ML20216E611

Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases

ML20216E611
Person / Time
Site:	Davis Besse
Issue date:	09/07/1999
From:	CENTERIOR ENERGY
To:
Shared Package
ML20216E600	List: ML20216E596 ML20216E605 ML20216E611
References
NUDOCS 9909150176
Download: ML20216E611 (12)

Text

.

LAR 98-0005 Pige 8 INSTRUMENTATION ADDill0NAL CHANGES PREVIOUSLY PROPOSED BY LETTER 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION Serial No. 2. 58 3 Date 7/zclet SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Safety Features Actuation System (SFAS) functional units shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4, with the exception of; Instrument Strings Functional Units b. c.

d, and e, and Interlock Channels Functional Unit a, wfiich shall be set consistent with the

~

Allowable Value column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.  ;

ACTION:

a. With a SFAS functional unit trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the functional unit inoperable and apply the applicable ACTION requirement of Table 3.3-3, until the functional unit is restored to OPERABLE status with the trip setpoint adjusted consistent with Table 3.3-4.

b. With a SFAS functional unit inoperable, take the action shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each SFAS functional unit shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shown in Table 4.3-2.

i 4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power 1 CHANNEL FUNCTIONAL TEST of functional units affected by bypass operation. The total I bypass function shall be demonstrated OPERABLE at least once per REFUELING INTERVAL 4 during CHANNEL CALIBRATION testing of each functional unit affected by bypass operation.

4.3.2.1.3 The SAFETY FEATURES RESPONSE TIME

• of each SFAS function shall be  !

demonstrated to be within the limit at least once per REFUELING INTERVAL. Each test shall include at least one functional unit per function such that all functional units are tested at least once every N times the REFUELING INTERVAL where N is the total number of redundant functional units in a specific SFAS function as shown in the " Total No. of Units" Column of Table 3.3-3.

• The response times (except far manual initiation) include diesel generator starting and sequence loading delays, when applicable. The response time limit (except for manual initiation) includes movement of valves and attainment of pump or blower discharge pressure.

DAVIS-BESSE. tJNIT 1 3/4 3 9 Amendment No. 218,225 9909150176 990907 PDR ADOCK 05000346 P- PDR

ke$8u D

$e  : 3s t3 EC g # E r:l m ll =c  ::c l

l l l

a r C hE p

3a  ::MN D  :

N O

E T f #ff!

C C I E 0 0000 1 1 1 1 1 T L 1 1111 1 1 1 1 1 C E A D 4 4 4 4 4 E ** , , , ,,

L D 3 3333 3 3 3 3 3 B E AS T , , , , , , , , ,,

CE E 2 2222 2 2 2 2 2 ID L LO E , , , , , , , , ,,

PM D 1 1111 1 1 1 1 1 P

A N

O I E T M L D A USB E T MTA T N IIR E 3 3333 2 2 2 2 2 E NNE L M IUP E U M O D R

T S

N P D I SI E .

TR T M IT E 2 2?22 1 1 1 1 1 E N L T UQ E 3

S Y

- I D 3 S 3 N .

O OS D E I NT E L T I T B A LN E 4 4444 2 2 2 2 2 A U AU L T T T E C OE D s A TQ r o

S t E a R r U e e T nn v A - - w oe n i E o n iG o s F e e lw o t i s r r - o i cl t i Y

T u u wwL :t: ee: c:  : m r

E s s oo - 1 a2js3e4 yS s s LLw #l#ne#j# a# pe F e e o o Ii n r mP A r r - L l sl DlIl pl u S P P eI ee e eSeSn ee- v vrgvev v o S t t rr eteunereteti G n n uul lnLsiLuLnlnt N e ehsse e st s e ea I m mgssv tmtertst mtml R Dn nieee nnnranennnnu T Ei iHrrL ei ePt e r ei ei c T S Ta a PP C dad SdPdadar I Ethth T I itih i ititi N T L n g n gS S S 5 c n c gd c w c n c n c U N E oi oi C C W O n o ni n n o n o n o e E DCHCHRRB L ICIHaILICICR L M A U T N R U O T P I S T T N . . . . . . U . . . . .

C I ab c def O a b c d e N

U . .

