Text

Proposed Tech Spec Changes,Moving Tables Listing Secondary Containment Bypass Leakage Paths & Containment Isolation Valves Into Bases,Adding Three Penetrations & Updating Tables for Planned Mods
	ML20197J555
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/14/1986
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20197J542	List: ML20197J538; ML20197J555;
References
	NUDOCS 8605200071
	Download: ML20197J555 (33)
	v • d • e

f 9

h ATTACHMENT 1 PROBOSED TECHNICAL TECHNICAL SPECIFICATION CHANGES 8605200071 860514 PDR ADOCK 05000369 p

PDR L.

(

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION

3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

At least once per 31 days by verifying that all penetrations

not

. a.

capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in fem 4P*4=6ef I

Specification 3.6.3; b.

By verifying that each containment air lock is in compliance with Specification 3.6.1.3; and After each closing of each penetration subject to Type B testing, c.

except the containment air locks, if opened following a Type A or 8 test, by leak rate testing the seal with gar at P, 14.8 psig, and verifying that when the measured leakage rate for these seals is a

added to the leakage rates determined pursuant to Specification 4.6.1.2d.

for all other Type B and C penetrations, the combined leakage rate is less than 0.60 L,.

"Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and the annulus and are locked, sealed or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be 7

performed more often than once per 92 days.

Amendment No (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 6-1 Amendment No.

(Unit 1)

(

4 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE

(.

LIMITING CONDITION FOR OPERATION e

3.6.1.2 Containment leakage rates shall be Ifmited to:

An overall integrated leakage rate of:

a.

1)

Less than or equal to L, 0.30% by weight of the containment f-air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,,,14.8 psig, or 2)

Less than or equal to L, 0.14% by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a rhduced pressure of P 7.4 psig.

t b.

A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type 8 and C tests, w$en pressurized to P,,

and A combined bypass leakage rate of less than 0.07 L, for all c.

penetrations identified ' '

^ ' I as secondarf containment bypass leakage paths when pressurized to P,.

APPLICA8ILITY: MODES 1, 2, 3, and 4.

ACTION:

With (a) the measured overall integrated containment leakage rate exceeding 0.75 L or 0.75 L ratef8rall as applicable, or (b) the measured combined leakage 0.60L,or(penekr,ationsandvalvessubjecttoTypesBandCtestsexceeding l

restor $theoverallintegratedleakageratetolessthan0.75Lc) the combined or equal to 0.75 L, as applicable, and the combined leakage rate $r, less than penetrations and vlives subject to Type 8 and C tests to less than 0.60 L for all and the combined bypass leakage rate to less than 0.07 L increasingtheReactorCoolantSystemtemperatureabovef00*F.

prior to SURVEILLANCE REQUIREMENTS 4.6.1.2 test schedule and shall be detemined in conformance with the cr fled in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 or the mass plot method:

Amendment No. 3)(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 6-2 Amendment No.6ib (Unit I)

W 4

8 PAGES 3/4.6-5 THRU 3/4.6-9a DELETED

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES

(

~

LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves-spe t'i d i T.L;= ;.. ; shall be OPERABLE; wit' i::1: tie.- tice: = she r in Teb k 2.0 2.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the isolation valve (s) :p uifi a in Tou k :.: 2 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,,

a.

or vo lv '-

b Isolate each affected penetration Nithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least f

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

c.

one closed manual valve or blind flange, or

--9 Inser-+

A ttack.cl

~ Ke Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN witnin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.3.1 The isolation valves s;niff:d ir Tdk 2.0---2 shall be demonstrated

['

OPERABLE' prior to returning the valve to service after maintenance, repair or replacement workais performed on the valve or its associated actuator, control l

or power circuit by performance of a cycling test and verification of isolation time.

-that c.cald o M e.c.t-M Valve,'s p er b r'" "

A mend me.nr No.

(unir2.:

McGUIRE - UNITS 1 and 2 3/4 6-22 Amand ment do-(Unit-lj L

1 d.

Operate the manual penetration valves on an intermittent basis under administrative control, or m

O 4

s W

.ed m.

b gi E

A d'

pW'

D l

l PAGES 3/4.6-24 THRU 3/4.6-30 DELETED k

CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAIN!1ENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA.

The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.

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 and is consistent with the requirements of GDC 54 thru 57 of Appendix A to 10 CFR Part 30.

Containment isolation within' the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be ccnsistent with the assumptions used in the analyses for a

/

LOCA.

4 COMBUSTIBLE GAS CONTROL s

The OPERABILITY of. the equipment and systems required for the detection

(

and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions, Either recombiner unit is capable of controlling the expected hydrogen generation associated with:

(1) zircon,ium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of I

metals within containment.

These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA", March 1971.

