ML20212B782

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Proposed Tech Specs,Reflecting Deletion of Isolation Times for Specific High Pressure Injection & Containment Spray Containment Isolation Valves & Redundant Listing for Containment Isolation Valves DH87 & DH88
ML20212B782
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 07/31/1986
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20212B773 List:
References
NUDOCS 8608070227
Download: ML20212B782 (14)
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[$NEd,b CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 At least two independent containment cooling units shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one of the above required containment cooling units inoperable, restore at least two units to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 />.

SURVEILLANCE REQUIREMENTS i

e 4.6.2.2 At least the above required containment cocling units shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting (unless already operating) each unit from the control room, and 2.

Verifying that each unit operates for at least 15 minutes.

b.

At least once per 18 months by verifying that each unit starts automatically on low speed upon receipt of a SFAS test signal.

t DAVIS-BESSE, UNIT 1 3/4 6-13 i

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3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION l

3.6.3.1 The containment isolation valves specified in Table 3.6-2 shall be OPERA 8LE with isolation times as shown in Table 3.6-2.

APPLICABILITl: MODES 1, 2, 3 and 4.

ACTION:

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

a.

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

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hours, or 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 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 l

1 east one closed manual valve or blind flange; or

..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 />.

s 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 naintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by perfomance of a cycling test and verification of isolation time.

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

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUT 00WN 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.

b.

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

I DAVIS-BESSE, UNIT 1 3/4 6-15 l

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FORINGRMAIiBN Bhil TABLE 3.6-2 l

CONTAIMENT ISOLATION VALVES l

PENETRATION VALVE ISOLATION l

NUMBER

, NUMBER FUNCTION TIME l

(se onds) l l

A.

CONTAI MENT ISOLATION l

1 RC240A Pressurizer Sample Line 30 1

RC2408 Pressurizer Sample Line 30 2 # 55607 Steam Generator Secondary Water Sample Line I

10 3

CC1411A Component Cooling Water Inlet Line 15 3

CCl4118 Component Cooling Water Inlet Line 15 4

CC1407A Component Cooling Water Outlet Line 15 4

CC14078 Component Cooling Water Outlet Line 15 8A CV5070 Containment Vessel Vacuum Breaker 15

'N 88 CV5071 Containment Vessel Vacuum Breaker 15 8C 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 Yessel Vacuum Breaker 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 l

12 CC15678 Control Rod Drive Cooling Supply Line 15 13 DR2012A Containment Vessel Normal Sump Drain 15 13 DR20128 Containment Vessel Nomal Sump Drain 15 14 MU3 RCS Letdown Line 10 14 MU2A RCS Letdown Line 15 t

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

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TABLE 3.6-2

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CONTAINMENTDSOLATIONVALVES(Continued)

ISOLATION PENETRATION VALVE NUMBER NUMBER FUNCTION TIME (seconcs) 16 RC1719A Containment Vessel' Vent Header 10.

16 RC17198 Containment Vessel Vent Header 10 18 i S5598 Steam Generator Secondary Water 10 Sample Line 19 MU33 Nonnal RCS Makeup Line 10 I" ! ll" A llip. Tic;;are Infc;tica Line 15 20 i !iPd Hij.i."rn;;r:If.jecticaLins 15-2!

DW6831A Demineralized Water Supply Line 10 21 DW6831B Demineralized Water Supply Line 10 22 i liP20 tiip. T.es;;rs !ajectisa Line

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25 C:1531 C= t:fr ;;t grey Lins 3

25 C1500 C;;taicacat Sprey Lia; 30 i DH9A Containment Sump Emergency Recire 71 Lina

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Containment Sump Emergency Recire 31 i DH98 71 Line 32' MC1773A RCS Drain to RC Drain Tank 10 32 RC17738 RCS Drain to~RC Drain Tank 10 37 i FW601 Main Feedwater Line 15 38 i FW612 Main Feedwater Line 15 5

