ML20096F258

Proposed Tech Specs,Removing Process Penetration M308 & Containment Isolation Valves RN-429A & 432B

ML20096F258
Person / Time
Site:	Catawba
Issue date:	01/11/1996
From:	DUKE POWER CO.
To:
Shared Package
ML20096F246	List: ML20096F244 ML20096F258
References
NUDOCS 9601230286
Download: ML20096F258 (28)

Text

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4 ATTACHMENT 1.A .

MARKED-UP PROPOSED TECHNICAL SPECIFICATIONS PAGES FOR CURRENT TECHNICAL SPECIFICATIONS CATAWBA NUCLEAR STATION i

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9601230286 960111  :

PDR ADOCK 05000413  !

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TABLE 3.6-1 (Continued)

SECONDARY CONTAll#4ENT BYPASS LEAKAGE PATHS -

E E PENETRATION TEST

, NUMBER SERVICE RELEASE LOCATION TYPE M323 Ccaponent Cooling to Component d :ooling Drain Sump Auxiliary Building Type C

e. M240 Nuclear Service Water to Reactor u Coolant Pump and Lower Cont.

Vent. Units Auxiliary Building Type C M230 Nuclear Service Water From Reactor Coolant Pump and Lower Cont.

Vent. Units Auxiliary Building Type C M385 Nuclear Service Water to Upper Containment Ventilation Units In Turbine Building Type C

. M308 Huclear Service Water to Upper i Containment Ventilation Units out Turbine Building Type C M213 Incore Instrumentation Room Purge In Auxiliary Building Type C M140 Incore Instrumentation Room Purge Out Auxiliary Building Type C M456 Upper Compartment Purge Inlet Auxiliary Building -

Type C M432 Upper Compartment Purge Inlet Auxiliary Building Type C M357 Lower Compartment Purge Inlet Auxiliary Building Type C M368 Coitainment Purge Exhaust Auxiliary Building Type C M433 Containment Purge Exhaust Auxiliary Building Type C M434 tower Compartment Purge Inlet Auxiliary Building Type C e

~

w 4 .

TABLE 3.6-1 (Continued) k SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS E

y PENETRATION TEST

, NUMBER SERVICE RELEASE LOCATION TYPE b M386 Containment Air Release Auxiliary Building Type C g M204 Containment Air Addition Auxiliary Building Type C b M316 Int. Fire Protection Header - Auxiliary Building Type C Hose Racks H337 Demineralized Water Auxiliary Building Type C M220 Instrument Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C R

• M215 Breathing Air Auxiliary Building Type C T

• M329 Reactor Coolant Pump Motor Oil Fill Auxiliary Building Type C M361 Int. Fire Protection Header - Auxiliary Building Type C Sprinklers M119 Containment Purge Exhaust Auxiliary Building Type C kk

==

M331 Nitrogen Supply to Cold Leg Accumulators Auxiliary Building Type C R&

hh H322 Safety Injection Test Line Auxiliary Building Type C f M454 UHI Test Line Auxiliary Building Type C Note 1 l jj M328* Component Cooling to Reactor Auxiliary Building Type C cc Vessel Support and RCP Coolers

3. 3.

es gg *Not applicable for Unit I until after the first refueling outage.

Note 1: Upon capping of per.etrations associated with deletion of UHI, this specification is no longer applicable. j

ihf: /%f Aff /",cA6/E OR ONW1 Rh REbdsg ocfA6t IEoc9, Net opplcablE O (Ja;i2 Af4En REettg od6E 2EOC7 s w

• J Y .

g TABLE 3.6-2a-(Continued) .

5 g CONTAIMENT ISOLATION VALVES L

MAXIMUM .

E VALVE NUMBER FUNCTION ISOLATION TIME (s)

Z

2. Phase "B" Isolation (Continued)

• • RN-437B Supply to NC Pumps and LCVU Supply Outside Containment Isolation s 60

" Return from NC Pumps and LCVU Return Inside Containment Isolation RN-484A s 60' RN-487A Return from NC Pumps and LCVU Return Outside Containment Isolation s 60 ,

RN-404B Supply to Upper Containment Supply Ventilation Units Containment s 10 Isolation (Outside)

RN-429B 4 # Return from Upper Containment Ventilation Units Containment Isolation s 10 (Inside) .