The OPERABILITY of at least 64 of 66 igniters ensures that the Distributed Ignition System will maintain an effective coverage throughout the containment.

This system of igniters will initiate combustion of any significant amount of hydrogen released after a degraded core accident.

This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random ignition source.

L lised Contamme.nr isolatten volve.s and theic-ce.guired rsolatton Trrnes are.

t able.

B a/w 6-2. Secondo c.entatnment b poss le.oko3e_ pa+hs and 3

in The. requked test gpe be C cm. hsted in ubk B 3N.6-l.

McGUIRE - UNITS 1 and 2 B 3/4 6-4

e, 3/4. c - t TABLE 3-&-F l

SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS l,

PENETRATION TEST

~

NUMBER SERVICE RELEASE LOCATION TYPE l

M216 Pressurizer Relief Tank Makeup Auxiliary Building Type C e

M212 Nitrogen to Pressurizer Relief Tank Auxiliary Building Type C M259 Reactor Makeup Water Tank to NV System Auxiliary Building Type C H373 Ir Condenser Glycol In Auxiliary Building Type C M372 Ice Condenser Glycol Out Auxiliary Building Type C M330 Nitrogen to Accumulators Auxiliary Building Type C M321 Safety Injection Test Line AuxiliaryBuilding Type C UpperHeadInjection,JestLine#

Auxiliary Building Typed M348 P6LS D is dorgo M374 Containment Floor Sump Incore Instrument Sump Discharge Auxiliary Building Type C M360 Reactor Coolant Drain Tank Gas Space to Waste Gas System Auxiliary Building Type C M375 Reactor Coolant Drain Tank Heat

'f Exchanger Discharge Auxiliary Building Type C 9o-M356 Equipment Decontamination Auxiliary Building Type C hk M235 Pressurizer Sample Auxiliary Building Type C h.a M309 Reactor Coolant Hot Leg Sample Auxiliary Building Type C M322 Component Cooling to Component r g; Cooling Drain Tank Auxiliary Building Type C c =;

r a

B3/9 6-1 TABLE -6-+ (Continued)

SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS 5

PENETRATION e

NUMBER SERVICE TEST C

RELEASE LOCATION E

EPE M307 d

Nuclear Service Water to Reactor Coolant Pump Auxiliary Building Type C

~

m M315 E

Nuclear Service Water From Reactor Coolant Pump Auxiliary Building Type C m

M213 Incore Instrumentation Room Purge In Auxiliary Building Type C M138 Incore Instrumentation Room Purge Out bd Auxiliary Building Type C M367 Upper Compartment Purge Inlet Auxiliary Building Type C cn M454 Upper Compartment Purge Inlet puxiliary Building Type C

(

.c M357 o-Lower Compartment Purge Inlet Auxiliary Building Type C M456 Lower Compartment Purge Inlet Auxiliary Sullding Type C M368 Containment Purge Exhaust Auxiliary Building Type C M455 Containment Purge Exhaust Auxiliary Building Type C M119 Containment Purge Exhaust Auxiliary Building Type C f

M337 Demineralized Water Sg Auxiliary Building Type C M240 Containment Ventilation Cooling g

Water In Turbine Building Type C At M385

,9 o Containment Ventilation Cooling Water In Turbine Building Type C ms O

, s hO e

^

m B Jh.6 -l TABLE 3-6-1 (Continued) z SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS 5

PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE e

E M390 U

Containment Ventilation Cooling Water Out Turbine Building Type C e

o M279 Containment Ventilation Cooling E

Water Out Turbine Building Type C m

M220 Instrument Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C M215 Breathing Air Auxiliary Building Type C M378 Containment Sample Out Auxiliary Building Type C m

M325 Containment Sample In Auxiliary Building Type C k

1 M358 Refueling Cavity to RW Pump Auxiliary Building Type C M377 Refueling Cavity From RW Tank Auxiliary Building Type C M331 Hydrogen Purge In Atmosphere Type C M326 RCP Motor Drain Tank Pump to Waste Oil Storage Auxiliary Building Type C P P 3 3 M221 Containment Ventilation Units

{9 Condenser Drains to Condenser y

Drain Tank Auxiliary Building Type C 4

M359 Instrument Air Auxiliary Building Type C fb M386 Instrument Air Auxiliary B 11 ding Type C e n

n; ;

DO

B 3/4, (, - )

TABLE W 1 (Continued) 8 i

2 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS PENETRATION NUMBER SERVICE TEST E

RELEASE LOCATION TYPE

]

M317 Instrument Air Auxiliary Building Type C M243 Containment Air Release e

Auxiliary Building Type C M384 Containment Air Addition Auxiliary Building Type C M361 Reactor Coolant Pump Motor Oil Supply Auxiliary Building Type C a

M353 Fire Protection Header Auxiliary Building Type C M376 Component Cooling Water to Auxiliary Building Type C t'

Reactor Coolant Drain Tank Heat Exchanger m

O M355 Component Cooling Water from Auxiliary Building Type C b

Reactor Coolant Drain Tank Heat Exchanger M327 Component Cooling Water to Auxiliary Building Type C Reactor Vessel Support Coolers and RCP Coolers

'33

'RR M320 Component Cooling Water from Auxiliary Building Type C

'& 3 Reactor Vessel Support 55 Coolers and RCP Coolers zz

?P Flued Head to Guard Pipe Atmosphere, or Welds on all Hot Auxiliary Building, Penetrations m

EE or Turbine Building

??

