ML20059E923

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Revised Proposed TS Pages for Increase in Allowable MSIV Leakage Rate & Deletion of MSIV Leakage Control Sys
ML20059E923
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 01/06/1994
From:
GEORGIA POWER CO.
To:
Shared Package
ML20059E921 List:
References
NUDOCS 9401130057
Download: ML20059E923 (5)
v • d • e


Text

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Enclosure 4 Edwin I. IIatch Nuclear Plant - Unit 2 Request to Revise Technical Specifications:

Increase in Allowable MSIV Leakage Rate and Deletion of the MSIV Leakage Control System P_ age Change Instructions The proposed changes to the Plant Hatch Unit 2 Technical Specifications will be incorporated as follows:

Eagg instruction 3/4 6-3 Replace 3/4 6-4 Replace 2

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l 4468 E4-1 9401130057 940106 Y PDR ADOCK 05000366 p;g P PDR 0;!

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:
1. s L a, 1.2 percent 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 Pa , 57.5 psig, or
2. s L t, 0.849 percent 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 a reduced pressure of Pt , 28.8 psig,
b. A combined leakage rate of:
1. s 0.60 La for all penetrations and valves, except for main steam isolation valves, subject to Type B and C tests when pressurized to Pa , and
2. s 0.009 La for the following penetrations *:

(a) Main steam condensate drain, penetration 8; (b) Deleted (c) Reactor water cleanup, penetration 14; (d) Equipment drain sump discharge, penetration 18; (e) Floor drain sump discharge, penetration 19; and (f) Chemical drain sump discharge, penetration 55; (g) Deleted

c. When tested at 28.8 psig**, 100 scf per hour for any one main steam isolation valve and a combined maximum pathway leakage rate of 250 scf per hour for all four main steam lines.

APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

  • Potential bypass leakage paths.

HATCH - UNIT 2 3/4 6-3 techsp\h\88-20u2\101

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continuedi ACTIOM:

With:

a. the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L,, as applicable, or i
b. the measured combined leakage rate for all penetrations and valves, except main steam isolation valves, subject to Type B or with the measured combined and C tests leakage rateexceeding 0.60 L,d potential bypass leakage path for all specifie penetrations exceeding 0.009 L,, or
c. the main steam isolation valve measured leak rate exceeding 100 scf per hour for any one MSIV or a total maximum pathway '

leakage rate of > 250 scf per hour for all four main steam lines, Restore:

a. the overall integrated leakage rate (s) to < 0.75 L, or < 0.75 L, as applicable, and
b. the combined leakage rate for all penetrations and valves, except main steam isolation valves, subject to Type B and C tests to s 0.60 L and the combined leakage rate for the specified potential bypass leakage path penetrations to l s 0.009 L , and '
c. the leakage rate to s 11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage rate to s 250 scf per hour, Prior to increasing the reactor coolant temperature above 212 F.

SURVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the 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 N45.4 - (1972):

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at either P 57.5 28.8 psig during each 10-year service,, period.psig or at PThe third Test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

HATCH - UNIT 2 3/4 6-4 techsp\h\3_4-64U2. Pro \240

_ ..- _-. . . _ _ . _ _ _. _ _ . _ _ . -_.-__ _ . _m r

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 -Primary containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:
1. s L a,1.2 percent 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 a , 57.5 psig, or
2. 5 Lt, 0.849 percent by weight of the containment air per-24 hours at a reduced pressure of Pt , 28.8 psig.  ;
b. A combined leakage rate of:
1. 5 0.60 La for all penetrations and valves, except for main steam isolation valves, subject to Type B and C tests when pressurized to Pa, and
2. s 0.009 La for the following penetrations *:

(a) Main steam condensate drain, penetration 8;  !

(b) Deleted l (c) Reactor water cleanup, penetration 14; (d) Equipment drain sump discharge, penetration 18; (e) Floor drain sump discharge, penetration 19; and (f) Chemical drain sump discharge, penetration 55; (g) Deleted D N scf per hour for any one main steam isolation valvep hen-g'en tested at 28.8 psig.* and a cornbin 4 Icar47c PA&c ed o415o th4Almum pa%wd 3 cf pe, ha S w ati 4. o rn ain 34ee m y APPLICABILITY: When PR! MARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

  • Potential bypass leakage paths. )

HATCH - UNIT 2 3/4 6-3 Amendment l'a. 29,101 .

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1

-,n , , . - , , , - - - - -n.~- - ,

e

  • e o CONTAINMENT SYSTEMS j

'l LIMITING CONDITION FOR OPERATION (Continued) ,

ACTION:

With:

a. the measured overall integrated containment leakage rate

. exceeding 0.75 L a r 0.75 L , as applicable, or, t

b. the measured combined leakage rate for all penetrations and ,

valves, except main steam isolation valves, subject to Type 8 and C tests exceeding 0.60 La or with the measured combined leakage rate for all specified potential bypass leakage path  !

penetrations exceeding 0.009 La, or

c. the main steam isolatio'n valve measured leak rate exceeding i

/* +1-5 scf per hour for any one MSIV go r 4 +o4at rnax;inum pai6way leax4S e Yake a5 ? L50 Sct e es- h ouw t er ass .;aus rnain s Seam San es, Restore:

i

a. the overall integrated leakage rate (s) to < 0.75 La car < 0.75 Lt as applicable, and the combined leakage rate for all penetrations and valves,  !

b.

except main steam isolation valves, subject to Type B and C -l i

tests to s 0.60 La and the combined leakage rate for the specified potential bypass leakage path penetrations to s 0.009 La, and g

c. the leakage rate to s 11.5 scf per hour for any one main steam isolation valve +hy 44 cy c en As 100 s c( fee.r heue, an A regg,rc +8 e

- corn b a n < ci m4 Mtwum pa%w ay l ea kaye Paf e to 6 250 s e f f:>cp s,,,,,, i

/

Prior to increasing the reactor coolant temperature above 212 F. 1 SURVEILLANCE REQUIREMENTS 1 l 4.6.1.2 The containment leakage rates shall be demonstrated at the l following test schedule and shall be determined in conformance with the i criteria specified in Appendix J of 10 CFR 50 using the methods and  ; i provisions of ANSI N45.4 - (1972):  ;

i

a. Three Type A tests (Overall Integrated Containment Leakage i Rate) shall be conducted at 40 + 10 month intervals during shutdown at either Pa , 57.5 psig or at P , 28.8 psig during each 10 year service period. Thethirdkestofeachsetshall y !

be conducted during the shutdown for the 10 year plant inservice inspection.

HATCH - UNIT 2 3/4 6-4 i

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