ML20071A751

Proposed Tech Specs Re Generic Ltr 88-01, NRC Position on IGSCC Austenitic Stainless Steel Piping.

ML20071A751
Person / Time
Site:	Hatch
Issue date:	04/12/1991
From:	GEORGIA POWER CO.
To:
Shared Package
ML20071A749	List: HL-1446, Application for Amends to Licenses DPR-57 & NPF-5 Revising Tech Specs Re Generic Ltr 88-01, NRC Position on IGSCC Austenitic Stainless Steel Piping ML20071A751
References
GL-88-01, GL-88-1, NUDOCS 9104170075
Download: ML20071A751 (15)

Text

. - - -

t

+

LIMillNG CONDlil0NS FOR OPERAll0N $URVllLL ANCT " 10VIREMEN15 3.6.F.2.c. When the time limits or maxi- 4.6.F.2.c.3. Primary coolant pH shall mum conductivity or chloride be measured at least once concentration limits are ex- every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever ceeded, an orderly shutdown reactor coolant conduc-shall be initiated and the tivity is > 2.0pmho/cm reactor shall be in the Cold at 25'C.  !

Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Whenever the reactor is not pressurtred, a sample of the reactor coolant shal)  ;

be analyted at least every l 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for chloride ion I content and pH.

G. Peactor Coo' ant Leakaat* G. Reactor Coolant Leahne

1. Unident' oied and Total Unident$fied sources of reactor Any time irradiated fuel is in coolant system leakage shall be the reactor vessel and reactor checked by the drywell floor coolant temperature it above drain sump system and 212'1: recorded at least once per 8 l hours, Identified sources of

a. reactor coolant system leak- reactor coolant system age into the primary contain- leakage shall be checked by ment f rom unidentified sources the equipment drain sump shall not exceed 6 gpm; system and recorded at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The readings

b. reactor coolant system leakage provided by the primary l into the primary containment containment atmosphere f rom unidentified sources particulate radioactivity shall not increase more than monitoring system, the.

2 gpm within a 24-hour primary containment radio-period or less; and iodine monitoring system, and the primary containment

c. the total reaci.. coolant sys- gaseous radioactivity tem leakage into the primary monitoring system shall 1 containment shall not exceed also be recorded at .least 25 gpm within any 24-hour once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

period. l l when checked in accordance with 4.6.G.

2. Leakaae_ Detection $vstems

a. At least one of the leakag6-measurement instruments assoc-isted with each sump shall be operabia and two of the.other three 161kago detection systems identified in Table 3.2-10 note e shall-be operable when irradiated fuel is

• Not requirea .uring performance of an inservice hydrostatic or leakage test even if react er coolant temperature is above 212'F.

HATCH - UNIT 1 3.6-7 Proposed -TS/03724/214-160 9104170075 910412' PDR ADOCK 05000321 P PDR.  ;

- - . . . - - .-~ . _. - - . -. . - . . . . _ . . - _ . _ - - - _ - _ . --

LIMll!NG CONDlilpN$ F OR OPf RA110N SWRyttllANCE REQUIRlM(Ni$

G. Reactor Coolant leakace

2. (fligge Detection Systems (Cont'd)

a. (Continued) in the reactor vessel and reactor coolant temperature is above 212'F. Further, the primary containment atmosphere particulate radioactivity monitoring system shall be among these two operable systems, or samples shall be obtained and analyzed at least once each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. l b, From and af ter the date that any two of the four systems identified in Table 3.2-10 note c are made or found to be inoperable, but with the primary containment atmosphere particulate radioactivity monitoring system operable, reactor power operation may continue for the succeeding 30 days provided the primary containment atmosphere particulate radioactivity monitoring system reading is checked and recorded at least once each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. l

c. From and af ter the date that any two of the four systems, including the primary containment atmosphere particulate rcdioactivity monitoring system, identified in Table 3.2-10. note c are made or found to be inoperable, reactor power operation may

' continue for the succeeding 30 dayt provided samples of the

( containment atmosphere are l obtained and analyzed at least j once tech 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

l l

t 1

i HATCH - UNIT 1 3.6-8 Proposed TS/03720/214-93 l

.--_~_._._ - - _ _ . . - . . _ _ _ , - _ - . _ . ~ _ _ - - _ _ . , - - . - _ - .

