Text

Proposed Tech Specs 3/4.6 Re Containment Systems
	ML20133D399
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/06/1997
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20133D394	List: ML20133D390; ML20133D399;
References
	NUDOCS 9701090173
	Download: ML20133D399 (30)
	v • d • e

,s , e .

Attachment 1 I

I 1

l PDR

! 3/4.6 CONTAINMENT SYSTEMS j

i 3/4.6.1 PRIMARY CONTAINMENT i CONTAINMENT INTEGRITY j l LIMITING CONDITION FOR OPERATION l I

i 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

f APPLICABILITY: MODES 1, 2, 3, and 4. W * ( Foor NorE- A-TMc MD) i j ACTION:

i Without primary CONTAINMENT INTEGRITY, restore CONTAINHENT INTEGRITY within I

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 l SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS l

j. 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

l

a. At least once per 31 di.ys by verifying that all penetrations

not

capable of being closed by OPERABLE containment automatic isolation l valves or operator action during periods when containment isolation i valves are open under administrative control,** and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions;

b. By verifying that each containment air lock is in compliance with Specification 3.6.1.3; and i

c. After each closing of each penetration subject to Type B testing, ,

except the containment air locks, if opened following a Type A or B i

. test, by leak rate testing the seal with gas at P,, 14.8 psig, and verifying that when the measured leakage rate for these seals is 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 veri-fied closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

- The following valves may be opened on an intermittent basis under adminis-trative control: NC-141, NC-142, WE-13, WE-23, VX-34, VX-40, FW-11, FW-13, FW-4.

McGUIRE - UNIT 1 3/4 6-1 Amendment No. 166

LIMITING CONDITION FOR OPERATION l 3.6.1.2 Containment leakage rates shall be limited to:

. a. An overall integrated leakage rate of:

~

1) Less than or equal to L , 0.30% by weight of the containment 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 t

air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of Pt , 7.4 psig.

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

and

c. A combined bypass leakage rate of less than 0.07 L, for all penetra-tions identified as secondary containment bypass leakage paths when pressurized to P,.

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

With (a) the measured overall integrated containment leakage rate exceeding 0.75 L o t enetrations and valves subject to Types B and C tests exceeding 0.60 for all p)r 0.75 L , as applicable, or (b) the measured combin L,, or (c the combined bypass leakage rate exceeding 0.07 L restore the overall integrated leakage rate to less than 0.75 L, or less,,han t or equal to 0.75 L , as applicable, and the combined leakage rate for all penetrations and t

valves subject to Type B and C tests to less than 0.60 L , and the combined bypass leakage rate to less than 0.07 L, prior to increa,ings the Reactor l Coolant System temperature above 200*F SURVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in confonnance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 or the mass-plot method:

l McGUIRE - UNIT 1 3/4 6-2 Amendment No. 166

CONTAINMENT SYSTEMS l ANNULUS VENTILATION SYSTEM

! LIMITING CONDITION FOR OPERATION l .

3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4. * { Fo" ^'OE A-w Ac h d ACTION:

~

i a. With one Annulus Ventilation System inoperable for reasons other

than the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5, restore the inoperable system to OPERABLE status within 7 days 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 j

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I b. With the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable, j restore the inoperable pre-heaters to OPERABLE status within 7 days, i or file a Special Report in accordance with Specification 6.9.2 l within 30 days specifying the reason for inoperability and the planned actions to return the pre-heaters to OPERABLE status.

SURVEILLANCE RE0VIREMENTS

{ 4.6.1.8 Each Annulus Ventilation System shall be demonstrated OPERABLE:

l a. At least once per 31 days on a STAGGERED TEST BASIS, by initiating, from the control room, flow through the HEPA filters and charcoal

{

adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the pre-heaters operating; j b. At least once per 18 months, or (1) after any structural maintenance i ,

on the HEPA filter or charcoal adsorber housings, or (2) following l painting, fire, or chemical release in any ventilation zone communi-l cating with the system, by:

. 1) Verifying that the ventilation system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance of Regulatory Positions C.5.a. C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 8000 cfm i 10%;

2) Verifying within 31 days after removal that a laboratory anal-ysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-sion 2, March 1978, and tested per ASTM 03803-89 has a methyl iodide penetration of less than 4%; and

3) Verifying a system flow rate of 8000 cfm i 10% during system operation when tested in accordance with ANSI N510-1975.

Amendment No. 166 McGUIRE - UNIT 1 3/4 6-11

CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM i

l LIMITING CONDITION FOR OPERATION i

3.6.1.9 Each containment purge supply and/or exhaust isolation valve shall be

! OPERABLE and:

'. a. Each containment purge supply and/or exhaust isolation valve for the j lower compartment (24-inch) and instrument room (12-inch and 24-

inch) shall be sealed closed, and

! b. The containment purge supply and/or exhaust isolation valve (s) for

the upper compartment (24-inch) may be opened for up to 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months j during a calendar year provided no more than one pair (one supply j and one exhaust) are open at one time.

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

b O T #

i ACTION:

a. With any containment purge supply and/or exhaust isolation valve for i the lower compartment or instrument room open or not sealed closed, i

close and/or seal closed that valve or isolate the penetration (s)

! within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in at least HOT STANDBY within the next j 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 .

