Text

Proposed Tech Specs Revised to Permit Use of 10CFR50 App J, Option B,Performance-Based Containment Leakage Testing for Type A,B & C Leak Rate Testing
	ML20135A775
Person / Time
Site:	Waterford
Issue date:	12/02/1996
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20135A768	List: ML20135A766; ML20135A775;
References
	NUDOCS 9612040041
	Download: ML20135A775 (24)
	v • d • e

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. . j INDEX ADMINISTRATIVE CONTROLS 1

i SECTION PAGE 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-22 !

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

i 6.13 PROCESS CONTROL PR0 GRAM.................................... 6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................ 6-24 4

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9612040041 961202 PDR ADOCK 05000302 P PDR W FRFORD - UNIT 3 XVIII Amendment No. 68

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3/4.6 CONTAINMENT SYSTEMS i

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l. 3/4.6.1 PRIMARY CONTAINMENT

, CONTAINMENT INTEGRITY 4

! LIMITING CONDITION FOR OPERATION l

l j 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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

t j ' ACTION:

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! Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within '

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 . I

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! l l SURVEILLANCE REQUIREMENTS l i

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4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

1 i a. At least once per 31 days-by verifying that all penetrations

not i capable of being closed by OPERABLE containment automatic isolation i

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 i administrative control as permitted by Specification 3.6.3. l l

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

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

test, by leak rate testing the seal with gas at P,, 44 psig, and l verifying that when the measured leakage rate for these seals is l added to the leakage rates determined pursuant to Specifica-i tion 4.6.1.2d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,. ;

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) "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 penet.ations shall be verified

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closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

l WATERFORD - UNIT 3 3/4 6-1 AMENDMENT NO. 75

CONTAINMENT SYSTEMS

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CONTAINMENT LEAKAGE i

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

j a. An overall integrated leakage rate of:

1. Less than or equal to L 0 1 containment air per 24 h,our.50 s at percert by weight of the P,, 44 psig, or 2* Less than or equal to L 0 containment air per 24 h,our.25 percent by weight of the !

22 psig. s at a reduced pressure of P,, ;

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A combined leakage rate of less than or equal to 0.60 L for all penetrationsandvalvessubjecttoTypeBandCtestsw$en pressurized to P,.

c.

A combined bypass leakage rate of less than or equal to 0.06 L, for i all penetrations that are secondary containment bypass leakage paths when pressurized to P,.

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

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L*, as applicable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.06 L restore 0.60 t L ,he overall integrated leakage rateequal to less to tha l

0.75 leakageL,,,or rate for lessall penetrations than orand equal to 0.75 and v as applicable, L'a,lves the combinedsubject to ype B and C tests to less than or equal to 0.60 L i equal to 0.06 L, prior to inc, and the bypass leakage rate to less than or above 200*F. reasing the Reactor Coolant System temperature l

SURVEILLANCE RE0UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated as follows:

WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO. 5 66,110

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I CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

a. Type A tests shall be conducted in accordance with the schedule and criteria specified in 10 CFR 50, Appendix J, as modified by approved exemptions.

b. 44 psig, at Type B and intervals C teststhan no greater shall24 be conducted months except with gas at P., involving:

for tests

1. Air locks,

2. Purge supply and exhaust isolation valves with resilient !

material seals. '

e WATERFORD - UNIT 3 3/4 6-3 AMENDMENT NO. 4 5 ,110

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS' (Continued) l

c. Purge supply and exhaust isolation valves with resilient material l seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.7.2.

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, d. The combined bypass leakage rate shall be determined to be less than l l by applicable Type B and C tests at least once '

or equal per to excep 24 months 0.06 L,t for penetrations which are not individually l testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while ,

the containment is pressurized to P., 44 psig, during each Type A j

test. '

e. Air locks shall be tested and demonstrated OPERABLE per Surveillance l l Requirement 4.6.1.3. -

f. The provisions of Specification 4.0.2 are not applicable. l I

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WATERFORD - UNIT 3 3/4 6-4 AMENDMENT NO. 4786,110

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i PAGES 3/4 6-6 THROUGH PAGE 3/4 6-8 I NOT USED WATERFORD - UNIT 3 m

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fCONTAINMENT SYSTEMS 1 i

CONTAINMENT AIR LOCKS .

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' LIMITING CONDITION FOR OPERATION

' 3. 6. L 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' l- air lock door shall be closed, and 1

b. An overall air lock leakage rate of less than or equal to 0.05 L, at ,

P,, 44 psig.

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

} ACTION:

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a. With one containment air lock door inoperable:

1 - 1. Maintain at least the OPERABLE air lock door closed and either I< restore the ' inoperable air lock door to OPERABLE status 'within L 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 .

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 door 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 STANDDY 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 .

