ML20246P149

Amends 144 & 146 to Licenses DPR-44 & DPR-56,respectively. Amends Revise Tech Specs to Incorporate 90 H Purging Restriction,Addl Tech Spec for Containment Purge & Vent Isolation Valves

ML20246P149
Person / Time
Site:	Peach Bottom
Issue date:	05/08/1989
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246P155	List: ML20246P149 ML20246P164
References
NUDOCS 8905220100
Download: ML20246P149 (18)

Text

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UNITED STATES 8'

NUCLEAR REGULATORY COMMISSION L

n WASHINGTON, D, C. 20555

....../

PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTCM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. DPR-44 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 31, 1979 as amended on June 4, 1984 and September 15, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 Commission; 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 Commission's regulations; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

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(2)

Technical Specifications i

The Technical Specifications contained in Appendices A'and B, as revised through Amendment No.144, are hereby incorporated in-the license.- PECO shall operate the facility in accordance with the

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Technical Specifications.

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3.

ThislicenseamendmentiseffEctivewithin60daysofitsdateofissuance except that the inflatable seal program.specified in Technical

-Specification 4.7.E.1 shall become effective during the first refueling outage commencing six months.following issuance of thisjamendment.

FOR'THE NUCLEAR REGULATORY = COMMISSION

-/s/

Walter R; Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical

' Specifications Date of Issuance: May 8, 1989 l

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(2)

Technical Specifications

~The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 144, are hereby incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

-This license amendment is effective within 60 days of its date of issuance except that the inflatable seal program specified in Technical Specification 4.7.E.1 shall become effective during the first refueling outage commencing six months following issuance of this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION N

2/W

+

Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specif. etions Date of Issuance: May 8, 1989 s

l l

ATTACHMENT'T0 LICENSE AMENDMENT NO.

144 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the. Appendix A Technical Specifications wish.

the enclosed pages. The revised areas are indicated by marginal'11nes.

Remove Insert 175 175 177 177-178 178 178a 202 202

PBAPS UNIT 2 1

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j

3.7.B.

Standby Gas Treatment System 4.7.B.

Standby Gas Treatment System I

1.

Except as specified in 1.

At least once per operating 3.7.B.3 below, both filter cycle, the following condi-trains of the Standby Gas tions sbil be demonstrated.

Treatment System and at least two system fans a.

Pressure drop across shall be operable at all the combined HEPA filters times when secondary and charcoal absorber containment integrity banks is less than 8 is required.

Only one of inches of water at the two Standby 6as Treat-approximately 8,000 CFM.

ment System (SGTS) trains shall be used at a time b.

Inlet heater is l

for primary containment capable of providing purge / vent operations at least 40 KW.

using the large isolatiori valves.

Both SGTS trains 2.a. The test and sample analysis shall be operable as required of Specification 3.7.B.2 by Specification 3.7.E.

shall be performed initially and at least once per year 2.a. The results of the in-for standby service; or place cold DOP and after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of halogenated hydrocarbon filter train operation; or tests at approximately 8000 following significant CFM on HEPA filters and painting, fire or chemical charcoal adsorber banks release in any ventilation shall show >/= 99% D0P zone communicating with the removal and >/= 99%

system when it is in operation.

halogenated hydrocarbon removal or that filter

b. Cold DOP testing shall be train shall not be performed after each complete considered operable.

or partial replacement of the HEPA filter bank orafter any

b. The results of Laboratory structural maintenance on the carbon sample analysis shall system housing.

show >/= 95% radioactive methyl I

iodide removal at a velocity

c. Halogenated hydrocarbon refrig-within 20% of system design, erant testing shall be performed 0.5 to 1.5 mg/m3 inlet methyl after each complete or partial iodide concentration, >/=70%

replacement of the charcoal relative humidity and >/=190 adsorber bank or after any I

degrees F or that filter structural maintenance of the l

train shall be considered system housing.

inoperable.

I c.

