ML20237G259

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Proposed Tech Specs,Removing All Safety Features Actuation Sys Response Times & Containment Isolation Time Requirements from Valves on Secondary Side of Steam Generators
ML20237G259
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 08/07/1987
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20237F807 List:
References
TAC-65685, NUDOCS 8708130380
Download: ML20237G259 (22)
v • d • e


Text

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hil PAGE PROYlDED l FORINFORMATIOM ONL INSTRUMENTATION 3/a.3.2 SAFETY SYSTEM INSTRUMENTATION 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 setpoint', set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-S.

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 func-tional unit is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

i

b. With a SFAS functional unit inoperable 'take the action shown 1

. 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 CFANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the. MODES and at the frequencies shewn in Table 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demtInstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of functional units affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 montns 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 18 months.

Each test shall include at least one functional unit per function such that all functional units are tested at least once every N times 18 .

months 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.

DAVIS-BESSE. UNIT 1 3/4 3-9 B708130380 B70007 '

PDR ADOCK 05000346 P PDR

THIS PAGTPROVIDE

~

l- "'"-'

FORINFORMAll0N ON SAFETY FEATURES SYSTEM RESPONSE TIMES RESPONSE TIME IN SECONDS INITI ATING SIGNAL AND FUNCTION _

1. Manual
a. Fans MA
1. Emergency vent Fan NA
2. Containment Cooler Fan .
b. NV & AC ! solation Valves NA
1. ECCS Room NA

- 2. Emergency Ventilation Containment Air Sample NA

3. -

NA

4 Containment Purge ,

Pentration Room Purge NA S.

NA

c. Control Room HV & AC Units
d. High Pressure Injection High Pressure Injection Pumps MA l 1. NA
2. High Pressure Injection Valves
e. Component Cooling Water Component Cooling Water Pumps NA l
1. NA
2. Component Cooling Aux. Equip. Inlet valves Ccmponent Co. ling to Air Compressor Valves NA 3.
f. Service Water System l NA
1. Service Wa ter Pumps
2. Service Water From Component Cooling Heat Exchanger Isolation Valves NA NA
g. Contaiment Spray Isolation Valves NA
h. Emergency Diesel Generator
1. Contaiment Isolation Valves NA
1. Vacus Relief NA
2. Nonnal Sump RCS Letdown Delay Coil Outlet NA
3. NA
4. RCS Letdowr High Temperature DAVIS-BESSE UNIT 1 3/4 3 14

TABLE 3.3-5 (Continued)

SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

1. ContainmentIsolationValves(cont'd)
5. Pressurizer Sample NA
6. Service Water to Cooling Water NA l 7. Vent Header NA
8. Drain Tank NA
9. Core Flood Tank Vent NA

'10. Core Flood Tank Fill NA l

11. Steam Generator Sample NA
12. Atmospheric Vent NA
12. Eh Quench Tank NA
13. M. Emergency Sump NA
t a . W. RCP Seal Return NA 15.M. Air Systems -

NA l 16.1+. N System NA

17. W. Q,ench u Tank Sample _

NA

19. Mein Stet.m Wermup Drein NA ';

18.B&. Makeup NA  !

19. Eh RCP Seal Inlet NA 2o. 22. Core Flood Tank Sample NA 2t . M. RCP Standpipe Demin Water Supply NA 22.04 Containment2H Dilution Inlet NA 23.35. Containment 2H Dilution Outlet NA
j. BWST Outlet Valves NA
k. Low Pressure Injection l 1. Decay Heat Pumps NA l 2. Low Pressure Injection Valves NA
3. Decay Heat Pump Suction Valves NA l 4. Decay Heat Cooler Outlet Valves NA
5. Decay Heat Cooler Bypass Valves NA
1. Containment Spray Pump NA
m. Component Cooling Isolation Valves
1. Inlet to Containment -

NA

2. Outlet from Containment NA
3. Inlet to CRDM's NA 4 CRDM Booster Pump Suction NA
5. Component Cooling from Decay Heat Coolers NA 1

StGam and IG&iw6tEi 150ldtiOn Vhlvn

i. Me in S tEEE d T16 MN DAVIS-BESSE, UNIT 1 3/4 3-15

~

TABLE 3.3-5 -(Continued)