I t.lM111NG COND1110N5 FOR OPE RA1'10N SURVEILLANCE REOUIRIMENTS ,

i

! 3.6.K. EfRUCTURat INT [GRITY a.6.K. $TRUCTURat INTfGRITY l 1. Normal Ct>ndition surveillance ReQuirernents for in-service E

. inspection and testing of A$ME Code The structural integrity of ASME Class 1, 2. and 3 (equivalent) components Code Class 1. 2. and 3-(equiva- shall be applicable as follows:

lent) compona ts shall be j

maintained in accordance with the 1. In-service inspection of A$ME  !

i Surveillance Recuirements of Code Class 1. 2. and-3 (equivalent) specification 4.6.K.

! components and in-serivce testing of A$ME Code Class 1, 2. and 3

2. Off-Normal Conditions (equivalent) pumps and valves shall be performed in accordance with *

a. With the structural $0ction 11 of the ASME Boiler and

' integrity of any A$ME Code Pressure Yessel Code.and applicable Class I component not Addenda as required by 10Cf R50, conforning to the above 5ection 50.55a(g), except where requirements, restore the specific relief has been structural integrity of granted by the Commission pursuant the affected component (s) to 10CFR50, Section 50.55a(g) to within its limit or (6)-(1),

isolate the affected component (s) prior to e increasing the Reartor 2. Performance of the above in-service 4

l Coolant System temperature inspection and testing activities more than 50'F above the shall be in addition to other minimum temperature required specified Surveillance

by NDT considerations. Requirements, s

b. With the structural integrity 3. Nothing in the A$ME Boiler and of any ASME Code Class 2 Pressure Vessel Code shall be-component (s) not conforming construed to supersede the l to the above requirements, requirements of any Technical restore the structural -

Specification.

integrity of the affected component (s) to within its 4. The Intervice Inspection Program limit or isolate the af fected for piping identified in NRC i component (s) prior to .

Generic letter 88-01 shall be increasing the Reactor Ceolant- performed in accordante with the System temperature above 212'F. staff positions on schedule, methods and personnel, and sample

c. With the structural integrity _ expansion included in the generic of any A$ME Code Class 3 letter, except where specific component (s) not conforming to written relief has been granted the above requirements, restore by the Comission.

the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

I L

. HATCH - UNIT 1

.J.6-10: Proposed 15/03720/214-119

.=;

-_,s-,,. . . . . ..,..,_ - ..- . - - . . . - . ..-,._,,_......_.-,,_,,____...,r_.,.... . , , . . , . . , _ , . . _ _ , ._..-.m,_ . . ~ , , . . . , , . .

I APPLICABILITY i

SURVEILLANCE REQUIREMENTS (Continued)

, b. A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified i surveillance interval. -

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification. Surveillance require-ments do not have to be performed on inoperable equipment..

4.0.4 Entry into an OPERATIONAL CONDITION or other specified a.jplicable state shall not be made unless the Surveillance Requirement (s) bss>ciated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows: ,

a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class-1, 2, and 3 pumps and valves shall be performed in accordance with Section XI l

of the ASME Boller and Pressure Vessel Code -and applicable Addenda as. required by 10 CFR 50, Section XI 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to 10 CFR 50. Section 50.55a(g)(6)(1),

b. Surveillance intervals specified in Section XI of-the ASME Boiler and Pressure Vessel Code and applicable Addenda for'the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in thesa Technical Specifications:

HATCH.--UNIT 2 3/4 0-2 Proposed TS/0370q/214-0 tt' f f p og-yw-.4x> y---g-r p--- +g&-- y y ge- %1-w sp p g g 9 we a r-*-g- g9 pqi9-9.g.y,,9., ..sy egwp,9.-. p-peo.mg.-w e q w qg,ei%4,-----gg w.,-ep.,y-,.-% g%#,1,. *y e--w.Asn,og aw- se%-' n _-g-'ee'-p-+wy,r3c g.cc gi'

.__ _ - - --. - - - . . - - . . -- -- . ._ . - . . - . . = . . - _ - . _ - - -

3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

ASME Boller and Pressure Vessel Required frequencies Code and applicable Addenda for perforning inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days

c. The provisions of Scecification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements,