If gas finw capability of

d. Testing of gasket seals for 8,000 CFM +/-800 CFM can housing doors downstream of not be provided to a filter the HEPA filters and charcoal train by the fans, that adsorbers shall be performed filter train shall not be at and in conformance with each j

considered operable.

test performed for compliance with Specification 4.7.B.2.a.

1 Amendment No.144

- 175 -

4 L

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D Primary Containment 4.7.D Primary Containment Isolation Valves Isolation Valves 1.

During reactor power operating 1.

The primary containment conditions,.all isolation isolation valve surveillance valves listed in Table 3.7.1 shall be performed as follows:

and all reactor instrument line excess flow check valves a.

At least once per shall be operable except as operating cycle the operable specified in 3.7.D.2 and isolation valves that are 3.7.D.3 below.

power operated and automatically initiated shall be tested 2.

In the event any isolation for sioulated automatic valve specified in Table 3.7.1 initiation and closure becomes inoperable for isolation, times.

maintain at least one isolation valve operable in the affected b.

At least-o.n.ce per quarter:

penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

(1) All normally open power operated isolation a.

Restore the inoperable valve valves (except for to operable status, or the main steam line power operated b.

Isolate the affected penetra-isolation valves) tion by use of at least shall be fully closed one deactivated automatic and reopened.

valve secured in the isolation position *, or (2) With the reactor power less than 75% trip main c.

Isolate the affected penetra-steam isolation valves tion by use of at least individually and verify one closed manual valve

• closure time.

or blind flange.

c.

At least once per week the d.

Otherwise be in at least Hot main steam line power-operated Shutdown within the next isolation valves shall be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown exercised by partial closure j

within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

and subsequent reopening.

l 2.a. Whenever an isolation valve listed in Table 3.7.1 is

)

inoperable, the position of at least ene other valve in each line having an inoperable valve j

shall be recorded daily.

]

l

b. The isolation valves specified in Table 3.7.1 shall be demonstrated to be operable prior to returning to service after maintenance on or replace-

• Isolation valves closed to ment of the valve, actuator, satisfy these requirements may control or power circuit by be reopened on an intermittent performance of a cycling test, basis un+

administrative control.

and verification of isolation timt l Amendment No.144

- 177 -

PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.

If any reactor instrumentation

'3. At least once per operating line excess. flow check cycle the operability of l

valve is inoperable, within the reactor coolant system l

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

instrument line flow check valves shall be verified.

a.

Restore the inoperable excess flow check valve to operable status or, b.

Isolate the instrument line and declare the associated instrument inoperable.

c.

Otherwise be in at least Hot Shutdca within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.7.E Large Primary Containment 4.7.E Large Primary Containment Purge / Vent Isolation Valves Purge / Vent Isolation Valves 1.

The large primary containment 1.

The inflatable seals for purge / vent isolation valves the large containment venti-(6 and 18 inches) shall be lation isolation valves operated in accordance with shall be replaced at specification 3.7.D and with least once every third specifications 3.7.E.2 and refueling outage.

3.7.E.3 below.

2.

When the reactor pressure is 2.

The LLRT leak rate for greater than 100 psig, and the large containment the reactor critical, ventilation isolation and the reactor mode valves shall be compared to switch in the "Startup" or the previously measured leak "Run" mode, primary contain-rate to detect excessive ment purging or venting shall valve degradation.

be subject to the following restrictions:

a.

The large primary containment purge / vent isolation valves may be opened only for inerting, de-inerting, and pressure control.

b.

The accumulated time a purge or vent flow path exists shall be limited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per calendar year.

l Amendment No. 144

- 178 -

i l

3 Unit 2 PBAPS

' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

'c.

The flow paths. subject to this specification are listed below:

. Penetration Flow Path Valves N25.

A0-2505 - A0-2520 A0-2519 - A0-2520 N26 A0-2506 - A0-2507 N205B A0-2521A - A0-2521B A0-2519 - A0-2521B N219 A0-2511 - A0-2512 d.

