ML17164A435

Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS

ML17164A435
Person / Time
Site:	Susquehanna
Issue date:	11/21/1994
From:	PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17164A434	List: ML17164A433 ML17164A435 ML18026A535 PLA-4228, Forwards Proposed Amends 178 & 132 to Licenses NPF-14 & NPF-22,respectively,eliminating MSIV-LCS Including PCIVs Associated w/MSIV-LCS & Increasing Allowable TS MSIV Leakage Rates
References
NUDOCS 9411290140
Download: ML17164A435 (23)

Text

ATTACHMENTTO PLA-4228 ENCLOSURE I TECHNICALSPECIFICATION CHANGES 9411290140 941121 PDR ADQCK 05000387 P

.PDR,

4

INDEX LIMITING CONOITIONS FOR OPERATION ANO SURVEILLANCE RE UIREMENTS

'ECTION PAGE 3/4. 6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT Primary Containment Integrity........................

3/4 6-1 Primary Containment Leakage..........................

3/4 6-2 Primary Containment Air Locks........'.................

3/4 6-5

~

~

~

~

~

~

~ ~ ~ ~ ~ ~

~ ~ ~

~ ~ ~ ~ ~

~

~

~

~

~ ~

Qgl GTE, Primary Containment Structural Integrity.............

3/4 6-8 Orywell and Suppression Chamber Internal Pressure....

3/4 6-9 3/4: 6. 2 Orywe11 Average Air Temperature.............'.........

Orywell and Suppression Chamber Purge System,'........

OEPRESSURIZATION SYSTEMS aJ Suppression Chajebero

~ ~ ~

~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Suppression Pool Sprayoo

~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~

~ ~ ~ ~ ~ ~

~ ~ ~

Suppression Pool Cooling.............................

3/4 6-10 3/4 6-11 3/4 6-12 3/4 6-15 3/4 6-16 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES..............."..

3/4 6-17 3/4. 6. 4 ACUUM RELIEFo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~

~ ~ ~ ~ ~

V 3/4 6-29 3/4.6.5 SECONOARY CONTAINMENT Secondary Containment Integrity......................

3/4 6-31 Secondary Containment Automatic Isolation Oamper s....

3/4 6-32 Standby Gas Treatment System............;............

3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Orwell and S'uppr ession Chamber Hydrogen ecoabi ner Systems.................................

R 0>el 1 Air flow Systemo

~ ~ ~ ~ ~ ~

~ ~

~

~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~

Orywell and Suppression Chamber Oxygen Concentl ationo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~

~ ~ ~

~

~ ~ ~ ~

~ ~ ~

~

3/4 6-34 3/4 6-37 3/4 6-38 3/4'6-39 SUSQUEHANNA - UNIT 1

BASES INOEX SECTION 3/4.5 EMERGENCY CORE COOLING SYSTEMS PAGE 3/4.5.1 and 3/4.5.2 ECCS - OPERATING ANO SHUTGSO.........

8 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER.............................

B 3/4 5-2 3/4. 6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT Prfmary Containment Integrfty...................

Prfmary Contafnment Leakageo

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

Prfmary Contafnment Afr Locks...................

8 3/4 6-1 8 3/4 6-1 8 3/4 6-1 Prfmary Contafnment Structural Integrfty.....

D~ll and Suppressfon Chaeber Internal Pressuree

~

~ ~ ~ ~

~

~

~ i ~ ~ ~ ~ ~

~ ~ ~ ~

~

~

~ ~ ~ ~ ~ ~ ~ ~

~

~

~ ~ ~

~

Orpull Average Afr Temperature.................

8 3/4 6-2 8 3/4 6-2 8 3/4 6-2 Drywall and Suppressfon Chamber Purge System....

8 3/4 6-2 3/4.6. 2 OEPRESSURIZATION SYSTEMS........................

8 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............

8 3/4 6-4 3/4.6. 4 3/4. 6. 5 VACUN RELIEF...................................

SECONDARY CONTAINENTo ~ ~

~ ~ ~

~ ~ ~ ~ o

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

8 3/4 6-4 8 3/4 6-5 3/4.6.6 PRIMARY CONTAINENT ATMOSPHERE CONTROL..........

8 3/4 6-5 SUSQUEHANNA - UNIT 1 xfv

E) sd per labour 8~v any one h14iK ~te4M ihdlnk nn Palp'e cA.vJ a.