M412 Equipment Hatch Atmosphere Type C C$

suant to Specification 4.6.1.2f.

^

O s

O

m m

4 B 3/4. (, - t 2

TABLE 9-6-t(Continued)

E c

SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS m

7 PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE l cz 3

M280 Sample from Accumulator Auxiliary Building Type C I[

M342 Auxiliary Seal Injection Auxiliary Building Type C s

Line from Annulus to

[

Reactor Coolant Pumps M394 Ice from Rotary Valve Auxiliary Building Type C Assembly to Ice Condenser a

Cyclone Receiver be M255 ILRT Pressure Impulse Line Auxiliary Building Type C

{

M323 Cont. Rad. Monitors Auxiliary Building Type C EMF-38, 39, 40 M118 Cont. Press Monitors Auxiliary Building Type C

-t-

/

P M118 ILRT Press Impulse Line (Unit 2)

Augillary Building Type C

(_ 7 M239 Cont. Press Monitors Auxiliary Building Type C M239 Cont. Hydrogen Monitor "A" Train Auxiliary Building Type C 7

l M313 Cont. Press Monitors Auxiliary Building Type C 55 M402 Cont. Press Monitors Auxiliary Building Type C 2

xx y

?P Cont. Hydrogen Monitor "B" Train Auxiliary Building Type C C

N gg M392 Air to Upper PAL Aux Bldg Auxiliary Building Type C gg Side Door Seals

/

en

(_.

4m M152 Air to Lower PAL Aux Bldg Auxiliary Building:

Type C Side Door Seals f-

3 3h.G-l g

TABLE N (Continued)

SECONDARY CONTAIMERT BYPASS LEAKAGE PATHS A

PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE g

-d Cont. Press. Monitor -

Auxiliary Buf1 ding Type C

(

Harrow Range y

7

(

M354 Fuel Transfer Tube Auxiliary Building Type 8 j-

< r m

M2&O 0011p Seem es 4,,,,v/v3 Tye&A C. q 19 cak.y w<. E < r

nnolas

[. y c g ook y sus.urr Ancalu s fyr a x 7,p s 6 x tv R

iG

.I h

\\.'II$.$

I Ea EE AK 2E S"

r <+

\\

.-~

y t ~ k h'm l.1)bm W e u M o,a n l

iieso, 2.o a yy and win uu.'- be. 6 Pats d (schong__

Ws pencreat con is A for-tha. u nI. +est Li na_

s - s% J,1-s us, 2. -59 3, ond 2 -s99,

S fo & win 3 h e tin pte m sn m n w o E Nm

B 3/4. 6 - 2_

TABLE m n

E CONTAINMENi ISOLATION VALVES E

MAXIMUM E

VALVE NUMBER ISOLATION FUNCTION TIME (SEC)

-e 1.

Phase "A" Isolation 8

BB-1B#

Steam Generator A Blowdown Containment Outside Isolation

<10 BB-2Bf Steam Generator B Blowdown Containment Outside Isolation 710 BB-3B#

Steam Generator C Blowdown Containment Outside Isolation 710 BB-4B#

Steam Generator D Blowdown Containment Outside Isolation 710 BB-5A#

Steam Generator A Blaydown Containment Inside Isolation 510 BB-6A#

Steam Generator B Blowdown Containment Inside Isolation

<10 BB-7A#

Steam Generator C Blowdown Containment Inside Isolation 710 g

BB-8A#

Steam Generator D Blowdown Containment Inside Isolation 510 f

R CF-26AB#

Stean Generator D Feedwater Containment Isolation

<5 CF-28AB#

Steam Generator C Feedwater Containment Isolation 75 9'

CF-30AB#

Steam Generator B Feedwater Containment Isolation 75 5

CF-35AB#

Steam Generator A Feedwater Containment Isolation 75

.r CF-126B Steam Generator A Main Feedwater to Auxiliary Feedwater T

SO 39 Nozzle Isolation CF-127B Steam Generator B Main Fee'dwater to Auxiliary Feedwater 110 Nozzle Isolation CF-128B Ii Steam Generator C Main Feedwater to Auxiliary Feedwater

<10 Nozzle Isolation

~

's CF-129B Steam Generator D Main Feedwater to Auxiliary Feedwater

<10 Nozzle Isolation U

CF-134A Steam G'nerator A Feedwater Containment Isolation Bypass

$10 e

CF-135A Steam Generator B Feedwater Containment Isolation Bypass

<10 T

CF-136A Steam Generator C Feedwater Containment Isolation Bypass 510 CF-137A Steam Generator D Feedwater Containment Isolation Bypass

<10 CF-151A Auxiliary Nozzle Temper SG A 510 i2 td m

R

-m m

/

E 3}H, G, - 2.