SAFETY FEATURES SYSTEM RESPONSE TIMES-- -

i- INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

. S team-a4Feedwa tee-Isoht4en-Vahc: (cont 4nced) 2---Mafn-feedwater-Stop NA
3. Main Steam-Warmttp NA-
2. Containment Pressure - High
a. Fans
1. Emergency Vent Fans < 25*
2. Containment Cooler Fans i45*
b. HV & AC Isolation Valves-
1. ECCS Room < 75*
2. Emergency Ventilation 7 75*
3. Containment Air Sample 7'30*

4 Containment Purge 7 15*

5. Penetration Room Purge [75*
c. Control Room HV & AC Units < 10* -
d. High Pressure Injection
1. High Pressure Injection Pumps < 30*
2. High Pressure Injection Valves i30*
e. Component Cooling Water
1. Component Cooling Water Pumps < 180*
2. Component Cooling Aux. Equip. Inlet Valves 7 180*
3. Component Cooling to Air Compressor Valves i180*
f. Service Water System

~

1. Service Water Pumps < 45*
2. Service Water From Component Cooling Heat Exchanger Isolation Valves < NA*
g. Containment Spray Isolation Valves < 80*
h. Emergency Diesel Generator < 15*

DAVIS-BESSE, UNIT 1 3/4 3-16 .

TABLE 3.3-5 (Continued)_

)- SAFETY' FEATURES SYSTEM RESPONSE TItiES INITIATING SIGNAL AND FUN'CTION' RESPONSE TIME IN SECONDS

2. Containment Pressure - High (Continued)
1. Containment Isolation Valves
1. Yacuum Relief <.30*'
2. Normal Sump i25*-
3. RCS Letdown Delay Coil Outlet < 30*
4. RCS Letdown High Temperature 1 30*
5. Presstri7er Sample 1 48*
6. Service Water to Cooling Water < 45*
7. Vent Header < 15*
8. Drain Tank 7 15*
9. Core Flood Tank Vent 7 15*
10. Core Flood Tank Fill 7 15*
11. Steam Generator Sample 7 15*
12. ALuosphm iu Vent

~ 17-

12. +S. Quench Tank 7 15*
13. M. Emergency Sump ~ NA*
g. 4. RCP Seal Return < 45*

is 44. Air System ~ 15*

t (o . H . N7 System 7 15*

17. +8*. 00ench Tank Sample 7 35*

- 10. "ein Steem "erm p Dreir. ~ 15'

17. M. Makeup 7 30*

19 . M. RCP Seal Inlet 7 17*

20. & Core Flood Tank Sample 7 15*
21. M . RCP Standpipe Demin Water Supply 7 15*
22. M. Containment2H Dilution Inlet 7 75* -l 2325. Containment H2 Dilution ' Ou tl et - ~

1 75* j

j. BWST Outlet Valves NA*  !
k. Low Pressure Injection j
1. Decay Heat Pumps < 30* i
2. Low Pressure Injection Valves 7 NA*
3. Decay Heat Pump Suction Valves 7 NA 4 Decay Heat Cooler Outlet Valves 7 NA*
5. Decay Heat Cooler Bypass Valves ~ NA*
3. Containment Pressure--High-High
a. Containment Spray Pump 1 80*
b. Component Cooling Isolation Valves
1. Inlet to Containment -< 25*
2. Outlet from Containment 25*

DAVIS-BESSE, UNIT 1 3/4 3-17

y

, 'I i

TABLE 3.3-5 (Continued)

SAFETY FEATURES SYSTEM RESPONSE TIMES i I

INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS I

b. ~ComponentCoolingIsolationValves'(Continued) i
3. Inlet to CRDM's < 35* I
4. CRIM Booster Pump Suction 7 35
  • j
5. -Component Cooling from Decay Heat Cooler 5 M* l l

- --- c . SteGm-eftd-feedwater-f3015ticG V51VE5

1. Mein Steam-tdne 4 10'
2. Main-Teedneter Stop 7W
3. Main-Steam-Warmup ~ 15:

l

4. RCS Pressure-Low l j a. Fans )

l  !