I b. With the containment purge supply and/or exhaust isolation valve (s) for the upper compartment open for more than 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months during a calendar year, close any open valve or isolate the penetration (s)

! within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise 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 .

c. With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifica-

- tions 4.6.1.9.3 and/or 4.6.1.9.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise 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 . ll l

i McGUIRE - UNIT 1 3/4 6-13 Amendment No. 166

_,,:..__... ~. .. .. .. .. -- - - ---

. a - - ;f IX l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 41 CONTAINMENT INTEGRITY !.

M .

LIMITING CONDITION FOR OPERATION y a

3,6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

h APPLICABILITY: MODES 1, 2, 3, and 4. W F $ 8 * "f-MCd ") $

ACTION:

M 3

3 Without primary CONTAINNENT INTEGRITY, restore CONTAINMENT INTEGRITY within (j 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 a SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . W-.s SURVEILLANCE REQUIREMENTS f

1 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: M g

a. At least once per 31 days by verifying that all penetrations

not 4 capable of being closed by OPERABLE containment automatic isolation valves or operator action during periods when containment isolation %'

valves are open under administrative control,** and required to be 9 closed during accident conditions are closed by valves, blind h d

flanges, or deactivated automatic valves secured in their positions;

b. By verifying that each containment air lock is in compliance with y Specification 3.6.1.; and

)M

c. After each closing of each penetration subject to Type B testing, p

,, except the containment air locks, if opened following a Type A or B h 14.8 psig, and g test, by leak verifying rate testing that when the seal the measured with gas leakage rate at forPt ,hese seals is y added to the leakage rates determined pursuant to Specification g 4.6.1.2d. for all other Type B and C penetrations, the combined y leakage rate is less than 0.60 L,. il I l 5 .

(,

'j i 2 '

Except valves, blind flanges, and deactivated automatic valves which are h located inside the containment and the annulus and are locked, sealed or

otherwise secured in the closed position. These penetrations shall be veri-c fied closed during each COLD SHUTDOWN except that such verification need not f be perfonned more often than once per 92 days.

f **The following valves may be opened on an intennittent basis under adminis-l.

r trative control: NC-141, NC-142, WE-13, WE-23, VX-34, VX-40, FW-11, FW-13, 1 FW-4.

4 [-

[ McGUIRE - UNIT 2 3/4 6-1 Amendment No. 148 ,

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CONTAINMENT SYSTEMS j CONTAINMENT LEAKAGE l

h

, LIMITING CONDITION FOR OPERATION l' 5

h.4 3.6.1.2 Containment leakage rates shall be limited to:

h ,

a. An overall integrated leakage rate of:

g 1) , 0.30% by weight of the containment j i.i Less air perthan or equal 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to L,14.8 psig, or at P,, }.

>$ l N 2) Less than or equal to L , 0.144 by weight of the containment t [.

p air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of P , 7.4 psig.

t !

I e.

b. A combined leakage rate of less than 0.60 L for all penetrations !

andvalvessubjecttoTypeBandCtests,w$enpressurizedtoP,, !

and I

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l

c. A combined bypass leakage rate of less than 0.07 L, for all penetra-A tions identified ~as secondary containment bypass leakage paths when y; pressurized to P,.

APPLICABILITY: MODES 1, 2, 3, and 4. V (Foom on A N C )

e ACTION: k' t.

f With (a) the measured overall integrated containment leakage rate exceeding '

'I.

0.75 L or 0.75 L , as applicable, or (b) the measured combined leakage rate t h

{j for all penetrations and valves subject to Types B and C tests exceeding 0.60 [.

gj L , or (c) the combined bypass leakage rate exceeding 0.07 L,, restore the !

h overall integrated leakage rate to less than 0.75 L, or less than or equal to i

5 0.75 L , as applicable, and the combined leakage rate for all penetrations and t

% , and the combined valves bypass subject leakage to Type rate B and to less thanC0.07 testsL to less than 0.60 L,ing the Reactor h .

Coolant System temperature above 200*F., prior to increas y SURVEILLANCE RE0VIREMENTS 1 4 1

b

)

4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in confonnance with the criteria spec 1- ;

fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI h f N45.4-1972 or the mass-plot method: j 1 (

i !

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j McGUIRE - UNIT 2 3/4 6-2 Amendment No. 148

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4 CONTAINMENT SYSTEMS NN ANNULUS VENTILATION SYSTEM

. }T) 4 LIMITING CONDITION FOR OPERATION 4

g 3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.

I

,a.,

b APPLICABILITY: MODES 1, 2, 3, and 4. -U (Foot-Nort NMAc l+ED ,)

h;,

~

. ACTION:

'W a. With one Annulus Ventilation System inoperable for reasons other 3

' % than the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5, restore ;

% the inoperable system to OPERABLE status within 7 days or be in at Q 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 :

g within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . I til b. With the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable,

, ',- restore the inoperable pre-heaters to OPERABLE status within 7 days,

j or file a Special Report in accordance with Specification 6.9.2

/, within 30 days specifying the reason for inoperability and the

!Q 't ,

planned actions to return the pre-heaters to OPERABLE status.