TABLE-5.6-2-(Continued)

CONTAINMENT' ISOLATION VALVES MAXIMUM ISOLATION VALVE NulGER FUNCTION TIME (SEC) 1.

Phase "A" Isolation (continued)

CF-153A :

Auxiliary Nozzle Temper SG 8 110 CF-1558 Auxiliary Nozzle Temper SG C 110 CF-1578 Auxiliary Nozzle Temper SG D

_10 KC-3058#

Excess Letdown Hx Supply Pent. Isolation Outside 130 KC-3158#

Excess Letdown Hx Ret. Hdr. Pent. Isolation Outside

<30 KC-320A NCDT Hx Supply Hdr. Pent. Isolation Outside 515 KC-3328 NCDT Hx Supply Hdr. Pent. Isolation Inside 115 KC-333A NCDT Hx Return Hdr. Pent. Isolation Outside

<15 KC-4298 RB Drain Header Inside Coritainment Isolation

<15 KC-430A RB Drain Header Outside Contal nt Isolation 315 NS-2608 Reactor Makeup Water Tank to NV System

<15 NC-538 Nitrogen to Pressurizer Relief Tank Containment 110 Isolation Outside NC-54A Nitrogen to Pressurizer Relief Tank Containment

<10 Isolation Inside NC-568 PRT Makeup 110 NC-1958 NC Pump Motor Oil Containment Isolation Outside 115 NC-196A NC Pump Motor Oil Containment Isolation Inside

_15 NF-228A Air Handling Units Glycol Supply Containment

$15 Isolation Outside d

NF-233A Air Handling Units Glycol Supply Containment 115 d

Isolation Inside NF-234A Air Handling Units Glycol Supply Containment 115 Isolation Outside 2'

NI 47A Accumulator Nitrogen Supply Outside Containment 115 Isolation NI-95A

,g Test HOR Inside Containment Isolation 110

.d

8 J/q.lo - 2 TABLE 3.G-2-(Continued) 2 CONTAINMENT ISOLATION VALVES MAXIMUM c3 VALVE NUMBER ISOLATION FUNCTION a

TIME (SEC) 1.

Phase "A" Isolation (continued) g

- s NI-968 Test HDR Outside Containment Isolation

[

NI-1208

<10 Safety Injection Pump' to Accumulator Fill Line Isolation 510 NI-122B Hot Leg Injection Check nil 24, NI128 Test Isolation -

NI-255B UHI Check Valve lest Line Isolation

$10 NI-258A UHI Check Valve Test Line Isolation 110

<10 NI-264B yHI Check Valve Test Line-Isolation 510 NI-266A UHI Check Valve Test Line Isolation (p

NI-267A UHI Check Valve Test Line Isolation 510 510 wg NM-3A Pressurizer Liquid Samp.le Line Inside Containment Isolation 115 NM-6A Pressurizer Steam Sample Line Inside Containment Isolation

<15 NM-7B i

Pressurizer Sample Header Outshde Containment Isolation 715 NM-22A NC Hot Leg #1 Sample Line Inside Containment Isolation 515 y

NM-25A NC Hot Leg #4 Sample Line Inside Containment Isolation 115 HM-26B NC Hot Legs Sample Hdr. Outside Containment Isolation

$15 NM-728 NI Accumulator A Sample'Line Inside Containment Isolation

$15 NM-75B NI Accumulator B Sample Line Inside Containment Isolation

$15 NM-78B NI Accumulator C Sample Line Inside Containment Isolation

$15 HM-81B NI Accumulator D Sample Line Inside Containment Isolation

$15 NM-82A NI Accumulator Sample Hdr. Outside Containment Isolation 115 HM-187A#

SG A Upper Shell Sample Containment Isolation Inside

$15 NM-190A#

SG A Blowdown Line Sample Containment Isolation Inside 515 HM-191B#

SG A Sample Hdr. Containment Isolation Outside 115 HM-197B#

SG B Upper Shell Sample Containment Isolation Inside 515 g

HM-200B#

SG B Blowdown Line Sample Containment Isolation Inside 115 g

NM-201A#

SG B Sample Hdr. Containment Isolation Inside 115 A

NM-207A#

SG C Upper Shell Sample Containment Isolation Inside SIS D

NM-210A#

SG C Blowdown Line Sample Containment Isolation Inside

<l5 k

NM-211B#

SG C Sample Hdr. Containment Isolation Outside 515 sg NM-2178#

SG D Upper Shell Sample Containment Isolation Inside 115 t

HM-220B#

SG D Blowdown Line Sample Containment I' solation Inside

_.l 5 b

d

~

n l

8 3/q. &.

p TABLE &firt (Continued) 2 CONTAIl#4ENT ISOLATION VALVES MAXIMUM ISOLATION 5

VALVE NUMBER FUNCTION TIME (SEC) 4 1.