WATERFORD - UNIT 3- .3/4 6-9

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CONTAINMENT SYSTEMS 1

! SURVEILLANCE REQUIREMENTS l

4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each closing, except when the air lock is j being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by '

j verifying seal leakage to be less than or equal to 0.005 L, when determined-by pressure decay or precision flow rate measurement with I the volume between the door seals pressurized to greater than or equal I to 10 psig, for at least 15 minutes,

b. By conducting overall air lock leakage tests at not less than P , l 44 psig, and verifying the overall air lock leakage rate is wit $1n j

its limit

1. At least once per 6 months,# and

2. Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.*

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

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The provisions of Specification 4.0.2 are not applicable

This constitutes an exemption to Appendix J of 10 CFR Part 50.

WATERFORD - UNIT 3 3/4 6-10

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, J 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 l 200 F. '

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SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for ear.' Type A containment leakage rate test (reference Specification 4.6.1.2) by ,* 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 degra- '

dation. Any abnormal degradation of the containment vessel detected during 4 the above required inspections shall be reported in a Special Report to the l Commission pursuant to Specification 6.9.2 within 15 days. 1 WATERFORD - UNIT 3 3/4 6-14 4

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l CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM.

LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve (CAP 103,

-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 a.

ACTION:

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

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

Requirement 4.6.1.7.2, restore the inoperable valve (s) to OPERABLE j 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 I 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 . '

SURVEILLANCEJggIREMENTS

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

4.6.1.7.2 At least once per 3 months

each containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.06 L, when pressurized to P,.

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 1 52*

open.

1 9tntil STARTUP following the first refueling outage, the containment purg; supply and exhaust isolation valves shall be tested during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 92 days.

WATERFORD - UNIT 3 3/4 6-15

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! 3/4.6 CONTAINMENT SYSTEMS l

4 BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY 4

i Primary CONTAINMENT INTEGRITY ensures that the release of radioactive 3

materials from the containment atmosphere will be restricted to those leaka paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY accident conditions. radiation doses to within the limits of 10 CFR Part 100 du 141 6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment analyses at the leakage peak accident volume will pressure,not exceed P the value assumed in the safety measured overall integrated leakage rate I. As an added conservatism, the equal to 0.75 L or less than or equal to 0.76 s further L aslimited to less than or i applicable during '

'performanceofIheperiodicteststoaccountfor,,possibledegradationofthe containment leakage barriers between leakage tests.

The surveillance requirements for measuring leakage rates are consistent with the requirements of 10 CFR 50, Appendix J and performed in accordance-with the methods and provisions of ANSI N45.4-1972.

Secondary containment bypass leakage paths previously, Table 3.6-1, have been incorporated into plant procedure UNT-005.026. '

3/4.6.1.3 CDNTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required leak rate. to meet the restrictions on CONTAINMENT INTEGRITY and containment 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 B 3/4-6-1 AMENDMENT NO. 76766,110

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PROCESS CONTROL PROGRAM (Continued)

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l A determination that the change will maintain the overall conformance of the solidified wasta product to existing

requirements of Federal, State, or other applicable regulations.

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j Shall become effective after review and acceptance by the PORC and 4

the approval of the Plant Manager.

l 6.14 0FFSITE DOSE CALCULATION K^?LIAL (nneM) l l

. 6.14.1 The 00CM shall be approved by the Commission prior to implementation.

1 l 6.14.2 Licensee-initiated changes to the ODCM: .

I a. Shall be documented and records of reviews performed shall be -

i retained as required by Specification 6.10.3p. This document shall i contain:

1. Sufficle'it information to support the change together with the appropriate analyses or evaluations justifying the change (s) and l 2. A determination that the change will maintain the level of i- radioactive effluent control required pursuant to 10 CFR l 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 l CFR Part 50 and not adversely impact the accuracy or reliability i of effluent, dose or setpoint calculations.

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! b. Shall become effective after review and acceptance by the PORC and i

the approval of the Plant Manager. )

, c. Shall be submitted to the Commission in the form of a complete, i

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

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G WATERFDRD - UNIT 3 6-24 Amendment No. 66A4,116

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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.11 RADIATION PROTECTlON PROGRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 6.12 HIGH RADIATION AREA.. ..... . ..... . ........ .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 6.13 PROCESS CONTROL PROGRAM ...... .... ..... ..... . ... ......... ... . . . . . . ... ....... ... 6-23

- 6.14 OFFSITE DOSE CALCULATION MANUAL... . . . . . . . . . . . . . . . . . . . . . . . . . . .. 6-24 i

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

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, WATERFORD - UNIT 3 XVill Amendment No. 68 t

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1 3/4.6 CONTAINMENT SYSTEMS ,

3/4.6.1 PRIMARY CONTAINMENT 4

CONTAINMENT INTEGRITY l_IMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT 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 i 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILt ANCE REQUIRFMFNTS 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 administrative control as permitted by Specification 3.6.3 i

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

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.

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

- containment and are locked, sealed or otherwise secured in the closed position. These penetrations i shall be verified closed during each COLD SHUTDOWN except that such verification need not be '

performed more often than once per 92 days.