Only one of two Standby Gas Treatment Systems (SGTS),

trains shall be used for purging or venting at any time.

e.

Both SGTS trains shall be operable.

3.

If the provisions of specification 3.7.E.2 cannot be satisfied, isolate the penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Amendment No.144

- 178a -

PBAPS Unit 2 Large Primary Containment Purce/ Vent isolation Valves 1

The large containment purge / vent isolation valves are subject to the restrictions of Specification 3.7.E.2 to limit the total time that a flow path exists through certain containment penetrations.

Consequently, the impact on plant risks resulting from a LOCA while purging and the potential for failure of the Standby Gas Treatment System contribute little to the likelihood of an uncontrolled radioactive release.

Additionally, containment purging is permitted only for inerting, de-inerting, and pressure control of the containment environment.

Included within the scope of de-inerting is the need to purge containment to ensure personnel safety during the performance of inspections beneficial to nuclear safety; e.g., inspection of primary coolant integrity during plant startups and shutdowns.

Adjustments in primary containment pressure to perform tests such as the drywell-to-torus bypass leakage test are included within the scope of pressure control purging.

Purging for humidity and temperature control using _

the large valves is excluded by the specification.

.The T-ring inflata'ble seal in the valves assures very low rates of leakage.

Following valve closure, the seal chamber is automatically I

pressurized, establishing a tight seal against the periphery of the closed butterfly disc. - The seal is subject to some compression set over a period of time due to radiation and temperature effects.

This phenomena will not be a problem for the Peach Bottom valves because the inflatable T-ring seal maintains a constant and uniform sealing compression.

However, as a preventive maintenance measure, the seals will be replaced every third refueling outage, which approximates the manufacturer's recommendations of every four years.

W Amendment No. 30,144

- 202 -

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UNITED STATES 8"

' g NUCLEAR REGULATORY COMMISSION n

i WASHINGTON, D. C. 20655 PHILADELPHIA ELECTRIC COMPANY' PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-?78 PEACH BOTTOM ATOMIC P,0,WER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.146 License No. DPR-56 1.

The Nuclear Regulatory Commission (the Commission) hcs found that:

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 31, 1979 as amended on June 4, 1984 and September 15, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 Commission; 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 Commission's regulations; D.

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of I

the Commission's regulations and all applicable requirements have been l

satisfied.

)

4 2.

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

)

and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby j

amended to read as follows:

1 I

1 i

+,,

(2). Technical Specifications The> Technical-Specifications contained'in Appendices-A and-D, as.

revised through Amendment No.146,' are hereby incorporated in the.

license.

PECO shall operate the facility in accordance with the Technical Specification.

3.

'This... license amendment is effective within 60 daysiof.its date of issuance except that the.-inflatable seal program specified in Technical

' Specification 4.7.E.1 shall become effective ~during.the first refueling outage commencing six months following issuance of this' amendment.

FOR THE NUCLEAR REGULATORY COMMISSION-

/s/

Walter R. Butler, Director

. Project Directorate.I-2

'l

~!

Division'of Reactor Projects I/II-ttachment:.

Changes to the_ Technical-Specifications Date of= Issuance: May 8, 1989 f

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a- (2).

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146, are hereby incorporated in' the license. PECO shall operate the facility in accordance with the Technical-Specifications.

3.

This license amendment is effective within 60 days of its date of issuance except that the inflatable seal program specified in Technical Specification 4.7.E.1 shall become effective during the first refueling outage' commencing six months following issuance of this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION

$ht A Sn$u Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: May 8, 1989 l-1

.- c n

ATTACHMENT TO LICENSE AMENDMENT NO.~

146 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET N0. 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove '-

Insert 175 175 177 177 178 178 178a 202 202 i

i ~

l l

1

s q

l PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Standby Gas Treatment-System 4.7.B.

