Text

Proposed Tech Specs Re Primary Containment Leakage Testing
	ML17333A020
Person / Time
Site:	Columbia
Issue date:	01/19/1996
From:	; WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	;
Shared Package
ML17291B208	List: GO2-96-014, Application for Amend to License NPF-21 Re Primary Containment Leakage Testing; ML17333A020;
References
	NUDOCS 9601290266
	Download: ML17333A020 (31)
	v • d • e

CONTA NHENT SYST e

IHITING CONDITION FOR OPERATION Continued

~A T ON:

(Continued) c ~

d.

The leakage rate to less than or equal to 11.5 scf per hour for any one main steam line isolation valve, and The combined leakage rate for all ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such va7ves,

. prior to.increasing reactor coolant system temperature above 200'F.

SURVEILLANCE RE UIREHENTS 4.6.1.2 Perform required primary containment leakage rate testing in accordance with the Primary Containment Leakage Rate Testing Program described in Specification 6.8.4.f.

a.

Deleted b.

Deleted c.

Deleted L =3 0 e)ci e-ign

,eQ dO ALA o'o

%u AJCI OCt N

( vM c)ce I OGI

'0 o.L, t

ett WASHINGTON NUCLEAR - UNIT 2 3/4 6-3 Amendment No. 137

l

CONTROLLED COPY s

SURVEILLANCE RE UIREHEHTS Continued d.

Deleted e.

Deleted f.

Hain steam line isolation valves shall be leak tested at least once per 30 months.

g.

Delete h.

Deleted i.

Deleted j.

Deleted WASHINGTON HUCLEAR - UNIT 2 3/4 6-4 Amendment Ho. 44&44,137

CONTA NM NT S ST MS CONTROLLED COPY LIMITING CONDITION FOR OPERATION Continued

~CT~Ot (Continued) 3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

The provisions of Specification 3.0.4 are not applicable.

C With the primary containment air lock inoperable, except as a result of an inoperable air lock door or an inoperable interlock mechanism, 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 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:

a.

C.

By verifying interlock operation (i.e., that only one door in each air lock can be opened at a time).

1.

Prior to using the air lock in Operating Conditions 1,

2 and 3

but not required more than once per 6 months, 2.

Following maintenance that could affect the interlock mechanism.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each closing, except when the air Tock is 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 verifying seal leakage rate less than or equal to 0.025 L, when the gap between the door seals is pressurized to 10 psig.

By conducting an overall air lock leakage test at P and by verifying that the overall air lock leakage rate is within its limit:

1.

At intervals determined in accordance with 10 CFR 50 Appendix J using the methods and provisions outlined in the Primary Containment Leakage Rate Testing Program described in Specification 6.8A.f., and 2.

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

Exception to Appendix J of 10 CFR 50.

WASHINGTON NUCLEAR UNIT 2 3/4 6-6 Amendment No. 9,137

comaoLLEo co< v ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) d.

Radioactive Effluent Controls Pro ram (continued) 9)

Limitations on the annual and quarterly dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE 80UNDARY conforming to Appendix I to 10 CFR Part 50, 10)

Limitations on venting and purging of the containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable, and Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

e.

Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the r adiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure

pathways, and (2) verification of ihe accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the OOCM, (2),conform to the guidance of Appendix I to 10 CFR Pari 50, and (3) include the following:

1)

Monitoring, sampling, analysis and reporting of radiation and radionuclides

'in the environment in accordance with the methodology and parameters in the OOCM.

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the 'ITE 80UNOAR".are identified and that modifications to the monitoring program are made if required oy the results of this

census, and 3)

Participation in the Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program ror environmental monitoring.

Prim Containmcnt Leaka e Rate Testin Pro am Aprogram shall be established to implement the leakage testing for the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J. This program shall be in accordance with the guidelines ofRegulatory Guide 1.163, Revision 0, "Performance-Based Containment Leak-Test Program", as modified by approved exemptions and the followingexceptions:

1.

Compensation forflowmeter inaccuracies in excess ofthose specified in standard ANSIIANS56.8-1994 willbe accomplished by increasing the actual instrument reading by the amount ofthe Mlscale inaccuracy when assessing the effect oflocal leak rates against the criteria established in Technical Specification 3.6.1.2.b.