1. Emergency Vent Fans < 25* j
2. Containment Cooler Fans 7 45*

I

b. HV & AC Isolation Valves l

! 1. ECCS Room < 75*

2. Emergency Ventilation 7 75
  • I
3. Containment Air Sample 7 30*
4. Containment Purge 7 15* j 5: Penetration Room Purge i75*

l

c. Control Room HV & AC Units  ; 10*
d. High Pressure ?njection 1
1. High Pressure IH ection Pumps < 30*
2. High Pressure Injection Valves i30*
e. Component Cooling Water
1. Component Cooling Water Pumps -

< 180*

2. Component Cooling Aux. Equipment Inlet Valves < 180*
3. Component Cc'oling to Air Compressor, Valves i180*
f. Service Water System
1. Service Water Pumps < 45*
2. Service Water from Component Cooling Heat Exchanger Isolation Yalves 1 M*
g. Containment Spray Isolation Valves 1 80*
h. Emergency Diesel Generator 1 15*

DAVIS-BESSE, UNIT 1 3/4 3-18 i

TABLE 3.,3-5 (Continued)_

(f.f ETY FEATUCES S'.'1TCfi RCSTCi:SC TIMES.

RESP 0ftSE T!!;E If1 SECON05 j II:1T!?.TIMG SIGNf.L AND TURCTIO_N ,

4. CCSPressurc-Lou (continued)

I

1. Containm:nt Isolatioi; Valves
1. Vacuum Relief < 30* l
2. f:ormal Sump 7 25*
3. RCS Letdown Delay Coil Outlet 7 30* * "
4. RCS Letdown High Temperature 7 30*
5. Pressurizer Sample 7 45'
6. Service Water to Cooling I!ater 7 45* '

l

7. Vent Header 7 15'
8. Drain Tank 7 15' l 9. Core Flood Tank Vent 7 15*

I 10. Core Flood Tank Fill 7 15*

11. Steam Generator Sample 7 15*
12. AL...u w b u k Veni 7 17 ^
12. B. Quench Tank 7 15*
13. M. Emergency Sump NA*

! 14. +5. Air Systems 1 15*

i5. M . N2 System i 15' -

g g . -Fr. Quench Tank Sample 1 35*

10. "ein Stzs: We,wwp Orein i 1." - -  !

iT. i . Core Flood Tank Sample < 15*

)

l 17. eE . RCP Standpipe Demin Water Supply 515*

Containment H> Dilution Inlet < 7 5*

, 19. i!t.

20 .d. Containment Hj Dilution Outlet 5 75*  ;

j. BWST Outlet Valves NA*
5. RCS Pressure--Lew-Low l a. Low Pressure Injection l 1. Decay Heat Pumps < 30*

!  ?. Low Pressure Injection Valves 7 NA' j 3. Cecay Heat Pump Suction Valves 7 NA*

4 Decay Heat Cooler Outlet Yalves 7 NA*

5. Decay Heat Cooler Bypass Valves {.W

~

b. Component Cooling Isolation Yalves
1. Auxiliary Equipment In' *t < 90*

~

2. Inlet to Air Compresso.- 7 90*
3. Component Cooling from Decay Heat Cooler

[NA*

. Containment Isolation valves I- RCP Seal Return < 45*

2- Makeup {30*

3. RCP Seal Inlet 1 17*

l- nAuf %utu _ um 1 eu em

~

THIS PAGE. PROVID FORINFORMATION DNL l

_ I TABLE 3.3-5 (Continued) i SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS j

6. Containment Radiation - High
a. . Emergency Vent fans < 25*
b. HV & AC 1 solation Yalves
1. ECCS Room < 75* 1
2. Emergency Ventilation {75* i
3. Containment Air Sample < 30*
4. Containment Purge 7 15*
5. Penetration Room Purge i75* ]

l c. Control Room HV & AC Units l

_10*

6 TABLE NOTATION <

Diesel generator starting and sequence loading delays included when applicable. Response time limit includes movement of valves and l attainment of pump or blower discharge pressure.

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s d & J DAY!S-8 ESSE. UNIT 1 3/4 3-11 Amendment No.,X ,../#, 4";

3/4.3 INSTRUMENTATION l BASES l

! ADD h0NAL CHANCES PREVl00 S l

3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND '

PROPOSED BY LETTER

)Mr.IY SYSTEM INSTRUMENTATION I Serbl No.__/ 354 DateJ-2317 i l

The OPERABILITY of the RPS, SFAS and SFRCS instrumentation systems ensure that 1) 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 maintenance, and 4) sufficient systern functional capability is available for RPS, SFAS and SFRCS purposes from div2rse parameters.