COIYll)HKCl Iha St AuM P @5 Way Ieaka<CC rate ak "'56 sl CONTA!NNENT SYSTEHS PRIHARY CONTAINMENT LEAKAGE LIMITING CONOITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a.

b.

C.

An overall integrated leakage rata of less than or equal to L

1.0 percent by weight of the containment air pet 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at k 45.0 psfg.

A combfned leakage rate of less than or equal to 0;60 L

for all'enetratfons and all valves lfstad fn Table 3.6.3-1, ax3apt for main steam line isolation valves

, main steam line drain valves" and valves which are hydrostatically leak tasted per Table 3.6.3-1,

'b ect to T e

B and C tests when pressurized to Pa, 45 0 psig.

~Lass than or equal to-4C-scf per hour for all four main steam Ifnes through the isolation valves when tasted at Pt, 22.5 pstg.

'-Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tasted at P

, 45.0 psfg.

a' combfned leakage rate of less than or equal to 3.3 gpm for all contafnment fsolatfon valves in hydrostatically tasted lines which penetrate the primary containment, when tasted at l. 10- Pa,

49. 5 psig.

APPLICABILITY: Nen PR! %RY CONTAINHENT INTEQR!TY fs required per Speciffcation 3.6. 1. I.

ACTIN:

0th C.

~ e Tha measured overall integrated primary containment leakage rata

'exceeding 0.75 L, or The measured combined leakage rate for all penetrations and all valves Ifstad in Table 3.6.3-1, except for main steam line isolation valves",

main steam Ifne drafn valves" and valves which are hydro-statfcally leak tasted per Table 3.6.3-1, sub)ect to Type B and C

tests exceeding 0.60 L, or The measured leakage ra e excaedfng scf per hour for all four main steam lines through the isolation valves, or The measured leak rata exceeding 1.2 scf per hour for any one main steam line drain valve, or The measured cmabfned leakage rate for all containment isolation valves fn hydrostatfcally tasted lines which penetrate the primary containment axcaadfng 3.3 gpm, emption to ppenafx IJ" of IO.CFR 50.

'bb scf par Bur Par ~ay one nncaTn sfea~

ic~)cfish v'alve era.

totdl Mcvinhllwl path~ay I lakage rde d'3 bD SUSQUEHANNA - UNIT 1 3/4 6-2 Amendment'o.

29'

I C

(

II 5 s+J f4~ +<"

R < ~<) ~I~ s<e ~ isclctio~ v'elva thcd ~aug Ico g f pa~ +~, a,M rcStcre fke co~4i~ed ~y,/~>~

p ~~~-

)~ ~

LOG.y restore:

a.

The overall integrated leakage rate to less than or equal to 0.76 L and b.

The combined leakage rate for all penetrations and all valves listed in Table 3.8.3-1, except for main steam line Isolation valves, main steam line drain valves and valves which are hydrostatically leak tested per Table 3.8.3-1, subject to Type 8 and C tests to less than or equal to 0.80 L and c.

The leakage rate to less than or equal to scf per hour for atl four main steam linea through the isolation valves, and d.

The leakage rate to less than or equal to 1.2 scf per hour for any one main steam line drain valve, and e.

The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 2004F.

4.6.1.2 The primary containment leakage rates shaN be demonstrated at the following teat schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 60 using the methods and provisions of ANSI N46.4 - 1972:

Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 a 10 month intervals during shutdown at P46.0 psig, during each 10-year service period.~

b.

Ifany periodic Type A teat fails to meet.75 L the teat schedule for subsequent Type A tests shall be reviewed and approved by the Commission.

Iftwo consecutive Type A tests fail to meet.75 L~ a Type A teat shall be performed at least every 18 months until two consecutive Type A tests meet.75 L at which time the above test schedule may be resumed.

C.

The accuracy of each Type A test shall be verified by a supplemental teat which:

2.

Confirms the accuracy of the teat by verifying that the difference between the supplemental data and the Type A teat data is within 0.25 L,.

Has durathn sufficient to establish accurateiy the change In leakage rate between the Type A test and the supplemental teat.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental teat to be equivalent to at least 25 percent of the total measured leakage at P~ 46.0 psig.

Exemption to Appendix J of 10CFR50.