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical l

Specification.

f. The I; service Inspection Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the j steff positions on schedule, methods and personnel, and sample excansion included in the generic letter, except where specific written relief has been granted by the Commission.

l l

l l

HATCH - UNIT 2 3/4 0-3 Proposed TS/03700/214-0

l REACTOR COOLANI S'i 5f LH 3/4.a M QCTra C00LAff_, F TEM LEAKAGE LEM.ACEDETLC,T_IONSisTEMS L?MitfNG CONDITION FOR OPERATION l

3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

a. The primary containment atmosphere particulate radioactivity monitoring system,

b. The primary containment floor drain and equipment sump level and flow monitoring systems, and

c. The primary containment gaseous radioactivity monitoring system.

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

a. With either the primary containment atmosphere particulate radioactivity monitoring system or the primary containment gaseous radioactivity monitoring system inoperable, operation may continue for 30 days prcvided grab samples of the containment atmosphere are obtained and analyzed at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />;

b. With at least one leakage monitoring instrument OPERABLE for l both the primary containment floor drain sump and the equipment

sump, operation may continue for 30 days;

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

SURVEILLANCE REQUIREMENTS l 4.4.3.1 The leakage detection systems shall be demonstrated OPERABLE by:

a. Primary containment atmosphere gaseous and particulate monitor-ing system-performance of a CHANNEL CHECK at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months,

b. Primary containment sump level and flow monitoring system-performance of a sensor check at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, CHANhtL FUNCTIONAL TEST at least once per 31 deys and a CHANNEL CALIBRATION at least once per 18 months.

HATCH - UNIT 2 3/4 4-5 Proposed TS/03?1q/214-0

]

react 0R COOLANT SYSTEM OPERATIONAL LEAKAGE q LIMITING CONDITION FOR OPERATION I -

~-

l 3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. S gpm UNIDENTIFIED LEAKAGE,

c. 25 gpm total leakage averaged over any 24-hour period, and

d. 2 gpm increase in UNIDENT!FIED LEAKAGE within a 24-hour period or less.

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUT-DOHN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24-hours.  ;

b. With any reactor coolant system leakage greater than the limits '

specifically in b or c above, reduce the leakage rate to within j the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. With any reactor coolant system leakage greater than the limits i specified in d above, reduce the leakage rate to within the- /

limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within \

the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24-hours.

SURVElt. LANCE REQUIREMENTS 4.4.3.2 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a. Monitoring the primary containment floor drain sump and equip-ment sump levels and flow rates at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and

b. Monitoring the_ primary containment atmospheric particulate and l gaseous radioactivity at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, i

)

HATCH - UN11 2 3/4

4-6 Proposed TS/0371g/214-0:  !

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

m _

l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.6.F^.2.c. When the time limits or maxi- 4.6.F.2.c.3. Primary coolant pH shall mum conductivity or chloride be measured at least once

(- concentration limits are ex- every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever ceeded, an orderly shutdown reactor coolant conduc-shall be initiated and the tivity is > 2.0pmho/cm reactor shall be in the Cold at 25'C.

Shutdown Conditioh within 24

' hours. d. ,Whenever the reactor is not pressurized, a sample of

(. the reactor coolant shall be analyzed at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for chloride ion content and pH.

S. Peactor Coolant Let).ljLt* lG. Reactor Coolant Leakane

1. Unidentified and Total

(~ Any time irradiated fuel is in Unidentified sources of reactor coolant system leakage shall be the reactor vessel and reactor checked by the drywell floor coolant temperature is above drain sump system and 212'F: recorded at least once psr A ' 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Identified sources of

a. reactor coolant systern leak- reactor coolant system age into the primary contain- leakage shall be checked by ment from unidentified sources the equipment drain sump shall not exceed 5 gpm;whom- system and recorded at _least g-arver;;;; ;;;r ; 24 hegr i,eriodt once per AWhours. The readings W )

provided by the primary

b. reactor coolant system leakage containment atmosphere into the primary containment particulate radioactivity from unidentified sources monitoring system, the g,g

{ Ag , shall not increase more than primary containment radio-r..d .,. (s o 90 Wh**~*V'T;s;d eVei i iodine monitoring system, e-peried; and and the primary containment gaseous radioactivity

c. the total reictor coolant sys- monitoring systesa shall tem leakage into the primary also be recorded at least containment shall not exceed once per / hours.

