Text

Amend 124 to License NPF-38,changing TSs to Reflect Adoption by Licensee of Containment Leakage Rate Testing Program
	ML20137R931
Person / Time
Site:	Waterford
Issue date:	04/10/1997
From:	Chandu Patel; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20137R936	List: ML20137R931; ML20137R939;
References
	NUDOCS 9704140300
	Download: ML20137R931 (17)
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UNITED STATES s

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20006 4001

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ENTERGY OPERATIONS. INC.

DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 124 License No. NPF-38 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated December 2,1996 as supplemented by letters dated February 4 and March 14, 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 set forth in 10 CFR Chapter I; j

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 (1) 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; 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 Comission's regulations and all applicable requirements have been satisfied.

9704140300 970410 PDR ADOCK 05000382 P

PDR

. 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. NPF-38 is hereby amended to read as follows:

(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.124, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 10,1997 i

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ATTACHMENT TO LICENSE AMENDMENT NO.124 TO FACILITY OPERATING LICENSE NO. NPF-38 i

DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indic.ating the areas of change. The corresponding i

overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAGES XVIII XVIII 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 l

3/4 6-4 3/4 6-5 3/4 6-9 3/4 6-9 3/4 6-10 3/4 6-10 3/4 6-14 3/4 6-14 3/4 6-15 3/4 6-15 B 3/4 6-1 B 3/4 6-1 6-24 6-24 6-25 l

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p MI ADMINISTRt!"I'VE CONTROLS r

SECTION M

6.5.2 SAFETY REVI EW C0PMITTEE...................................

6-10 FUNCTION...............................................

6-10 COMPOSITION............................................

6 ALTERNATES.............................................

6-10 CONSULTANTS............................................

6-10 MEETING FREQUENCY..................................~..

6-11 QU0 RUM.................................................

6-11 REVIEW.................................................

6-11 AUDITS.................................................

6-12 AUTHORITY..............................................

6-13 REC 0RDS................................................

6-13 6.6 REPORTABLE EVENT ACTI0N.....................................

6-13 6.7 SAFETY LIMIT VIOLATION......................................

6-13 6.8 PROCEDURES AND PR0 GRAMS.....................................

6-14 6.9 REPORTING RE0VIREMENTS......................................

6-16 6.9.1 ROUTINE REP 0RTS...........................................

6-16 STARTUP REP 0RT.........................................

6-17 ANNUAL REP 0RTS.........................................

6-17 MONTHLY OPERATING REPORT...............................

6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.....

6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.............

6-19 INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT............

6-20 CORE OPERATING LIMITS REP 0RT...........................

6-20 6.9.2 SPECIAL REP 0RTS...........................................

6-20a 6.10 RECORD RETENTION...........................................

6-20a I

WATERFORD - UNIT 3 XVII AMENDMENT NO. 5",at,102 FA9 1 1995

lHDil ADMINISTRATIVE CONTROLS SECTION P.A[il 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-22 6.12 HIGH RADIATION AREA........................................

6-22 6.13 PROCESS CONTROL PR0 GRAM....................................

6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM...................

6-24 l

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i WATERFORD UNIT 3 XVIII Amendment No. 68,124 l

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l 3/4.6 CONTAINMENT SYSTFJS 3/4.6.1 PRTMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION J

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: NODES 1, 2, 3, and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY w'ithin I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN 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 capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under l

administrative control as permitted by Specification 3.6.3.

b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

a c.

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

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment 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.

WATERFORD - UNIT 3 3/4 6-1 AMENDMENT NO. M,124

CONTAINMENT SYSTEMS CONTAINMENT _1EAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be in accordance with the Containment Leakage Rate Testing Program.

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

ACTION:

With containment leakage rate not within limits, restore containment leakage rates to within limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be determined in accordance with the Containment Leakage Rate Testir.g Program.

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WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO. 75 05,120, 124

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PAGES 3/4 6-4 THROUGH PAGE 3/4 6-8 NOT USED l

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1-r WATERFORD'- UNIT 3.

3/4 6-3 AMENDMENT NO. 75'110, 124 (Next page is 3/4 6-9) 9

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CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS l

r LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one a

air lock door shall be closed, and l

b.

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

e APPLICABILITY: MODES 1, 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 OPERABLE 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 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 .

1.

