ML20244B233

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Proposed Tech Specs Re App J Hydrostatic Testing
ML20244B233
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/06/1989
From:
Public Service Enterprise Group
To:
Shared Package
ML20244B224 List:
References
NUDOCS 8906130037
Download: ML20244B233 (6)


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ATTACHMENT 2

.HCGS LICENSE CHANGE REQUEST 89-05, NLR-N89100, ,

HYDROSTATIC APPENDIX;J TESTING'

' a The following Technical: Specifications have.

b e e n r e v i s e d t o . r e f l e c t -.:. t h e p r o p o s e d -.c h a n g e ::.

Technical Specification ~ Pace 3.6.1.2.e 3/4.'6-2land'. ,

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4'.6.1.2.1 Table 3.6.3-1 3/4-6-42o

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CONTAINMENT SYSTEMS' PRIMARY CONTAINMENT LEAKAGE -

d LIMITING CONDITION FOR OPERATION q

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3.6.1.2 Primary containment leakage rates shall be limited to:

a. An overall integrated. leakage rate of less than or equal to La , 0.5 per-cent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 48 y p j, g
b. A combined leakage rate of less than or equal to 0.60 L for all penetrationsandallvalveslistedinTable3.6.3-1,ex8eptformain I 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 when pressurized to P,, 48.1 psig. ]

c. *Less than or equal to 46.0 scfh combined through all four main steam j lines when tested at 5 psig (seal system AP).
d. A combined leakage rate of less than or equal to 10 gpm for; all con-tainment isolation valves which form the boundary for the long aterm seal of the feedwater lines in Table 3.6.3-1, when tested at 1.10 Pa, 52.9 psig.

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

containment isolation valves in~hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment, when tested atgPa,

52. 9 = g psig ap. 1.10 APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

ACTION:

With-

a. The measured ov'erall integrated primary containment leakage rate exceeding 0.75 L, 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 exceeding 0.60 La ' I

c. The measured leakage rate exceeding 46.0 scfh combined through all four main steam lines, or
d. The measured combined leakage rate for all c..,ntainment 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 INSERT
e. The measured combined leakage rate for all other/ containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment exceeding 10 gpm, restore:
a. Theoverallintegratedleakagerate(s)tolessthanorequalto0.75La'""!

HOPE CREEK 3/4 6-2

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' CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continue'd)

' ACTION (Continued) -

b. The 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 l other valves wh4b are hydrostatic.11y tested per Table 3.6.3-1, subject to Type 8 and C tests to.less than or equal to 0.60 L,, and 1

c. The leakage rate t> less than or equal to 46.0 scfh combined through 1 all four main steam lines, and  ;
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  !

to less than or equal to 10 gps, and-

e. The combined leakage rate for all other/ containment l isolation valves-in j 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'F. ,

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SURVEILLANCE REQUIRC4ENTS .

1 1

4.'.1.2 6 The primary containment leakage rates shall be. demonstrated at thei i following test schedule and shall be determined in conformance with the criteria.

specified in Appendix J of 10.CFR 50 using the methods and provisions of ANSI i N45.4 - 1972:

a. 'Thre, Type A Overall Integrated Containment Leakage Rate tests'shall-be conducted at 40 + 10 month intervals during shutdown at P,,.

48.1 psig, during each 10 year service' period. 'The. third-test of.

each set shall be conducted during the shutdown for the 10 year plant-inservice. inspection. ' '

b. If any periodic Type A test fails to meet 0.75,L,, the 'est~t schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L,, a Type A test shall be performed at least every 18 months until two consecutive Type A- tests: meet 0.75 L,, at which time the above test-schedule may be resumed,
c. The accura:y of.each Type A test shall be verified Dy'a supplemental test which:

, .1. Confirms the accuracy of-the test by verifying that.the difference--

- between.the supplemental data and the Type A test data is within-0.25 L,.