<q- SURVEILLANCE RE0VIREMENTS 4.6.1.8 Each Annulus Ventilation System shall be demonstrated OPERABLE

[

N a. At least once per 31 days on a STAGGERED TEST BASIS, by initiating, 1 1

1 '

from the control room, flow through the HEPA filters and charcoal

. adsorbers and verifying that the system operates for at least 10

. hours with the pre-heaters operating;

b. At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone comuni-cating with the system, by:

1) Verifying that the ventilation system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance of Regulatory j Positions C.S.a. C.5.c and C.S.d of Regulatory Guide 1.52, '

Revision 2, March 1978, and the system flow rate is 8000 cfm

10%;

2) Verifying within 31 days after removal that a laboratory anal-ysis of a representative carbon sample obtained in accordance y with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-sion 2, March 1978, and tested per ASTM D3803-89 has a methyl

>gj iodide penetration of less than 4%; and M

M 3) Verifying a system flow rate of 8000 cfm i 10% during system gl operation when tested in accordance with ANSI N510-1975.

W]

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McGUIRE - UNIT 2 3/4 6-11 Amendment No. 148 l e , y;g

T . . - l t

CONTAINMENT SYSTEMS j ,/ CONTAINMENT VENTILATION SYSTEM V3 LIMITING CONDITION FOR OPERATION

'3 3.6.1.9 Each containment purge supply and/or exhaust isolation valve shall be

~d; g OPERABLE and:

n Each containment purge supply and/or exhaust isolation valve for the Q, '

a.

lower compartment (24-inch) and instrument room (12-inch and 24-

'i,.'

inch) shall be sealed closed, and I

t. l 3 b. The containment purge supply and/or exhaust isolation valve (s) for i the upper compartment (24-inch) may be opened for up to 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months !

during a calendar year provided no more than one pair (one supply and one exhaust) are open at one time.

l APPLICABILITY: MODES 1, 2, 3, and 4. (19xNort. A-rrec (46 D )

ACTION:

a. With any containment purge supply and/or exhaust isolation valve for the lower compartment or instrument room open or not sealed closed, close and/or seal closed that valve or isolate the penetration (s)

I within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , othemise 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 .

t

,' l

b. With the containment purge supply and/or exhaust isolation valve (s) l for the upper compartment open for more than 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months during a calendar year, close any open valve or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in at least HOT STANDBY within the next l 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 .

I t c. With a containment purge supply and/or exhaust isolation valve (s)

! having a measured leakage rate in excess of the limits of Specifica-

-i - tions 4.6.1.9.3 and/or 4.6.1.9.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise 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 .

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I McGUIRE - UNIT 2 3/4 6-13 Amendment No. 148 i.____...._... . . . . _ . . . . . . _ - . . - - - - - . - -

e Proposed Revision to Technical Specifications 3.6.1.1, 3.6.1.2, and 3.6.1.9.

Add the following footnote to the Applicability statement for the affected Technical Specifications:

"A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2."

Proposed Revision to Technical Specification 3.6.1.8.

Add the following footnote to the Applicability statement for the affected Technical Specification:

"A one-time change is granted in Modes 3 and 4 to allow repair activities for the containment purge supply and/or exhaust isolation valves for the upper and lower compartment that were open in Modes 3 and 4 following the steam generator replacement outage."

I l

1

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. l i

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

ACTION:

l 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 H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD i 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:

a. At least once per 31 days by verifying that all penetrations

not l capable of being closed by OPERABLE containment automatic isolation valves or operator action during periods when containment isolation valves are open under administrative control,** and required to be ,

closed during accident conditions are closed by valves, blind l flanges, or deactivated automatic valves secured in their positions;

b. By verifying that each containment air lock is in compliance with i Specification 3.6.1.3; and I

c. After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P,, 14.8 psig, and I verifying that when the measured leakage rate for these seals is 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 performed more often than once per 92 days.

- The following valves may be opened on an intermittent basis under adminis-trative control: NC-141, NC-142, WE-13, WE-23, VX-34, VX-40, FW-11, FW-13, FW-4.

- - A one-time change is granted to have the containment purge supply and/or

. exhaust isolation valves for the upper and lower compartment open in Modes

! 3 and 4 following the steam generator replacement outage. The cumulative i time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 1 3/4 6-1 Amendment No.

l 1 -

l l

1

! CONTAINMENT SYSTEMS i CONTAINMENT LEAKAGE ,

I 1

i LIMITING CONDITION FOR OPERATION 1 i l 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

l I 1) Less than or equal to L , 0.30% by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,,14.8 psig, or 1

1

2) Less than or equal to L , 0.14% by weight of the containment t

air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of P , 7.4 psig.

t j b. A combined leakage rate of less than 0.60 L for all penetrations j andvalvessubjecttoTypeBandCtests,wSenpressurizedtoP,,

and i

j c. A combined bypass leakage rate of less than 0.07a L for all penetra-tions identified as secondary containment bypass leakage paths when i pressurized to P,.

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

ACTION: l l

With (a) the measured overall integrated containment leakage rate exceeding 0.75 L or 0.75 L ,t as applicable, or (b) the measured combined leakage rate l for L,, orall(cp)enetrations and leakage the combined bypass valvesrate subject to Types exceeding 0.07 L B restore and Cthe tests exceedin overall integrated leakage rate to less than 0.75 L, or less,,han t or equal to 0,75 L , as applicable, and the combined leakage rate for all penetrations and t

valves subject to Type B and C tests to less than 0.60 L d the combined bypass leakage rate to less than 0.07 L sing the Reactor Coolant System temperature above 200*F , prior to increa ,

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 or the mass-plot method:

A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be j sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 1 3/4 6-2 Amendment No.