F 1 2 ghRM' s=[ ' y YE F3&@" E' ,$e1r ~"

rb yO8 " I a l

" D "

~k- WE"" N3M"f TNgC===CmOT =

1 N

O f 1C E @ QyN I 2 2 5 5 S 3 4 T 1 1 1 1 I 1 1 C

A E

L 4, 4, 4, 4, 4,

• B

• AS 3, 3, 3, 3, 3, 3,

• CE

• ID LO 2, 2 2

, 2, 2, 2,

• PM 1 1 1 1 1 1 3 P

A E S S S N M L U U U O USB B B B I MTA / / /

T IIR 2 2 2 2 2 1 2 A NNE T IUP N M O E

M U

R T S S S S P U U U

) N SI B B B d I TR / / /

e IT 2 2 2 2 2 1 2 u M N n E UO i T T t S n Y o S C *

( N .

• O OS

• 3 I NT * '

- T I

• 3 A LN 2 2 4 4 4 1 2 U AU 3 T T C OF e E A TO '

v L t p l B S nm , a A E eu tl V T R mS ra U n r ai n T iy S e tt o s A ac L d) Sn i r E t n y E e% e t e F ne a N e0 rs a t og r N F9 os l a Y Cr) p A ( tE S o e T en S H s a L s H E N t mo C up rn E I F O pEi t Bi eo N r A I e t n C r n N t e S T cda e I r lT ed) A a z A xnl m G e a Ge% H e i T U eau n O c ir h9 C H r I T ( c i L n t e l s5 u N C yr a e nk e ( K y s U A Sai t E u ea sd C a s Arc n C q se eas O c e L L F pe o N e sr iou L e r A A SSR C E S EB DLB R D P N U U E O N Q T I A . . E . . . N . .

T M a b S a b c I a b C

N U . . .

F 3 4 S

$- >M & R ?. = " .,'t -I .h.

l

$". eE[ . '

t$' g 1. 3

': 5

I LAR,98-0005 Tills PAGE PROVIDED

~TdBLE 3.3-3 (ContFAM) REI AM AMBU

_ABLE T NOTATIf4 J g g gg

• Trip function may be bypassed in this MODE with RCS pressure below 1800 psig. Bypass shall be automatically removed when RCS pressure exceeds 1800 psig.

• • Trip function may be bypassed in this MODE with RCS pressure below 660 psig. Bypass shall be automatically removed when RCS pressure exceeds 660 psig.

• • • DELETED

• • • • DELETED

• • • • • All functional units may be bypassed for up to one minute when starting each Reactor Coolant Pump or Circulating Water Pump.

• • • • • • When either Decay Heat Isolation Valve is open.

1. The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 10 - With the number of OPERABLE functional units one less than the Total' Nut:iber of Units, STARTUP and/or POWER OPERATION may proceed provided both of the following conditions are satisfied: l I

The inoperable functional, unit is placed in the tripped I a.

condition within one hour. l

b. The Minimum Units OPERABLE requirement is met; however, one additional functional unit may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 11 - With any component in the Output Logic inoperable, trip the associated components within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

DAVIS-BESSE, UNIT 1 3/4 3-12 Amendment No. 28,37,52.102T F35,2 59,185,2:1,2: S,-22)

Corrected by letter dated 6/2/98

LAR 98-0005 TlilS PAGE PROVIDED IABLE 3.3-3 (CorF' ' d ACTION STATE l

~

ACTION 12 - With the number of OPERABLE Units one less than the Total Number of Units, restore the inoperable functional unit to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least fl0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 13 - a. With less than the Minimum Units OPERABLE and indicated reactor coolant pressure 2 328 psig, both Decay Heat Isolation Valves (DHll and DH12) shall be verified closed.

b. With Less than the Minimum Units OPERABLE and indicated reactor coolant pressure < 328 psig operation may continue; however, the functional unit shall be OPERABLE prior to increasing indicated reactor coolant pressure above 328 psig. l ACTION 14 - With less than the Minimum Units OPERABLE and indicated reactor coolant pressure < 328 psig, operation may continue; however, the.

functional unit shall be OPERABLE prior to increasing indicated reactor coolant pressure above 328 psig, or the inoperable functional unit shall be placed in the tripped state.

ACTION 15 - a. With the number of OPERABLE units one less than the Minimum Units Operabic per Bus, place the inoperable unit in the tripped condition within one hour. For functional unit 4.a the sequencer shall be placed in the tripped condition by physical removal of the sequencer module. The inoperable functional unit may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

b. With the number of OPERABLE units two less than the Minimum Units Operable per Bus, declare inoperable the Emergency Diesel Generator associated with the.. functional units not meeting the required minimum units OPERABLE and take the ACTION required of Specification 3.8.1.1.