7 25 gpm when averaged over.a*4og i 24-hour period; when checked in accordance with 4.6.G.

2. Leakace Detection Systems

a. At least one of the leakage

(

measursment instruments assoc-isted with each sump shall be operable and two of the other three leakage detection systems _

identified in Table 3.2-10 note c shall be operable when irradiated fuct is

• Not required during performance of an inservice hydrostatic or leakage test even if reactor coolant temperature is above 212'F.

HATCH - UNIT -

3.6-7 Amendment No. 6 $2.93.160 4 l

I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS ,

G. Reactor Coolant teakane

2. Leakaoe Detection Systems (Cont'd)

4. (Continued) in the reactor vessel and reactor coolant temperature is eboye 712'F. Further, the 1 W

primary containment atmosphere f particulate radioactivity monitoring system shall be among these two operable systems, or samples shall be obtained and analyzed at least once each ,k hours.

f

b. From and after the date that any two of the four systems identified in Table 3.2-10, note c a*e made or found to be inoperable, but with the primary containment atmosphere particulate radioactivity monitoring system operable, reactor power operation may '

continue for the succeeding 30 days provided the primary containment atmosphere particulate radioactivity monitoring system reading is checked and recorded at least once each t hours.

/

c. From and after the date that any two of the four systems, including the primary containment atmosphere particulate radioactivity rtonitoring system, identified in Table 3.2-10 note c are made or found to be inoperable, reactor power operation may continue for tht succeeding 30 days provided samples of the -

containment atmosphere are obtained and analyzed at least once each A' hours. *

(

l l

l HATCH - UNIT 1 3.6-8 Amendment No. O , g3

.- _ .. _ _ - _ _ . - .-- __ .._ ____ _ _ _ ~ . _ ._ __ _ - _ . _ _ . _ _._..._. _ .

's SURVEllLANCE Rt0VIR(MENTS

_ LIMITING COND1110NS FOR OPERATION 3.6.K. STRUCTURAL INTEGRITY 4.6.K. STRUCTURAL INT [GRITY

)

1. Nomal Condition Surveillancs Requirements for in-service inspecilon and testing of ASME Code The structural integrity of ASME Class 1, 2, and 3 (equivalent) components Code Class 1, 2, and 3 (equiva- shall be applicable as follows:

lent) components shall be .

I maintained in accordance with the 1. In-service inspet, tion of ASME .)

? Surveillance Requirements of Code Class 1, 2, and 3 (equivalent)

Specification 4.6.K. components and in-serivce testing of ASME Code Class 1, 2, and 3

2. Of f-Nomal Conditions (equivalent) pumps and valves shall be perfomed in accordance with

a. With the structural Section XI of the ASME Boiler and integrity of any ASME Code Pressure Vessel Code and applicable )

Class 1 component not Addenda as required by 10CFR50, confoming to the above Section 50.55a(g), except where reouirements, restore the specific relief has been structural integrity of granted by the Commission pursuant the af fected component (s) to 10CFR50, Section 50.55a(g) to within its limit or (6) (i),

isolate the affected component (s) prior ta increasing the Reactor 2. Perfomance of the above in-service Coolant System temperature inspection and testing activities more than 50'F above the shall be in addition to other minimum temperature required specified Surveillance by NOT considerations. Requirements,

b. With the structural integrity 3. Nothing in the ASME Boiler and of any ASME Code Class 2 Pressure Vessel Code shall be component (s) not conforming construed to supersede the to the above requirements, requirements of any Technical restore the structural Specification.

integrity of the effected component (s) to within its 1, limit or isolate the affected t he 1mey,g y/Mj,3 pyJ fy component (s) prior to p"9 'g'^ h 4',' d in AJ RC Guer/c increasing the Reactor Coolant N f7- c i s 6it L c. pe(o,.,,4 A System temperature above 212'F.

o ccer im ,s'm g 4g c

c. With the structural integrity of

/*8 dt* % .~ scA,g m# d'^^j pus.M %d any ASME Code Class 3 component (s) meg,g 'A Da 3 **p k ugu e,L not conforming to the above g engq g g.cf j requirements, restore the structural g/

l 6"4c . /

integrity of the affected component (s) ecl, e( kg g,<,spe e, g . e, %

, O ,,

l to within its limit or isolate the affected component (s) from service.

