ML20217C189

Amend 104 to License NPF-57,changing TS 4.6.1.1, Primary Containment Integrity, 3/4.6.1.2, Primary Containment Leakage, 3/4.6.1.3, Primary Containment Air Locks, & 4.6.1.5.1, Primary Containment Structural Integrity

ML20217C189
Person / Time
Site:	Hope Creek
Issue date:	09/18/1997
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Public Service Electric & Gas Co, Atlantic City Electric Co
Shared Package
ML20217C193	List: ML20217C189 ML20217C195
References
NPF-57-A-104 NUDOCS 9710010252
Download: ML20217C189 (15)

Text

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NUCLEAR REGULATORY COMMISSION

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,f wAsHINoToN, D.C. 30mHoot PUBlIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY E0rKET NO._50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATI M LICENSE _

Amendment No. 104 1.icense No. NPF-!,7 1.

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

A.

& Gas Company (PSE&G) dated April 1, 1997, letter dated May 30, 1997, requirements of the Atomic Energy Act of 1954, as amendedcompli Act), and the Commission's rules and regulations set forth(in 10 the CFR Chapter I; B.

provisions of the Act, and the rules and regulations

, the Commission; C.

There is reasonable assurance:(i by this amendment can be conducted)without endangering the he and safety of the public conducted in compliance w,ith the Commission's regulations se forth in 10 CFR Chapter I; D.

defense and security or to the health and safety and E.

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

ju"1885! 3B3@

. 2.

Accordingly, the license is amended by changes to License Condition 2.D '

on page 6 of Facility Operating License No NPF-57*, and the license is also amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,hereby amended to read as and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is follows:

l (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.104, and the Environmental Protection Plan conta<ned in Appendix B, are hereby incorporated into the license.

PSE&G shall operate the facility in accordance with the Technical Specifications and-the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION C

)du N

]

Jo

. Stolz, Director Pr t Directorate I-D ion of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Attachments:

1.

Changes to page G of Lclense No NPF-57 2.

Changes to the Technical Specifications Date of Issuance:

September 18, 1997

• Page 6 of the license is attached, for convenience, for the composite license to reflect this change.

ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATihG LICENSE NO, NPF-57 DOCKET NO. 50-354 1.

Remove Insert Page 6 of License Page 6 of License 2.

Replace the following pa with the attached pages.ges of the Appendix 'A' Technical Specifications The revised pagon r,re identified by Amendment number and contain vertical lines indicating the area of change.

i Remove Insert l

l 3/4 6-1 3/4 6-1 l

3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 3/4 6-8 3/4 6-8 3/4 6-11 3/4 6-11 B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2 6-16b

, (13) Safety Parameter Disclav system (section 19.2, ssrR No. s)

Prior to the earlier of 90 days after restart from the first refueling outage or July 12, 1988, PSE&G shall add the following parameters to the SPDS and have them operational:

a. Prinary containment radiation

b. Primary containment isolation status

c. Combustible gas concentration in primary containment

d. Source range neotron flux (14) Additional conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.

are hereby incorporated into this license.

Public Service Electric and Gas Company shall operate the facility in accordance with the Additional conditions.

j D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.

An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in Special Nuclear Material Lices.ie No. 1953, dated August 21, 1985.

This exemption is described in Section 9.1 of Supplement No. S to the SER.

This previously granted exemption is continued in this operating license. An exemption from certain requirements of Appendix A to 10 CFR Part 50, is described in Supplement No. 5 to the SER.

This exemption la a schedular exemption to the requirements of General Design Criterion 64, permitting delaying functionality of the Turbine Building

(

Circulating Water System Radiation Monitoring System until 5 percent power for local indication, and until 120 days af ter fuel load for control room indication (Appendix R of SSER 5).

Exemptions from j

certain requirements of Appendix J to 10 CFR Part 50, are described i

in Supplement No. 5 to the SER.

These include an exemption from the requirement of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing on traversing incere probe system shear valves (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and an exemption from Appendix J, exempting Type C testing of thermal relief valves (Section 6.2.6 of SSER 5).

These exemptions are euthorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security.

These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12.

With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulaticas of the Commission.

Amendment No. 73, 97, 104

3/4.6 CONTAINMENT SYSTEMS i

3/4.6.1 PRIMARY CONTAINMENT' PRIMARY CONTAINMENT INTEGRITY I

LIMITING CONDITION roR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: OPERATIONAL' CONDITIONS 1, 2* and 3.

I ACT10N:

i Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY

[

within-I hour 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 />.-

SURVEILLANCE-REQUIREMENTS f

4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated l

a.

After each closing of each penetration subject to Type B testing, except the primary containment air lockr., if opened following Type l

A or B test, by leak rate testing in i.ccordance with the Primary containment Leakage Rate Testing Program.

1 b.

At least once per 31 days by verifying that all primary containment-penetrations ** not capable of being closed by OPERABLE containment l

automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.3-1 of Specification 3.6.3.

By verifying each primary containment air lock is in compliance c.

l

_ with the requirements of Specification 3.6.1.3.