RN-432B 4 .4% Return from Upper Containment Ventilation Units Containment Isolation s 10

, (Outside) s VI-77B Instrument Air Containment Outside Isolation s 10 0 SM-1 # Main Steam ID Isolation NA SM-3 # Main Steam IC Isolation NA SM-5 # Main Steam IB Isolation NA SM-7 # Main Steam 1A Isolation NA SM-9 # Main Steam 10 Isolation Bypass Ctrl. NA SM-10 # Main Steam IC Isolation Bypass Ctrl. NA '

,, SM-Il f Main Steam IB Isolation Bypass Ctrl. NA gg SM-12 # Main Steam 1A Isolation Bypass Ctrl. NA as  ;

&I SV-19 # Main Steam 1A PORV s5 SV-13 # Main Steam IB PORV s5 SV-7 # Main Steam IC PORV s5 -

EE SV-1 # Main Steam 10 PORV s5 gg WL-867A** Containment Vent Unit Drains Inside Containment Isolation slo

-y WL-869B** Containment Vent Unit Drains Outside Containment Isolation s 10 EE

. . _ _ , . _ . .- . . . - ~ _ . _ _ . _ _ _ _ _ _ _

% ssp TABLE 3.6-2a (Centinued) l l UNIT 1 CONTAINMENT ISOLATION VALVES S .

D MAXIMUM

E VALVE NUMBER FUNCTION ISOLATION TIME (s) .

I M

• 3. Manual (Continued) e i ** SM-103# Main Steam IC N.A.

l N- SM-119# Main Steam IC .N.A.

SM-141# Main Steam IC N.A.

SA-4# Main Steam IC N.A.

SM-19# Main Steam 10 N.A.

SM-70#^ Main Steam 10 N.A.

SM-102# Main Steam 10 N.A.

SM-Il8# Main Steam 10 N.A.

m SH-140# Main Steam 10 N.A.

) WE-20* Cont Bldg Supply 1 901 N.A.

.. WE-22* Cont 81dg Supply Isol N.A.

A WE-56" Cont Bldg Supply Isol N.A.

• FW-4* Refueling Water N.A.

NV-862#^ Pressurizer Auxiliary Spray ND Outside Containment N.A.

WLA-21#* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.

WLA-24#* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.

TABLE NOTATIONS

• May be opened on an intermittent basis under administrative. control.

• • Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.

1. Not subject to Type C leakage tests.

NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times.

See Specification 3/4 3.2 for system actuation response times.

NN Not ApplicAblE fo DMit I AfhR RESoEliMS odAGE. IEOC9, s

,(_)b .

TABLE 3.6-2b (Continued)

UNIT 2 CONTAINMENT ISOLATION VALVES

. HAXIMUM ~

VALVE NUMBER FUNCTION ISOLATION TIME fs) d 2. Phase "B" Isolation (Continued) b RN-437B Supply to NC Pumps and'l_CVU Supply Outside Containment Isolation s 60

~ RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolation s 60 RN-487A Return from NC Pumps and LCVU Return Outside Containment Isolation s 60 RN-404B Supply to Upper Containment Supply Ventilation Units Containment s 10 Isolation (Outside) -

RN-4298 dh O Return from Upper Containment Ventilation Units Containment Isolation s 10 (Inside)

RN-432B $ $ Return from Upper Containment Ventilation Units Containment Isolation s 10 (Outside)

VI-77B Instrument Air Containment Outside Isolation s 10 cn O

• SM-1 # Main Steam 2D Isolation NA SM-3 # Main Steam 2C Isolation NA SM-5 # Main Steam 2B Isolation NA SM-7 # Main Steam 2A Isolation NA SM-9 # Main Steam 2D Isolation Bypass Ctrl. NA SM-10 # Main Steam 2C Isolation Bypass Ctrl. NA SM-ll # Main Steam 2B Isolation Bypass Ctrl. NA pp SM-12 # Main Steam 2A Isolation Bypass Ctrl. NA hh gg SV-19 #

SV-13 #

Main Steam 2A PORV Main Steam 28 FORV s5 s5

"" SV-7 # Main Steam 2C PORV s5 gg SV-1 # Main Steam 2D PORV s5 a WL-867A** Containment Vent Unit Drains Inside Containment Isolation s 10 9 53 WL-869B** Containment Vent Unit Drains Outside Containment Isolation s 10 EE

3. 3.

en 4

- . . .. . _ . - . - - - - . - . - . . -- . - . . . . . . . . . ~ _ ~ - - - ..