Phase "A" Isolation (continued) b NM-221M SG 0 Sample Hdr. Containment Isolation Outside

$15 NV-7Bf Letdown Containment Ipolation Outside

<10 NV-94M NC Pumps Seal Return Containment Isolation Inside 310 NV-958#

NC Pumps Seal Return Containment Isolation Outside

$10 NV-457M 45 gpa Letdown Orifice Outlet - Containment Isolation

$15 NV-458M 75 gpa Letdown Orifice O'utlet - Containment Isolation 115 NV-459M High Pressurizer Letdown Orifice Outlet - Containment

$15 Isolation 3

NV-842AC Standby Makeup Pump Suction Containment Isolation Inside

$15 L

NV-849A Standby Makeup Pump to RCS seals

$15 t

I L

RF-821A Containment Isolation Outside (Unit 1)

<15 RF-832A Containment Isolation Outside (Unit 2) 315

{

V8-498 Breathing Air Containment Isolation

$15 VE-SA Containment #2 Purge to Annulus Inside Containment Isolation

<15 VE-6B Containment #2 Purge to Annulus Outside Containment Isolation 315 VE-10A Containment #2 Purge Blower Outlet, Containment Isolation

-<15 (outside)

~

VI-1488 Instru. Air Upper Containment Outside Isolation

$15 s

e O

F a

83/q a lo A TABLE 3. E 2 (Continued) 2

!S l5 CONTAINMENT ISOLATION VALVES

'M MAXIMUM c.

iE VALVE NUMBER ISOLATION FUNCTION u

TIME (SEC) 1.

Phase "A" Isolation (continued)

.g k

VI-362A RB Isolation Valve for VI Supply to Annulum Vent.

_15

.m VP-1B**

Upper Containment Purge Supply #1 Outside Isolation 13 VP-2A**

Upper Containment Purge Supply #1 Inside Isolation 13 VP-3B**

Upper Containment Purge Supply #2 Outside Isolation 53 VP-4Aa*

Upper Containment Purge Supply #2 Inside Isolation

$3 VP-6B**

Lower Containment Purge Supply #1 Outside Isolation

$3 bo VP-7A**

Lower Containment Purge Supply #1 Inside Isolation 13 VP-8B**

Lower Containment Purge Supply #2 Outside Isolation 13 m

)

VP-9A**

Lower Containment Purge Supply #2 Inside Isolation 13 VP-10A**

Upper Containment Purge

Exhaust #1 Inside Isolation 13 VP-11B**

I Upper Containment Purge Exhausk #1 Outside Isolation

$3 VP-12A**

Upper Containment Purge Exhaust #2 Inside Isolation

$3 k

VP-138**

Upper Containment Purge Exhaust #2 Outside Isolation 53 VP-15A**

Lower Containment Purge Exhaust #1 Inside Isolation

<3 VP-16B**

h Lower Containment Purge, Exhaust #1 Outside Isolation 23 VP-17A**

Incore Instru. Room Purge Supply Inside Isolation 13 VP-188**

Incore Instru. Room Purge Supply Outside Isolation

$3-VP-19A**

Incore Instru. Room Purge Exhaust Inside Isolation 53 VP-20B**

Incore Instru. Room Purge Exhaust Outside Isolation

<3 VQ-1A Containment Air Release Inside Isolation 13 VQ-2B Containment Air Release Outside Isolation 13 VQ-5B

. Containment Air Addition Outside Isolation

$3 VQ-6A Containment Air Addition Inside Isolation 53 VS-128 Containment Station Air Outside Isolation

$15

(

VX-31A Containment Atmosphere Inside Isolation 55 g

5.

VX-33B Containment Atmosphere Inside Isolation, 55 8

g m

m re o

.m 8 3/y, 6 - 2_.

TABLE G-6-2 (Continued)

CONTAINMENT' ISOLATION VALVES MAXIBM o

ISOLATION VALVE NUMEER FUNCTION TIME (SEC) 1.