de--tit,4<, bN

)

p HATCH - UNIT 1 3.6-10 Amendment No. 31,.42, N f, 119 I

m..,-. , _ - _ , .4,., y. - r,- y -m vw--- - - - - ,, y -- +- -m e y,y- -n-e-,.- r-- - - - -t- , - * ** -

e " - - * * --t- r - ' ""- --'"#

l. ' '

' l APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) _

i i

b. A total maximum combined interval Olme for any 3 consecutive .

surveillance intervals not to exceed 3.25 times the specified

ll surveillance interval. I I 4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for.a Limiting Condition for Operation and_ associated ACTION statements unless otherwise required by the specification. Surveillance require-ments do not have to be performed on inoperable equipment,

)  ;

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance Requirement (s) associated with the limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable' as follows:

4. Dur4ag-the-time-peeled;

4. Ns-it s ua nce-o f-t he-Fac 444 ty-Opees t i ng -L4 c on se-to-the r

+44rt-of-fac444ty-commercia.1-operat4on r -ineeev4ce-testint )

-of-ASME-Code-04ess-1 r-2 3 -&-4-pumps-*nd-valvee-sha44-k

-pe r fo rmed-i n-a cco rda nc e-w i t h-Sec t ion-X I-of-t he- A SME-

-Be ll e r-a nd-P re s sure-Ve s sel-G ede-1974-Ed i t4 en;-a nd-Addende-

-through-summer-1975 7 -**c*pt-where-ePecifle-vefiten-re44ef-ha s-been -g ra n ted-by-the-C omm t-SM on,. .

! ct . 2. Fol4owing-start-of--f4c444ty-commercial-operation Tnservice inspection of ASME Code Class 1, 2, and 3 components and I inservice-testing of ASME Code Class 1, 2, and-3 pumps L and valves shall be performed in accordance with Section XI of the'ASME Boiler and Pressure Vessel Code'and l- appitcable' Addenda-as required by-10 CFR 50, Section 50.55a(g), except-where specific written relief has been: 1 i granted by the Commission-pursuant.to 10 CFR 50, Section I 50.55a(g)(6)(1).

, b. Surveillance intervals specified in Section XI of the ASME ,

Boiler and Pressure Vessel Code and applicable Addenda for the-inservice inspection and testing activities _ required by the ASME Boiler and Pressure Vessel Code and. applicable Addenda shall be ] '.

applicable as follows in these Technical Specifications:

4

- HATCH - UNIT-2 3/4 0-2 _

,w ,~ n.-w,---,---nn--- ,e .,w,---. 8-,, n.m,+,- , . . - . , , ,e.w e,.vnen.--,,,,- -..n+-c..-e-se,-s-,.,mw,n,.,~m,-e-.mee,e-.rn,r-,,..,-mv

- - - - - .-- - - - -.. - -.- __- - -. __. - =-

3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

/-

(' ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once por 7 days Monthly At least once per 31 days Quarterly or every 3 rnenths At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities,

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements,

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

f. T he L Jerv.( e. 1^ 5f cc 4 ~ i'r y4 Or perin3 # dtdd.< d A #4 Gu e r.t LL th e ep-on .3 h . ll bc pe r fo ~ < J m occ.cJ .m J.4 h o r

CbU pesd oons on s c hs d.< h , m t %

• d L M d peuom0 , md s'v ta C + f *'

• i n o n melJ 04 b o'n 4hc y tA t.r.'s IL tf te p e y gep4 w hc rt, 3p g g', Qs we ith ed.t f has l> < t n grewha b J ht C m, , s s , '. q ,

3 4

HATCH - UNIT 2 3/4 0-3 g

,f REAtiCR COOLANT $Y$ TEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEuASE DETECTION SYSTEMS

, LIM!ilNG CONDITION FOR OPERATION . ..

i . . _ .

3.4.3.1 The following reactor coolant system leakage detection systems '

shall be OPERABLE:

(

a. The primary containment atmosphere particulate radioactivity monitoring system,

b. The primary containment floor drain and equipment sump level and flow monitoring systems, and

c. The primary containment gaseous radioactivity monitoring system.