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TABLE 3.6-2b (Continued)

UNIT 2 CONTAlletENT ISOLATION VALVES ,

s>

a MAXIftlM '

g VALVE NUMBER FUNCTION ISOLATION TIME (s) m 3. Manual (Continued) w 8- SM-103# Main Steam 2C N.A.

m SM-119# Main Steam 2C N.A.

SM-141# Main Steam 2C N.A.

SA-4# Main Steam 2C N.A.

SM-19# Main Steam 2D . N.A.

SM-70#* Main Steam 2D N.A.

SM-102# Main Steam 2D N.A. ,

SM-118# Main Steam 20 N.A.

, SM-140# Main Steam 20 N.A.

• g WE-20* Cont Bldg Supply Isol N.A.

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. WE-22* Cont Bldg Supply Isol N.A.

a WE-56* Cont B1dg Supply Isol N.A.

i N FW-4* Refueling Water N.A.

NV-862#* Pressurizer Auxiliary Spray ND Outside Containment N.A.

WLA-218* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.

i WLA-24#* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.

TABLE NOTATIONS

• May be opened on an intermittent basis under administrative control.

• • Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.

1. Not subject to Type C leakage tests.

NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times.

See Specification 3/4 3.2 for system actuation response times.

M # Nof applienble fo Dui+ 2 AMER RELEhg outage 2Eoc f.

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i ATTACHMENT 1.H PROPOSED TECHNICAL SPECIFICATIONS PAGES FOR PLANNED

) DIVIDED TECHNICAL SPECIFICATIONS CATAWHA NUCLEA2 STATION 1 i

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i PROPOSED TECHNICAL SPECIFICATIONS PAGES FOR DIVIDED TECHNICAL SPECIFICATIONS '

CATAWBA NUCLEAR STATION UNIT I 4.

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T.',BLE 3.6-1 (Continued)

SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS -

PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE M323 Component Cooling to Component Cooling Drain Sump Auxiliary Building Type C -

M240 Nuclear Service Water to Reactor '

Coolant Pump and Lower Cont.

Vent. Units Auxiliary Building Type C M230 Nuclear Service Water From Reactor Coolcnt Pump and Lower Cont.

Vent. Units Auxiliary Building Type C M385 Nuclear Service Water to Upper Containment Ventilation Units In Turbine Building Type C M308 f Nuclear Service Water to Upper Containment Ventilation Units Out Turbine Building Type C M213 Incore Instrumentation Room Purge In Auxiliary Building Type C M140 Incore Instrumentation Room Purga Out Auxiliary Building Type C M456 Upper Compartment Purge Inlet Auxiliary Building Type C M432 Upper Compartment Purge Inlet Auxiliary Brilding Type C M357 Lower Compartment Purge Inlet Auxiliary Building Type C M368 Containment Purge Exhaust Auxiliary Building Type C M433 Containment Purge Exhaust Auxiliary Building Type C M434 Lower Compartment Purge Inlet Auxiliary Building Type C CATAWBA - UNIT 1 3/4 6-6 Amendment No. l i

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l TABLE 3.6-1 (ContJnued)

SECONDARY CONTAllS4ENT BYPASS LEAKAGE PATHS .

, PENETRATION TEST

{ NUMBER SERVICE RELEASE LOCATION TYPE .

M336 Containment Air Release Auxiliary Building Type C M204 Containment Air Addition Auxiliary Building Type C M316 Int. Fire Protection Header - Auxiliary Building Type C Hose Racks M337 Demineralized Water Auxiliary Building Type C -

P.

