Text

Amends 174 & 156 to Licenses NPF-9 & NPF-17,respectively, Revising Portions of TS to Permit one-time Operation of Containment Purge Ventilation Sys During Modes 3 & 4 After SG Replacement Outages
	ML20138B535
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/24/1997
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20138B538	List: ML20138B535; ML20138B552;
References
	NUDOCS 9704290194
	Download: ML20138B535 (14)
	v • d • e

'*09 g

t UNITED STATES s

j NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20056-0001

\\...../

DUKE POWER COMPANY DOCKET NO. 50-369 MCGUIRE NVCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. NPF-9 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company, dated January 6, 1997, as supplemented by letters dated April 10 and 15, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

9704290194 970424 PDR ADOCK 05000369 P

pan

1-2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license 4

amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:

Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.174

, which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION c

H bert N. Berkow, Director roject Directorate 11-2 1

Division of Reactor Projects - I/II Office of Nuclear. Reactor Regulation

Attachment:

Technical Specification l

Changes Date of Issuance:

April 24, 1997 i

i

i ATTACMENT TO LICENSE AMENDMENT NO.174 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-11 3/4 6-11 4

3/4 6-13 3/4 6-13 l

1

..x

-a a

_,.s_

a as

-a..a.a x w s

s --

w a

CONTAINMENT SYSTEMS j

CONTAINMENT LEAXAGE LIMITING CONDITION FOR OPERATION l

3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of 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, I

b.

A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, when pressurized to P,

and

{

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

tions identified as secondary containment bypass leakage paths when pressurized to P,.

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

l 1

j ACTION:

With (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) the measured combined leakage rate for all penetrations and bypass leakage rate exceeding 0.07 L bined leakage or (c) the combined

, restore the overa rate to less than 0.75 L and the com and valves subject to Ty,pe B and C tests to less than 0.60 L combined bypass leakage rate to less than 0.07 L, prior to in, and the 3.

creasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 Type A containment leakage rates shall be demonstrated as required by 10 CFR 50.54(o) and Appendix J of 10 CFR 50, Option B, as modified by approved exemptions, and in accordance with the guidelines of Regulatory Guide 1.163, September, 1995.

i t

j

A one-time change is granted to have the containment purge supply and/or exhtust 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 6-2 Amendment No.174

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. ***

&GILQN:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or 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 .

SURVEILLANCE REOUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations

not t

capable of being closed by OPERABLE containment automatic isolation j

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 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 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.,hese seals is14.8 psig, and verifying that when the measured leakage rate for t 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 of ten 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 1 3/4 6-1 Amendment No.174

CONTAlhMfJC SYSTEM 3 1"JLUS VENTILATION T,' STEM LIMITING CONDITION FOR OPERATION 3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.

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

.s AfJ195:

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 a.

the inoperable system to OPERABLE status within 7 days or be in at l

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 .

With the )re-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable, b.

restore tie 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 Each Annulus Ventilation System shall be demonstrated OPERABLE:

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

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; At least once per 18 months, or (1) after any structural maintenance b.

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

cating wit Verifying that the ventilation system satisfies the in-place 1) 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.S.d of Regulatory Guide 1.52, i

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

10%;

Verifying within 31 days after removal that a laboratory anal-2) ysis of a representative carbon sample obtained in accordance with Pegulatory 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 Verifying a system flow rate of 8000 cfm

10% during system 3) operation when tested in accordance with ANSI N510-1975.

A one-time che9e 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 ontage.

McGUIRE - UMLT 1 3/4 6-11 Amendment No. 174

I-CONTAlletENT SYSTEMS CONTAlletENT VENTILATION SYSTEM i

~

LIMITING CONDITION FOR OPERATION j

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

OPERABLE and:

Each containment purge su) ply and/or exhaust isolation valve for the a.

Iower compartment (24-inct) and instrument room (12-inch and 24-inch)shallbesealedclosed,and b.

Thecontainmentpurgesupplyand/orexhaustisolationvalve(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 u

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

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

ACTION:

With any containment purge supply and/or exhaust isolation valve for l

a.

the lower compartment or instrument room open or not sealed closed, close and/cr 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 STAND 8Y 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 .

b.

Withthecontainmentpurgesupplyand/orexhaustisolationvalve(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 te 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 .