WASHINGTON NUCLEAR - UNIT 2 6-1.5b Amendment No. 98

ATTACHMENT3 Basis for No Significant Hazards Consideration Determination Page 1 of 2 In accordance with the criteria established in 10 CFR 50,92, the Supply System has evaluated the proposed amendment to Operating License NPF-21 and determined that it does not represent a significant hazards consideration.

The following discussion is provided in support of this conclusion.

Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed license amendments revise the Technical Specifications to reflect the adoption of a performance-based containment leakage testing program. The Nuclear Regulatory Commission approved the use of a performance-based option when it amended 10 CFR Part 50 Appendix J (60 FR 49495).

No changes are proposed to containment leakage limits currently specified in the WNP-2 Technical Specifications.

Consequently, the radiological consequences of containment leakage during and after an accident are unchanged, and remain as documented in the Final Safety Analysis Report.

The proposed change is limited to allowing use of either Option A or Option B of Appendix J of 10 CFR Part 50 as alternatives in establishing requirements for containment leak testing, and, because no changes to allowable leakage rates are being proposed, the effect would be limited to establishing testing schedules on the basis of actual performance of the primary containment and penetrations per Appendix J Option B, rather than as prescribed by Appendix J Option A.

The test methodology required under Appendix J Option B is defined in ANSI/ANS 56.8-1994, and is technically equivalent to that currently in use at WNP-2.

Neither the frequency of Type A, B, and C containment testing nor leak test methodology is identified as a factor in initiation, progression, or mitigation of any accident.

Therefore the proposed change does not involve a significant increase in the probability or consequences of a previously evaluated accident.

Does the change create the possibility of a new or different kind of accident from any previously evaluated?

The proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

The proposed license amendments revise the Technical Specifications to reflect the adoption of a performance-based containment leakage testing program. The Nuclear Regulatory Commission approved the use ofa performance-based option when it amended 10 CFR Part 50 Appendix J (60 FR 49495).

Page 2 of 2 The proposed change is limited to allowing use of either Option A or Option B of Appendix J of 10 CFR Part 50's alternatives in establishing requirements for containment leak testing, and, because no changes to allowable leakage rates are being

proposed, the effect would be limited to establishing testing schedules on the basis of actual performance of the primary containment and penetrations per Appendix J Option B, rather than as prescribed by Appendix J Option A. The test methodology required under Appendix J Option B is defined in ANSI/ANS 56.8-1994, and is technically equivalent to that currently in use at WNP-2. Type A, B, or C testing willcontinue to be performed using these accepted

methods, although on a schedule permitted under Appendix J. Therefore the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

Does the change involve a significant reduction in margin of safety?

The proposed change does not involve a significant reduction in margin of safety, but willresult in reduction ofcumulative occupational radiation exposure due to reduced leak test frequencies.

An assessment of potential increased risk to the public resulting from reduced containment test frequencies, as may result from implementation of Option B of Appendix J, is summarized in NUREG-1493, "Performance-Based Containment Leak-Test Program."

The conclusion is that reducing the frequency of integrated leak rate testing (ILRT) from the current three per ten-year period to one in a twenty year period would lead to only a small increase in risk because (1) ILRTs identify very few leaks that are not also found by routine Type C local leak rate tests, and (2) the experience is that as-found test results for the few failed ILRTs were only marginally above the acceptance criterion which are very conservative with respect to public health and safety.

The report identifies that Type B and C local leak rate tests identify the majority

(>95%) of all unacceptable leaks.

However, a performance-based schedule for Type B and C tests can be adopted without significant risk because Type B test failures are infrequent, and essentially all detected leaks are through containment isolation valves.

Based on a detailed evaluation, no correlation of Type C test failures was found with type of containment isolation valve or plant service, but it was possible to correlate Type C test failures with repeated failures ofindividual components.

A performance-based test schedule would require continuing frequent testing of valves that failed prior tests, and would therefore result in approximately the same test frequency for such valves as is currently required under Appendix J Option A.

Therefore, the proposed change does not involve a significant reduction in margin of safety because any reduction in test frequencies would be based on actual measured performance, and would therefore not result in less frequent testing of Type B or C penetrations having a history ofweaker performance.

The Primary Containment Leakage Rate Testing Program willassure that the overall leakage rate, and thus onsite and offsite post-accident radiation exposure, is maintained within allowable limits.

Page 1 of 17 "Improved" Technical SpeciTication for Containment Leakage Testing

Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6. 1. 1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION RE(UIRED'CTION COMPLETION, TIME A.

Primary containment inoperable.