M220 Instrument Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C M215 Breathing Air Auxiliary Building Type C M329 Reactor Coolant Pump Motor Oil Fill Auxiliary Building Type C M361 Int. Fire Protection Header - Auxiliary Building Type C Sprinklers Ml}9 Containment Purge Exhaust Auxiliary Building Type C Nitrogen Supply to Cold Leg M33:

Auxiliary Building Type C Accumulators -

l M322 S4.ety Injection Test Line Auxiliary Building Type C M328 Component Cooling to Reactor Auxiliary Building Type C Vessel Support and RCP Coolers

1. Not applicable after refueling outage IEOC9 CATAWBA - UNIT 1 3/4 6-7 Amendment No.

TABLE 3.6-2 (Continued) ,

CONTAINMENT ISOLATION VALVES MAXIMUM i VALVE NUMBER FUNCTION ISOLATION TIME (si-

2. Phase "B" Isolation (Continued)

RN-4378 Supply.to NC Pumps and LCVU Supply Outside Containment Isolation- s(60 RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolatien s>60 RN-487A Return from NC Pumps and LCVU Return Outside Containment Isolation s 60 RN-404B Supply to Upper Containment Supply Ventilation Units Containment s 10 Isolation (Outside)

RN-4298 ff Return from Upper Containment Ven.tilation Units Containment Isolation s 10-(Inside)

RN-4328 ff Return from Upper Containment Ventilation Units Containment Isolation s 10-(Outside)

VI-77B - Instrument Air Containment Outside Isolation s 10 SM-1 # Main Steam ID Isolation NA' SM-3 # Main Steam IC Isolation NA '

SM-5 # Main Steam IB Isolation NA SM-7,# Main Steam 1A Isolation 'NA' SM-9 # Main Steam 10 Isolation Bypass Ctr1. -

NA SM-10 f Main Steam IC Isolation Bypass Ctrl. NA' SM-11 i Main Steam.1B Isolation Bypass Ctrl. .NA SM-12 i Main Steam 1A Isolation Bypass Ctrl. NA SV-19 # Main Steam 1A PORY NA SV-13 # Main Steam IB PORV NA SV-7 # Main Steam IC PORY NA .

SV-1 # Main Steam 1D PORY NA WL:-867A** Containment Vent Unit Drains Inside Containment Isolation- s 10 WL-869B** Containment Vent Unit Drains Outside Containment Isolation s 10 CATAWBA - UNIT 1 3/4 6-27 Amendment No.

.-___._--m - . . , . _ . . + - ,

- ,,,a. -.e -- . . -. ., . - ' _._m___ __m ___ ____,_ .__ _

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. 1 TABLE 3.6-2 (Continued)

CONTAINMENT ISOLATION VALVES .

NAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s)

3. Manual (Continued)

SM-1037 Main Steam IC NA SM-119f Main Steam IC NA

'SM-141# Main Steam IC NA SA-47 Main Steam IC NA SM-19# Main Steam 1D NA SM-70f* Main Steam 10 NA SM-102f Main Steam 1D NA SM-118f Main Steam ID -

NA SM-140f Main Steam 10 NA WE-20* Cont Bldg Supply Isol NA WE-22* Cont Bldg Supply Isol NA WE-56* Cont Bldg Supply Isol NA-FW-4* Refueling Water NA NY-862#* Pressurizer Auxiliary Spray ND Outside Containment NA WLA-21f* Steam Generator Drain Pump Discharge Outside Containment Isolation NA WLA-24f* Steam Generator Drain Pump Discharge Outside Containment Isolation NA i

TABLE NOTATIONS

• May be opened on an intermittent basis under administrative control.

• • Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.

l # Not subject to Type C leakage tests.

1. 1. Not applicable after refueling outage 1EOC9.

NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times.

See Specification 3/4 3.2 for system actuation response times.

CATAWBA - UNIT 1 3/4 6-29 Amendment No.