I d.-

By verifyitig the suppression chamber is in coroliance with the requirements of Specification 3.6.2.1.

• see Special Test Exception 3.10.1 L

• • Except valves,. blind flanges, and deactivated automatic valves which are

-located inside the primary containment, and are locked, sealed or otherwise

-secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once per 92 days.

t HOPE CREEK 3/4 6-1 Amendment No.104 l-1--

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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited tot An overall integrated leakage rate (Type A test) in accordance with a.

the Primary containment Leakage Rate Testing Program.

b.

A combined leakage rate in accordance with the Primary Containment Leakage Rate Testing Program for all penetrations and all valves g

listed in Table 3.6.3-1, except for main steam line isolation valves *,

valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests.

l

• Less than or equal to 46.0 scfh combined through all four main steam c.

lines when tested at 5 psig (seal system AP).

d.

A combined 3eakage rate of less than or equal to 10 gpm for all containment isolation valves which form the haundary for the long-term seal of the feedwater lines in Table 3.6.3-1, when tested at 1.10 Pa, 52.9 psig.

A combined leakage rate of less than or equal to 10 gpm for all other e.

penetrations and containment isolution valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment, when tested at 1.10 Pa, 52.9 psig op.

APPLICABILITY:

When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

ACTION:

Withs The measured overall integrated primary containment leakage rate (Type a.

A test) not in accordanca with the Primary Containment Leakage Rate Testing Program, or b.

The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *,

valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests not in accordance with the Primary Containment Leakage Rate Testing Program, l

or The measured leakage rate exceeding 46.0 scfh combined through all c.

four main steam lines, or

• Exemption to Appendix "J" vf 30 CFR 50.

HOPE CREEK 3/4 6-2 Amendment No. 104 q

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

KCTION (Continued) d.

The measured conbined leakage rate for all conu inment isolation valves which form the boundary for the long term seal of the feedwater lines in Table 3.6.3-1 exceeding 10 gpm, or The measured combined leakage rate for all other penetrations and e.

containment isolation valves in hydrostatically tested lines in Table 3.6.1-1 which penetrate the primary containment exceeding 10 gpm, restore The overall integrated leakage rate (s) (Type A test) to be in accordance a.

with the Primary Containment Leakage Rate Testing Program, and b.

The combined leakage rate for all penetrations and all valves listed in l

Table 3.6.3-1, except for main steam line isolation valves *, valves which form the boundary for the long term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests to be in accordance with the Primary Containment Leakage Rate Testing Program, and The leakage rate to less than or equal to 46.0 scfh combined through all c.

four main steam lines, and f

I d.

The combined leakage rate for all containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 to less than or equal to 10 gpm, and The combined leakage rate for all other penetrations and containment e.

isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment to less than or equal to 10 gpm, prior to increasing reactor coolant system temperature above 200*P.

SURVEILLANCE REQUIREMENTS l

4.6.1.2.a The primary containment leakage rates shall be demonstrated in accordance with the Primary Containment Leakage Rate Testing Program for the following:

1. Type A test.

2. Type B and C tests (including air locks).

b.- DELETED.

c. DELETED.

j

• Exemption to Appendix "J" of 10 CFR 50.

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HCPE CREEK 3/4 6-3 Amendment No. 104

CONTAIMMENT SYSTEMS SURVE!!1ANCE REQUIREMENTS (Continued) l seeeeeeemmenesesseeeeeeeeemassenessessessemensommenemommesse..................

d.

DELETED.

e.

DELETED.

f.

Main steam line isolation valves shall be leak tested at least once per 18 months.

g.

Containment isolation valves which form the boundry for the long term seal of the feedwater lines in Table 3.6.3 1 shall be hydrostatically tested at 1.10 P., 52.9 psig, at least once per 18 months.

h.

All containment isolation valves in hydrostatically_ tested lines in Table 3.6.3 1 which penetrate the primary containment shall be leak tested at least-once per le months, i.

DELETED.

-j.- DELETED.

HOPE CREEK 3/4 6-4 Amendment No.104

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION

..................m...........................................................

3.6.1.3 Each primary containment air lock shall be OPERABLE with:

Both doors closed except 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 Primary conta!.nment Leakage Rate Testing Program.

l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

l ACTION:

With one primary containment air lock door inoperable:

a.

1.

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

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the primary containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 *Pe following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• See Special Test Exception 3.10.1.

HOPE CRELK 3/4 6-5 Nmendment No.104

o CONTAINMENT SYSTEMS SURVEILLANCE REQUIRE 4ENTS

==================================================================

4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:

i' a.

_By verifying seal leakage rate in accordance with the Primary containnent Leakage Rate Testing Program.

b.

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

At least cnce per 6 months by verifying that only one door _ in each air c.

lock can be opened at a time.**

• • Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the primary containment has been de-inerted.

HOPE CREEK 3/4 6-6 Amendment No.104

0 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.5 The structural integrity of the primary containment shall be naintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.1.

APPLICABILITY OPERATIONAL CONDITIONS 1, 2 and 3.

ACTIONt With the structural integrity of the primary containment not conforming to the l

above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 />.

l SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment shall be determined in accordance with the P:imary containment Leakage Rate Testing Program.