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 con-d i t. ions .

The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

i The surveillance requirements specified for these systems ensure

! that the overall system functional capebility is r.aintained comparable to the original design standards. The periodic surveillance tests l

perfonned at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the RPS, SFAS, and SFRCS action fLnction associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the anal with response times indicated as not applicable. yses for those channels Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such test demonstrate the total channel response time as defined. St.sor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sehsors with certified response times.

An SFRCS channel consists of 1) the sensing device (s), 2) associated l ogic and output relays (including Isolation of Main Feedwater Non Essential V alves and Turbine Trip), and 3) power sources.

Safety-grade anticipatory reactor trip is initiated by a turbine trip (aove 25 percent of RATED THERMAHL POWER) or trip of both main feedwater pump r turbines. This anticipatory trip will operate in advance of the r eactor coolant systes high pressure reactor trip to reduce the peak' o perated relief system eactor coolant valve. pressure and thus reduce challenges to the power This anticipatory reactor trip system was installed to satisfy item II.K.2.10 of NUREG-0737.

DAVIS-BESSE Unit 1 B 3/4 3 1 knendment No. 73 -

~

TH 8 %E PR0"DfD

0R NFORFE0N ON.Y CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION -

3.6.3.1 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve (s) specified in Table 3.6-2 inoperable, either: ,

l I

a. Restore the inoperable valve (s) to OPERABLE status within 4  !

hours, or l

b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or l

l c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 'by use of at -

least one closed manual valve or blind flange; or 4

d. 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 />.

SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve l

or its associated ac+9ator, control or power circuit by performance of a cycling test and verification of isolation time.

DAVIS-BESSE, UNIT.1 3/4 6-14

TlilS PAGE PROVIDE FORINFORMATION 1'

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4.6.3.1.2 Each isolation valve specified'in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a containment' isolation test. signal, each automatic isolation valve actuates to its isolation position. I
b. Verifying that on a Containment Purge and Exhaust isolation '

test signal, each Purge and Exhaust automatic valve actuates to its isolation position. .

~. . ,

l 1

. 1

1 l

l I

~-

DAVIS-BESSE, UNIT 1 3/4 6-15 .

4 L____________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

THIS PAGE PROVIDE FORINFORMATION ON I

q TABLE 3.6-2 CONTAINMENT ISOLATION VALVES PENETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION TIME

.(seconds)

A. CONTAINMENT ISOLATION 1 RC240A Pressurizer Sample Line 30' 1 RC240B Pressurizer Sample Line 30-2 # SS607 Steam Generator Secondary Water Sample Line 10- 4 3 CC1411A Component Cooling Water Inlet Line 15 3 CCl411B Component Cooling Water Inlet Line 15 4 CC1407A' Component Cooling Water Outlet Line 15 I 4 CC14078 Compcw Cooling Water Outlet Line. 15 8A CV5070 contair. ment Vessel Vacuum Breaker 15

8B CV5071 Containment Vessel Vacuum Breaker 15 BC CV5072 Containment Vessel Vacuum Breaker 15 80 CV5073 Containment Vessel Vacuum Breaker , 15

! 8E CV5074 Containment Vessel Vacuum Breaker 15 8F CV5075 Containment Vessel Vacuum Breaker 15 8G CV5076 Containment Vessel Vacuum Breake,- 15 8H CV5077 Containment Vessel Vacuum Breaker' 15 81 CV5078 Containment Vessel Vacuum Breaker 15.

8J CV5079 Containment Vessel Vacuum Breaker 15 12 CC1567A Control Rod Drive Cooling Supply ,

Line 15 12 CC1567B Control Rod Drive Cooling -Supply Line 15 13 DR2012A Containmrt Vessel Normal Sump Drain 15 13 DR2012B Containment Vessel Normal Sump Drain 15 3 14 MU3 RCS Letdown Line 10 j 14 MU2A RCS Letdown Line 15 i i

1 DAVIS-BESSE, UNIT 1 3/4 6-16 t _ _ _ _ - _ _ _ _ _

a MDlil0NAl. CHANGES PREVIOUSLY ,

. PROPOSED BY LETTER. )