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, 88 PROPOSED TECHNICAL SPECIFICATIONS PAGES FOR DIVIDED TECHNICAL SPECIFICATIONS ,

CATAWBA NUCLEAR STATION UNIT 2 6 A

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TABLE 3.6-1 (Continued) 1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS- -

PENETRATION -TEST NUMBER SERVICE RELEASE LOCATION P JJYPE M323 Component Cooling to Component Cooling Drain Sump Auxiliary Building Type C 3

M240 Nuclear Service Water to Reactor Coolant Pump and Lower Cont. <

Vent. Units Auxiliary Building Type C M230 Nuclear Service Water From Reactor ,

Coolant Pump and Lower Cont. i Vent. Units Auxiliary Building Type C l M385 Nuclear Service Water to Upper Containment Ventilation Units In Turbine Building Type C i

M308 # Nuclear Service Water to Cpper  ;

Containment' Ventilation Units Out Turbine Building Type.C.

M213 Incore Instrumentation Room Purge In Auxiliary Building Type C '

M14e Incore Instrumentation Room Purge Out Auxiliary Building Type C M456 Upper Compartment Purge Inlet Auxiliary Building Type C M432 Upper Compartment Purge Inlet Auxiliary Building Type C M357 Lower Compartment Purge Inlet Auxiliary Building Type C i

M368 Containment Purge Exhaust Auxiliary Building . Type C M433 Containment Purge Exhaust Auxiliary Building Type C  :

M434 Lower Compartment Purge Inlet Auxiliary Building Type C CATAWBA - UNIT 2 3/4 6-6 Amendment No.

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-TABLE 3.6-1 (Continued) ,

SECONDARY CONTAIMENT BYPASS LEAKAGE PATHS' PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE M386 Containment Air Release ,

Auxiliary Building Type C .,

'M204 Containment Air Addition Auxiliary Building Type C -

M316 Int. Fire Protection Header - Auxiliary Building ' Type C ,

Hose Racks. '

M337 Demineralized Water Auxiliary Building Type C M220 Instrument Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C M215 Breathing Air Auxiliary Building Type C -

M329 Reactor Coolant Pump Motor Oil Fill Auxiliary Building Type C  !

M361 Int. Fire Protection Header - Auxiliary Building Type.C Sprinklers M115 Containment Purge Exhaust Auxiliary Building Type C t i M331 Nitrogen Supply to Cold Leg Auxiliary Building . Type C Accumulators j

M322 Safety Injection Test Line Auxiliary Building Type C

~

M328 Component Cooling to Reactor Auxiliary Building Type C vessel Support and RCP Coolers

1. Not applicable after refueling outage 2E0C8.

CATAWBA - UNIT 2 -

3/4 6-7 Amendment No.

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TABLE 3.6-2 (Continued)

• i:

' .H CONTAINMENT ISOLATION VALVES.

MAXIMUM-VALVE NUMBER- FUNCTION ISOLATION TIME (s) o ,

l 2. Phase "B"-Isolation (Continued) ,

p J

RN-437B Supply.to NC Pumps and LCVU Supply Outside Containment Isolation s 60 '.

l' RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolation s 60 RN-487A Return from NC' Pumps and LCVU Return Outside Containment Isolation' s 60' l' RN-4048 Supply to Upper Containment Supply Ventilation Units Containment' s 10 Isolation (Outside)

-RN-429B ## Return from Upper Containment Ventilation Units Containment Isolation s 10 j (Inside)

RN-43?.B ## Return from Upper Containment Ventilation Units Containment Isolation- s 10  :

, (Outside) O l D l VI-77B Instrument Air Containment Outside Isolation , s 10- j p

l SM-1 # Main Steam 2D Isolation NA d SM-3 # Main Steam 2C Isolation NA It SM-5 # Main Steam 2B Isolation NA l!

SM-7.i Main Steam 2A Isolation NA il SM-9.# Main Steam 2D Isolation Bypass Ctrl. NA i; SM-1d # Main Steam 2C Isolation Bypass Ctrl. NA '

SM-II # Main Steam 2B Isolation Bypass Ctrl. NA SM-12 # Main Steam 2A Isolation Bypass Ctrl. NA

:

E i SV-19 # Main Steam 2A PORY NA . li i

SV-13 # Main Steam 2B PORY NA b SV-7 i Main. Steam 2C PORY NA SV-1 #

Main Stea;n 2D PORV MA i .

WL-867A** Containment Vent Unit Drains Inside Containment Isolation s 10 WL-869B** Containment Vent Unit Drains Outside Containment Isolation s 10 CATAWBA - UNIT 2 3/4 6-27 Amendment No.

