Text

Amends 207 & 188 to Licenses DPR-70 & DPR-75,respectively, Revising TSs to Adopt Option B,Of 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactor
	ML20203L392
Person / Time
Site:	Salem
Issue date:	02/27/1998
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20203L396	List: ML20203L392; ML20203L402;
References
	DPR-70-A-207, DPR-75-A-188 NUDOCS 9803060012
	Download: ML20203L392 (22)
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30046-0001 n%...../

PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA SECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50 272 SALEM NUCLEAR GENERATING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 207 License No. DPR 70 1.

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

A.

The application for amendment filed by the Public Service Electric & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 15,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

j 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common deft,nse 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 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-70 is hereby amended to read as follows:

9903060012 980227 PDR ADOCK 05000272 P

PDR J

1 (2) Tschsica Soscincei;cas and Environmental Pie;ection Plan The Technical Spec.7,ceuens contained in Appendices A and B, as revised through Amendment No.207are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Spec.?,ceuens.

3.

This license amendment is effective as of its date of lasuance to be implemented within 60 6*ys.

FOR THE NUCLEAR REGUI.ATORY COMMISSION J-

k. Stolz, Director Directorate I 2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

February 27, 1998

)

4 ATTACHMENT TO LICENSE AMENDMENT NO. 207 FACILIW OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Bamove Paoes insert Paoes 3/46-2 3/4 6-2 3/4 6-5 3/4 6-5 3/4 6 Sa 3/4 6-5a 3/4 6-8 3/4 6-8 6-19 6-19 B 3/4 6-1 B 3/4 6-1 B 3/4 6 2 B 3/4 6-2

e CoefTAIntGlNT SYSTEMS CottTAIntGlNT T M W m LIMITING CONDITION FOR OPERATION 3.6.1.2 containment leakage rates shall be limited tot a.

An overall integrated leakage rate (Type A test) in accordance with the Containment Leakage Rate Testing Program, b.

A ocabined leakape rate in accordance with the containment Leakage Rate Testing Program for all penetrations and valves subject to Type B and C tests.

APPLICABILITY: MODES 1, 2, ? ud 4.

ACTION:

With either (a) the measured overall integrated containment leakage (Type A test) not in accordanoe with the ' Containment Imakage Rate Testing Proggan, os; (b) with the measured' combined leakage rate for all penetra,tions and valvis subject to Types R and C, tests not in accor h oe with the Containment Le p age Rate Testing Program, resto,re the leakage rate (s) to within the lini,t(s) prior to increasing the Reactor Cool, ant Sys, tem tager,a,ture abM 2,00'$'.

SURVEILLANCE REQUIRENDITS 4.6 1.Q That containment leakage rates sha11'be demonstrated as follows{

l Type A tests shall be in accordance with the Contaipment Leakage a.

RSte Teating Program s b.

Type B and C teste shall be conduqted in accordance wi.th the Containment Leakage Rate Testi,ng Programs Air looks shall be. tested and demonstrated OPERABLE in accordance o.

with the Containment Leakage Rate Testing Program.,

A one-time change is granted to have the containment purge supply and/or exhaust isolation valves open in Modes 3,and 4 following the steam generator replaagmeht outage (1R13), The cumulative time for having the valves open in Modes 3 and 4 is" limited to fourteen (14) days., Eagh valvje will be immobilised in, the shut position prior to initial 'eritry into Mode 2.,

The one-time exemption expins with initial entry into Mode 2 following 1R13.

SALEM - UNIT 1 3/4 6-2 Amendment No. IS4,f89, 206,207

j CONTAINMENT SYSTEM _S CONTAIlttENT AIR LOCKS, LIMITING CONDITION FOR CPERATION

......c 3.6.1.3 Each containment air Icek shall be OPE 3ABLE withs Both doors closed except when the air lock is being used for a.

normal transit entry and exit through the containment, then at least one air look door shall be closed, and b.

An overall air look leakage in accordance with the Containment Leakage Rate Testing Program.

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

With an air lock inoperable, restore the air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least BOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SEUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each contairment air lock shall be demonstrated OPERABLE:

By verifying seal leakage rate in accordance with the containment a.

Leakage Rate Testing Program, b.

By conducting an overall air look leakage test in accordance with the Containment Imakage Rate Testing Program.

At 3 east once per 6 months by verAfying that only one door in c.

each air lock can be opened at a time.

SALEM - UNIT 1 3/4 6-5 Amendment No.89,207

CONTAIM4ENT SYSTEMS CONTAIMMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION n....

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3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in specification 4.6.1.6.

APPLICABILITY: nodes 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined in accordance with the Containment Leakage Rate Testing Program.

4.6.1.6.2 Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFR50.72 and 10CFR50.73.