SerialNo. /c246 Date 7-3/- F6 TABLE 3.6-2

. CONTAINMENT 50LATION YALVES (Continued)'

PENETRATION VALVE .. ISOLATION NUMBER NUMBER FUNCh 0N TIME 4 (seconas) 16 RC1719A Containment Vessel'Yent Header 10._ _

~ '

16 .RC17198 Containment Vessel Vent Header 10 18 i 55598 Steam Generator Secondary Water '

.l '

Sample Line 10 19 MU33 - Normal RCS Makeup Line - 10.  :

19 i HP2A High Pressure Injection Line. 15 20 i 'HP2B High Pressure lidection Line 15~

21 DW6831A Demineralized Water Supply Line 10-21 DW6831B Demineralized Water Supply Line- 10 22 i HP2D High Pressure Injection Line 15 25 C51531 Containment Spray Line 35 U 26 C51530 containment Spray Line -

35 30 i . DH9A Containmer.t Sump Emergency Recire 71 Line 31 i DH98 Containment Susp Emergency Recire Line 71 32 MC1773A RC5 Drain to RC Drain Tank 10 i

32 RC1773B RCS Drain to RC Drain Tank 10 .

l 7i FW601 Main Feedwater Line l 38 d612 Main Feedwater Line 15

19 i MS375 Main 5 Line 10  !

10  !

39 f M5100-1 Main Steam

    • 40 i M5101 Main Line 5 i
    • 40~l IC5118 ain Staas Line 10 l

40 i Pe Main Steam Line - 10 1 i

4 M5101-1 Main Steam Line 0 DAVIS-BESSE, UNIT 1 3/4 6-17 . Amendment No. /, 72 i

I

___ _ _ _ _ _ _ _ ___[_._______________.________.______.___________.___. . . . . _ _ .-

- ADDlit0NAL CHANCES PREVI'00 SLY PROPOSED BY LETTER SerialNo 42G5 Date 78/-f6 i

ADDITIONAL CHANGES PREVIOUSLY PROPOSED BY LEITER .,

. SeriaINo. /375 Date54-f7 TABLE 3.5-2 CONTAINMENT ISOLATION VALVES (Continued)

PENETRATION VALVE NUMBER ISOLATION NUMBER FUNCTION

__ TIME (seconas) 41 RC232 Pressurizer Quench Tank Circulating Inlet Line 10 42A SA2010 Service Air Supply Line 10 42B CY5010E Containment Vessel Air Sample Return 15 43A IA2011 Instrument Air Supply Line 10 43B CY5011E Containment Vessel Air Sample Return 15 44A CF1541 Core Flood Tank Fill and N2 Supply Line 10

~ 44B NN236 Pressurizer Quench Tank N2 Supply Line 10 47A CV1545 Core Flood Tank Sample Line 1 10 47B CY1542 Core Flood Tank Vent Line 10  !

48 RC229A Pressurizer Quenen T. ink Circulating Outlet Line 10 48 RC229B Pra_ssurizer Quench Tank Circulating 10 Outlet Line 50 f HP2C High Pressure Injection Line 15 51 LV5037 Hydrogen Purge System Exhaust Line 60 51 CY5038 Hydrogen Purge System Exhaust Line 60 52 MU5fA Reactor Coolant Pump Seal Su;, ply 12 l 53 MU56B Reactor Coolant Pump Seal Supply 12 54 MU66C Reactor Coolant Pump Seal Supply 12 55 MU66D Reactor Coolant Pump Seal Supply r 12 56 MU38 Reactor Coolant Pump Seal Raturn 12 56 MU59A- Reactor Coolant Pump Seal Return l

30 56 MU598 Reactor Coolant Pump Seal Return 30 56 MU59C Reactor Coolant Pump Seal Return 30 56 MU590 Reactor Coolant Ptap Seal Return 30 07 iG003 Stcom Genc,atur Bluwduwn Line 80 00 70 011 Steein Genereter Olewdcwn Line . 00 l

DAVIS-BESSE, UNIT 1 3/4 6-18 Amendment No. 79

, ADDlil0N/L CHANGES PREVIOUSLY PROPOSED BY LETTER SerialNo. /l246 Date 7-3/ -%

TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)

PENETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION TIME (seconds) 67 CY5090 Hydrogen Dilution System Supply 60 68A SS235A Pressurizer Quench Tank Sample 30 68A SS235B Pressurizer Quench Tank Sample 30 r 68B CV5010B Containment Air Sample 15 68B CV50llB Containment Air Sample 15 l 69 CV5065 Hydrogen Dilution System Supply 60 71B CV5010A Containment Air Sample 15 718 CV5011A Containment Air Sample 15 71C CV1544 Core Flood Tank N2 Fill 10 73B CV5010C Containment Air Sample 15 73B CV5011C Containment Air Sample 15 74B CV50100 Containment Air Sample 15 748 CY50llD Containment Air Sample 15 B. CONTAINMENT PURGE AND EXHAUST ISOLATION 33 ## CV5005 Containment Vessel Purge Inlet Line 10 33 #/ CV5006 Containment Vessel Purge Inlet Line 10 34 ## CY5007 Containment Vessel Purge Outlet Line 10 34 ## CV5D08 Containment Vessel Purge Outlet Line 10 C. OTHER 5 # SW1366 Containment Air Cooling Units SW inlet Line N/A 6 # SW1368 Containment Air Cooling Units SW

. Inlet Line N/A 7 # SW1367 Containment Air Cooling.U SW Inlet Line N/A 9 # SW1356 Containment Air Cooling Units SW Outlet Line N/A DAVIS-BESSE, UNIT 1 Amendment No. 81,75 3/4 6-19

NN NN -

- ADDITIONAL CHANGES PREVIOUSLY.

~

' IIIIU gnML I U '[

e_l"La "h 1A,2 3. .

FORINFORMATIO

. CONTAINMENT. ISOLATION VALVES '(Continued)

  • PENETRATION. VALVE NUMBER ISOLATION NUMBER FUNCTION TIME fseconas) 10'# SW1358 Containment Air Cooling Units SW~ N/A Inlet Line 11 # SW1357 Containment Air Cooling' Units SW Outlet ' Line N/A.

17 C'd43 Containment Vessel Leak Test Inlet Line {

17 Flange Co~ntainment Vessel Leak Test Inlat-Line'(Inside Containment) N/A.

19 # HP5/ High Pressure Injection Line N/A-4 20 # HP56 N1gh Pressure Injection Line

' N/A 22 i HD49 Nigh Pressure Injection Line N/A 23 # SF1 Fuel Transfer Tube N/A 23 Flange Fuel Transfer' Tube N/A 24 9 SF2 Fuei Transfer Tube N/A 24 Flange Fuel Transfer Tube 'N/A

'25 CS17 Containment Spray Line '

N/A 25 SA536 Containment Spray Line N/A 25 SA532 Containment Spray'Line N/A

  • 25 CS18 Containment Spray Line N/A 25 SA535 Containment Spray Line N/A -l 26 SA533 Containment Spray Line N/A 27 # DH1A Low Pressure. Injection Line N/A 27 # DH76 Low Pressure Injection Line N/A "i DH1B Low Pressure Injection Line . N/A 28 # DH77 Low Pressure trige: tion Line N/A l

l DAVIS-BESSE, UNIT 1 3/4 6-20 Amendment No. 3 r  !

~

. 'n E__________________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.

_j

ADDil10NAL CHANGES PREVIOUSLY TABLE 3.6-2 PROPOSED BY LETTER Seriat No. /ch5 Date 7-3 -%)

CONTAINMENT ISCLATION VALVES (Contin;ed)

PENETRATION YALVE ISOLATION NUMBER HUMBER FUNCTION TIME

  • 29 # DH11 Decay Heat Pump Suction Line N/A
  • 29 DH23 Decay Heat Pump Suc':1on Line N/A i 29 i PSV4849 Decay Heat Pump Suction Line N/A' 35 i AF599 Aukiliary Feedwater Line N/A

_Inser b 36 # AF608 Auxiliary Feedwater Line N/A A

  • I

+39 # FG107 Main Steam Line N/A '

+39 # M5107A Main Steam Line N/A

  • 40 i K5106 Main Steam Line N/A 33ef 4 +40 i M5106A Main Steam Line N/A 3 41 RC113 Pressurizer Quench Tank Inlet Line N/A 42A SA502 Service Air Supply Line N/A 428 CV124 Containment Vessel Air Sample Return N/A