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TABLE 3.6-2 (Continued) .

CONTAINMENT ISOLATION VALVES .

MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) -

3. Manual (Continued)

SM-103# Nain Steam 2C N.A.

SM-119f Main Steam 2C N.A. -

SM-141f Main Steam 2C N.A.

SA-4# Main Steam 2C N.A.

SM-19f Main Steam 2D N.A. ,

SM-70f* Main Steam 2D N.A.

SM-102f Main Steam 2D N.A.

SM-118f . Main Steam 2D N.A.

SM-140# Main Steam 2D N.A.

WE-20* Cont Bldg Supply Isol N.A.

WE-22* Cont Bldg Supply Isol N.A.

WE-56* Cont Bldg Supply Isol N.A.

FW-4* Refueling Water N.A.

NY-862f* Pressurizer Auxiliary Spray ND Outside Containment N.A.

WLA-21f* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.

WLA-24f* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.

t TABLE NOTATIONS

• May be opened on an intermittent basis under administrative control.

• • Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.

1. Not subject to Type C leakage tests.

1. 1. Not applicable after refueling outage 2E0C8.

NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times. See ,

Specification 3/4 3.2 for system actuation response times.

1 CATAWBA - UNIT 2 3/4 6-29 Amendment No.

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ATTACHMENT 2 IIACKGROUND AND DESCRIPTION OF REQUEST i

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! BACKGROUND  ;

1 i Both units' containment process penetration M308 piping and associated containment ' j

' isolation valves are currently not in service. Modifications were incorporated on both J

i - units' normal cooling supply to the Upper Containment Ventilation Units (UCVUs)

) which changed the ventilation units' cooling water from raw water (Nuclear Service ,

. Water System - RN) to chilled water (Containment Cooling Water System - YV). This  !

p

! modification was completed on Unit I during refueling outage IEOC7 in 1994 and j completed on Unit 2 during refueling outage 2EOC6 in 1994.

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i These modifications tied the UCVU return header to the Lower Containment Ventilation l

Units (LCVUs) return header inside of containment. The UCVU return header no longer ,

t serves a useful purpose. Following the modifications, containment isolation valves RN-i

.429A and RN-432B were tagged closed with power removed to eliminate the potential j for failure during a containment isolation event. Accordingly, these valves' inoperability i for stroke-time testing are tracked in the Technical Specification Action Item Log .

i (TSAIL) and are no longer stroke-time tested since they are already positioned to their j j fail-safe position. However, both Unit I and Unit 2 valve RN-429A are still included in

! the Containment Seal Injection Water System (NW) Leak Test program since they are

serviced by the NW System for containment leakage. The NW valve servicing Unit 2 l valve RN-432B recently failed it's NW leak test and was unable to be repaired. Further 2

modifications were performed so that the piping from Unit 2 valve RN-432B, to where j the RN pipe was cut and capped outside of containment, was upgraded to Class B piping l and the penetration was changed from an NW leak test penetration to a Type C leak test 4 i

penetration. These containment isolation valves and equipment associated with process  !

penetration M308 represent an unnecessary challenge to containment isolation, NW j System leak-rate testing and the condition of control room instrumentation relative to the l

) requirements of NUREGs 0700 and 0737.

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Duke Power Company plans to implement modifications for both units to remove

! containment isolation valves RN-429A and RN-432B of penetration M308, remove i

) associated wiring and control room instrumentation, cut / cap tubing providing l Containment Valve Injection Water to these containment isolation valves during Unit 1 i

j. refueling outage IEOC9 (currently scheduleo to begin in June,1996) and Unit 2 refueling

, outage 2EOC8 (currently scheduled to begin in March,1997). This planned modification i i also deletes all but a small portion of process penetration M308 piping such that the

. remaining section of piping is capped on each end, both inside and outside of containment, with removable flanges for temporary use during refueling outages to

. support containment cooling. A test connection will be provided for the required post-

- modification test, periodic Type B leak-rate tests, and subsequent 'as-needed' retests  !

l following use of the penetration. The reliability of containment isolation and integrity ,

j will be improved by this planned modification. Please refer to Attachment 5 (Modified

] Process Penetration M308) for a detailed sketch of the planned modification to

[ penetration M308. .