DAVIS-BESSE, UNIT 1 3/4 3-12a Amendment No. ES,52,10;b435,211, 218

ho8"

?% U Eg5%g*h=32Ey m 88 g h9 m$nF 9 $* h" 7 S

T N

O S I

P E

1 U E L # #

S A #

a a 0 P V i s

i s

p # # # 5 I

E p 02 4 #

R L 2 2 g

g 2 c e

• T B 5 3 i s

i s H s s s #

N A D 8 3 p p d . l t

d r1 #

ni n 3 o no g O t 1 2 2 vee af0 I W l 8 5 6 4 a 7 s*

i s

p T O E 3 6 7 1 31 8 s 1 7l t

N A L L 9 1 5 4 8 01 5

5 8 0 o 5 8 2 O -

T L E 1 4 1 4 8 37 2 v0 3 I .

N A D s s 2 2 2 s 2s 2 < T A

E _

M R U B I

R L 4-T S

A C

N 3

3 E

L I

ME O2 H

n

. l t

s o

L E

N B i i v N A s T 5 0 e A T Y . 0 5 e H S N I A. A. 0 1

r o

4 s 21 C f

N O P N N s s s0 d n

O D c c d l t

d a T

I i i i o n T T b t p p n a ve e a5 S S A S l E 4. 5 4 s 1 0 E p.E U P L

i. . 4 7 r Ta T T IR E

?  ?

9 7 8 0 o .

tL C T

?  ? A. A. 8 37 2 f A.

LnA A D s s 'N N 2 2s 2 N Ao S NiN OtaO t

E ) I n I R

U  % TeT cmc T

A hg 0

9

(

n o nun UtU r E S i

p d e Fn sF F i r iL H- L T h S lee Y hg hg E r Er _

1 N e d e NsuN _

E t

i H

i H w N k

a e

a o S l v NsN ara e A S G - - o A r L) L a HPH S e e L H B r%

t E V SC T N I

r u r u w w- C r e a9 t N n r CCro T R s s o o C d S( 5 N o te rRf fo i

s s L e N T e e L I e r s A t a a e ee U S r r - - G F ou H l

o eh u L T P

t P

t e r

e r l O s t

aB r C sH I r l

ut aoa l

n L u A

N N

ED e m

n e

m u

s s

u s

s e

v e E B el a ni et K

C t e az ei r Veelde tV t e e C Gen l

O M l n n r r L N i a

s O Hu s l bna cb I

UE i i P P T a t ys aew l

T a E n e s L C RL t n

o t

n S C

S S U e s

sE e R aer c wreo N TE SD C C o

R C W Q s i D

E eP ofl l el U R B E E T Dd l A RA F N I a b

c

d. e

f. S a b

N I aa

.n O e@M .

E{ 5NN K y gLFM~

l .

)

LAR 98-0005

• Page 14 1 TABLE 3.3'-5 SAFETY FEATURES SYSTEM RESPONSE TIMES DELETED THIS PAGE PROVIDED FORINFORMATDN DNLY i

i DAVIS-BESSE, UNIT 1 4 -

endment No. 40r44rl4h444rl-3W-225

t- $8 l l 4g M OM @Qg =

gE a

~

mgy =2 c H 4 4 4 4 4 4 4 CE , ,,,,

IC , ,

HND D33333 3 3 3 3 3 3 3 3 WAE E S LR T , , ,,, , ,,,, , , ,

T NLI E22222 2 2 2 2 2 2 2 2 N IIU L E EO E , , , , , , ,,,, , , ,

M SVE D11111 1 1 1 1 1 1 1 1 E ERR R DU I OS U M O

E R L A D E LN E)) ) )

C EOT T22 1

(

1

(

N NIS E((

A NTE LMMMMM M M M M M M M M L ACT E l HN D l CU E F V

R U

S N O

N LI D O ET E A

I NA T A A T NR EEERRE E E E E E N N N A AB L T HI E 2 N CL D 3 E A M C 4 U R

E T L S L D B N EK E I NC T A A A NE ESSSSS S S S S S N N S T M AH L E HC E

)