The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective action taken.

SALEM - UNIT 1 3/4 6-8 Amendment No. I 8 #,2 07

i ADMINISTRATIVE CONTROL 5 (vi)

A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d.

Backup Method for Determining subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling Margin. This program shall include the following (1) Training of personnel, and (ii) Procedures for monitoring e.

Postaccident Sanpling A program

which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions, The program shall include the following:

(i)

Training of personnel (ii)

Procedures for sampling and analysis, (iii)

Provisions for maintenance of sampling and analysis equipment.

6.8.4.f.

Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54 (o) and 10CFR50, Appendix J, Option B, as modified by approved exesptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program", dated september 1995.

The peak calculated containment internal pressure for the design basis los s of coolant accident, P.,

is 47.0 psig.

The==visum allowable containment leakage rate, L.,

at P.,

shall be 0.1% of primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

Primary containment leakage rate acceptance criterion is less a.

than or equal to 1.0 L..

During the first unit startup

It is acceptable if the licensee maintains details of the program in plant operation manuals.

SALEM - UNIT 1 6-19 Amendment No. 133,207

n ADNINISTRATIVE CONTROLS following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 L. for Type B and Type C tests and less than or equal to 0.75 L. for Type A tests; b.

Air lock testing acceptance criteria are:

1)

Overall air look leakage rate is less than or equal to 0.05 L. when tested at greater than or equal to P.,

2) seal leakage rate less than or equal to 0.01 L. per hour when the gap between the door goals is pressurized to 10.0 psig.

Test frequencies and applicable extensions will be controlled by the Primary Containment Leakage Rate Testing Program.

The provisions of specification 4.0.3 will be applied to the Primary Containment Leakage Rate Testing Program.

l SALEM - UNIT 1 6-19a Amendment No.207

I 3/4.6 CONTAI)tGENT SYSTMS mASES 3/4.6.1 PRIMARY CONTAI M ENT 3/4.6.1.1 CONTAInt(ENT INTEGRITY Primary CONTAlledENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident ecnditions.

3/4.6.1.2 CONTAInt4ENT LEARAGE The limitations on containment leakage rates ensure that the total containment leakage voluna will not exceed the value assumed in the accident analyses at the accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate (Type A test)is further limited to s 0.75 - 2. or l

5 0.75 Ls, as applicable, during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage l

l tests.

The surveillance testing for measuring leakage rates is consistent with the Containment Leakage Rate Testing Program.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAI) STENT INTEGRITY and the Containment Leakage Rate Testing Program. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

sAIM - UNIT 1 B 3/4 6-1 Amendment No. 207

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CONTAIIedIrf SYSTEMS BASES 3/4.6.1.4 INTE3tNAL PRESSURE The limitations on containannt internal pressure ensure that:

1) the containsu nt structure is prevente(. from exceeding its design negative pressure differenttal with respect to the outside atmosphere of 3.5 peig and 2) the containment peak pressure does not exceed the design pressure of 47 psig during the limiting pipe break conditions.

The pipe breaks considered are LOCA and steam line breaks.

The limit of 0.3 peig for initial positive contairunent pressure is consistent with the accident analyses initial conditions.

The===4==

peak pressure espected to be obtained from a LOCA or steam line break event is s 47 peig.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air tesperature ensure that the overall containment average air temperaturo does not exceed the initial i

I tesperature condition assumed in the accident analysis for a LOCA or steam line break.

In order to determine the containment average air tesperature, an average is calculated using measurements taken at loca; ions within containment selected to provide a representative sasple of the overall containment atmosphere.

-1 3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment ~

will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment

' will withstand the design pressure. The visual inspections of the concrete and 2tner and the Type A leakage test both in accordance with the containment leakaga Rate Testing Program are sufficient to demonstrate this capability.

SALEN - UNIT 1 B 3/4 6-2 Amendment No.

195,207

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UNITED STATES p

y NUCLEAR RESULATORY COMMISSION WASHINGTON, D.C. 300eH001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY E8. ECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Ame?Jment No. 188 License No. DPR-75 1.

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

A.

The application for amendment filed by the Public Service Electric & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 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 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common 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 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-75 is hereby amended to read as follows:

i i

g -

2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.188 are hereby incorporated in the licwnse. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance to be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION J hrt F. Stolz, Director d I

P ct Directorate 1-2 Division of Reactor Projects - Ull Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date ofissuance: February 27, 1998 1

t g

ATTACHMENT TO LICENSE AMENDMENT NO.1 R8 FACILITY OPERATING LICENSE NO. DPR-75 L

DOCKET NO. 50-311 l

Revise Appendix A as follows:

Egmqve Pages insert Paaes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/46-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-8 3/4 6 8 6-19 6-19 B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6 2 4

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3/4.6 CONTAlle4ENT SYSTINS 3/4.$.1 PRIMARY CON *AImtENT CONTAISEDrr INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAIMMENT INTEGRITY shall be maintained.

j APPLICABILITY : HODES 1, 2, 3 and 4.

