ML20058N751

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Proposed Tech Specs Eliminating Requirements to Maintain Operational & Test Hydrogen Recombiners
ML20058N751
Person / Time
Site: Waterford Entergy icon.png
Issue date: 10/15/1993
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20058N739 List:
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 l 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

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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_

I WATERFORD'- UNIT 3 VII -

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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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i CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS - W L

LIMITING CONDITION FOR OPERATION i

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

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0PERABLE. .

JAPPLICABILITY: MODES 1 and 2.

ACTION-K .

With one hydrogen recombiner system inoperable, restore the inopersbie system 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

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

' 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.).

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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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- 3/4; 6.3 CONTAIMENT ISOLATION VALVES l + 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 l 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.  ;

-" Containment Isolation-Valves" u poratedtinto Plant- Procedure WT-005

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026. previously Table 3.6-2, have been inco '

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.

23/4.6.5 VACUW L 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 +

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tainment internal pressure differential does not became more negative than the 3' ~ ' 1 i containment design limit for internal pressure differential of 0.55'pst This

situation would occur, for the worst case. if All containment heat removal systems.(containment ~ spray, containment cooling' ,'and other WAC s
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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 c CONTADeWif AIR LOCK 5. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-9' INTERNAL PRESSURE.................................... 3/4 6-11  ;

AIR TD rERATURE......................................- 3/4 6-13 CONTADeWit VESSEL STRUCTURAL INTIBRITY. . . . . . . . . . . . . . 3/4 6-14 CONTADeWif VENTI LATION $Y3791. . . . . . . . . . . . . . . . . . . . . . . 3/4 6-15

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3/4.' 8. 3 ; .DEPitESSURIZATI0lt Afe COOLING SYSTEME CONTADOWlf SPRAY $Y8798. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-16 l y CONTADOWlf COOLDIB 5V3758. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-18 j 3/4.6.3: CONTA!Ie WIf ISOLATI0li VALVES............................ 3/4 6-13 l

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. : COIGUSTISLE GAS CRETMIL i ,

NYORDSBI AIIALYZERS................................... 3/4 6-34 DMW ,,,,,,,,,,,,,,, ;f: ; :: .

-3/4.4.s - 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

  1. 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 . .,

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.3/4. 4. . SPECIFIC ACTIVITY.................................. .. B 3/4 4-5 4 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)- i o

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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 -i i

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 <

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. 3/4.6.5 VACULM RELIEF VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-4 -l 3/4.6.6- SEC0fSARY CONTAIl94ENT................................. B 3/4 6-5 I 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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t NC0TAINMENTSYSTEMS I ELEC C HYOROGEN RECOMBINERS - W ~

N LIMITING NDITION FOR OPERATION /

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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 togreaterthanorequalt within 90 minutes. Upon reaching 700 F, increase the power atti to maximum power for 2 minutes and 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

W BASES 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 E . event of a release of' radioactive material to the containment atmosphere or

-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.

" Containment Isolation Valves"

- porated ints' Plant Precedure026. LWT-00E previously Table 3.5-2, have 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 maintain the- M ._~-~

-- i_ l .f - within asent belos its flammable  ;

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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.S -13/46.3 CONTAlleqENT ISOLATION VALVES : "

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

containment atmosphere will be isolated from the outside environment in the

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

R ' 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 Lautomatically ensures that the release of radioactive material.to the environ- l L"

ment will be consistent with the assumptions used in'the analyses for a LOCA. l' x

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

? 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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r these valves'in an accident situation. and (3) assuring that environmental 1

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

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

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

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4 I 3/4.6.5f VACLA#98 RELIEF VALV5 -

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

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 - I 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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