of.the following sources: The startup j
transformer, the standby transformer or either of the two emergency
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diesel generators. The startup transformer provides all auxiliary power during plant startup and until the main generator is synchronized with
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the system. After synchronization, the plant auxiliary buses lAl and 1A2 are manually transferred to the auxiliary transformer. The startup transformer continues to provide the normal source of power to essential i
l AC buses lA3 and 1A4.
The standby transformer is connected to either of l
the two essential AC buses by automatic switching upon loss of power from the startup transformer.
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This Specification assures that at least two offsite and two onsite AC
.i power sources will be available before the reactor is taken beyond "just i
critical" testing. The two offsite sources are 161 KV and 345 KV power.
which are supplied to the startup and standby transformers respectively, 7
l through the DAEC site switchyard. These power sources are provided.
l through the several transmission lines tied to the regicnal power grid.
l In addition to assuring power source availability, all of the associated.
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essential AC switchgear must be operable as specified to assure that the j
emergency core cooling equipment can be operated, if required, from the power sources.
l The minimum diesel fuel supply of 36,317 gallons will supply one l
emergency diesel generator for a minimum of seven days of operation l
satisfying the load requirements for the operation of the essential equipment. Additional fuel can be obtained and delivered to the site from nearby sources within the seven day period.
l A battery charger is supplied with each of the two 125 volt DC station I
batteries.
In addition, a spare charger is available and can supply
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l power to either 125 Volt DC System.
Since this alternative source is i
available, one battery charger can be allowed out of service for maintenance and repairs. Similarly, one of the two battery chargers j
l provided for the 250 volt DC station battery can be allowed out of service for maintenance and repairs.
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Adequate power is available to operate all essential equipment from either the startup transformer or the standby transformer.
In addition, I
each of the emergency diesel generator units-is capable of supplying the essential AC powered loads required under postulated design basis accident conditions.
Each unit is physically and electrically independent of the other and of any offsite power source. Therefore, one emergency diesel generator can be allowed out of service for a f
period of seven days to allow reasonable repairs.
.In,such cases, emergency diesel generator OPERABILITY demonstrations will be limited to i
an unloaded start test.
f In the event that the startup or standby transformer and one emergency r
diesel generator is inoperable, adequate power is available to operate the essential equipment from either the OPERABLE transformer or the OPERABLE emergency diesel generator.
If both the startup and standby transformers are inoperable, either emergency diesel generator is
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sufficient to operate the essential AC-powered loads.
l Each of the two 125 volt DC and the 250 volt DC station batteries has j
enough capacity to energize its vital buses and supply DC power to the l
l other ensential DC-powered equipment for four hours without being.
-l recharged. Due to the high reliability of battery. systems, one of the i
two batteries may be out of service for up to three days.- This
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'l minimizes the probability of unwarranted shutdown by providing adequate time for reasonable repairs. A station battery is considered inoperable
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if more than one cell is out of service. A cell will be considered out
't of service if its float voltage is below 2.13 volts and the specific l
gravity is below 1.190 at 77'F.
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l RTS-243A 3.8-8 03/93
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The 250 Volt DC System provides power for the HPCI system and other a
primary containment isolation valves.
If.the battery is taken out of f
-service, the HPCI system would.be inoperable and the requirements of-
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l Specification 3.5.D for this condition must be satisfied. Certain-L
' l primary containment isolation valves would also be inoperable, thus the l
requirements of Specification 3.7.D must be satisfied.
The 24 Volt DC System provides power for reactor neutron monitoring and' process radiation monitoring. The neutron monitoring function is j
fail-safe in that loss of 24 volt DC power would cause the associated trip to occur (UFSAR Section 8.3.2).
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The battery room is ventilated to prevent accumulation of hydrogen gas-exceeding 4 percent concentration. On loss of battery room ventilation, l
the use of portable ventilation equipment and daily sampling provides i
assurance that potentially hazardous quantities of hydrogen gas will not accumulate.
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l RTS-243A 3.8-9 03/93 i
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DAEC-1 1
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4.8 BASES
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l Offsite power availability and onsite power distribution is continuously I
monitored by INSTRUMENTATION which alerts operators to any problems so
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l that appropriate action can be taken.
In addition to the annunciators, j
automatic switching occurs to maintain power to the emergency buses at-l l
all times.
The breakers and distribution panels are subjected to l
preventive maintenance based on manufacturer's recommendations.
The l
schedule is based on performance of maintenance on one of the buses (IAl, lA2, lA3 and 1A4) each Refuel Outage.
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The monthl; ests of the emergency diesel generators (EDGs) are i
conducted to demonstrate satisfactory system performance and 3
l OPERABILITY. To prevent excessive wear and stress on the diesel l
engines, the diesels are manually etsrted and the speed incrementally
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j increased to synchronous speed. WL 1 one EDG inoperable, the remaining l
l EDG can be demonstrated to be OPERABLE by starting and verifying proper
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output voltage and frequency. Once every six months, a fast-start test is performed to demonstrate the capabilities of the diesel engines to
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accelerate to rated speed as required for the design basis for the i
plant.
The test of the automatic starting circuits will prove that each j
EDG will receive all automatic start signals. The loading of each EDG is conducted to demonstrate proper operation at maximum expected l
emergency loading and at equilibrium operating conditions. Generator l
experience at other generating stations, and NRC published guidance (Generic Letter 84-15), indicates that the testing frequency is adequate to assure a high reliability of operation should the system be required.
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l Each EDG has two independent starting air supply systems. One consists 1
of a motor driven air compressor which automatically recharges two air i
receivers and the other consists of a diesel driven air compressor which 3
is manually operated to recharge a third air receiver. During the 1
l monthly check of the EDG, both air start systems vill be checked for
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proper operation.