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

having a measured leakage rate in excess of the limits of Specifica-tions4.6.1.9.3and/or4.6.1.9.4,restoretheinoperablevalve(s)to 4

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 1

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 i

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

i l

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. 174

i M**u p

UNITED STATES y

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. asseHop1

\\...../

DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 l

AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. NPT-17 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the 4

_ Duke Power Company (licensee) dated January 6, 1997, as supplemented by letters dated April 10 and 15,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i

Commission; C.

There is reasonable assurance (1) that the activities-authorized by this amendment can be conducted without endangering the health and 1

safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and 4

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

i 4

-~

w

.m

. 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.156

, are hereby incorporated into this license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION Qy

/

H rbert N. Berkow, Director s

Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

April 24, 1997 i

ATTACHMENT TO LICENSE AMENDMENT NO.

156 FACILITY OPERATING LICENSC NO. NPF-17 DOCKET NO. SQ-J22 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-11 3/4 6-11 3/4 6-13 3/4 6-13 1

.d l

r 3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAIMENT INTEGRITY LINITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICA3ILITY: MODES 1, 2, 3, and 4. *"

EI13:

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 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAIMENT 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 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 c.

After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or 8 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

)

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.156

-a,~

,,,w---,,,--,

t CONTAIMENT SYSTEMS CONTAIMENT LEAKAGE l

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

An overall integrated leakage rate of less than or equal to L.,

a.

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, b.

A combined leakage rate of less than 0.60 L for all penetrations andvalvessubjecttoTypeBandCtests,whenpressurizedtoP, and A combined bypass leakage rate of less than 0.07 L, for all penetra-c.

tions identified as secondary containment bypass leakage paths when pressurized to P,.

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

l ACTION:

With (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L.,ll integrated leakag or (c).the combined bypass leakage rate exceeding 0.07 L.bined leakage rate for all penetrations

, restore the overa rate to less than 0.75 L and the com and valves subject to Ty,pe B and C tests to less than 0.00 L, and the combined bypass leakage rate to less than 0.07 L, prior to in, creasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE RE0VIREMENTS 4.6.1.2 Type A containment leakage rates shall be demonstrated as required by 10 CFR 50.54(o) and Appendix J of 10 CFR 50, Option B, as modified by approved exemptions, and in accordance with the guidelines of Regulatory Guide 1.163, September, 1995.

f

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. 156

i

~

CONTAlletENT SYSTEMS i

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

4 l

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

M' With one Annulus Ventilation System inoperable for reasons other i

a.

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 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 .

i With the >re-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable, b.

restore tse 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 OPCRABLE status, 4

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

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

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; At least once per 18 months, or (1) after any structural maintenance b.

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

Verifying that the ventilation system satisfies the in-place 9

1) penetration and bypass leakage testing acceptance criteria of a.

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 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 l

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 i

the containment purge supply and/or exhaust isolation valves for the upper and lower compartment that care open in Modes 3 and 4 following the steam generator replacement outage.

McGUIRE - UNIT 2 3/4 6-11 Amendment No.156 i

1 i

~

CONTAllefENT SYSTEMS CONTAlletENT VENTILATION SYSTEM 1

LIMITING C6NDITION FOR OPERATION Each containment purge supply and/or exhaust isolation valve shall be 3.6.1.9 OPERA 8LE and:

Each containment purge supply and/or exhaust isolation valve for the l

a.

lower compartment (24-inch) and instrument room (12-inch and 24-inch) shall be sealed closed, and

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

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 i-andoneexhaust)areopenatonetime.

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

l AGIl05:

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

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 .

With the containment pdrge supply and/or exhaust isolation valve (s) b.

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 o>en valve or isolate the penetration (s) i within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise )e in at least HOT STAN08Y within the next i

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

With a containment purge supply and/or exhaust isolation valve (s) 6 l

c.

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 l

OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise be in at least NOT STANOBY 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

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 l

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

time for having the valves open in Modes 3 and 4 is limited to fourteen (14)

All other provisions of this specification apply with the exception days.

Each valve will be of those containment purge valves open in Modes 3 and 4.

sealed closed prior to initial entry into Mode 2.

McGUIRE - UNIT 2 3/4 6-13 Amendment No.156 '

--

ML20138B535

Text

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