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1 DESCRIPTION OF AMENDMENT REOUEST 1 This Technical Specification amendment request addresses the containment integrity function of process penetration M308 relative to secondary containment bypass leakage paths and containment isolation. This proposed Technical Specifications change removes process penetration M308 and containment isolation valves RN-429A and RN-432B from Technical Specifications since planned modifications to modify penetration configuration, which includes removal of associated containment isolation valves, effectively relegates the penetration to a spare penetration with provisions for temporary j use only during refueling outages. Appropriate post-modification Type B leak-rate testing, subsequent Type B periodic leak-rate testing and retesting following use, will be performed A2 2

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i ATTACHMENT 3 CIIANGES TO TECIINICAL SPECIFICATIONS AND TECIINICAL JUSTIFICATION 4

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CHANGES TO TECIINICAL SPECIFICATIONS The requested amendment adds a footnote to Technical Specifications Table 3.6-1 (Secondary Containment Bypass Leakage Paths) for process penetration M308 (Return from Upper Containment Ventilation Units) to state that penetration M308 no longer applies to Unit I following refueling outage IEOC9 (currently scheduled to begin in June,1996) and no longer applies to Unit 2 following refueling outage 2EOC8 (currently scheduled to begin in March,1997). The proposed amendment also deletes the associated containment isolation valves RN-429A (Return from Upper Containment  ;

Ventilation Units Containment Isolation Valve - Inside) and RN-432B (Return from Upper Containment Ventilation Units Containment Isolation Valve - Outside) from Table

- 3.6-2a (Unit 1 Containment Isolation Valves) following refueling outage IEOC9 and from Table 3.6-2b (Unit 2 Containment Isolation Valves) following refueling outage 2EOC8.

Catawba's Technical Specifications will soon be divided into two (2) volumes, the first volume specific only to Unit I and the second volume specific only to Unit 2. This is necessary due to the planned Unit I steam generator replacement in June,1996. The Catawba divided Technical Specifications amendment was submitted to your staff July 18,1994 and may be approved prior to NRC approval of this proposed Technical Specification amendment.

l TECIINICAL JUSTIFICATION l I

The original basis for process penetration M308 was to provide a return for raw water containment cooling water from the upper containment ventilation units. Containment ventilation is necessary to maintain containment temperatures within the criteria specified by Technical Specifications. However, when the upper containment ventilation units 1 were modified to be serviced by chilled water, the upper containment ventilation return header was tied into the lower containment ventilation unit return header inside of containment, effectively rendering process penetration M308 out of service. However, penetration M308 and its associated components continue to serve as a containment boundary with respect to containment integrity. Planned modifications during the l upcoming Unit I refueling outage (IEOC9, currently scheduled to start in June,1996) I will remove containment isolation valves RN-429A and RN-4328 from the process piping of penetration M308. These modifications will enhance the integrity of containment and reduce unnecessary challenges to containment isolation, NW System  ;

leak-rate testing, and the condition of control room instrumentation.

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. ATTACHMENT 4 NO SIGNIFICANT IIAZARDS CONSIDERATION DETERMINATION AND ENVIRONMENTAL IMPACT ANALYSIS i

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i 6 j NO SIGNIFICANT 11AZARDS CONSIDERATION 1)ETERMINATION l i

As required by 10 CFR 50.91, this analysis is provided concerning whether the requested  :

j Technical Specification amendments involve significant hazards considerations, as defined by 10 CFR 50.92. The standard for determining that a Technical Specification j a'mendment request involves no significant hazards considerations requires that operation 1 of the facility in accordance with the requested amendment will not: ,

I l) Involve a significant increase in the probability or consequences of an accident previously evaluated; or k

2) Create the possibility of a new or different kind of accident from any accident

previously evaluated; or b

I 3) Involve a significant reduction in the margin of safety, I

j This requested amendment removes process penetration M308 from Technical i

Specifications Table 3.61 and removes containment isolation valves RN 429A and RN-

'l j 4328 from Technical Specifications Table 3,6-2a and Table 3.6-2b due to planned i modifications which physically remove these valves from process penetration M308.