ACTION Without primary CONTAI) DENT INTEGRITY, restore CONTAInt(ENT INTEGRITY within one hour or be in at least BOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD sNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , sURVE!LLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY ahall be demonstrated

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

not e

capable of being closed by OPERABLE ntnf.ainment automatic isolation valves and required to be cloved during accident conditiona are closed by va),ves, blind ftanges, or deactivated automatic valves secured in their positions, except for valves that may be opened under Administrative control as pern.itted by specification 3.6.3.1, and all equipment hatches are closed and sealed.

b. By verifying that each containment air look is OPERABLE per specification 3.6.1.3.

c. After each closing of a penetration subject to Type B testing, except containment air locks, if opened following a Type A or B tost, by leak rate tesung in accordance with the containment Leakage Rate Testing Program.

Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days.

SALEM - UNIT 2 3/4 6-1 Armandment No. f 72, j 88 i

CONTAtMMENT SYSTEMS CONTATMMENT IJtARAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Contairunent leakage rates shall be limited tot a.

An overall integrated leakage rate (Type A test) in accordance with the contairument Leakage Rate Testing Program.

b.

A combined Joakage rate in accordanoe with the containment Leaknge

~

Rate Testing Program for all penetrations and valves subject to Type B and C tests.

1 APPLICABILITYI NODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rato (Type g

A test) not in accordance with the containment Leakage Rate Testing Program or (b) with the measured abined leakage rate for all penetrations and valves subject to Types 2 and C toute not in accordance with the Containment Leakage Rata Testing Program, restore the leakage rate (s) to within the limit /r) prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated as follows:

a.

Type A tests shall be in accordance with the Containment Leakage Rate Testing Program.

b.

Type 2 and C tests shall be conducted in accordance with the Containment Leakage Rate Testing Program, c.

Air locks shall be tested and demonstrated OPERABLE in accordance with the Containment Leakage Rate Testing Program.

l SALEN - UNIT 2 3/4 6-2 Amendment NoJ56,772,188

n coNTAlletENT SYSTEDt3 CONTAftedENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.4.1.3 Each containment air look shall be OPERABLE withs Both doors closed emoept when the air lock is being used for normal a.

transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate in accordance with the containment Leakage Rate Testing Program APPLICABILITY: NODES le 2, 3 and 4 ACTION:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to CPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least NOT STANDBY within the next six hours and in cold SNUTDONN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.

The provisions of Specification 3.0.4 are not applicable, b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock det, e cic.sudl restore the inoperable air lock to OPERABLE status within F3 hours or be in at least NOT STANDBY within the next six hosts and in cold SEUTDONN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQULtJilMENTS 4.s.l.3 Each containment air lock shall be demonstrated OPERABLE:

sAtuN - UNIT 2 3/4 s-4 Amendment No. 188

CC4fTATDMENT SY8TEMS Cobf7Af tedENT AIR 1hCES SURVEILIANCE REQUIREMENTS (Continued)

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w......

a.

By verifying seal leakage rate in accordance with the Containment 14akage Rate Testing Program b.

By conducting an overall air lock leakage test in accordance with the Containment Leakage Rate Testing Program o.

At least onoe per 6 months by verifying that only one door in each air lock can be opened at a time.

SALIM - UNIT 2' 3/4 6-5 Amendment No. $ 2,188

._~ _ __._______._ _ _ ___.

l CONTA!ISSNT SYSTBt3 CONTAtlOGENT STRUCWRAL INTEGRITY LIMIT 1No CONDIT!cWS FOR OPERATICW t

3.6.1.6 The structural integrity of the contairument shall be maintained at a level consistent with the mooeptance criteria-in Specification 4.6.1.6.

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

s

?

ACTIONI With the stavotural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILIANCE REQUIREMENTS 4.6.1.6.1 Contairument Surfaces The structural integrity of the exposed sooessible interior and exterior surfaces of the-containment, including the liner plate, shall be determined in sooerdance with the containment Leakage Rate Testing Program 4.6.1.6.2 Reports Any abnormal degradation of the conteirument structure detected during the above required inspections shall be evaluated for reportability pursuant to 10c m50.72 and 10CFR50.73. The evaluation shall be documented and shall include a description of the condition of the concrete, I

the inspection procedure, the toleranoes on oracking, and the corrective action taken.