1

_ .._ __ -- . _ ~ _ _ . _ . _ _ . __ _. _ .._ _. _ _ . . __.._ ___ _ .._. _ _ _ .

w CONTAINMENT SYSTEMS f

ANNULUS VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.

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

4 ACTION:

, a.- With one Annulus Ventilation System inoperable for reasons other

than the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5, restore i

the inoperable system to OPERABLE status within 7 days 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 i within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable, restore the inoperable pre-heaters to OPERABLE status within 7 days, or file a Special Report in accordance with Specification 6.9.2 within 30 days specifying the reason for inoperability and the planned actions to return the pre-heaters to OPERABLE status.

SURVEILLANCE RE0VIREMENTS 4.6.1.8 Each Annulus Ventilation System shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS, by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the pre-heaters operating;

b. At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating with the system, by:

1

1) Verifying that the ventilation system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance of Regulatory Positions C.S.a. C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 8000 cfm i 10%;

2) Verifying within 31 days af ter removal that a laboratory anal-ysis of a representative carb~on sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-sion 2, March 1978, and tested per ASTM D3803-89 has a methyl

. iodide penetration of less than 4%; and

3) Verifying a system flow rate of 8000 cfm

10% during system operation when tested in accordance with ANSI N510-1975.

i

A one-time change is granted in Modes 3 and 4 to allow repair activities for the containment purge supply and/or exhaust isolation valves for the upper and lower compartment that were open in Modes 3 and 4 following the steam generator replacement outage.

McGUIRE - UNIT 1 3/4 6-11 Amendment No.

CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION-3.6.1.9 Each containment purge supply and/or exhaust isolation valve shall be OPERABLE and:

a. Each containment purge supply and/or exhaust isolation valve for the lower compartment (24-inch) and instrument room (12-inch and 24-inch) shall be sealed closed, and

b. The containment purge supply and/or exhaust isolation valve (s) for the upper compartment-(24-inch) may be opened for up to 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months during a calendar year provided no more than one pair (one supply and one exhaust) are open at one time. ,

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

ACTION:

a. With any containment purge supply and/or exhaust isolation valve for the lower compartment or instrument room open ar not sealed closed, close and/or seal closed that valve or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise 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 .

b. With the containment purge supply and/or exhaust isolation valve (s) i for the upper compartment open for more than 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months during a !

calendar year, close any open valve or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in at least H0T 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 .

c. With a containment purge supply and/or exhaust isolation valve (s) i having a measured leakage rate in excess of the limits of Specifica-tions 4.6.1.9.3 and/or 4.6.1.9.4, restore the. inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise 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 .

A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative

, time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 1 3/4 6-13 Amendment No.

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

4 l 1

j .

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT i CONTAINMENT INTEGRITY k JTING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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

1 ACTION:

l Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within l 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least H0T 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 j 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves or operator action during periods when containment isolation valves are open under administrative control,** and required to be i closed during accident conditions are closed by valves, blind flanges, or deactivued automatic valves secured in their positions; i b. By verifying that each containment air lock is in compliance with Specification 3.6.1.3; and

c. After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P,, 14.8 psig, and verifying that when the measured leakage rate for these seals is 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 La-

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 performed more often than once per 92 days.

- The following valves may be opened on an intermittent basis under adminis-trative control: NC-141, NC-142, WE-13, WE-23, VX-34, VX-40, FW-11, FW-13, FW-4.

- - A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 2 3/4 6-1 Amendment No.

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of: l 1

i 1) Less than or equal to L , 0.30% by weight of the containment l air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,,14.8 psig, or l

2) Less than or equal to L t, 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 reduced pressure of Pt , 7.4 psig.

b. A combined leakage rate of less than 0.60 L for all penetrations j j and valves subject to Type 8 and C tests, w$en pressurized to P,, 1 and I

c. A combined bypass leakage rate of less than 0.07 L, for all penetra-tions identified as secondary containment bypass leakage paths when pressurized to P,.

APPLICABILITY: MODES 1, 2, 3, and 4.* i ACTION: l With (a) the measured overall integrated containment leakage rate exceeding 0.75 L or 0.75 L , as applicable, or (b) the measured combined leakage rate t

for all penetrations and valves subject to Types 8 and C tests exceeding 0.60 L,, or (c) the combined bypass leakage rate exceeding 0.07 L , restore the overall integrated leakage rate to less than 0.75 L, or less,than or equal to 0.75 Lt , as applicable, and the combined leakage rate for all penetrations and

, and the combined valves subject rate bypass leakage to Type to less B than and C tests 0.07 to less La prior than 0.60 L,ing the Reactor to increas Coolant System temperature above 200*F SURVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 or the mass-plot method:

A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 2 3/4 6-2 Amendment No.

i

=.

CONTAINMENT SYSTEMS ANNULUS VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.