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l Following the tests (at least monthly) or other operation of the EDGs, the fuel volume remaining in the diesel oil storage' tank will be.
checked.
l At the end of the monthly load test of the EDG, the fuel oil transfer pump will be operated to refill the day tank and to check the operation of this pump.
The day tank level indicator and alarm switches and fuel oil transfer pump control switches will be checked at this time.
l The test of the EDGs once each OPERATING CYCLE will be more l
comprehensive in that it will functionally test the system; i.e.,
it I
will check starting of the diesel and closure of electrical breakers and i
i sequencing of essential loads. The test will be initiated by simulation l
l of a loss-of-coolant accident.
In addition, a loss of normal AC power-i l
condition will be imposed to simulate a loss of offsite power. The l
essential load sequence timing will be checked to assure proper loading in the time required. Periodic tests check the capability of the units to start in the required time and to deliver the expected emergency load i
requirements.
Periodic testing of the various components plus a j
FUNCTIONAL TEST each OPERATING CYCLE are sufficient to maintain adequate reliability.
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Recording the diesel fuel supply after each operation (at least monthly)
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assures that the minimum fuel supply requirements will be maintained.
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New fuel is tested against the specification, ASTM D975-77 (API gravity, l
viscosity and water and sediment prior to addition, and the other characteristics within 30 days of addition to the storage tank).
A i
monthly test for quality of the diesel fuel oil will be performed to l
verify that viscosity and water and sediment are within the limits-specified in ASTM D975-77.
The quality of the diesel fuel oil will be l
acceptable if the results of the tests are within the limiting l
requirements for diesel fuel oils shown on Table 1 of. ASTM D975-77.
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Additionally, a quarterly test for particulate accumulation in the l
l RTS-243A 3.8-10 03/93 t
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stored fuel oil will provide further assurance that the fuel oil is not.
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deteriorating to the point that EDG operation would be affected.
This f
characteristic is trended so'that actions can be taken to restore fuel.
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quality prior to reaching unacceptable-levels. Should a test result show unacceptable particulate accumulation which does not fit an j
established trend, a second sample is allowed to be tested prior to taking actions to restore the fuel.
Although the station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. The type of surveillance described in this specification is i
that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
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The Service Discharge Test provides adequate indication of the batteries' ability to satisfy the design requirements (battery duty l
cycle) of the associated DC system. This test will be performed using l
simulated loads at the rates and for the durations specified in the design load profile.
I The Performance Discharge Test provides adequate indication and assurance that the batteries have the specified ampere hour capacity.
The rate of discharge during this test shall be in accordance with the manufacturer's discharge characteristic curves. The results of these I
tests will be recorded and compared with the manufacturer's I
racommendations of acceptability.
The Emergency Service Water System has two loops with one pump each.
If one Emergency Service Water System loop becomes inoperable, the other I
l loop provides sufficient cooling to components to assure performance of the safety function after an accident. Continued plant operation with one loop inoperable is restricted to a seven-day period during which i
l time the OPERABLE Emergency Service Water loop is verified to be j
j OPERABLE.
The surveillance test intervals for the Emergency Service Water pumps and associated valves are based on Section XI of the ASME Code.
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j RTS-243A 3.8-11 03/93
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RTS-243A to NG-93-0067 Page 1 of 1 ENVIRONMENTAL CONSIDERATION i
10 CFR 51.22(c)(9) identifies certain licensing and regulatory
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actions which-are eligible for categorical exclusion from the requirement to perform an environmental assessment.
A proposed amendment to an operating' license for a facility requires no environmental assessment if operation of.the_ facility in accordance with the proposed amendment would not: _ (1) involve a significant hazards consideration; (2)-result in a significant l
change in the types or significant increase in the amounts of any effluents that may be released offsite; and (3) result in an
-l Increase in-individual or cumulative occupational radiation exposure.
Iowa Electric Light and Power has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement _or environmental assessment needs to be prepared in connection with the issuance of the amendment.
The basis for this determination follows:
r Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
t i
1.
As demonstrated in Attachment 1, the proposed: amendment does-not' involve a significant hazards consideration.
2.
The proposed revisions to the Limiting Conditions for-l Operation and Surveillance Requirements for the systems and j
equipment of TS Sections 3/4.8, " Auxiliary Electrical l
Systems" have no effect on the types or amounts of effluents l
released offsite.
3.
The proposed revisions to TS Sections 3/4.8, " Auxiliary l
Electrical Systems" have no effect on individual or i
cumulative occupational radiation exposures.
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0-RTS-243A Attachment'4 to NG-93-0067 Page 1 of 1 SAFETY ASSESSMENT 1.
Introduction By letter dated March 24, 1993, Iowa Electric LightLand Power Company (IELP) requested' changes to the Duane Arnold Energy Center (DAEC) Technical Specifications (TS).to revise Sections 3/4.8, " Auxiliary Electrical Systems."
The requested change would revise the Limiting Conditions for Operation and Surveillance Requirements for the essential AC and DC power systems.
This change was initiated as a result l
of a comprehensive review of DAEC TS which compared them to.
TS from peer plants, standard TS and the then draft Improved TS (NUREG-1433).
This change will result in improved organization and clarity.
2.
Assessment Based on the above evaluation of DAEC TS, Sections 3/4.8 have been rewritten.
The purpose of this rewrite was to improve clarity and' consistency for the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs),
provide consistent shutdown requirements and make appropriate editorial changes.
The revised LCOs and SRs are consistent with other TS sections and BWR Standard TS.
In addition to these changes, the minimum amount of fuel oil
-t required to be onsite to' support emergency diesel generators (EDGs) has been increased based on an engineering i
calculation.
This revision will require enough fuel to l
operate the EDGs for seven days.
.I Based on the above assessment, we conclude that this request is acceptable.
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