ML20058N751

Proposed Tech Specs Eliminating Requirements to Maintain Operational & Test Hydrogen Recombiners

ML20058N751
Person / Time
Site:	Waterford
Issue date:	10/15/1993
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20058N739	List: ML20058N735 ML20058N751
References
NUDOCS 9310200263
Download: ML20058N751 (12)

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-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

'1 SECTION PAGE 3/4.6' CONTAINMENT SYSiEMS 3/4,6.1-PRIMARY CONTAINMENT.

CONTAI MENT-INTEGRITY................................

3/4 6-1 CONTAIMENT LEAKAGE..................................

3/4 6-2 l

CONTAI MENT-AIR L0CES................................

3/4 6-9 INTERNAL PRESSURE....................................

3/4 6-11 A n TeeERATuRE......................................

3/4 6-u CONTAI MENT VESSEL STRUCTURAL INTEGRITY..............

3/4 6-14

-3 CONTAI MENT VENTILATION SYST M.......................

3/4 6-15 3/4.6.2 - DEPRESSURIZATION AM COOLING SYRIMS CONTA!M Wif SPRAY SYSTIN.............................

3/4 6-16 CONTAIM Wff COOLING SYSTIN...........................

3/4 6-18

3/4.6.3 CONTAIm elf ISOLATION VALVES............................

3/4 6-19

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V 3/4.'6.4 -

Co muSTIBLE GAS CONTROL

'NYDROSS ANALYZERS...................................

3/4 6 ELECTRIC NVDADSDI MC0 MINERS........................

3/4 6-35 3/4.6.5 VACUISI RELIEF VALVES....................................

3/4 6-36 3/4.6.6 SECONDARY CONTADOWIT SNIELD OUILDDIB YENTILATION SYSTEM...................

3/4 6-37

$NIELD SUILDINE INTEGRITY............................

3/4 6-40 SNIELD BUILDING STRUCTURAL INTEGRITY.................

3/4 6-41 9

3/4,7 PUUff $YSTRE W

L-23/4.7.1 TURBI E CYCLE SAFETY VALVES........................................

3/4 7-1 DERBENCY FEEDWATER SYSTEN...........................

3/4 7-4 CON 00tSATE STORAGE P00L..............................

3/4 7-6 it 3_

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INDEX BASES SECTION PAGE 3/4.4 REACTOR COOL *NT SYSTEM (Continued) 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE.

B 3/4 4-4 3/4.4.6 CHEMISTRY.....................................

B 3/4 4-4 3/4.4.7 SPECIFIC ACTIVITY...................

B 3/4 4-5 3/4.4.8 PRESSURE / TEMPERATURE LIMITS.................

B 3/4 4-6 3/4.4.9 STRUCTURAL INTEGRITY...........................

B 3/4 4-11 3/4.4.10 REACTOR COOLANT SYSTEM VENTS.........

B 3/4 4-11 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS.SUBSY3TEMS...........................

B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE P00L..........................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...................................

B 3/4 6-1 3/4.6.2 DEPRE55URIZATION AND COOLING SYSTEMS..................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES..........................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...............................

B 3/4 6-4 3/4.6.5 VACUUM RELIEF VALVES..................................

B 3/4 6-4 3/4.6.6 SECONDARY C0NTAIMENT.................................

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......

B 3/4 7-3 L

i WATERFORD - UNIT 3 XII L-

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CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS - W L

LIMITING CONDITION FOR OPERATION i

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3.6.4.~2 Two independent containment hydrogen recombiner systems shall be.

0PERABLE.

JAPPLICABILITY:

MODES 1 and 2.

ACTION-With one hydrogen recombiner system inoperable, restore the inopersbie system K

. to OPERABLE status within 30 days or be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS

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4.6.4.2 Each hydrogen _recoebiner system shall be demonstrated OPERABLE:

i At least once per 6 months by verifying during a.recombiner system a.

functional. test that.the minimum heater sheath temperature. increases to greater than or. equal to 700*F within 90 minutes.

Upon reaching 700*F, increase.the power setting to maximum power for 2 minutes and verify that the power meter rends greater than or equal to 60 kW.

b.

At least once per 18 months by:

1.

Performing a CHANNEL CALIBRATION of all recombiner

' instrumentation and control circuits, i

2.

Verifying through a visual examination that there is no' evidence i

of abnormal conditions within the recombiner enclosure (i.e.,

loose wiring or structural connections, deposits of foreign materials,etc.).

t 3.

. Verifying the integrity of the heater electrical circuits by performing a resistance to ground test following the above required functional test.

The ' resistance to ground for any n

heater phase shall be greater than or equal to 10,000 ohns.

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The 0PERABILITYLof the containment isolathn valves ensures that the-w, 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 and is consistent with the requirements of

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GDC 54 through GDC 57_of Appendix A to 10 CFR Part 50.

Containment isolation within'the time limits specified for those isolation valves designed to close

automatically ensures that the release of radioactive meterial to the environ-1 ment will be consistent with the assumptions used-in the analyses for a LOCA.