10 39 i M5100-1 Main Steam Line 5

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DAVIS-BESSE, UNIT 1 3/4 6-17 AmendmentNo./3 72 I

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TABLE 3.5-2

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CONTAllfENT ISOLATION VALVES (Continued)

ISOLATION-PENETRATION VALVE NUMBER NUMBER FUNCTION TIME (seconas) 41 RC232 Press'urizer Quench Tank Circulating 10 Inlet Line 42A SA2010 Service Air Supply Line 10 428 CY5010E Containment Yessel Air Sample Return 15 1

43A IA2011 Instruent Air Supply Line 10 l

438 CY5011E containment Vessel Air Sample Return 15 44A CF1541 Core Flood Tank, Fill and N2 Supply i

10 j

Line l

448 NNZ36 Pressurizar Quench Tank N2 Supply 10 Line OS/6ff

!1545 Core Flood Tank Sample Line 10 dr/cpa 5"2 Core Flood Tank Vent Line 10 l

48 RC229A Pressurizer Quench Tank Circulating 10

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Outlet Line 48 RC2298 Pr.ssurizer Quench Tank Circulating to Outlet Line 15 50 0 !!PE

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51 CY5037 Hydrogen Purge System Exhaust Line 50 50 51 CY5038 Hydrogen Purge System Exhaust Line 52 MU66A Reactor Coolant Pump Seal Supply 12 53 MU5EB Reactor Coolant Pump Seal Supply 12 54 MU56C Reactor Coolant Pu=p Seal Supply 12 55 MU65D Reactor Coolant Pump Seal Supply 12 56 MU38 Reactor' Coolant Pump Seal Return 12 55 MU59A Reactor Coolant Pump-Seal Return 30 56 MU598 Reactor Coolant Pump Seal Return 30 56 MU59C Reactor Coolant Pump Seal Return 30 30 56 MU59D Reactor Coolant Pump Seal Return 80 57 M5603 Steam Generator Blowdown Line 80 60 75611 Steam Generator Blowdown Line Amendment No. 79 OAVIS.8E55E, UNIT 1 3/4 6-18

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TABLE 3.6-2 CONTAINMENTISOLATIONVALVES(Continued)

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PENETRATION VALVE ISOLATION MUMBER NUMBER FUNCTION TIME (seconds) 67 CV5090 Hydrogen Dilution System Supply 60 68A SS235A Pressurizar Quench Tank Sample 30 68A 552358 Pressurizer Quench Tank Sample 30 688 CV50108 Containment Air Sample 15 688 CV50118 ' Containment Air Sample 15 69 CV5065 Hydrogen Dilution System Supply 60 718 CV5010A Containment Air Sample 15 718 CV5011A Containment Air Sample 15 GFsfp

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Core Flood Tank N2 Fill 10 l

738 CV5010C Containment Air Sample 15 738 CV5011C Containment Air Sample 15 748 CV50100 Containment Air Sample 15 jf

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74B CV,5DL1D Containment Air Sample 15 B.

C0tlTAINMENT PURGE AND EXHAUST ISOLATION 3? N CV5005 Containment Vessel Purge Inlet Line 10 33 g/ CV5006 Containment Vessel Purge Inist Line 10 34 H CV5007 Containment Vessel Purge Outlet Line 10 34 N CV5t)08 Containment Vessel Purge Outlet Line 10 C.

OTHER 5 i SW1366 Containment Air Cooling Units SW Inlet Line N/A 6 i SW1368 Containment Air Cooling Units SW Inlet Line N/A 7i SW1367 Containment Air Cooling Units SW

- Inlet Line N/A 9 i SW1356 Containment Air Cooling Units SW Outlet Line N/A Amendment No. AJ,75 DAVIS-BESSE. UNIT I 3/4 6-19 s

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TABLE 3.6-2

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CONTAINMENT ISOLATION VALVE 5 (Continued)

PENETRATION VALVE ISOLATION NUM8ER NU.*EER FUNCTION TIME..