T C D S n Y o S h .e i g rl e e t N i t ue r t t v ya O H n ss u n ni al I - e se s e es ru T hh m ei s m ms pc A gg n rD e n ni Sr U ii i P r i i m i T HH a g P a ar t c C t hn t t e ne A - - w n gi w n nP o

eR m

o o it o o np S S ee lw C Hr L C Cn E rr o a o im L R uuwwL  : :t  :  : :i au E U ssoo - 1 2S 3 4 5t tSy N T ssLLw # # # # # a n a N A S ee o d l oyr A E G rr- L l l n l l l u Ccp H F

Y T

E T N

I R

T S

PP tt rr nnuul eesse ee-C e

v enenrene LoLooLoL i

ea v

it sv e

i e

v ec vr ei lc e

N O

I T

A te pg*,

ern cee nS C C

I G

F I mmssv I ttttattt nancrncnyn tR U xmm EEn O

L A N T Dnneee G T S U N EiirrL O el eeeeeeaap C ( i E TaaPP L dodjndjdrdm A da E L M Ett T i s i n e i n i pi u Snt C A U L nnSSS T cI cIGcI cScS L Aan N N R E ooCCW U n n n n n A F o E O T DCCRRB P I I I I I U S C U I S T N Q T N . . . . . . U . . . . . A . . E C I abcdef O a b c d e M a b S N .

U . . .

4 F 1 2 3 g  ?> '" . g R o. i' E9&9[E 'r

• L41 }@%

g

a t>$m 88 3 cESm

'd (33C

1. gMg TN'4O,r:

8 l

C 3

c2 2Q l

~

mllCyg l

e h

l t lL i H AE e CE N S

IC HND 3 LH

.N A i

g n

T WAE AC y N LR ,

V l E NLI 2#

M Ra p IIU # E p E EO ,

Te a R SVE 13 Nv I ERR Ii y U DU e b O OS Gc E M Ne r R I r e E L t C El t N L Ul i A A Fa m L LN Eh s .

L EOT ** Rs nr I NIS ** ae E NTE rn rt V ACT eo tt pi i R HN U CU ea t

hs em S F cu tn

)

N nt a d O N oc gr e O a nt u I N t i n T LI O ss se .

i A ET I ad ih n t T NA RR T er ct e n N NR A l a r p o E AB T u ef o C M HI O t g xo

( U CL N ae e s R A f . e i 2 T C E das ed

- S L esy e N di 3 I B t a us v A sld l l 4 L T ea ce a M EK t u1 nt V E E NC SS n3 i a L T NE ea i n B S AH o Y HC bmr l r A S C e l p i T lhp ao t N lt hr a aie sp l O e o I v hwc s

p s

T l n Ta A a do S I U V 1 se Ee ett Th t T .

has t a C n e A o d. cia t ce L

Ao H ir 2 iol Nt S

E te at 5 ws sst O

I e y

a R l a . c U S oe aa Tr T

4 n Cu e L sH oyT Ns D A E I n i rS Us E N r o r F N ttE Fe te i aiT r e -

Y A az t uu Lp h T H ei a t cL E t T I C Hr c crA Nr i E N u i e F U K ys f aiN No A C as cO A D S

' i l I Hm E n L O ce c art Cu T e A L er e ueC u E h -

N R DP p nhN ec L W O E S atU ha E -

I T MoF Tv D T N . . e _

C I ab e N S ) )

U F 5 1

(

2

( #

f E5TE 5 eE[ w1 wk'" g E : :

" ku" h '

a r ' ari vy j

LAR 98-0005 Page 17 i 3/4.3 INSTRUMENTATIQN ADDITIONAL CHANGES PREVIOUSLY BASES PROPOSED BY LETTER

, Serial No._ 2 5 8 3 Date 7h&/n 3/4.3'.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND 5/JiEY GTGTD '  ;

IN8'lKUMENTATION The OPERABILITY of the RPS, SFAS and SFRCS instrumentation systems ensure that I) the associated action and/or trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint,2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or mainenance, and 4) sufficient system functional capability is available for RPS, SFAS and SFRCS purposes from diverse parameters. l The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The lategrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. The response time limits for these instrumentation systems are located in the Updated Safety Analysis Report and are used to demonstrate OPERABILITY in accordance with each system's response time surveillance requirements.