2. Has' duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3. ' Require's the quantity of gas injected into the containment'or ,

, bled from the' containment during the supplemental test to be,

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between 0.75 L, and 1.25 L,.

HOPE CREEK , 3/4 6-3

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INSERT.'for Technical Specification 3.6.1.2.e, pages 3/4-6-2 & 6-3'-

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. CONTAINMENT' SYSTEMS.

ERVEILLANCE REQUIREMENTS (Cor,tinued) '

.The formula to be used is: [L, + L,, .0.25 L,] s Lc Y El o *L am

+

0.25 L,] where L es supplement test result; L,s superimposed. leakage;

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and L,a measured Type A-leakage..

d.

Type B and C tests shall be conductedw 'ith gas at P,, 48.1 psig*,

at intervals no ' greater'than 24 months ** except for tests involving: '

1. Air locks,
2. Main steam line isolation valves,- 1
3. Valves pressurized with fluid from a seal system, 4.

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All containment isolation valves in hydrostatically't'sted lines e

in Table.3.6.3-1 which penetrate the primary containment, and j 4 5.. Purge supply and exhaust isolation valves with resilient material seals. -

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

'f.

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

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g. 'i Containment isolation valves which form the boundary for the;1ong- -

i term seal of the feedwater lines in Table 3.6.3-1 shall be hydrostati-  !

cally tested at 1.10 P,, 52.9 psig, at least once per 18 months. I

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 18, months. i

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' Purge supply and exhaust isolation valves with resilient material seals l shall be tested and demonstrated OPERABLE per. Surveillance.Regbirements 4.6.1.8.2.In d '.5.1.0.0.I ,

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The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, 4.6.1'2.d. and 4.6.1.2.e.

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  • Unless a hydrostatic test is' required per Table 3.6.3-1.

C*A Type C test interval extension to the first refueling outage is permissible i

i for. primary containment isolation valves listed in-Table 3.6.3-1, which are i identified in Public Service Electric & Gas Company?s letter to~ the NRC-(letter No. NLR-N87047), dated April 3,1987, as needing a plant outage to i

test. ;For this one time test interval, tha' requirements of Section 4.0.2

.are not applicable.

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j HOPE CREEK 3/4 6-4 Amen'dment No.4 l

TABLE 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES

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NOTES NOTATION ~

1. Main Stear ' solation Valves are sealed with a' seal system that maintains a positive pressure.of 5 psig above reactor pressure. Leakage is in-leakage and is not added to 0.60 La allowable leakage.*
2. Containment Isolation Valves are sealed'with a water seal from the..'HPCI and/or RCIC system to. form the long-term seal boundary of.the feedwater; lines. . The valves are tested with water at 1.10 Pa, 52.9 psig, to ensure the' seal boundary will prevent by pass leakage. . Seal boundary l liquid leakage will be limited to 10 gpm.

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3. ' Containment Isolation Valve, Type C gas test at Pa, 48.1 psig. Leakage.

added to 0.60La allowable leakage. -

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4. Containment Isolation Valve, Type C water. test a Pa, 6 sig A P.-

Leakage added to 10 gpm allowable leakage. .

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5. Containment boundary is discharge nozzle of relief valve, leakage tested during Type A test.*
6. rywell and suppression chamber p~ressure and level instrument root valves and excess flow check valves, leakage tested during Type A.*
7. Explosive shear valves (SE-V021'through SE-V025) not Type C tested.*
8. Surveillance to be performed per Specification 3.6.1.8.
9. All valve I.D. numbers are preceded by a numeral I which represents an -

Unit 1 valve.  !

10. The reactor vessel head seal leak detection.line (penetration J5C) excess flow check valve (BB-XV-3649) is not subject to OPERABILITY testing. This valve will not be exposed to primary system pressure except under the unlikely conditions of a seal failure where it could  ;

be partially pressurized to reactor pressure. Any leakage path is ^

restricted at the source; therefore, this valve need not be ,

OPERABILITY tested. .

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HOPE CREEK 3/4 6-42

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