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

ACTION:

a. With one Annulus Ventilation System inoperable for reasons other than the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5, restore l the inoperable system to OPERABLE status within 7 days or be in at I least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable, restore the inoperable pre-heaters to OPERABLE status within 7 days, or file a Special Report in accordance with Specification 6.9.2 within 30 days specifying the reason for inoperability and the planned actions to return the pre-heaters to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.6.1.8 Each Annulus Ventilation System shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS, by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the pre-heaters operating;

b. At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating with the system, by:

1) Verifying that the ventilation system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance of Regulatory Positions C.S.a C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 8000 cfm

10%;

2) Verifying within 31 days after removal that a laboratory anal-ysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-sion 2, March 1978, and tested per ASTM D3803-89 has a methyl iodide penetration of less than 4%; and

3) Verifying a system flow rate of 8000 cfm i 10% during system operation when tested in accordance with ANSI N510-1975.

A one-time change is granted in Modes 3 and 4 to allow repair activities for the containment purge supply and/or exhaust isolation valves for the upper and lower compartment that were open in Modes 3 and 4 following the steam generator replacement outage.

McGUIRE - UNIT 2 3/4 6-11 Amendment No.

- . _ . . _ _ _ . . . _ _ ___ _. _ _ - _ _ _ . . _.. . _ _ __ _ ~ - . _ _

' CONTAINMENT SYSTEMS i

CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION I 3.6.1.9 Each containment purge supply and/or exhaust isolation valve shall be OPERABLE and:

a. Each containment purge supply and/or exhaust isolation valve for the j lower compartment (24-inch) and instrument room (12-inch and 24-inch) shall be sealed closed, and

b. The containment purge supply and/or exhaust isolation valve (s) for the upper compartment (24-inch) may be opened for up to 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months during a calendar year provided no more than one pair (one supply and one exhaust) are open at one time.

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

l ACTION:

a. With any containment purge supply and/or exhaust isolation valve for the lower compartment or instrument room open or not sealed closed, close and/or seal closed that valve or isolate the penetration (s) 7' within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in at least HOT STAND 8Y 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 .

4

b. With the containment purge supply and/or exhaust isolation valve (s) for the upper compartment open for more than 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months during a calendar year, close any open valve or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in at least H0T STANDBY within the next

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTD0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifica-tions 4.6.1.9.3 and/or 4.6.1.9.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise 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 .

4

A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 1

3 and 4 following the steam generator replacement outage. The cumulative

, time for having the valves open in Modes 3 and 4 is limited to fourteen (14) l days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 2 3/4 6-13 Amendment No.

Attachment 2 4

Anachm:nt 2 McGuire Nuclear Station Technical Specification Change Page 1 of 11 Proposed Revision to Technical Specifications 3.6.1.1, 3.6.1.2, and 3.6.1.9. ,

l Add the following footnote to the Applicability statement for the affected Technical Specifications:

"A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having ;

the valves open in Modes 3 and 4 is limited to fourteen (14) I days. All other provisions of this specification apply with '

the exception of those containment purge valves open in Modes 3 and 4. Each valve will be sealed closed prior to initial entry into Mode 2."

Proposed Revision to Technical Specification 3.6.1.8.

Add the following footnote to the Applicability statement for the affected Technical Specification: ;

"A one-time change is granted in Modes 3 and 4 to allow repair activities for the containment purge supply and/or exhaust isolation valves for the upper and lower compartment that were I open in Modes 3 and 4 following the steam generator 1 replacement outege."

I

Background

The McGuire Nuclear Station, Units 1 and 2 steam generators will be replaced during outages which are currently scheduled to begin approximately February 7, 1997 and September 28, 1997, respectively. Along with the replacement of the steam generators, there will be modifications to interfacing system piping and supports due to differences in the replacement steam generators.

During the initial heatup of the replacement steam generators and interfacing piping systems, thermal decomposition product (TDP) gases will be produced which could cause a respiratory hazard to personnel. It is expected that the concentration of respiratory hazardous gases inside containment will exceed personnel allowable exposure.

1 l

l 1

1 Anachnmnt 2 McGuire Nuclear Station

' Technical Specification Change Page 2 of 11 A major source of respiratory hazardous gas will be the approximately 13,000 square feet of new fiberglass thermal ;

insulation. The fiberglass thermal insulation has had )

laboratory analysis performed to identify and quantify the TDP gases. One of the TDP gases which is difficult to remove and protect against is carbon monoxide (CO). This is compounded by the fact that McGuire is an ice condenser plant which has a !

smaller' lower containment free air volume that is separated from upper containment. This lower containment compartment )

free air volume is 237,000 cubic feet compared to a typical dry containment which would have a free air volume of

>2,000,000 cubic feet. Because of this, it is projected that the thermal insulation source alone could result in a CO concentration of more than twice the personnel allowable exposure limit in lower containment. Typically respiratory j protection measures would be initiated if the hazardous gas J concentrations equate to above 50% of the exposure limit. The ,

projected CO respiratory hazard would make it impossible for l personnel to enter lower containment without respiratory protection.