The:openi'ng of locked or sealed clossd containment isolation valves on an intermittent basis ~ under administrative control includes tho'following consid-1 erations::(1) stationing an operator,-who-is in constant communication with l

control room,'at the; valve controls,'(2) instructing this operator to close l

these valves:in an accident situation, and (3) assuring that environmental 1

iconditions will not preclude access to close the valves and that this action will preventithe release of, radioactivity outside the containment.

poratedtinto Plant-Procedure WT-005 previously Table 3.6-2, have been inco

-" Containment Isolation-Valves" u

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3/4. 6.' 4 r COSUSTIBLE GAS CONTROL

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The'.0PERASILITY of the equipment and systems required for the' detection

..and control?of hydrogen pas ensures that this equipment will be available to maintain the concentration within containment below its flammable.

m limitEduring post-conditions.

Either recombiner unit is capable of controlling the expect 6d hydrogen generation' associated with (1) zirconium-water reactions,:(2) radiolytic decomposition of water, and.(3) corrosion of metals within containment. ' These hydrogen con +rol-systems are consistent with the recommendations of Regulatory Guide 1.7" Control of Combustible Gas Concentrationsin.containmentFollowinga'LECA," March 1971.

L 23/4.6.5 VACUW RELIEF VALVES The OPERABILITY:sf the primary containment to annulus vacuma relief valves with a setpoint of-less than or equal + 0.3 psid ensures?that the con +

tainment internal pressure differential does not became more negative than the

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i containment design limit for internal pressure differential of 0.55'pst This 3' ~ ' 1

situation would occur, for the worst case. if All containment heat removal

inadvertently started with.onlyLone vacuun relief valve OPERABLE.yste systems.(containment ~ spray, containment cooling','and other WAC s g

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, t.IMITING CONDITIONS FOR' OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTDts 3/4.5.1 PRIMARY CONTAIM WIT CONTAIleENT INTEGRITY................................

3/4 6-1 CONTAImerf LEAKAdBE..................................

3/4 6-2 CONTADeWif AIR LOCK 5................................

3/4 6-9' c

INTERNAL PRESSURE....................................

3/4 6-11 AIR TD rERATURE......................................-

3/4 6-13 CONTADeWit VESSEL STRUCTURAL INTIBRITY..............

3/4 6-14

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CONTADeWif VENTI LATION $Y3791.......................

3/4 6-15 3/4.' 8. 3 ;.DEPitESSURIZATI0lt Afe COOLING SYSTEME CONTADOWlf SPRAY $Y8798.............................

3/4 6-16 l

CONTADOWlf COOLDIB 5V3758...........................

3/4 6-18 j

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CONTA!Ie WIf ISOLATI0li VALVES............................

3/4 6-13

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.3/4.6.4 COIGUSTISLE GAS CRETMIL i

NYORDSBI AIIALYZERS...................................

3/4 6-34 DMW

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- vAcuWe AELIEF VALVES....................................

3/4 6-34 3/4.6.6 SECOISARY CBITADBENT SNIELD BUILDDE VOITILAT!W SYSTWL..................

3/4 6-37 SIIIELS ButLSIMB INTIERITY............................

3/4 6-40.

SitIELB SUILSINR STRUCTURAL INTEGRITY.................

3/4 6-41 3/4,7._PLAHLETIfEE 3/4.7.1 TURBIIE CTCLE SAFETY VALVES........................................ -3/4-7-1 DERBENCY FEEndATER SYST58...........................

3/4'7-4 j

COISSISATE STORAGE P00L............................... 3/4 7-6 I

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'SECTI'ON pAGE

.i/4.4 -REACTOR COOLANT SYSTEM'(Continued)

-3/4.4.S REACTOR COOLANT SYSTEM LEAKAGE........................

B 3/4 4-4' 3/4.4.6 CHEMISTRY...........................................

B 3/4 4-4 e

.3/4. 4.. SPECIFIC ACTIVITY..................................

B 3/4 4-5 4

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3/4.4.8 PRESSURE / TEMPERATURE LIMITS.....................

B 3/4 4-6 13/4.4.9 STRUCTURAL-INTEGRITY..................................

B 3/4 4-11 0

3/4.4.10' REACTOR COOLANT. SYSTEM VENTS..........................

B 3/4 4-11

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3/4.' S EMERGENCY CORE COOLING SYSTEMS (ECCS)-

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3/4.5.1 SAFETY INJECTION TANKS................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3

'ECCS SUBSYSTEMS...........................

B 3/4~5-1

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3/4.5.4 REFUELING WATER STORAGE P00L..........................

B 3/4 5-2 q

3/4.6 CONTAINENT ' SYSTEMS -

3/4.6.1 PRIMARY C0NTAINENT...................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS..................

B 3/4 6-3

-3/4.6.3 CONTAIMENT ISOLATION VALVES..........................

B 3/4 6 : DELETE.

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-I 3/4.6.5 VACULM RELIEF VALVES..................................

B 3/4 6-4 3/4.6.6-SEC0fSARY CONTAIl94ENT.................................

B 3/4 6-5 L.

3/4.7 PLANT SYSTBE 3/4.7.1 TUIS INE CYCLE.........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR. PRESSURE / TEMPERATURE LIMITATION.......