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 door 4

closed; restore the inoperable 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and j

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

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WATERFORD - UNIT 3 3/4 6-9 Amendment No.124 L

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CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS f

4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By verifying seal leakage in accordance with the Containment Leakage Rate Testing Program, 8

b.

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

l c.

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

I WATERFORD - UNIT 3 3/4 6-10 Amendment No.124

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CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION

3. 6.1. 5 Primary containment average air temperature shall not exceed 120 *F.

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

ACTION:

With the containment average air temperature greater than 120 *F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

J SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures at any three of the following locations and shall be determined at laast once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

Location a.

Containment Fan Cooler No. lA Air Intake b.

Containment Fan Cooler No.1B Air Intake c.

Containment Fan Cooler No. IC Air Intake d.

Containment Fan Cooler No. 1D Air Intake WATERFORD - UNIT 3 3/4 6-13

1 CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

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

ACTION:

With the structural integrity of the containment vessel 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 RE0VIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test and at the intervals as specified in the Containment Leakage Rate Testing Program by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel and verifying no apparent changes in appearance of the surfaces or other abnormal degradation in accordance with the Containment Leakage Rate Testing Program.

WATERFORD - UNIT 3 3/4 6-14 Amendment No.124

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CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM i

LIMITING CONDITION FOR OPERATION i

3.6.1.7 Each containment purge supply and exhaust isolation valve (CAP 103, j

CAP 104, CAP 203, and CAP 204) shall be OPERABLE and may be open at no greater than the 52* open position allowed by the mechanical stop for less than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 days.

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

ACTION:

j a.

With a containment purge supply and/or exhaust isolation valve (s) open for greater than or equal to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 days at any open position, close the open valve (s) 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 .

1 b.

With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate exceeding the limits of Surveillance i

Requirement 4.6.1.7.2, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.1.7.1 The cumulative time that the purge supply or exhaust isolation valves are open during the past 365 days shall be determined at least once per 7 days.

4.6.1.7.2 At it.ast once per 3 months each containment purge supply and erhaust isolation valve with resilient material seals shall be demonstrated OPERABLE in accordance with the Containment Leakage Rate Testing Program.

4.6.1.7.3 Each containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by veri-fying that the mechanical stops limit the valve opening to a position < 52" open.

WATERFORD - UNIT 3 3/4 6-15 Amendment No.124

s CONTAlletENT SYST MS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTDt3 CONTAlletENT SPRAY SYSTEM s

LIMITING CONDITION FOR OPERATION 3.5.2.1 Two independent containment spray systems shall be OPERCE with each a

spray system capable of taking suction from the RWSP on a conta1 A nt spray i

actuation signal and automatically transferring suction to the safety i

injection system sump on a recirculation actuation signal. Each spray system flow path from the safety injection system sump shall be via an OPERABLE shutdown cooling heat exchanger.

$PPLICABILITY: $WDES 1, 2, 3, and 4*.

gIlgg:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SUkVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

i At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifyin that the water level in the' containment spray header riser is > 14l.5 feet MSL elevation.

a.

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b.

At least once per 31 days by verifying that each valve (manual, in the flow path that is not locked, power-operated, or automatic)in position, is correctly positioned to sealed, or otherwise secured take suction from the RWSP.

c.

By verifying, that on recirculation flow, each pump develops a total head of greater than or equal to 219 psid when tested pursuant to specification 4.0.5.

d.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates 1

to its correct position on a CSAS test signal.

With Reactor Coolant System pressure > 400 psia.

WATERFORD - UNIT 3-3/4 6-16 Amendment No. 89 j

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v 3/4.6 CONTAINMENT SYSTEMS RASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT 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 safety 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 LEAKAGE i

The limitations on containment leakage rates ensum that the total containment leakage volume will not exceed the value a%umed in the safety mea >ured overall integrated leakage rate I. As an added conservatism, the analyses at the peak accident pressure, P s further limited to 5 0.75 L during the performance of the periodic Type A tests to account for posslble i

degradation of-the containment leakage barriers between leakage tests. Also,

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the summation of penetration leakages measured during Type B and C testing is i

limited to 0.6 L. At all other times between required leakage rate tests, overall containm,ent leakage is limited to L,ight of the containment air per 24 The maximum allowable 4

is 0.5 % by we containment leakage rate, L,ident pressure, P., of 44 psig.

hours at the design basis acc The surveillance requirements for measuring leakage rates are consistent l

with the requirements of 10 CFR 50, Appendix J, Option B, and leakage rate testing is performed in accordance with the guidelines contained in Regulatory Guide 1.163, "Performanace-Based Containment Leak-Test Program".