Phase "A" Isolation (continued) i WL-18 NCDT Pumps Discharge Outside Containment Isolation

<10 WL-2A NCDT Pumps Discharge Inside Containment Isolation 310 WL-39A NCDT Vent Inside Containment Isolation

<10 WL-418 NCDT Vent Outside Containment Isolation 210 WL-64A RB Sump Pump Discharge Inside Containment Isolation 315 WL-65B RB Sump Pump Discharge Outside Containment Isolation

$15 WL-321A Containment Vent Unit Drains Inside Containment Isolation

<l5 WL-322B g g Containment Vent Unit Drains Outside Containment Isolation 515 i

YM-115B Demin. Water Containment Outside Isolation

$15 W

2.

Phase "B" Isolation i

k KC-338B NC Pump Supply Header Pent. Isolation (outside) 140 h

KC-424B NC Pumps Return Hdr. Pent Inside Isolation

<40 KC-425A NC Pumps Return Hdr. Outs'ide Isolation 540 RN-252B Nonessential Supply to RB Penetration Outside Isolation 130 RN-253A Nonessential Supply to RB Penetration Inside Isolation 13Q RN-276A Nonessential Return to RB Penetration Inside Isolation

<30 RN-2778 Nonesseni.ial Return to RB Penetration Outside Isolation 530 RV-32A Lower Containment Vent. Unit Supply Containment Isolation 160 (outside)

RV-33B Lower Containment Vent. Unit Supply Containment Isolation 160 L

(inside) s 3.

RV-76A Lower Containment Vent. Unit Discharge Containment Isolation 160 p

(inside) s RV-778 Lower Containment Vent. Unit Discharge Containment Isolation 160 g

(outside) 3 b

VI-129B "A" Header Containment Outside Isolation 5 515 g

VI-150B Instrument Air Lower Containment Outside is != tion

<l5 VI-160B "B" Header Containment Outside Isolation 315

9 e

er WL1301B PALS DISCHARGE OUTSIDE CONTAINMENT ISOLATION ##

1 15 WL1302A PALS DISCHARGE OUTSIDE CONTAINMENT ISOLATION ##

1 15

r3 % 6 -

2 E

TABLE-3.C 2 (Continued) 5 CONTAINMENT ISOLATION VALVES

=

MAXIMUM "z

VALVE NUMBER ISOLATION FUNCTION C

TIME (SEC) 2.

Phase "B" Isolation (continued) g

=g RV-79A Upper Containment Vent. Unit Supply Containment Isolation Outside RV-808 130,

Upper Containment Vent. Unit Supply Containment Isolation Inside RV-101A 130 Upper Containment Vent. Unit Discharge Containment Isolation Inside RV-1028

$30 Upper Containment Vent. Unit Discharge Containment Isolation Outside _<30 3.

Main Steam Isolation SM-1AB#

Main Steam D Isolat$on W

<S SM-3AB#

Main Steam C Isolation w

SM-5AB#

Main Steam B Isolation 55 D

SM-7AB#

Main Steam A Isolation

<5 IS 9

SM-9ABW Main Steam D Isolation Bypass trl.

MainSteamCIsolationBypass{ Ctrl.

35 g

SM-10AB#

T SM-11AB#

Main Steam B Isolation Bypass Ctrl.

55 Main Steam A Isolation-Bypass Ctrl.

15

.c SM-12AB#

15 4.

Manual NCl41*

NC Pump Motor Oil Drain N.A.

NC142*

NC Pump Motor Oil Drain N.A.

WE13*

Equipment Decontamination N.A.

=

WE23*

Equipment Decontamination N.A.

VX34*

Containment H Sample N.A.

VX40*

Contafnment H Sample N.A.

g FWil*

Refueling Wat r N.A.

g FW13*

Refueling Water N.A.

g FW4*

Refueling Water N.A.

May be opened on an intermittent basis under administrative control.

- Valve also receives a High Radiation (H) isolation signal.

'g

Not subject to Type C leakage tests.g *

Effecxwe. upon f m p lernentunm N5M l-1% 1 l-l%B,2-s93,2 -598 HOTE:

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

3 See Specification 3/4.3.2 for system actuatica response times.

I m

s s

O ATTACHMENT 2 JUSTIFICATION AND SAFETY ANALYSIS

. ~

_m

Justification and Safety Analyses

~

The proposed changes to the Technical Specifications involve the relocation of two tables and the addition of three containment penetrations.

The tables (3.6-1, Secondary Containment Bypass Leakage Paths; 3.6-2, Containment Isolation Valves) would be removed from the Technical Specifications and be placed in the Bases. The relocation of these tables is an administrative matter which would allow future changes to be made without a license amendment, which would relieve both the NRC and Duke Power of an administrative burden. Maintaining these tables in the Bases would also assure that the information is still available to the operators.