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WATERFORD - UNIT 3 3/4 6-1 AMENDMENT NO. M j i

CONTAINMENT SYSTEMS .l, CONTAINMENT LEAKAGE l

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I IMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be in accordance with the Containment Leakage Rate ,

Program. ~l 4 ;

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

. ACTION:

1 With containment leakage rates not within limits, restore containment leakage rates to within limits

! prior to increasing the Reactor Coolant System temperature above 200 F. ]'

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SURVFili ANCE REQUIRFMFNTS - !

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4.6.1.2 The containment leakage rates shall be determined in accordance with the Containment i Leakage Rate Testing Program.-

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1 WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO. 440 !

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

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WATERFORD - UNIT 3 3/4 6-3 AMENDMENT NO. 440 l

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CONTAINMENT SYSTEMS

, CONTAINMENT AIR LOCKS ,

i I IMITING CONDITION FOR OPERATION 4

i 3.6.1.3 Each containment air lock shall be OPERABLE with: ;

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i' a. Both doors closed except when the air lock is being used for normal transit entry and exit i through the containment, then at least one air lock door shall be closed, and l

! b. An overall air lock leakage rate in accordance'with the Containment Leakage Rate

Testing Program.

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 5

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

,f 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 .

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4. The provisions of Specification 3.0.4 are not applicable. !

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b. With the containment airlock inoperable, except as the result of an inoperable air lock l door, maintain at least one air lock door 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ;

i WATERFORD - UNIT 3 3/4 6-9 Amendment No.

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l CONTAINMENT SYSTEMS i

SURVFili ANCE REQUIRFMFNTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

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a. By verifying seal leakage in accordance with the Containment Leakage Rate Testing Program, i

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

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

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i WATERFORD - UNIT 3 3/4 6-10 Amendment No.

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I CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY I l_IMITING 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. {

l SURVFil1 ANCE REQUIRFMFNTS 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 l 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.

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

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CONTAINMENT SYSTEMS

- CONTAINMENT VENTILATION SYSTEM i IMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve (CAP 103, 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:

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 .

b. With a containment purge supply and/or exhaust isolation valve (s) having a measured )

leakage rate exceeding the limits of Surveillance 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 j 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 .

r SURVEILLANCE REQUIRFMENTS 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 Each containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE in accordance with the Containment Leakage Rate Testing Program at least once per 184 days an_d once within 92 days after opening the valve.

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 verifying that the mechanical stops limit the valve opening to a position < 52* open.

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

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a 3/4.6 CONTAINMENT SYSTEMS BASES 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 The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to < 0.75 La during the performance of periodic Type A tests to account for possible degradation of the containment leakage barriers between leakage tests. Also, the summation of penetration leakages measured during Type B and C testing is limited to 0.6 La. At all other times between required leakage rate tests, overall containment leakage is limited to La. The maximum allowable containment leakage rate, La, is 0.5 % by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at the design basis accident pressure, Pai of 44 psig.

The surveillance requirements for measuring leakage rates are consistent with the requirements of 10CFR50, Appendix J, Option B, and leakage rate testing is performed in accordance with the guidelines contained in Regulatory Guide 1.192, ' Performance-Based Containment Leak-Test Program'. Leakage rate testing is conducted periodicahy u 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 identified in Table 3.6-1 are now identified in the Technical Requirements Manual.

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 B 3/4 6-1 AMENDMENT NO. 440

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{~ ADMINISTRATIVE CONTROLS l PROCESS CONTROL PROGRAM' (Continued)-

$ 2. ' A determination that the change will maintain the overall conformance of the solidified l waste product to existing requirements of Federal, State, or other applicable

regulations.

1 j b. Shall become effective after review and acceptance by the PORC and the approval of j, the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM i 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

! 6.14.2 Licensee-initiated changes to the ODCM:

I a. Shall be documented and records of reviews performed shall be retained as required by

Specification 6.10.3p. This document shall contain; f

j

1. Sufficient information to support the change together with the appropriate analyses or

{ evaluations justifying the change (s) and i

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 l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of j effluent,' dose, or setpoint calculations.

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

I

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire l ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for .l 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, clearly indicating the area of the page that was changed,' a id shall indicate the date (e.g., month / year) the change was implemented.

6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM i A prograin 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-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment intemal pressure for the design basis loss of coolant accident, Pa.

is 44 psig.

The maximum allowable containment leakage rate, La, is 0.5% of containment air weight per day at

. Pa.

WATERFORD - UNIT 3 6-24 AMENDMENT NO. 64,847444

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. <a #

CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued)

Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance criteria is s 1.0 La. During the first unit startup following each test performed in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and s 0.75 La for Type A tests.

b. Air lock acceptance criteria are:

1. Overall air lock leakage rate is s 0.05 Lawhen tested at 2 Pa.

2. Leakage rate for each door is s 0.01 La when pressurized to 210 psig.

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.

l WATERFORD - UNIT 3 6-24 AMENDMENT NO. 68,84,116

ML20135A775

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