SUSQUEHANNA - UNIT 1 3/4 6-3 Amendment No. l21

CONTAINMENT SYSTEMS MSIV LEAKAGE CONTROL SYSTEM LIMITING CONOITION fOR OPERATION 3.6.1.4 Nth one IV leakage control system subsystem inoperable, restor he inooerable subsystem OPERABLE status within 30 days or be in at least HO SHUTOOQN within the n t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTDOlA within the folio ng 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, SURVEILLANCE RE U

ENTS

bELET, 4.6. 1.4 Each MSIV lea e control system subsystem all be demonstrated OPERABLE:

a.

At least once per 31 da by:

1.

- Startfng the blower(s) rom the ntrol room and operatin'g the blower(s) for at least 1

minu s.

2.

Energfxfng the heaters and

.ifyfng a temperature rise indicating heater operation on downs am iping.

b.

At least once per 18 month y:

1.

Performance of a f ctfonal test which includes simulated actuation of the subsys hroughout its operatf

sequence, and verifying that each inta ock and timer operates as

signed, each automatic valve actua to its correct posftion and e blower starts.

2.

Verffyfn that the blower develops at least the elow required vacuum the rated capacity:

.a)

Inboard valves, LS" H20 at 100 scfm.

b Outboard valves, 60" HZO at ZOO scfm.

c.

By erffying the operating instrumentation to be OPERABLE by per rmance ao 1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and SUS)UEHANNA - UNIT 1 3/4 6-7 Amendment No.

TABLE3.0W1 (Continued)

PRIMARY CONTAWNENT ISOLATION VALVES Volvo Function and Number Automatic isolation Valves (Continued) re i

HV-15766 HV-16768 Madmum isolation T(me (Second!)

30 30 teoletion Signal(e) (a)

B,Z B,Z HV-156F076 HV-155F079 R

V HV-149F062 HV-149F084 15 16 10 10 LB, Z LB, 2 KB,Z KB,2 C51-J004 A, 8, C, 0, E A,Z SV-157'100 A, 8 SV-157101 A, 8 SV-167102 A, 8 SV-167103 A, 8 SV-157104 SV-1 57106 SV-1 67106 SV-167107 b.

M n II bCLCTC N/A N/A N/A NIA

.NIA N/A NIA N/A (f)

(f)

(f)

(f)

(f)

(f)

(f)

(f)

~F~ed" HV-141F032 A, 8 HV-14182 A, 8 HV-149F013 1%~20 SUSOUEHANNA - UNIT 1 3/4 6-22 Amendment No.~

TABLE 3. 6. 3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER Excess Flee Check Valves (Continued)

Reacto~ Recirculation XV-143F003 A,B-XV-143F004 A,B XV-143F009 A,B,C,D XV-143F010 A,B,C,O XV-143F011 A,B,C,D XV-143F012 A,B,C,O XV-143F040 A,B,C,O XV-143F057 A,B Nuclear Bofler Vessel Instrument XV-142F041 XV-142F043 A,B XV-142F045 A,B XV-142F047 A,B XV-142F051 A,BC,D XV-142F053 A,B,C,O XV-142F055 XV"142F057 XV-142F059 A,B,C,D,E,F,G,H,L,M,N,P,R,S,T,U XV-142F061 KV-14201 XV-14202 Nuclear Boiler XV-141F070 A,B,C,O XV 141F071 A,B,C,D KV"141F072 A,B,C,O XV 141F073 A~B~CyQ XV-141F009 SUS/UEHANNA - UNIT 1 3/4 6-27 Aaenchent No.

40

~m cgiMc.

P

.~ ';~6/in&

C &0<

I 1

TA8LE 3.8.4.2. 1-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAO PROTECTION CONTINUOUS VALVE NUMBER HV Ell lF0288 HV Ell-1F0478 HV-Ell 1F0168 HV-Ell-1F0038 HV-Ell 1F0178 HV-E21-1F0318 HV-E21-1FOOIB HV-Ell-lF1038 HV Ell-1F0758 HV-Ell 1F0738 HV-Ell-IF0060 HV-Ell 1F0040 HV Ell 1F0248 HV-E21 1F0158 HV-E21 1F0048 HV E21-1F0058 SYSTEM(S)

AFFECTEO RHR RHR RHR RHR RHR CS CS RHR RHRSM RHRSM RHR RHR RHR CS CS CS HV E51 1F045 HV-E51 1F012 HV E51-1FOu HV 15012 HV ESI-lF046 HV-E51-lF008 HV-E51 lF031 HV-E51-1F010 RCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC SUSQUEHANNA - UNIT 1 3/4 8-31 Amendment No. g

PRIMARY CONTAINMENT INTEGRITY ensures that the release ot radioactive materials from the containment atmosphere willbe restricted.to those leakage paths and associated leak rates assumed in the accident analyses.