{

i i

j C1111ERION 1 J

l The physical removal of containment isolation valves RN-432B and RN-429A, ,

associated control room instrumentation, containment valve injection water connectionu i to these valves and the subsequent scaling of process penetration M308 will decrease  :

unnecessary challenges to containment isolation, containment valve injection water leak-

! rate testing and the condition of control room instrumentation, as opposed to the current i configuration. ,

t i I

j Since the scaling of process penetration M308 will be performed per the requirements of -

the applicable ASMll code piping safety class requirements, the confidence in the  ;

i. pressure boundary will be equivalent to the component as originally designed. Therefore,  !

this Technical Specification amendment to remove process penetration M308 from .

Technical Specification Tables 3.61 and to remove containment isolation valves RN-  !

429A and 432B from Technical Specification Tabic 3.6-2a and Table 3.6-2b will not j increase the probability or consequences of an accident that has been previously evaluated.

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_ . _ . ._ , ~ - _ _

CRITERION 2 Since no new failure modes are created, on the basis that the penetration is equivalent in confidence to the original design, and the plant will operate the same way it does now, this Technical Specification amendment to remove process penetration M308 from Technical Specification Tables 3.6-1 and to remove containment isolation valves RN-429A and 432B from Technical Specification Table 3.6-2a and Table 3.6-2b does not create the possibility of a new or different kind of accident from any accident previously evaluated.

CRITERION 3 This proposed change to Technical Specifications will not cause a significant reduction in the margin of safety. Upon completion of the removal of containment isolation valves RN-432B and 429A and the subsequent scaling of process penetration M308, the penetration will be Type B leak rate tested as part of post-modification testing, and will be retested periodically and following each use of the penetration for temporary containment cooling purposes during refueling outages. Therefore, the fuel, cladding, reactor coolant pressure boundary, and containment are not negatively affected by the proposed Technical Specification amendment. No assumptions made in any accident analysis are compromised by this proposed Technical Specification amendment.

ENVIRONMENTAL IMPACT ANALYSIS The proposed Technical Specification amendment has been reviewed against the criteria of 10 CFR 51.22 for environmental considerations. As previously shown above, the proposed change does not involve significant hazards consideration nor increase the types and amounts of effluents that may be released offsite, nor increase individual or cumulative occupational radiation exposure. Based on this, the proposed amendment meets the criteria given in 10 CFR 51.22(C)(9) for categorical exclusion from the requirements for an Environmental Impact Statement.

COMMITTEE REVIEWS This proposed change to the Technical Specifications has been reviewed and approved by the Catawba Plant Operating Review Committee and the Nuclear Safety Review Board.

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l ATTACHMENT 5 PLANNED MODIFICATION TO PROCFSS PENETRATION M308

~~

CONTAINMENT s

. VESSEL

- I"(TYR)

I 8" 1 ~ 6" 9" "

6" i

s QF \

6" DIA.WN 3 i FLANGE 7l/2" f,

= 51/2" - 31/2" i i , \

8 ll l PIPE CAP )

20" WN RF I W DIA. '

FLANGE p / i l

- 6 5/8" O.D.  ;

la r- jl /

l h57'-3" 18 20"

( AZ-194"-O l _, ar . ,. , , , , _ _ ,

i ,

0.D.

, _1 , 151 f -

- a,r -m m. m

' -- E 1 ip l g  ; , .  ; - --

• l!

s"otA.

i 8 LINO f

21"

\

!  :: < 34 . = W.

l 13 ,

201/2" _

RF FLASEBE  ;

l I/2" DI A. l'

! ' THREADED PLUG 31/ 2"- =- - - - -

l 7"  ;

d 28, 33 l (FOR LEAK TEST) i _

21/ 2"--- * -

6 A.

4

~

i EXISTING) l 5 11/16" -

r CONTAINMENT l = = '

13 3/16 = SLEEVE 8

1311/16"[  !

j 20"DIA.8LIND GASKET H n-- l/2" a l FLANGE l/2"* e i

ELEVATION VIEW-SEALED PENETRATION ( M-308)

SCALE: I"= lLO"

. -. . - - . . . ..