Standby Gas' Treatment System 1.

Except as specified in 1.

At least once per operating

-3.7.B.3 below, both filter cycle, the following condi-

. trains of the Standby Gas tions shall be demonstrated.

Treatment System and at least two system fans a.

Pressure drop across 1

shall be: operable at~all the combined HEPA filters

-times when secondary and charcoal absorber

- containment integrity banks is less than 8 3

is required.

Only one of inches of. water at

]

the two Standby Gas Treat-approximately 8,000 CFM.

ment System (SGTS) trains shall be used at a time b.

Inlet. heater is 1

for primary containment capable of providing purge / vent operations-at least 40 KW.

8 using the large isolation i

valves.' Both SGTS trains

~2.a. The test and sample analysis j I

shall be operable as required of Specification 3.7.B.2 I

by Specification 3.7.E.

shall be performed initially and at least once per year 2.a. The results of the in-for standby service; or place cold 00P and after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of halogenated hydrocarbon filter train operation; or tests at approximately 8000 following significant CFM on HEPA. filters and painting, fire or chemical charcoal adsorber banks release in any ventilation shall show >/= 99% DOP zone communicating with the removal and >/= 99%

system when it is in operation.

halogenated hydrocarbon removal or that filter

b. Cold DOP testing shall be train shall not be performed after each complete considered operable.

or partial replacement of the HEPA filter bank after any

b. The results of Laboratory structural maintenance on the carbon sample analysis shall; system housing.

show >/= 95% radioactive methyl iodide removal at a velocity

c. Halogenated hydrocarbon refrig-within 20% of system design, erant testing shall be performed 0.5 to 1.5 mg/m3 inlet methyl after each complete or partial iodide concentration, >/=70%

replacement of the charcoal relative humidity and >/=190 adsorber bank or after any degrees.F or that filter structural maintenance of the train shall be considered system housing, inoperable.

c.

If gas flow capability of

d. Testing of gasket seals for 8,000 CFM +/-800 CFM can housing doors downstream of not be provided to a filter the HEPA filters.and charcoal.

train by the fans, that adsorbers shall be performed filter train shall not be at and in conformance with each considered operable.

test performed for compliance l

with Specification 4.7.B.2.a.

Amendment No.146

- 175 -

7 PBAPS Unit 3

-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D Primary Containment 4.7.D Primary Containment Isolation Valves Isolation Valves

.l 1.

During reactor power operating 1.

The primary containment-conditions ~, all isolation isolation valve surveillance valves listed in Table 3.7.1 shall be performed as follows:

and all reactor instrument line excess flow check valves a.

.At least once per shall be operable except as operating cycle the operable specified in 3.7.D.2 and isolation valves.that are 3.7.D.3 below.

power operated and automatically 0

initiated shall be tested 2.

In the event any isolation for simulated automatic valve specified in Table 3.7.1 initiation and closure-becomes inoperable for isolation,

times, maintain at least one isolation.

valve' operable in the affected b.

At least once per quarter:

penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

(1) All normally open power operated isolation a.

Restore the inoperable valve valves (except for to operable status, or the main steam line l

power operated a

b.

Isolate the affected penetra-isolation valves) tion by use of at least shall be fully closed one deactivated automatic and reopened.

valve secured in the isolation position *, or (2) With the reactor power less than 75% trip main c.

Isolate the affected penetra-steam isolation valves tion by use of at least individually and verify.

one closed manual valve

• closure time, or blind flange.

i c.

At least once per week the d.

Otherwise be in at least Hot main steam line power-operated Shutdown within the next isolation valves shall be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown exercised by partial closure within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

and subsequent reopening.

l-2.a. Whenever an isolation valve listed in Table 3.7.1 is inoperable, the position of at least one other valve in each line having an inoperable valve shall be recorded daily.

b. The isolation valves specified in Table 3.7.1 shall be demonstrated to be operable prior to returning to service after maintenance on or replace-

• Isolation valves closed to ment of the valve, actuator, satisfy these requirements may control or power circuit by be reopened on an intermittent performance of a cycling test, basis under administrative control, and verification of isolation tim.