This restriction, in conjunction with the leakage rate limitation, willlimitthe site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

The limitations on primary containment leakage rates ensure that the total containment leakage volume willnot exceed the value assumed in the accident analyses at the peak ac@dent pressure of 45,0 psig, P,. As an added conservatism, the measured overall integrated leakage rate Is further limited to less than or equal to 0.75 I during performance of the periodic testa to account for possible degradation of the containment leakage barriers between leakage tests.

Operating experience with main steam line isolation valves and main. steam line draIn valves has indicated that degradation has occasionally occurred in the leak tightnesa of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measunng leakage rates Is consistent with the requirements of Appendix J

of 10 CFR Part 50 with the exception of exemptions granted for main steam isolation and drain valve leak testing and testing the airlocks after each opening.

The frequency for performing the Type A teats is consistent with the requIrements of 10CFR50 Appendix J

with the exception of the exemption granted to the schedular requirements of Section III.O.1 (a).

The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARYCONTAINMENTINTEGRITYand the primary containment leakage rate given in Specifications 3.8.1.1 and 3.8.1.2. The specification makes allowances forthe fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation.

Only one closed door in each air tock Is required to maintain the integrity of the containment.

in the po situations would be a small fraction of the 10 CFR 1

, provided the main steam line system valves up to and ne condenser remains ~

intact.

Operating experience has indicat on has occasionally occurred In the leak tightness ofthe MSIV's fied leakage requ always been maintained continuou u~rement for the leakage control system wIIIreduce the u kage from SUSQUEHANNA - UNIT 1 8 3/4 6-1 Amendment No. ~l

~INO LIHITINQ mONS FOR OPERATION ANO SURVEILLANCE RE IRENENTS SECTIQ!l 3/4. 6 CONTAI NBIT SYSTEMS 3/4.6. 1 PROSY CONTAINMENT Prfaary Contafreent Integrfty........................

3/4 6-1 Prfaary Contafraant Leakage..........................

3/4 6-2 Prfaary Contafneent Afr Locks........................

3/4 6-5 QSLucTB Prfeary Contafrmant Structural Integrfty.............

3/4 6-8 Or@all and Suppressfon Chaaber Internal Pressure....

3/4 6-9 0~11 Average Afr Temperature......................

3/4 6 10 Orywell and Suppressfon'haaber Purge Sys~.........

3/4 6-I1 314.6.2 OgPRKSSURIIATION SYSTEMS Suppressf on Ch&ro ~

~ ~ i ~ ~ ~ ~

~ ~ s ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

uppressf on Pool Spray@

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~

S Suppressf on Pool Cool fnge

~ ~ e ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4 6-12 3/4 6 i5 3/4 6 16 3/4.6. 3 PRIMARY CONTAINBIT ISOLATION VALVES-"~ ~"".-. ~. ~. ~

3/4 6-17 3/4.6. 4 VCN RELIEF........................................

3/4.6. S SECONARY CONTAIN%IT Secondary Contaf IwC Integrftye ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Secondary 'Contaf neert Autoeatf c Isolatf on Daspors....

Standby Gas Treatisoflt Sy544$i ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ t ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~

3/4.6.6 NIMARY CGNTAIN%NT AT&SPHERE CONTROL Otywell and Suppressfon, Chaaber Hydrogen Recoebfner Systel ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~

OFpE l 1 Af'r F10 Systewo

~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

O~ll and Suppressfon Chaaber Oxygen Concantratfon......................................

3/4 6-29 3/4 6-31 3/4 6-34 3/4 6-36 3/4 6-39 3/4 6 40 3/4 6-41 SUS/UEHANNA' UNIT 2 vff

BASES INOEX SECTION 3/4.5 EHERGENCY CORE COOLING SYSTENS PAGE 3/4.5.1 and 3/4.5. 2 ECCS - OPERATING ANQ SHUTDOlN.........

8 3/4 5-1 3/4.5.3 SUPPRESSION CHANER.............................