1 4

i J

i f

SALEM - UNIT 2 3/4 6-8 Amendment No. f f 2, f($, j 88

-2

___-.___._._...-__m

)

i ADMIN!aTRATIVE CMTROLs (vi)

A procedure identifying (a) the authority responsible for i

the interpretation of the data, and (b) the sequence and tianing of administrative events required to initiate l

corrective action.

i d.

Backup Method for Detersnining subcooling Margin A program which will ensure the capabili cy to accurately smonitor the Reactor Coolant systesa subt.ooling Margin. This program shall include the following:

1 j

(i)

Training of personnel, and 1

(11)

Procedures for anonitoring e.

Postaccident sampling A program

which will ensure the capability to obtain and analyse reactor coolant, radioactive lodines and particulates in plant gaseous affluents, and containsment atsnosphere sasples 1

under sooident conditions. The program shall include the followings (t)

Training of personnel (ii)

Procedures for saspling and analysis, (iii) Provisions for snaintenance of saspling and analysis 4

equipment.

6.8.4.f.

Prisnary containsment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as rsquired by 10CrR50.54 (o) and 10CFR50, Appendix J, Option B, as snodified by approved onesptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Perforinance-Based l

Containment Imak-Test Program, dated september 1995.

a The peak calculated containment internal pressure for the design-basis loss of coolant socident, P.,

is 47.0 psig.

I The maxianam allowable containment leakage rate, L.,

at P.,

shall be 0.1% of primary containsnent air weight per day.

Leakage Rate Aeoeptance criteria ares a.

Primary containment leakage rate acceptance criterion is less than or equal to 1.0 L..

During the first unit startup fo11 ewing testing in accordance with this program, the leakage rate

'It is acceptable if the licensee maintains details of the program in plant operation manuals..

aAzau - UNIT 2 6-19 Amendment No. f12,188 l

l

ADMINISTRATIVE CONTROLS acceptance criteria are less than or equal to 0.s L. for Type 3 and Type c tests and less than or equal to 0.75 L. for Type A tests; b.

Air lock testing acceptance criteria are:

1) overall air lock leakage rate is less than or equal to 0.05 L.

when tested at greater than or equal to P.,

2) Seal leakage rate less than or equal to 0.01 L. per hour when the gap between the door seals is pressurised to 10.0 psig.

Test frequencies and applicable extensions will be controlled by the Primary Containment Leakage Rate Testing Program.

The provisions of specification 4.0.3 will be applied to the Primary Containment Leakage Rate Testing Program.

4

-}

sALaw - curt 2 s-isa Amendment NO. 188

s 3/4.6 CONTAIW4ENT SYSTEMS l

mAsES l

l 3/4.6.1 PRIMARY CONTAIW4ENT

,3/4.6.1.1 CONTAlmtFNT INTEGRITY Primary CONTA!mtENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT IJtAKAGE The limitations on containment leakaga rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the accident pressure, p. As an added conservatism, the measured overall integrated leakage rate ('rype A test) is further limited to less than or equal to 0.75 L or less than or equal to 0.75 L.,

as applicable, during performance of the, periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the containment Leakage Rate Testing Program.

l 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINNENT INTEGRITY and the Containment Leakage Rate Testing Program. Surveillance testing of the air lock seals provide nasurance that the overall air look leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

sALaw - ou!T 2 a 3/4 6-1 Amendment No. 188

6 CONTA!nteNT SYSTEMS l

mASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure thatt

1) the contaitunent structure is prevented from eaceeding its design negative pressure differential with respect to the outside atmosphere of 3.5 poig, and 2) the containment peak pressure does not eaceed the design pressure of 47 psig during the limiting pipe break conditions. The pipe breaks considered are-LOCA and steam line breaks.

The limit of 0.3 poig for initial positive containment pressure is consistent with the accident analyses initial conditions.

The maxismun peak pressure espected to be obtained from a LOCA or steam line break event is s 47 psig.

3/4.6.1.5 AIR TEMPERATURE The limitations of. containment average air temperature ensure that the overall containment average air tosperature does not emoeed the initial tesperature condition assumed in the accident analysis for a LOCA or steam line break.

In order to determine the containment average air temperature, an average is calculated using measurements taken at locations within containment selected to provide a representative sample of the overall containment atmosphere.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the containment will withstand the design pressure. The visual inspections of the concrete and liner and the Type A leakage test, both in accordance with the containment Leakage Rate Testing Program, are sufficient to demonstrate this capability.

3/4.6.1.7 CONTAI) TENT VENTI 1ATION SYSTEM The containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA. Maintaining these valves closed during plant operations ensures that esoessive quantities of radioactive materials will not be released via the containment purge system.

=

SALEM - UNIT 2 a 3/4 6-2 Amendment No.7 7$,188 l

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ML20203L392

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