APPLICABILITY: CONDITIONS 1, 2 and 3. _ '

~m-ACTION: RITER 70 PME 3/4 4-5a IVR !GM ACTICH) us.u .. w s~. .e a. am Ma sE . 3= _ . . > . . . n . - nnes a n, e Mb titive'for up 50 30 daisIro'vi5Ad h' rah e l h f, [ 'ho khe

containment atmosp er 3t i ed and a 21,.ru at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required p radioactive monitor-ing system a e; otherwise, be in at leas I.Q2LN within 5 ' !? W- ed 4-COLD Sug g yu 9tu. t y . g g g, . ; ,u <& _

$URVEILLANCE REQUIREMENTS '

4.4.3.1 The leakage detection systems shall be demonstrated OPERABLE by: -

p ) a. Primary containment atmosphere gaseous and particulate monitor-L ing systerr.-performance of a CHAN'll CHECK at least once perg AT hours, a CHANNEL FUNCTIONAL TES' at least once per 31 days ano a CHANNEL CAtlBRA110N at least once per 18 months.

d. Primary containment sump level and flow monitoring system-(g performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CAllBRATION at least once per IB menths.

~

sensor check at least coce per ' hours,

) .

~

HATCH - UNii 2 3/4 4-5 PER DIE REQUIREMENPS OF COtFIM%70RY ORDER DATED JULY 8,1983

- . - . . . - . . _ - - - - - - ... -. . . - - - . . . . - . _ . . - - - - . ~ . ~

l 3.4.3.1 h

T __

bCT10Nt l a. With either the primary containment atmosphere particulate radioactivity monitoring system or tbe primary contalrusent gaseous radioactivity monitoring system inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />st.

b. With at least one leakage monitoring instnment OPERA 81.E for both the prismary containment floor drain pump and the I equipment sump, operation may continue for 30 daysi

c. Othetvise, be in at least HOT SHUTDOW within the next 12 .

y hours and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

=

i I - 4 ,

L , ,

/

, 1 i

( .

s I

u i

\

l l 6

/

l<

f I \

j \

l AATCH - UNIT 2 3/4 4 ",

PER THE REQUIREMENTS OF LOW 7IRMATORY ORDER DATED JULY 8, 1983 M%

i .

REACTOR COOLANT SY5iEM l  :

ODERAT10NAL LEAKAGE LIMITING CONDIT!0N COR CDERATIO.N. . --

3.4.3.2 Reactor cociant system leakage shall be limited to:

a. No PRES $URE BOUNDARY LEAKAGE,

b. 6 gpm UN!DENTIFIED LEAKAGE, c.

25 gpm total leakage averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, and g

d.

2 gpm increase in UNIDENTIFIED LEAKAGE withiry any[ hourqperted APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

a.

With any PdES$URE BOUNDARY LEAKAGE, be in at least HOT SHUT-00WN hours. within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in '*.'s -

COLD SHUTDOWN within the next 24

• ^

4 l

b.

(

With any reactor coolant system leakage greater than the limits

, ) ,

specifically in b or e above, reduce the leakage rate to within the limits within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> no hours or be in at least HOT $ HUT 00WN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. in COLD SHUTD0n'N within the following c.

With any reactor coolant system leakage greater than the limits specified in d above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTOOWN within thehours.

24 next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD $ HUT 00WN within the following

$URVElLLANCE RE03 IRE 3ENTS

~

+ .

4.4,3.2

{

The reactor coolant system leakage' shall be demonstrated to be within each cf the above limits by:

a.

Monitoring the p imary containment floor drain sump and equip-

- mer.t arc sumo levels and flow rates at least once perghours, g

~

b.

Po'itoring the p'imary cor.tainment atmospheric particulate and gasecus racioactivity at least once perphours.

a HAICH - UN;T 2 3/4 4 6 PER THE REQUIREMENTS OF CONFIRMATORY ORDER DATED JULY 8, 1983

+^-+-w-c , Tee gr h r- 4 -+-e-m--r--,9.. -

p. -

g. mg.,g-p .g-g ema w *rv w ? y w-

• g"=a - T- m y +"*n-9W-Nw'V 'We'

' " ' "*-e-M

• F- d*Mh- "