8 3/4 5-2 3/4.6 CONTAIQKNT SYSTB5 3/4.6. 1 PRIMARY CONTAINENT Prfaary Contafneent Integrfty...................

Prfwary Contafrment Leakage.....................

8 3/4 6-1 8 3/4 6-1 Prfsary Contafrment Afr Locks....................

8 3/4 6-1

~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Prfaary Contafneent Structural Integrfty........

8 3/4 6-2 Orwell and Suppression Chaaber Internal ressuree

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~

~ ~ ~

~ i ~

~

~

~

~

~

~ ~

P Orwell Average Afr Teeperature.................

8 3/4 6-2 8 3/4 6 2 Orywell and Suppressfon Chaaber Purge Systea....

8 3/4 6-2 3/4.6.2 OEPRESSURIZATION SYSTEMS.....................

3/4.6.3 PRINARY CONTAINMENT ISOLATION VALVES.........

3/4.6.4 VACUN RELIEF..................--...-."....

3/4.6. 5 SECONARY CONTAINMENT....... ~. ~

~

~

~ ~ ~ ~

~

~ ~ ~ ~

~ ~ ~

~ ~ ~

8 3/4 6-3 8 3/4 6-4 8 3/4 6-4 8 3/4 6-5 3/4. 6. 6 PRINAWY CONTAIIOKNT ATNSPHERE CONTROL..........

8 3/4 6-5 SUSQUEHANNA - UNIT 2 xfv

IOO sc.k fIer hair for any oNc Noir s4nw Isolofiaw vale'8 a n3 a.

ca ~b'iheJ e~ximum p Idhway lenka.ge rake cNEi300 CCNTAIQIENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE L'BAITING CONGITION FOR OPERATION 3.6.1.2 Prfaary contafraent leakage rates shall be 1fofted to:

a.

An overall fntegrated leakage rate of less than or equal to.L, 1.0 percent by wefght of the contafnaent afr per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at h, 45.0 psfg.

b.

A coabfned leakage rate of less than or equal to 0.60 L for all penetratfons and all valves lfsted fn Table 3.6.3-1, exhpt for mafn stone lfne fsolatfon valves", aafn steaa lfne drafn valves" and valves whfch are hydrostatf cally leak tested per Table 3.6.3-1,

~ct to T 8 and C test" when pressurfzed to P, 45.0 psfg.

c.

"Less than or equal to scf per hour for all four eafn steal lfnes through the fsolatfon valves when tested at Pt, 22.5 psfg.

d.. ~Less than or equal to 1.2 scf per hour for any one mafn steam 1fne drafn valve when tested at P, 45.0 psfg.

e.

A coebfned leakage rate of less than or equaT to 3.3 gpa for all contafment fsolatfon valves fn hydrostatfcally tested 1fnes whfch penetrate the prfeary contafrment, when tested at 1.10 Pa, 49.5 psfg.

APPLICASILITY: Nen PRINRY CONTAINENT INTEGRITY fs requf red per Specf ffcatfor 3.6.1.1.

ACTION:

Nth:

aN b.

Ci The aeasured overall fntegrated pr faary contafraent leakage rate exceedfng 0.75 L, or The aeasured coebfned leakage rate for all penetratfons and all valves lfsted fn Table 3.6.3-1, except for eafn stem lfne fsolatfon valves", aafn steaa l,fne drafn valves" and valves whfch are hydro-statfcally leak tested per Table 3.6.3-1, subject to Type 8 and C

tests f

0.60 L, or The eeasured leakage rate exceedfng scf per hour for all four aafn atom lfnes through the fsolatfon valves, or The eeasured leak rate exceedfng 1.2 scf per.hour for any one aafn stoa@ lfne drafn valve, or The aeasured coabfned leakage rata for all contafreent fsolatfon valves fn hydrostatfcally tested 1 fnes whfch penetrate the prfsary contafrment exceedfng 3.3 gpe, IOG sd per hour W any nw8 Auxin ckeau isolakiew valve ar a;

total Ivan'.in<urn paaI a) imPa,oe rate oE ) see SUSQUEHANNA - ONIT 2 3/4 6-2

II.S'C.f

~e~

kouv. For any +naia. Album isoiakie~

valve Vkat exceeds IQo st per hour, oed recure She csun.bi~J max'ieu~

Pcrfk~oy lea+a rHe I~ +~

~~ tContlnued}

restore:

a.