Leakage. rate i

testing is conducted periodically as specified in the Containment Leakage Rate Testing Program.

The periodic performance of Type A, B and C tests verifies that the containment leakage rate does not exceed the levels assumed in the safety analyses.

Secondary containment bypass leakage paths previously inderitified in Table 3.6-1 are now identified in the Technical Requirements Manual.

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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 CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

WATERFORD - UNIT 3 8 3/4 6-1 AMENDMENT NO. 75 "5,IM, 124 4

CON 7AkREW SYSVEM5 SL$ts 3/a.6.1.4 1NTERNAL pt[$$UR[

The limitations an containment internal pressure ensure that (1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.65 psis, (2) the contaiwont peak pressure does not exceed the desi of the ICC5 performance analysis (STP C55 81) is s and The maximum peak pressure expected to be obtained free an MSLB event is 42.3 psig. The limit for initial positive containment pressure of *27 inches water (approximately 1.0 psig) will limit the total pressure to less than 44 psig which is less than the design pressure and is consistent with the safety analyses. The limit for initial positive containment pressure includes a correction of 1.20 inches water for possible instroent error and an addi-tional 6.8 inches water fer conservatism.

4 The limit of 14.375 psia for initial negative containment pressure ensures that the minimum containment pressure is consistent with the ECCS perforeance analysis ensuring core reflood under LOCA conditions.

3/a E.1.5 AIR TEW8EtaTURE,

The limitation on containment average air temperature ensures that the cents'ement peat air temperature does not exceed the design temperature of 2ES.3'F caring LOCA conditions and 413.5'T during MSLB conditions and is consistent with tne safety analyses.

3 /a. E.1. 6 c0Ca:NWINT VISSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be asintained comparable to the original design standards

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for tne life of sne facility.

Structural integrity is required to ensure that the vessel wt11 withstand the maximum pressure of 43.76 p'sig in the event of a sain stets line breat accident. A visual inspection in conjunction with Type A leakage test is sufficient to deeonstrate this capability.

3 /a. 6.1. 7 c0MTAfkMEWT YENTILATION $Y$ TEN The use of the containment purge valves is restricted to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per year in accordance with Standard Review Plan 5.2.4 for plants with the Safety Ivaluation Report for the Construction License issued prior to July 1,1975. The purge valves have been' modified to limit the opening to approximately 52' to ensure the valves will close during a Lect er MSL8; and therefore, the 51TE SOUNDARY doses are Saintained within tha guidelines of 10 CFR Part 100. The purge valves, as modified, comply with all provis.ie of ITP C58 6 4 except for the Mconsended size of the purge line for systees to be used during plant operation.

l WATERFOR.D

UNIT 3 3 3/4 6 2 Amendment No. 27 I

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ADMINISTRATIVE CONTROLS

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PROCESS CONTROL PROGRAM (Continued) 2.

A detemination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the PORC and i

the approval of the Plant Manager.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This document shall contain:

1.

Su'ficient information to support the change together with the appropriate analyses or evaluations justifying the changels) and 2.

A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

b.

Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, i

clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM i

A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, 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-Barnd Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P,, is 44 psig.

i The maximum allowable containment leakage rate, L, is 0.5% of containment air

-weight per day at P,.

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L WATERFORD - UNIT 3 6-24 Amendment No. 50,05,115, 124 l

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CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued)

Leakage rate acceptance criteria are:

a.

Containment leakage rate acceptance criteria is 5 1.0 L,.

During the first unit startup following each test performed in accordance with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tests and 5 0.75 L, for Type A tests.

b.

Air lock acceptance criteria are:

1.

Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.

2.

Leakage rate for each door is s 0.01 L, when pressurized to 210 psig.

Combined bypass leakage rate acceptance criteria is s 0.06 L, when c.

tested at 2 P,.

d.

Containment purge valves with resilient seals acceptance criteria is s 0.06 L, when tested at 2 P,.

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

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

I WATERFORD - UNIT 3 6-25 Amendment No.124

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ML20137R931

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