Amendment No. 146 777 1

. e, -

PBAPS Unit 3 i

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.

If any reactor instrumentation

3. At least once per operating line excess flow check cycle the operability of valve is inoperable, within the reactor coolant system 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

ir,strument line flow check valves shall be verified.

a.

Restore the inoperable excess flow check valve to operable status or,,

b.

Isolate the instrument line and declare the associated instrument inoperable.

c.

Otherwise be in at least Hot Shutdown within the

~

next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.7.E Large Primary Containment 4.7.E Large Primary Containment Purge / Vent Isolation Valves Purge / Vent Isolation Valvet 1.

The large primary containment 1.

The inflatable seals for purge / vent isolation valves the large containment venti-(6 and 18 inches) shall be lation isolation valves

. operated in accordance with shall be replaced at specification 3.7.D and with least once every third specifications 3.7.E.2 and refueling outage.

3.7.E.3 below.

2.

When the reactor pressure is 2.

The LLRT leak rate for greater than 100 psig, and the large containment the reactor critical, ventilation isolation and the reactor mode valves shall be compared to switch in the "Startup" or' the previously measured leak "Run" mode, primary contain-rate to detect excessive

]

ment purging or venting shall valve degradation.

1 s

be subject to the following i

restrictions:

i I

.a.

The large primary containment j

purge / vent isolation valves i

may be opened only for j

inerting, de-inerting, and l

pressure control.

b.

The accumulated time a purge or vent flow path exists shall be limited to 90 houra per calendar year.

l Amendment No.146

- 178 -

A

j.

Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS k

F c.

The flow paths subject to this specification are listed below:

Penetration Flow Path Valves N25 A0-3505 - A0-3520 A0-3519 - A0-3520 N26 A0-3506 - A0-3507 i

N205B A0-3521A - A0-3521B A0-3519 - A0-3521B N219 A0-3511 - A0-3512 d.

Only one of two Standby-Gas i

Treatment Systems (SGTS) trains shall be used for purging or venting at any time.

e.

Both SGTS trains shall be operable.

3.

If the provisions of specification 3.7.E.2 cannot be satisfied, isolate the penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 i

i i

Amendment No.146 17g,_

1 m

---_-__.______-____.___---.___._______.m

i, PBAPS Unit 3

~

Large Primary Containment Purge / Vent isolation Valves The large containment purge / vent isolation valves are subject to the restrictions of Specification 3.7.E.2 to limit the total time that a flow path exists through certain containment penetrations.

Consequently, the impact on plant risks resulting from a LOCA while purging and the potential for failure of the Standby Gas Treatment System contribute little to the likelihood of an uncontrolled radioactive release.

Additionally, containment purging is permitted only for inerting, de-inerting, and pressure control of the containment environment.

Included within the scope of de-inerting is the need to purge containment to ensure personnel safety during the performance of inspections beneficial to nuclear safety; e.g., inspection of primary coolant integrity during plant startups and shutdowns.

Adjustments in primary containment pressure to perform tests such as the drywell-to-torus bypass leakage test are included within the scope of pressure control purging.

Purging for humidity and temperature control using the large valves is excluded by the specification.

The T ring inflatable seal in the valves assures very low rhes of leakage.

Following valve closure, the seal chamber is automatically pressurized, establishing a tight seal against the periphery of the closed butterfly disc.

The seal is subject to some compression set over a period of time due to radiation and temperature effects.

This phenomena will not be a problem for the Peach Bottom valves because the inflatable T-ring seal i

maintains a constant and uniform sealing compression.

However, as a preventive maintenance measure, the seals will be replaced every third refueling outage, which approximates the manufacturer's recommendations of every four years.

1 Amendment No. 79,146

- 202 -

_ _ _ _ _ _