A.1 Restore primary containment to OPERABLE status.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B.

Required Action and associated Completion Time not met.

B.l AND B.2 Be in MODE 3.

Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours WNP-2 3.6-1 Revision A

e Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and leakage rate testing except for primary containment air lock testing, in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

The leakage rate acceptance criterion is

< 1.0 L..

However, during the first unit startup following testing performed in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, the leakage rate acceptance criteria are

< 0.6 L. for the Type 8 and Type C tests, and

< 0.75 L. for the Type A test.

NOTE------

SR 3.0.2 is not applicable In accordance with 10 CFR 50, Appendix J, as modified by approved exemptions SR 3.6.1.1.2 Verify drywell to suppression chamber bypass leakage rate is less than or equal to the equivalent leakage rate through an orifice 0.005 ft't an initial differential pressure of Z 1.5 psid.

24 months AND

---NOTE------

Only required after two consecutive tests fail and continues until two consecutive tests pass 12 months WNP-2 3.6-2 Revision A

Prim Containment Air Lock 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6. 1.2 Primary Containment Air Lock LCO 3.6. 1.2 The primary containment air lock shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS-NOTES l.

Entry and exit is permissible to perform repairs of the air lock components.

2.

Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"

when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One primary containment air lock door inoperable.

NOTES------------

1.

Required Actions A.l, A.2, and A.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2.

Entry and exit is permissible for 7 days under administrative controls.

A.l Verify the OPERABLE door is closed.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND (continued)

WNP-2 3.6-3 Revision A

Pri Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.

Lock the OPERABLE door closed.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.3

NOTE---------

Air lock doors in high radiation areas or areas with 'limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE door is locked closed.

Once per 31 days B.

Primary containment air lock interlock mechanism inoperable.

NOTES------------

1.

Required Actions B.l',

8.2, and B.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2.

Entry into and exit from primary containment is permissible under-the control of a dedicated individual.

B.l Verify an OPERABLE door is closed.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND (continued)

MNP-2 3.6-4 Revision A

Prim Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COHPLETION TIME B.

(continued)

B.2 Lock an OPERABLE door closed.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.3

NOTE-------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE door is locked closed.

Once per 31 days C.

Primary containment air lock inoperable for reasons other than Condition A or B.

C.1 Initiate action to evaluate primary containment overall leakage rate per LCO 3.6.1.1, using current air lock test results..

Immedi ately AND C.2 Verify a door is closed.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C.3 Restore air lock to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

WNP-2 3.6-5 Revision A

prir Containment Air Lock 3.6.1.2 ACTIONS continued CONDITION RE(UIRED ACTION COMPLETION TIME D.

Required Action and associated Comp1etion Time not met.

0.1 AND Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months MNP-2 3.6-6 Revels>on A

Pri Containment Air Lock 3.6.1.2 SURVEILLANCE REQUIREMENTS

'SURVEILLANCE FREQUENCY SR 3.6.1.2.1

-NOTES-1.

An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2.

Results shall be evaluated against acceptance criteria of SR 3.6. 1. 1.1 in accordance with 10 CFR 50,.

Appendix J, as modified by approved exempti,ons.

Perform required primary containment air lock leakage rate testing in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

The acceptance criteria for air lock testing are:

a.

Overall air lock leakage rate is

< 0.05 L, when tested at > P,.

b.

For each door, leakage rate is z 0.025 L. when the gap between the door seals is pressurized to

> 10 psig.

NOTE------

SR 3.0.2 is not applicable In accordance with 10 CFR 50, Appendix J, as modified by approved exemptions SR 3.6. 1.2.2 Verify only one door in the primary containment air lock can be opened at a

time.

24 months MNP-2 3.6-7 Revision A

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY:

MODES I, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

ACTIONS

-NOTES-1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate.

Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4.

Enter applicable Conditions and Required Actions of LCO 3.6'.l.l, "Primary Containment,"

when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION RE(UIRED ACTION COMPLETION TIME A

NOTE---------

Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with one PCIV inoperable except due to leakage, not within limit.

A.l AND Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual

valve, blind flange, or check valve with flow through the valve secured.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for main steam line AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main steam line (continued)

WNP-2 3.6-8 Revision A

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2

NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per

31. days for isolation devices, outside primary containment AND Prior to entering MODE. 2 or 3 from MODE 4'f primary containment was de-inerted while, in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment.