, 43A IA501 Service Air Supply Line N/A 435 CY125 Containment Vessel Air Sample Return N/A 44A CF15 Core Flood Tank Fill and Nitrogen Supply Line N/A 44S NN58 Pressurizer Quench Tank Inle:

Line N/A ,

CF2A Core Flood Tank Samole Line N/A

  • CF25 Core Flood Tank Sample Line N/A i

'47B CF5A Core Flood Tank Vent Line N/A )

  • 478 CF5B Core Flood Tank Vent Line N/A 49 DH87 Refueling Canal Fill Line N/A i 49 DH88 Refueling Canal Fill Line N/A l 3

)

i i

[

CAVI5-BESSE, UNIT 1 3/4 6-21 Amendment No. 3

_-____-________O

J l

l

~I I

7nserb A 37 i FW601 Main Feedwater Line N/A 38 i FW612 Main Feedwater Line (A

29 i MS375 Main Steam Line N/A 39 i M5100-1 Main Steam Line N/A Inse r t B

j ADDITIONAL CHANGES PREVIOUSL I TABLE 3.6-2

! - PROPOSED BY LETTER SerialNo. /85 Date76/-%

CONTAINMENT ISOLATION VALVES (Contintud) l PENETRATION VALVE ISOLATION .

NUMBER HUMBER FUNCTION TIME 49 OH87 Refueling Canal Fill Line --

N/A 49 DH38 Refueling Canal Fill Line N/A 50 f HP48 High Pressure Injection N/A 52 MU242 RCP Seal Water Supply N/A 53 MU243 RCP Seal Water Supply N/A 54 MU244 RCP Seal Water Supply N/A 55 MU245 RCP Seal Water Supply N/A Deleted Deleted Del eted Deleted 59 Flange Secondary Side Cleaning (Inside Containment) N/A 59 Flange Secondary Side Cleaning (Outside DS Containment)

N/A 67 CY209 Nydrogen Dilution System Supply N/A 69 CY210 Hydrogen Dilution System Supply N/A 71A # CV20005 Containment Pressure Sensor N/A 71C CF16 Core Flood Tank Nitrogen Fill Line h/A 72A f CV2001B Containment Pressure Sensor N/A 72C f CV624B Containment Pressure Differential Transmitter N/A 73A # CV20028 Containment Pressure Sensor N/A 73C f CV645B Containment bessure Differential Transmitter N/A 74A f CY20038 Containment Pressure Sensor N/A

'740 OH2735 Pressurizer Auxiliary Spray N/A

'74C OH2736 Pressurizer Auxiliary Snray N/A vay be opened on an intermittent basis under administrative control.

fNot subject to Type C leakage tests.

" Surveillance .estint not reguired prior to entering MODE 4 but shall be perscrmed prior to entering Mode 3.

  1. fProvisions of Specification 3.0.4 are not applicable provided the valve is in the closed positions and deactivated.

DAVIS-BESSE, UNIT 1 3/4 6-22 Amendment No. X. J7,79

40 4

i d n 6 C ( E C-I f

' 57 MS603 Steam Generator Blowdosn Line N/A, 60 - MS611 Steam Generator Dlowdown Line g/A 1

I l

l l

l 1

1 l

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L_._________m__ _ _ _ _ _ _ . . _ _ _ . _ _ _ _ . _ - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ . - _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _.____.__.____.___.)

FORINFORMATION ON i

l l

CONTAINMENT SYSTEMS BASES leakage rate are consistent with the assumptions used in the safety analyses. The leak rate surveillance requirements assure that the leakage assumed for the system during the recirculation phase will not be exceeded.

3/4.6.2.2 CONTAINMENT COOLING SYSTEM .

The OPERABILITY of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits during nonnal operation, and 2) adequate heat removal ~ capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.

I l 3/4.6.3 CONTAINMENT ISOLATION VALVES l

The OPERAB". ITY of the containment isolation valves ensures that the i l containment atn sphere will be isolated from the outside environment in l I

l the event of a release of radioactive material to the containment atmsphere or pressurization of the containment. Containment isolation j within the time limits specified ensures that the release of radioactive i material to the environment will be consistent with the asstaptions used  ;

in the analyses for a LOCA.

i l

i DAVIS-BESSE, UNTI i 8 3/4 6-3

__. _ _ _ _ _ _ _ - - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _

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