The removal of such listings from the Technical Specifications has been identified by the Atomic Industrial Forum (AIF) and NRC Technical Specification improvement project as an area of Technical Specifications which may be addressed by an amendment to the existing Specifications, not requiring regulatory changes.

The changes to the tables reflect upcoming modifications to McGuire. Thr e_e.

penetrations are added to Table 3.6-1 (proposed Table B 3/4.6-1), Secondary Containment Bypass Leakage Paths and the service of an existing modification is changed, effective when the modifications are complete.

The three penetrations being added are outage services penetrations, that is they are to act as conduits for service line currently pulled through the personnel air lock doors and the equipment hatch. These penetrations are presently sealed with pipe caps which will be removed and replaced with pairs of flanges and blind flanges with a ball valve on the annulus side to permit testing of the panetrations. The penetrations will be sealed by the blind flanges except during outages when they are needed.

Future changes to the table would only be made after design reviews including an evaluation in accordance with 10CFR 50.59 to determine whether an unreviewed safety question is involved. As the criteria of 50.59 is virtually the same as the criteria of 10CFR 50.92, and is in fact slightly more restrictive (50.59 including " malfunction of equipment important to

,g, safety" and 50.92 including "significant", which is absent from 50.59), the same review is being performed at Duke Power for the modification as would be performed by the NRC for a license amendment. This proposal would eliminate the redundancy of review. A copy of the completed 50.59 review is included in attachment 4 for information.

Upon implementation of this proposal, future changes to the table may be implemented without a license amendment. Upon completion of the modification, Duke would send a copy of the af fected page(s) with the change (s) marked.

The designation change of penetration M348 (upon implementation of the modification) would change its designation from Upper Head Injection (UHI)

Test Line to PALS (Post Accident Liquid Sample) Discharge. The PALS discharge is being routed to containment in response to NUREG-0737 and the UHI system is being removed, pending NRC approval. This is also the nature of the change to Table 3.6-2 (proposed Table B 3/4.6-2), Containment Isolation Valves. The valves on the PALS will receive a Phase A containment isolation signal for automatic closure. Control room operator action will be required to open these two valves (WL1301B and WL1302A) wher a liquid sample is being taken is a post accident situation.

Justification and Safety Analyses (Continued)

The proposed changes to Specifications 3.6.1.1, 3.6.1.2 and 3.6.3 delete references to the tables as they will no longer be a part of the Technical Specifications. The tables would be referenced in the bases.

In addition, an Action is being added to Specification 3.6.3 to allow the operation of penetrations on an intermittent basis under administrative controls as approved by the NRC.

Presently, the footnote "May be opened on an intermittent basis under administrative control" is in Table 3.6-2 (proposed B 3/4.6-2) and applies to manually operated valves (reactor coolant pump motor oil drain, equipment decontamination, containment hydrogen sample, and refueling water. With the tables moved to the bases, the footnote in the table would not be applicable as it would no longer be part of the Technical Specifications.

The proposed change to Surveillance Requirement 4.6.3.1 is to clarify that work done on the valve that would not affect the valve's performance would not require a valve stroke test. Work on the valve such as regular preventatiye maintenance or handwheel replacement that does not degrade valve performance does not need a stroke test; this change would eliminate this requirement. Work that could affect valve performance would still require the retest, thus no existing safety margins are affected.

These changes are administrative in nature and are intended to update and improve the Technical Specifications; no question of safety is involved.

4 ATTACHMENT 3 ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATIONS

Analysis of Significant Hazards Considerations As required by 10CFR 50.91, this analysis provides a determination that the proposed changes to the Technical Specifications do not involve any significant hazards considerations, as defined by 10CFR 50.92.

Operation in accordance with the proposed change would not involve a significant increase in the probability or consequences of an accident previously evaluated. The movement of the tables from the Technical Specifications to the bases is an administrative change which does not impact plant safety. The changes to Specifications 3.6.1.1, 3.6.1.2, and 3.6.3 delete references to these tables (which is administrative - the actual requirements do not change) and add an additional Action to 3.6.3 which is in fact, now in force as a footnote to the table - placing it in the specification is strictly administrative. The addition of three penetrations does not increase the chance of containment leakage / failure a these penetratione presently exist through the containment vessel and no cutting of the containment vessel will take place. These penetrations will be leak tested in accordance with Technical Specifications and applicable regulations to assure their integrity.

Operation in accordance with the proposed change would not create the possibility of a new or different kind of accident from any accident previously evaluated. The movement of the tables is an administrative matter. Utilization of the three additional penetrations does not create 4

any new accident scenarios as these penetrations are structurally the same as other penetrations.

Operation in accordance with the proposed change would not involve a significant reduction in a margin of safety. The transfer of the tables from the Technical Specifications to the Bases is an administrative matter.

The three penetrations to be utilized do not affect the structural integrity of containment. As a potential leak path, the allowed leak rate of containment is unaffected thus no safety margin is affected.