(seconas) 10 f SW1358 Containment Air Cooling Units SW N/A Inlet Line 11 '#

SW1357 Containment Air Cooling Units SW

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Outlet Line N/A 17 CY343 Containment Vessel Leak Test Inlet Line 17 Flange Cc'ntainment Vessel Leak Test Irilet Line (Inside Containment)

N/A 19 i HP57 Nigh Pressure Injection Line N/A 20 # HPS6 High Pressure Injection Line N/A

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22 i HP49 High Pressure Injection Line N/A 23 i SF1 Fuel Transfer Tube N/A e

23 Flange Fuel Transfar Tube N/A k

24 i SF2 Fue1 Transfer Tube N/A

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24 Flange Fuel Transfer Tube N/A l

25 SA532 Containment Spray Line N/A

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26 SA533 Containment Spray Line N/A 27 i DH1A Low Pressure. Injection Line N/A 27 i DH76 Low Pressure Injection Line N/A "i DH18 Low Pressure Injection Line N/A 28 i DH77 Low Pressure trigaction Line N/A 19 d N/9A did P " " 5 W h" U"'

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DAVIS-BESSE. UNIT 1 3/4 6-20 Amendment No. 3

r TA8LE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)

PENETRATION VALVE ISOLATION NUMBER NUM5ER FUNCTION TIME

  • 29 i DH11 Decay Heat Pump Suction Line N/A
  • 29 DH23 Decay Heat Pump Suction Line N/A 29 i PSV4849 Decay Heat Pump Suction Line N/A 35 i AF599 Au'iliary Feedwater Line N/A x

36 i AF608 Auxiliary Feedwater Line N/A

+39 i M5107 Main Steam Line N/A

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=40 i M5106 Main Steam Line N/A I

e40 i M5106A Main Steam Line N/A 41 RC113 Pressurizar Quench Tank Inlet Line N/A 42A SA502 Service Air Supply Line N/A 428 CY124 Containment Vessel Air Sample Retum M/A 43A IA501 Service Air Supply Line N/A N

4 38 CY125 Containment Vessel Air Sample

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Retum N/A 44A CM5 Core Mood Tank Fill and Nitrogen Supply Line N/A 445 NN58 Pressurizer Quench Tank Inlet Line N/A

  • 47A CF2A Core Mood Tank Sample Line N/A

'47A CF28 Core Rood Tank Sample Line N/A

'478 CF5A Core Rood Tank Vent Line N/A

'478 CF55 Core Mood Tank Vent Line N/A

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

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TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)

PENETRAT!!3t VALVE ISOLATION snM8tR NUM8ER FUNCTION TIME 49 DH87 Refueling Canal Fill Line N/A 49 DH88 Refueling Canal Fill Line N/A N{0j yppc Hj g P(e,sy g g,ee g n g) g g_

MU242 RCP Seal Water Supply N/A 53 MJ243 RCP Seal Water Supply N/A 54 Mu244 RCP Seal Water Supply N/A 55 PtJ245 RCP Seal Water Supply N/A Deleted Deleted l

Deleted Deleted 59 Flange Secondary Side Cleaning (Inside Containment)

N/A 59 Flange Secondary Side Cleaning (Outside Contairunent)

N/A 67 CV209 Hydrogen Dilution Systes Supply N/A

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69 CY210 Hydrogen Dilution System Supply N/A 71A f CV20008 Containment Pressure Sensor N/A 71C CF16 Core Flood Tank Nitrogen Fill h/A Line 72A i CV20018 Containment Pressure Sensor N/A l

72C f CV6248 Containment Pressure Differential l

Transmitter N/A 73A # CV20028 Containment Pressure Sensor N/A 73C i CV6458 Containment Pressure Differential Transmitter N/A 74A i CV20038 Containment Pressure Sensor N/A

'74C DH2735 Pressurizer Auxiliary Spray N/A l

  • 74C DH2736 Pressurizer Auxiliary Spray N/A "may be opened on an intermittent basis under adminis rativs contr:1.
  1. Not subject to Type C leakage tests.