I For the RPS, SFAS Table 3.3-4 Functional Unit Instrument Strings h,g d, and e, and Interlock Channel a, I and SFRCS Table 3.3-12 Functional Unit 2:

Only the Allowable Value is specified for each Function. Nominal trip setpoints are speciGed in the setpoint analysis. The nominal trip setpoints ate selected to ensure the setpoints measured by CHANNEL FUNCTIONAL TESTS do not exceed the Allowable Value if the bistable is performing as required. Operation with a trip setpoint less conservative than the nominal trip setpoint, but within its Allowable Value,is acceptable provided that operation and testing are consistent with the assumptions of the specific setpoint calculations. Each Allowable Value specified is more conservative than the analytical limit assumed in the safety analysis to account for instmment uncertainties appropriate to the trip parameter. These uncertainties are defined in the specific setpoint analysis.

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Setpoints must be found within the specified Allowable Values. Any setpoint adjustment shall be consistent with the assumptions of the current specific setpoint analysis.

A CHANNEL CALIBRATION is a complete check of the instrument channel, including the sensor. The test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instmment drift to ensure that the instmment channel remains operational between successive tests. CHANNEL CALIBRATION shall find that measurement errors and bistable setpoint errors are within the assumptions of the setpoint analysis. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the setpoint analysis.

The frequency is justified by the assumption of an 18 or 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

DAVIS-BESSE, UNIT 1 B 3/4 3-1 Amendment No. 73,125,128,211,218,225

. (Next page is B 3/4 3-la)

LAR 98-0005

, Page 18 j l

374.3 INSTRUMENTATION TlilS PAGE PROVIDED BASES _

3/4.3.1 'nda3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEM INSTRUMENTATION (Continued)

The measurement of response time at the specified frequencies provides assurance that the RPS, SFAS, and SFRCS action function associated with each channel is completed within the time limit assumed in the safety analyses. l Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

The actuation logic for Functional Units 4.a. , 4.b. , and 4.c. of Table 3.3-3, Safety Features Actuation System Instrumentation, is designed to provide protection and actuation of a single train of safety features equipment, essential bus or emergency diesel generator. Collectively, Functi.onal Units 4.a., 4.b., and 4.c. function to detect a degraded voltage condition on either of the two 4160 volt essential buses, shed connected loads, disconnect the affected bus (es) from the offsite power source and start the associated emergency diesel generator. In addition, if an SFAS actuation signal is present under these conditions, the sequencer channels for the two SFAS channels which actuate the train of safety features equipment powered by the affected bus will automatically sequence these loads onto the bus to prevent overloading of the emergency diesel generator. Functional Unit 4.a. has a total of four units, one associated with each SFAS channel (i.e., two for each essential bus). Functional Units 4.b. and 4.c. each have a total of four units, (two associated with each essential bus); each unit consisting of two undervoltage relays and an auxiliary relay.

An SFRCS channel consists of 1) the sensin'g devics(s), 2) associated logic and output relays (including Isolation of Main Feedwater Non Essential Valves and Turbine Trip), and 3) power sources.

The SFRCS response time for the turbine stop valve closure is based on the combined response times of main steam line low pressure sensors, logic cabinet delay for main steam line low pressure signals and closure time of the turbine stop valves. This SFRCS response time ensures that the auxiliary feedwater to the unaffected steam generator will not be isolated due to a SFRCS low pressure trip during a main steam line break . accident.

Safety-grade anticipatory reactor trip is initiated by a turbine trip (above 1 45 percent of RATED THERMAL POWER) or trip of both main feedwater pump turbines. This anticipatory trip will operate in advance of the reactor coolant system high pressure reactor trip to reduce the peak reactor coolant system pressure and thus reduce challenges to the pilot operated relief valve.

This anticipatory reactor trip system was installed to satisfy Item II.K.2.10 of NUREG-0737. The justification for the ARTS turbine trip arming level of i 45% is given in BAW-1893, October, 1985. I DAVIS-BESSE, UNIT 1 B 3/4 3-la Amendment No. 73,12S,148A3k244,248r 225

Docket Number 50-346 License Number NPF-3 Serial Number 2586 Enclosure 2 o

COMMITMENT LIST THE FOLLOWING LISTIDENTIFIES THOSE ACTIONS COMMITTED TO BY DAVIS-BESSE NUCLEAR POWER STATION IN THIS DOCUMENT. ANY OTHER ACTIONS DISCUSSED IN TIIE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY DAVIS-BESSE. THEY ARE DESCRIBED ONLY AS INFORMATION AND ARE NOT REGULATORY COMMITMENTS, PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8466) AT DAVIS-BESSE OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE None. N/A.

I