Based on the preceding analysis, Duke Power Company concludes that the proposed amendments do not involve a significant hazards consideration.

l l

l 1

...m

8 9

e ATTACHMENT 4 NUCLEAR STATION MODIFICATION SAFETY EVALUATION

. -[(

M G - I-I 8 50 02637

. se i

y, FORM 160.2 REVISION 3

,9 17 w%

SHEET

_OF 3 DUKE POWER COMPANY Du$c73 FIG Ni CLEAR STATION MODIFICATION z

L SAFETY EVALUATION STATION:

MCbuifes NSM ID NO:

M 6 - Il 850 l

REVISION:

00 (3-5872 PART:

C/E O

E S.S. LeFler (3'7Cll0)

CONTACTS:

R.C.

Buev QA CONDITION:

,p

% n. x& Ph@Mt4 PART A - SAFETY EVALUATION (RPSS)

O DESCRIPTION OF MODIFICATION

See, a & d e ci shee3-2 OF 3.

TECHNICAL SPECIFICATION CHANGES REQUIRED. (Yes/No) Attach applicable pages if yes.

es,

see c4.Ha.clec) sheeA-3 of s.

10 CFR 50.59 EVALUATION - UNREVIEWED SAFETY QUESTIONS Section 50.59 states that an Unreviewed Safety Question is involved (i)if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be in-creased; or(ii)if a possibility for an accident or malfunction of a different type than evaluated previously in the safety analysis report may be created; or(iii)if the margin of safety as defined in the basis for any technical specification is reduced.

Address each part separately in the Safety Evaluation with appropriate justification. Th e <wa cl;ficcd;on unll clccreo.5e cufo.ge Mime.

No Safe,b/ SYSfems w'.ll ht clegrgclec} ancl no hf;gl C.hanges wd{ be, egoje, to any syske>h. No unreveewec) Sa.feff yueShion w;l be, involVeck OF Creoheck 08fer Oc appro va.} of Oc Sc8ely evedwcdico beincj on e, On Ne, L%C oE OR ctheve, penefrdions Eo r cu,fg e, mcdn fenance, cbeig refwelincj opern.fions. Ibis evoluc.hion it be;ng c{ene by AAC!

i5 h b e.

c one bebe k'he reEue).n3 od If the answer to any of the above is yes an Unreviewed Safety Question is involved, which requires a License Amendment pursuant to 10 CFR 50.90.

SIGNATURE:(RPSS)

V%

DATE:

3-l 7-8(o REVIEWED:(RPSS)

N

_"/

DATE:

,7Y7"'/d I

/

PART B - SAFETY ANALYSIS REPORT (RE)

SAFETY ANALYSIS REPORT SECTION(S) REVIEWED:

CHANGED:

O APPENDIX R OF 10 CFR 50 REVIEW CONDUCTED O 10 CFR 50.49(I) REVIEW CONDUCTED SIGNATURE:

O LEAD ENGINEER DATE:

REVIEWED:

DATE:

i l

,e NSMSE PROJECT DESCRIPTION MG 1850 Shee} 2 of 3.

MCGUIRE NUCLEAR STATION, UNIT 1 WELD FLANGES ON EXISTING SPARE PENETRATIONS E429. E461, AND M260 NSM MG-ll850/00; TASK 29368

. Purpose Outage activities such as eddy current testing, sludge lancing, and peening require that service lines be fed into containment from equ located outside containment.

the personnel air-lock doors and the equipment hatch. Currently these outage time, plans were made to utilize spare In order to reduce M260.

provide access into the containment.

Summary of Modification Pipe caps used to seal the spare sleeves shall be' removed.

flanges and blind flanges shall be installed as illustrated.

A pair of ball valve will be installed on the annulus side to permit testing of A one inch penetration.

C[O f="$s Annulus 4 =J 4_ =_ )..

f, Containment Vessel Summary of Design Activity Design En Briefly, gineering activities are listed by the Design and Electrical Divisions for compliance with their respective des requirements.

Test pipe and test valv' Flanged joints shall comply with AS requirements.

Class 2 requirements.

Qualification of the test pipe and valve will bee s based on the same criteria used to qualify vent and drain connec ESOB Gruup will revise MC-1921-01 to note use of sleeves E-429 and E 461 Piping and valve materials will be ordered as listed by the D Summary.

esign Scope

% ( {

[..;

4.1 i.

t....

2 TABLE 3.6-1(Continued)

S 5

SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS M

PENETRATION NUMBER SERVICE TEST RELEASE LOCATION TYPE g

Cont. Press. Monitor -

Auxiliary Building Type C Narrow Range.

i g

g M354 Fuel Transfer Tube Auxiliary Building Type B

~

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[

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