" Surveillance testing not reguired prior to entering MODE 4 but l

shall be performed prior to entering Mode 3.

ffProvisions 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 AmendmentNo.f.J7,79 l

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BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAI N NT INTEGRITY Primary CONTAINNT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.

This restriction, in conjunction with the leakage rate Ifmitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak. accident pressure of 38 psig. P. As an added conservatism, the measured overall integrated leakage,ra'te is further limited to < 0.75 L, during performance of the periodic tests a

to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.

l The special test for the containment purge and exhaust isolation t

valves is intended to detect gross degradation of seals on the valve seats.

The special test is performed in addition to the Appendix J requirements.

3/4.6.1.3 CONTAI M NT AIR LOCKS The limitations on c1csure and leak rate for the containment air locks are required to meet the restrictions on CONTAINNT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provide assurance that the overell air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

DAVIS-8 ESSE, UNIT 1 83/46-1 Amendment No. 90

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h BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure of 40 psig during LOCA conditions.

The maximum peak pressure obtained from a LOCA event is 37 psig.

The limit of 1 psig for initial positive containment pressure will limit the total pressure to 38 psig which is less than the design pressure and is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure than

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the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for 4 LOCA.

3/4.f.1.6 CONTAlf0ENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contain-ment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 38 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.

3/4.6.1.7 CONTAlleqENT VENTILATION SYSTEM The limitation on use of the Containment purge and Exhaust System limits the time this system may be in operation with the reactor coolant system temperature above 200*F. This restriction minimizes the time that a direct open path would exist from the containment atmosphere to the outside atmosphere and consequently reduces the probability that an accident dose would exceed 10 CFR 100 guideline values in the event of a LOCA occuring coincident with purge system operation. The use of this system is therefore restricted to non-r9utine usage not to exceed 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in any consecutive 365 day period which is equivalent to approximately 15 of the total possible yearly unit operating time.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTDtS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERA 81LITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment DAVIS-8 ESSE. UNIT 1 8 3/4 6-2

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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 CONTAIhMENT COOLING. SYSTEM The OPERASILI1Y of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits during nomal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assuptions used in the analyses for a LOCA.

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ak CONTAINMENT SYSTEMS BASES 3/4.6.4 COM8USTIBLE GAS CONTROL The OPERASILITY of the Hydrogen Analyzers, Con'tainment Hydrogen Dilution System and Hydrogen Purge System ensures that this equipment I

will be available to maintain the maximum hydrogen concen'tration within the containmen't vessel at or 'below three volume percent following a LOCA.

The two redundant Hydrogen Analyzers determine the content of hydro-gen within the containment vessel.

The Containment Hydrogen Dilution (CHD) System consists of two full capacity, redundant, rotary, positive displacement type blowers to supply air to the containment. The CHO System controls the hydrogen concentra-tion by the addition of air to the containment vessel, resulting in a pressurization of the containment and suppression of the hydrogen volume 7

fraction.

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l The Containment Hydrogen Purge System Filter Unit functions as a backup to the CHO System and is designed to release air from the con-tainment atmosphere through a HEPA filter and charcoal filter prior to discharge to the station vent.

3/4.6.5 SHIELD BUILOING 3/4.6.5.1 EMERGENCY VENTILATION SYSTEM The OPERASILITY of the emergency ventilation systeuis ensures that containment vessel leakage occurring during LOCA conditions into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere. This requirement is neces-sary to meet the assumptions used in the safety analyses and limit the site boundary radiation doses to within the limits of 10 CFR 100 during LOCA conditions.

' ORVIS-EESSE, UNIT 1 B 3/4 6 4 Amendment No. 56 J

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