Several options were explored as safeguards to address potential respiratory hazards, some of these are:

1. Sending people into containment with respiratory equipment during this period of time,

2. Preheating of the insulation at a vendor facility to )

release the gases before installation, and i I

3. Operation of the Containment Purge (VP) System to exhaust gases.

During the heatup process, personnel routinely enter containment to perform surveillances. After the replacement outage this will be especially_important due to additional surveillances which will be performed because of. changes in the steam generators and associated piping. It is currently planned for personnel to verify support gaps for selected supports in the Reactor Coolant System. These locations will be checked at regular intervals to ensure that there is no equipment damage due to thermal expansion during the heatup.

Personnel will also be required to perform leak checks on piping per ASME Code Case N 416-1.

AMachamnt 2 McGuire Nuclear Station Technical Specification Change Page 3 of 11 Use of respiratory equipment was examined as a possible alternative for solving the personnel access problem. This option was. determined to be impractical because of access requirements and increasing the personnel hazard of heat stress. At primary and secondary system temperatures above 450* F, the thermal insulation will begin to produce TDP gases. At system temperatures exceeding 450 F, lower containment temperature will be approaching 100 F. Many of >

the areas where personnel will be required are very restricted and require a significant physical effort to reach. Access by personnel wearing respiratory personal protective equipment may be unsafe due to adverse temperature and humidity conditions, and difficulty in maneuvering in the tight spaces in lower containment.

Preheating of insulation is not satisfactory as a primary solution because it does not address all expected respiratory hazardous gases. Preheating of the new thermal insulation by the vendor was done for Catawba Unit 1 in an effort to '

eliminate a major portion of the insulation produced TDP gases. Experience from the startup of Catawba Unit 1 following S/G replacement indicated that preheating of the insulation was beneficial but did not eliminate all TDP gases ,

from the insulation. Preheating of'the McGuire insulation is planned. Other sources of respiratory hazardous gases identified as TDP contributors are residues of a) lubricants, ;

b) cutting fluids, _c) cleaning fluids, d) nondestructive l examination gels, e) valve packings and f) hydraulic fluids. I Another non TDP contributor is coatings applied to non-heated I surfaces for which the curing time and securing of the j Containment Purge System overlap. Because of the additional use of these TDP and non TDP contributors and the introduction of the previously unheated metal surfaces to lower containment, the steam generator replacement outage is expected to have a greater quantity of hazardous gases produced in Modes 3 and 4 as compared to rormal refueling l outages.

I' j Purging the containment atmosphere and providing a supply of j fresh air is considered to be the best option available. This j option will allow purging of the containment atmosphere as

necessary during Modes 3 and 4 to ensure air quality meets i applicable standards for personnel safety. The normal means j of purging the containment during operation (the Containment i Air Release and Addition System) will not be sufficient to j serve this purpose because system flow rates are too low. The h

i 1

,, o Anachnmnt 2 McGuire Nuclear Station Technical Specification Change

' Page 4 of 11 ,

Containment Air Release and Addition System is used primarily to keep containment pressure within applicable limits, and provides its interface with upper containment. The release of gases will occur primarily in lower containment, and will

-require the use of a larger capacity. ventilation system to maintain acceptable air quality for personnel habitability.

The Containment Purge system is designed to provide an environment within containment suitable for personnel access during inspection, maintenance, and refueling operations. The Containment Purge System accomplishes these functions by exhausting air from the upper and lower compartments and incore instrumentation room through filters and replacing it with outside air. It was determined that this system could be used successfully to remove gases released during heatup.after replacement of the steam generators.

In order to use the Containment Purge System for this purpose, it is necessary to obtain temporary relief from Technical Specification 3.6.1.9, which requires that the containment isolation valves for this system be sealed closed during Modes 1, 2, 3, and 4. Relief from Technical Specifications 3.6.1.1 and 3.6.1.2 are needed because of the delay in performing the local leak rate test on the containment purge valves. Relief from Technical Specification 3.6.1.8 is needed to allow maintenance on the containment purge valves following purging and prior to entry into Mode 2. Maintenance could be necessary in meeting the leakage criteria of Tech Spec 3.6.1.2. As discussed previously, containment habitability needs to be maintained during heatup. Hazardous gases will q be produced through Mode 3, after the period of time where l Containment Purge Operation is currently not allowed. The Unit could be heated up, and then shut down to Mode 5 to allow purging, but this would not allow personnel access to perform surveillances during the unit heatup. This course of action would also add to tha number of heatup and cool down cycles for which the plan; is designed. There is also the concern that it would be firficult to determine when off gassing is complete.

Technical Justification Analyses have been performed to justify the operation of the Containment Purge System in Modes 3 and 4 following the steam

Attachnent 2 McGuire Nuclear Station Technical Specification Change i Page 5 of 11 generator replacement outage. The following initial conditions were assumed:

The unit is in Mode 3 following a 70 day outage;

A new cycle is in the reactor core (Approximately 1/3 of the fuel assemblies are unirradiated ), and e The Containment Purge System is in operation.

An analysis was performed to determine bounding conditions in the core following a postulated design basis LOCA. The licensing basis analysis of LOCA in which the ECCS is assumed to be available consistent with the minimum safeguards assumptions remains valid; however, for added conservatism, the analysis included calculations in which no credit was I taken either for the Emergency Core Cooling System (ECCS) or for convective heat transfer in the reactor vessel.