B 3/4 7-3 I

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LIMITING NDITION FOR OPERATION

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i 3.6.4.2 Two.i ependent containment hydrogen recombiner system shall be OPERABLE.

t APPLICABILITY:

M0 S 1 and 2.

ACTION:

With one hydrogen recomb er system inoperable, restor the inoperable system to OPERABLE status within 0 days or be in at least T STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner s tem s 11 be demonstrated OPERABLE:

a.

At least once per 6 months b erifying during a recombiner system functional test that the sin heater sheath temperature increases within 90 minutes.

Upon reaching togreaterthanorequalt atti to maximum power for 2 minutes and 700 F, increase the power verify that the power se r reads ater than or equal to 60 kW.

b.

At least once per 18 nths by:

1.

Performing a L CALIBRATION o all recombiner instrumentat and control circuits 2.

Verifying rough a visual examination t there is no evidence of ebne I conditions within the recomb r enclosure (i.e.,

loose ring or structural connections, sits of foreign mater 1s,etc.).

3.

Ve fying the integrity of the heater electri 1 circuits by rforising a resistance to ground test followin the above uired functional test.

The resistance to gro for any heater phase shall be greater than or equal to 10, 00 ohns.

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CONTAINMENTTSYSTEMS 1

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3/4.6.3 CONTAll#9ENT ISOLATION VALVES The OPERA 8ILITY 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 E

-pressurization of'the containment and is consistent with the requirements of GDC 54'through GDC 57 of Appendix A to 10 CFR Part 50. ' Contaimeent isolation within the time limits specified for those isolation valves designed-to close automatically ensures that the release of radioactive esterial to the environ-ment will be consistent with _the asstaptions used in the analyses.for _a LOCA.

The opening of locked or sealed closed containment-isolation valves'on an a

intermittent basis under administrative control includes the following consid-I erations: (1) stationing-an operator, who is in constant communication with control room, at the va ve controls (2) instructing this operater to close these valves in an accident situation, and (3) assuring that environmental

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conditions will not precludt access to close 'the valves and that this action wil1 prevent the release of radioactivity outside the containment.

- porated ints' Plant Precedure LWT-00E previously Table 3.5-2, have

" Containment Isolation Valves" 026.

h CWGUSTIBLE GA$ CONTM L The 0 the:eguipment and tems requi the detection assures that t s will:be available to and control-of M._~-~ i_ l.f - within asent belos its flammable maintain the-limit during post-conditions.

receshiner unit is le of controlling the sted with zirconime-water reactions, ( )

e decagositten and(

corrosion of metals within

> These liydrogen control' consistent-with the roc ens of Regulatory Guide 1.7, " Centre of Gas-

.Co ions in Centainment Fe11 swing's LOCA," Iterch 1971.

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' 3/4.6.5 VACIABI met fir VALVES The OPERASILITY of the priesty containment to annulus vacuus relief valves with a setpeist of less then er equal + 0.3 psid ensures that the con-tainment internal. pressure differential does not besses more negative than the -

containment design limit for internal pressure diffeigntial of 0.65 psi.

This situation would escur, for the verst case,:1f all containment heat removal systems (containment sprey, containment cooling,- and other WAC systans) were inadvertently started vita only'ene vacuum relief valve OPERABLE.

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-13/46.3 CONTAlleqENT ISOLATION VALVES :

The OPDM81LITY of the containment isolation. valves ensures that the-

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containment atmosphere will be isolated from the outside environment in the j

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event'of'a release of radioactive material to thel containment atmosphere or i-pressurization of the containment and is consistent with the requirements of 1

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' GDC 54 through GDC 57 of Appendix A to.10 CFR Part 50. ~ Containment isolation 1,

~.within the time limits specified for those' isolation valves designed to close L"

Lautomatically ensures that the release of radioactive material.to the environ-l ment will be consistent with the assumptions used in'the analyses for a LOCA.

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, ; The opening of locked or. sealed closed containment isolation valves on an f

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? intermittent basis under adminstrative control includes the follering consid-

. erations:. (1) stationing' an operator who is in constant'consunication with control room. at the valve controls. (2) instructing this operator, to close

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these valves'in an accident situation. and (3) assuring that environmental r

1 conditions;will'not preclude access to close the yalves'and that this action v

- wil1l prevent the release of radioactivity outside the containsent, j

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" Containment Isolation Valves", previously Table 3.6-2. has been incor-m porated into Plant Frocedure LMT 005-026. ~

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-3/4.6.4' This asetton is deleted.

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I /4.6.5f VACLA#98 RELIEF VALV5 -

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.The.0PERABILITY of-the primary contairuesnt to annulus vacuum relief

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valves with' a setpoint of less than or emaal _+ 0.3 psid ensures that the con-

= tainment intemal pressure differential does not become more negative than the -

1 containment desipt limit fler internal pressurt differential of 0.66 psi. This situation would occur.:for.the worst case. if all containment heat rimoval-

^ systems-(contairment spray containment cooling.' and other WAC systems) were E4

inadvertantly started with only one vacuus relief valve OPERABLE.

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