(continued)

WNP-2 3.6-9 Revision A

t 4

Y R

'V

PCIVs 3.6.1.3 ACTIONS continued CONDITION REQUIRED ACTION COMPLETION TIME B

NOTE---------

Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with two PCIVs inoperable except due to leakage not within limit..

B.l Isolate the affected'enetrationflow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

I hour C

NOTE---------

Only applicable to penetration flow paths with only one PCIV.

One or more penetration flow paths with one PCIV inoperable except due to leakage not within limit.

C.I AND Isolate the affected penetration flow path by use of at. least one closed and de-activated automatic valve, closed manual valve, or blind flange.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for excess-flow check valves (EFCVs)

AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for EFCVs (continued)

WNP-2 3.6-10 Revision A

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.

NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if'rimary containment was.

de-inerted while in MODE',

if not performed within the pl evious'2 days, for isolation devices inside primary containment (continued)

WNP-2 3.6-11 Revision A

PCIVs 3.6.1.3 ACTIONS continued CONDITION RE(UIRED ACTION COMPLETION TIME D.

One or more penetration flow paths with leakage rate not within limit.

D. 1 Restore leakage rate to within limit.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for main steam 1 ine.

AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main steam line E.

Required Action and associated Completion Time of Condition A, B, C, or 0 not met in MODE 1, 2, or 3.

E.1 AND E.2 Be in MODE 3.

Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours F.

Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during MODE 4 or 5.

F.l OR F.2 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

Initiate action to restore valve(s) to OPERABLE status.

Immedi ately Immediately WNP-2 3.6-12 Revision A

i IL l,~

e PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1

-NOTE-Not required to be met when the 24 inch and 30 inch primary containment purge valves are open for inerting, de-inerting, pressure

control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 24 inch and 30 inch primary containment purge. valve is closed.

31 days SR 3.6.1.3.2

-NOTES 1.

Valves and blind flanges in high radiation areas may be verified. by use of administrative means 2.

Not required to be met for PCIVs that are open under administrative controls.,

Verify each primary containment isolation manual valve and blind flange that is located. outside primary containment and is required to be closed during accident conditions is closed.

31 days.

(continued)

WNP-2 3.6-13 Revision A

l le'I

PCIVs 3.6.'1.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR '.6.1.3.3

-NOTES-1.

Valves and blind flanges in high radiation areas may be verified by use of administrative means.,

2.

Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual valve and. blind flange that. is located inside primary'ontainment and is required to be closed during accident.

conditions is closed.:

Prior to entering MODE 2 or=3 from MODE. 4 if primary containment'as.

de-inerted while in MODE-. 4, if'ot performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.

31 days SR 3.6.1.3.5 Verify the isolation time of each power operated and each automatic PCIV, except MSIVs, is within limits.

In accordance-with the Inservice Testing Program SR 3.6'.1.3.6 Verify the isolation time of each MSIV is

> 3 seconds and

~ 5 seconds.

In accordance with the Inservice Testing Program (continued)

WNP-2 3.6-14 Revision A

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal.

24 months SR 3.6.,1.3.8 Verify each EFCV actuates to the isolation position on an actual or simulated instrument line break signal.

24 months SR 3.6.1.3.9 Remove and test. the explosive. squib from each shear isolation valve of the TIP System.

24 months on a STAGGERED TEST'ASIS SR 3.6. 1.3. 10 Verify the'combined leakage rate for all secondary containment.

bypass leakage paths is g 0.74 scfh when pressurized to

> p..

---NOTE--

SR 3.0.2 is not.

applicable In accordance.

with 10 CFR 50,.

Appendix J,, as-modified. by approved exemptions (continued)

WNP-2 3.6-15 Revision A

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.6.1.3.11 Verify leakage rate through each MSIV is g 11.5 scfh when tested at

> 25.0 psig.

NOTE------

SR 3.0.2 is not applicable In accordance with 10 CFR 50, Appendix J,. as modified by approved exemptions, SR 3.6. 1.3. 12.

Verify combined leakage rate of g

1. gpm times the total number of PCIVs through hydrostatically tested lines that penetrate the primary containment is. not:

exceeded when these isolation valves are'ested at. ~ 1.1 P,

NOTE----

SR 3.0.2 is not applicable In accordance.

with 10 CFR 50,, Appendix J,, as modified, by approved exemptions.

WNP-2 3.6-16 Revision A

I e

I'

ML17333A020

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