Calculations showed that the source term available for release upon fuel heatup and melting would be significantly reduced as a result of the extended shutdown and the presence of new fuel. Furthermore, it was demonstrated that for the same reasons decay heat would be a small fraction of the decay heat associated with full power operations. With this information, it was shown that without any cooling (unavailability of the ECCS and no credit taken for convective heat transfer), there is a protracted period of time (at least 60 minutes) into this event sequence for the operators to initiate recovery before the source term appears in significant amounts or significant ;

fuel damage occurs. A constant supply of either steam or air '

to the core, either free or forced convection will prevent I both fuel damage and source term availability. The ECCS flow rate required to remove the decay heat generated in this event sequence is well within the capacity of any single ECCS pump.

Finally, calculations were performed to show that with credit taken for convective heat transfer, the fuel will not be heated to temperatures required to cause the release of significant amounts of source term from the fuel or a significant level of fuel damage. From this analysis, it is concluded that the likelihood of either significant level of i fuel damage or release of significant amounts of activity from l

the fuel is reduced due to the extended shutdown and the presence of unirradiated fuel in the core.

Calculations were performed by both Duke Power Company and the manufacturer of the Containment Purge containment isolation l

i Anachnunt 2 McGuire Nuclear Station Technical Specification Change Page 6 of 11 i valves to determine whether the valves would close under loads l associated with a Chapter 15 design basis LOCA. The assumptions in these calculations are consistent with the minimum safeguards assumption in the analysis reported in the McGuire UFSAR. The manufacturers' calculation employs a series of controlled laboratory flow tests on representative valves in an approach that mirrors EPRI's performance 4 prediction program. This is done to ensure that data and conclusions predicted by the calculation apply to the valves in the field. Calculations based on the resultant pressure drops were performed by the manufacturer of the Containment Purge containment isolation valves to determine the responses of the valves. It was determined that the inboard valves will close from any initial position. It was found that the outboard valves will close from any position up to and including 80 open. From this analysis, it is apparent that for initial conditions up to and including 80 open, the flow through the containment penetration " assists" the valves to close. The additional condition on the outboard valves is attributed to a higher calculated value of pressure drop across them than for the inboard valves, given compressible flow through the penetrations.

The actuators for the outboard valves will be modified to limit the travel of these valves to 80 open. It was determined that the structural integrity of the valves would not be adversely affected as they closed under the loads associated with the DBLOCA. It also was demonstrated that the Reactor Building integrity would not be challenged as a result of transport of either air or a mixture of steam and air through the Containment Purge Ventilation System containment penetrations before the isolation valves are projected to close.

The Containment Purge Ventilation System containment isolation valves and actuators are "QA Condition 1", safety related, Seismic Category I. The manufacturer confirmed that these actuators can perform the safety function to fail closed to isolate containment under all design basis loads, including those associated with the safe shutdown earthquake. The controls which cause the valves to fail closed are safety related, Class 1E, seismic. Finally, from the analysis 4

(reported above) of the response of the VP containment valves to conditions associated with the blowdown phase of the LOCA, it was determined that the torque required to close these valves from any initial position up to and including 80 open

. - - - - - . . - - - - = - - - _. - - . . . - . - - . . . - - - .

.t .' .

4 Anachnent 2 i McGuire Nuclear Station i Technical Specification Change Page 7 of 11 0,

is negative. The valves are " flow assisted" to close.

Therefore, even in the postulated event of a failure of the actuators to perform their intended function, the valves would close in a LOCA.

Calculations were performed to determine the upper bounds to

. the doses to the Exclusion Area Boundary (EAB), the Low i Population Zone (LPZ), and the Control Room for the above i sequence. The source term available for release is consistent with the TID 14844 methodology, with credit taken for the addition of new fuel and a 70 day decay of fuel after shutdown. Minimum safeguards were assumed. In particular, one train apiece of the Containment Spray System, the Containment Air Return System, the Auxiliary Building Exhaust System, and the Control Room Ventilation System was assumed to be available. No credit was taken for scrubbing of the containment atmosphere in the ice condenser. The VP containment isolation valves were assumed to close. However,

, leakage past the valves was assumed to occur for the entire period of time over which the radiation doses were calculated.

Initial values of leakage as high as 100% of the containment 2

volume per day were ascumed arbitrarily. Limiting doses were calculated to be as follows:

i Doses to the EAB Guideline Values (10 CFR 100)

! Whole Body Dose: 0.0692 Rem 25 Rem-Thyroid Dose: 88.3 Rem 300 Rem Doses to the LPZ Whole Body Dose: 0.0219 Rem 25 Rem Thyroid Dose: 18.5 Rem 300 Rem Doses to the Control Room Guideline Values (GDC 19, SRP 6.4)

Whole Body Dose: 0.012 Rem 5 Rem

, Skin Dose 5.39 Rem 75 Rem

Thyroid Dose 5.61 Rem 30 Rem

applicable with eye protection The doses reported above are comparable to the results of the I

licensing basis calculations. In addition, both the Offsite doses and the doses to the Control Room operators are within the corresponding guideline values by a significant margin, even with an arbitrarily high value taken for the containment leakage, and without credit taken for removal of radioactivity by the ice condenser. This may be attributed to the low

- - . . - , - . - - - . . - . - - - - -. - - . - -.-..=. . - - - -

t .' .

l

Attachment 2 McGuire Nuclear Station

, Technical Specification Change l~ Page 8 of 11 magnitude of the source term for this event sequence compared to a DBA occurring with the reactor initially at full power.