4.6.1.5.2 Reports Any abnormal degradation of the primary containment structure detected during the above required inspections shall be reported to the Conadssion pursuant to Specification 6.9.2 within 30 days. This report shall include a description of the condition of the containment, the inspection procedure, and the corrective actions taken.

HOPE CREEK 3/4 5-8 Amendment No.104

3 s

CONTAINMENT SYSTEMS I

DRYWs'f.t. AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION

.................................. 6..........................................

I 3.6.1.8 The drywell and suppression chamber purge system, including the 6 inch nitrogen supply line, may be in operation for up to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> each 365 1

days with the supply and exhaust isolation valves in one supply line and one j

exhaust line open for containnAnt prepurge cleanup, inerting, deinerting, or pressure control.*

APPLICABILITY:

OPERATIONAL CONDITIONS 1, *4 and 3.

ACTION:

a. With a drywell or suppression chamber purge supply and/or exhaust isolation valve and/or the nitrogen supply valve open, except as permitted above, close the valves (s) or otherwise isolate the penetration (s) 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 />.

4

b. With a drywell purge supply or exhaust isolation valve, or a suppression chamber purge supply or exhaust isolation valve or the nitrogen supply valve, having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.B.2, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 />.

SURVEILLANCE REQUIREMENTS 4

1 4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust, and nitrogen supply butterfly isolation valves shall be verified not to have been open for more than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in the previous 365 i

days.*

4.6.1.8.2 At least once per 24 months, the 26-inch drywell purge supply and exhaust isolation valves and the 24-inch suppression chamber purge supply and 4

exhaust isolation valves and the 6-inch nitrogen supply valve shall be demonstrated OPERABLE in accordance with the Primary Containment Leakage Rate Testing Program, d

4

• Valves open for pressure control are not subject to the 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per 365 days limit, provided the 2-inch bypass lines are being utilized.

HOPE CREEK 3/4 6-11 Amendment No.104 I

3/4.6 CONTAINMENT SYSTEMS BASES 3/ 4. 6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAIPMENT INTEGRITY PRIMARY CONTAINMFNT 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 lindt the site boundary radiation doses to within the lindts of 10 CFR Part 100 during accident conditions.

l 3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the l

total containment leakage volume will not exceed the value assumed in the i

accident analyses at the design basis LOCA maximum peak containment accident pressure of 48.1 psig, P..

As an added conservatism, the measured overall integrated leakage rate (Type A test) is further limited to less than or equal to 0.75 L. during performance of the periodic tests to account for possible I

degradation of the containment leakage barriers between leakage tests.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

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

3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the Primary containment Leakage Rate Testing Program.

Only one closed door in each air lock is required to maintain the integrity of the containment.

3/4.6.1.4 MSIV SEALING ZYSTEM Calculated doses resulting from the maximum leakage allowance for the main steamline isolation valves in the postulated LOCA situations would be a small fraction of the 10 CTR 100 guidelines, provided the main steam :.ine system from the isolation valves up to and including the turbine condenser remains intact.

Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.

The sealing system will reduce the untreated leakage from the MSIVs when isolation of the primary system and containment is required.

HOPE CREEK B 3/4 6-1 Amendment No.104

CONTAINMENT SYSTEMS RASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contkinment will be maintained comparable to the original design. standards for the life of

-the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 48.1 psig in the event of a LOCA. A visual inspection in accordance with the Primary containment Leakage Rate TeAting Program is sufficient.

3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The lindtations on drywell and suppression chamber internal pressure ensure that the containment peak pressure of 48.3 psig does not exceed the -

design pressure of 62-psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 3 paid. The limit of -0.5 to +1.5 psig for initial positive containment pressure will limit the total pressure to 48.1 psig which is less than the design pressure and is consistent with the safety analysis.

3 / 4. 6.1. *J DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average' air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340'F during LOCA conditions and is consistent with the safety analysis.

The 135*F average temperature is conducive to normal and long term operation.

3 / 4. 6.1. 8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The 500 nours/365 days limit for the operation of the purge valves and the 6" nitrogen supply valve during plant Operational Conditions 1, 2 and 3 is intended to reduce the probability of a LOCA occurrence during the above operational conditions when the applicable combination of the above valves are open.

Blow-out panels are installed in the CPCS ductwork to provide additional assurance that the FRVs will be capable of performing its safety function subsequent to a LOCA.

I HOPE CREEK.

B 3/4 6-2 Amendment No.104 V

ADt4INISTRATEVE CONTROLS 6.8.4.f primar/ Containment Leakace Rate Testina Procram 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 exemptions.

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 loss of coolant accident, P.,

is 48.1 psig.

The maximum allowable primary cc,tainment leakage rate, L.,

at P.,

shall be 0.5% 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 Lg.

During the first unit startup 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 lock leakage rate is less than or equal to 0.05 Lg when tested at greater than or equal to P.,

2)

Door seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater than or equal to 10.0 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate

~

Testing Program.

The provisions of specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

HOPE CREEK 6-16b Amendment No.104 o