4-4 COMPENSATORY ACTIONS J

The Containment Purge and Ventilation System is described in Section 9.4.5 of the McGuire UFSAR. Containment Purge is

. automatically isolated on a containment isolation, safety injection, or high radiation signal. These functions are required operable per Technical Specifications 3.3.2 and 3.3.3.1.

-Operation of the Containment Purge and Ventilation System will .

be conducted under administrative controls. A procedure will I

be specifically written to control and monitor purging operations. It will include control of the supply and exhaust fans and dampers and monitoring of Containment pressure, Ice Condenser temperature and Ice Condenser door position. It will also include contingency measures in the event of system leaks inside containment, ice condenser door openings or other events that would potentially necessitate manually securing

Containment purge prior to automatic isolation on high radiation, safety injection or containment isolation signals.

Prior to entry into Mode 4, the containment purge supply and exhaust isolation valves that will be open for Containment purge will be stroke time tested (5 second closure). Spring

, torque output will also be measured.

Prior to entry into Mode 4, the containment purge supply and exhaust isolation valves that were open for Containment purge will be local leak rate tested. The local leak rate test will be repeated prior to entry into Mode 2.

The refueling Boron concentration (as required by Tech Spec 3.9.1) will be maintained until satisfactory local leak rate testing of all purge valves.

In the unlikely event of significant Reactor Coolant System leakage and failure of a Containment Purge isolation valve, eye protection will be provided to Control Room personnel by '

Radiation Protection personnel if beta activity or noble gases are detected in the Control Room.

.t AMachmant 2 McGuire Nuclear Station Technical Specification Change Page 9 of 11 NO SIGNIFICANT HAZARDS EVALUATION The operation of the VP System associated with the proposed change has been evaluated against the standards of 10 CFR 50.92. The results of the evaluation of this activity are as follows:

1) The activity does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The VP System has no interfaces with any primary system, secondary system, or power transmission system. It has no interfaces with any reservoir of radioactive gases or liquids.

None of the systems listed above are modified by the activity.

In summary, no " accident initiator" is affected with the proposed operation of the VP System in Mode 3 and 4. For this reason, the activity does not involve an increase in the probability of an accident previously evaluated.

Analyses have been performed to determine upper bounds to the source term, the offsite doses, and the Control Room dose.

The results of that analyses are reported above. Both the source term and the doses were found to be significantly lower than the results of the corresponding design basis analyses.

In addition, it has been determined that with no credit taken for any heat transfer from the fuel and cladding to the moderator channels, that sufficient time would exist for the operators to initiate recovery of flow from the ECCS tx) the reactor core. The flow required from the ECCS to maintain the core in a coolable geometry was found to be well within the capacity of any one ECCS pump. Furthermore, it was determined that convective heat transfer to steam would be sufficient to prevent release of significant source term or a significant degree of fuel damage.

For the above reasons, it is determined that operation of the VP System in Mode 3 or 4 immediately following the steam generator replacement outage does not involve a significant increase in either the probability or the consequences of an accident previously evaluated.

2) The activity does not create the possibility of a new or different type of accident from any accident previously ,

evaluated. I 1

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Anachmsnt 2 McGuire Nuclear Station Technical Specification Change Page 10 0f 11 As discussed above, no " accident initiators" are affected by the proposed activity. Operation of the VP System proposed for Modes 3 and 4 will be the same as that routinely carried in other' modes of operation. For these reasons, the activity will not create the possibility of a new or different type of accident from any previously evaluated.

3) The activity does not involve a significant reduction in the margin - of safety.

Margin of safety is associated with confidence in the ability of the fission product barriers (the fuel and fuel cladding, the Reactor Coolant System pressure boundary, and the containment) to limit the level of radiation doses to the public. The proposed operation of the VP System will occur at the end of an extended outage. The level of decay heat and activity in the reactor is very low compared to the level of decay heat and activity associated with full power operations.

For this reason, the likelihood of damage to the fuel following a DBLOCA occurring during the proposed purging is reduced, as determined above. Both offsite doses and doses to the Control Room were found to be small compared to the limits of 10 CFR 100 and GDC 19. For these reasons, the activity does not involve a significant reduction in the margin of safety.

Environmental Impact Assessment This change to the Technical Specifications will allow the Containment Purge System to be operated during startup from the steam generator replacement outage. The Containment Purge and Annulus Ventilation Systems exhaust air from the containment and annulus, respectively, through high efficiency filters and radiation monitoring devices before exhausting it through the respective unit's ventilation stack. It has been determined that this amendment will not involve a significant hazards consideration, there is no significant change in the types _or significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in the individual or cumulative occupational radiation exposure. This amendment request therefore meets the criteria of 10 CFR 51.22. (c) (9) for categorical exclusion from an environmental impact statement.

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McGuire Nuclear Station i Technical Specification Change l Page 11 of 11 1

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j Commaittee. Reviews ,

3 This proposed change to the Technical Specifications has been reviewed and approved.by the McGuire Plant Operations Review l j Committee and the Nuclear Safety Review. Board. I 3

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ML20133D399

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