The overall integrated leakage rate to less than or equal to 0.76 L and b,

Co The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type 8 and C tests to less than or equal to 0.60 L and The leakage rate to less than or equal to 48-scf per hour for all four main steam lines through the Isolation valves, and d.

The leakage rate to less than or equal to 1.2 scf per hour for any one main steam line drain valve, and e.

The combined leakage rate for all containment Isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200oF.

4.6.1,2 The primary containment leakage rates shall be demonstrated at the following teat schedule and shall be determined in conformance withthe criteria speofied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N46.4 - 1972:

ao Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 x 10 month intervals during shutdown at P 46.0 psig, during each 10-year service period o b.

Ifany periodic Type A test fails to meet.75 L the teat schedule for subsequent Type A tests shall be reviewed and approved by the Commission.

Iftwo consecutive Type A tests failto meet.75 L~ a Type A test shall be performed at least every 18 months until two consecutive Type A testa meet.75 L~ at which time the above teat schedule may be resumed.

C.

The accuracy of each Type A teat shall be verified by a supplemental teat which:

2.

Confirms the accuracy of the teat by verifying that the difference between the supplemental data and the Type A teat data is within 0.26 L,.

Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental teat.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P~ 45.0 psig.

Exemption to Appendix J of 10CFR50.

SUSQUEHANNA - UNIT 2 3/4 6-3 Amendment No. 89

CONTAINBIT SYSTEMS MSIV LEAl(AGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.4 AP CABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

Nth one leakage control systea subsystea inoperable, restore e inoperable subsystea to PERABLE status wfthfn 30 days or be fn at least HO SHUTOGW within the n

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and fn COLD SHUTlMQI within the follow g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE UIR S

GL~LETL 4.6.1.4 Each MSIV lea control systee subsystea s

1 be demonstrated OPERABLE:

a.

At least once per 3 days by:

1.

Starting the blowe s) free th control rooe and operating the blower(s) for at 1 ~

15 oi s.

2.

Energfzfng the heaters verffyfng a tesperature ri.se fndfcat-fng heater operation on nstreaa piping.

k b.

At least once per 18 son by:

Perforaance of a nctfonal test ich fncludes sfeulated actuatfon of th subsystea throug fts oper ating sequence, and verfQfng at each fnterlock tfeer operates as

designed, ea autoeatfc valve actuate to fts correct position and the bl r starts.

Verffyf that the blower develops at least e below requfred v

at the rated capacfty:

a)

Inboard valves, 15" H 0 at 100 scfa.

Outboard valves, 60" Hs0 at 200 scfa.

c.

By 1.

2.

~rife.fng the operating fnst~ntatfon to be OPERABLE b erform-eof a:

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, CHANNEL FUNCTIONAL TEST at least once per 31 days, and SUSQUEHANNA - UNIT 2 3/4 6-7

IIKXILhlI Valve Function and Number AUToMATIC ISOLATION VALvaa (CONTINUEoi SUPPREssfoN PooL CLEANUI' Mes(mum (so)at(on Time (Seconds) lsofatlon Signal(s)

HV-2578S HV-25788 HPCI VAcUUM BAEAKol HV-255F075.,;.

HV-255F079 RCIC VAcUUM BaEAxEIt HV-249F062 HV-249F084 TIP BALLVALVES I+

C514004 A B C D E CONTAINMENT RAOIATION DETECTION SYSTEM SV 257100 A,B SV-257101 A,B SV-257102 A,B SV-257103 A,B SV-257104'V-257105 SV-257108 SV-257107 b.

MANUALIsoLATION VALvsa 35 30

.15'5 10 10 NIA N/A NIA N/A N/A NIA N/A N/A Bg;"

B,Z LB,Z~:

LB.Z KBg.

KB,Z A 2' w i, (f) lf)

W lf)

., (f).

(f)

FEEowATEa(e)

HV-241F032 A B RWCU Ries HV-24182 A B'CIC IILIEcTION HV-249F013 2%9<20 bEL 8 Tc=

SUSQUEHANNA - UNIT 2 3/4 6-22 Amendment No. ~2

TABLE 3. 6. 3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION ANO NUMBER Excess Flow Check Valves (Continued)

Reactor Recirculation XV-243F003 XV-243F004 XV-243F009 XV-243FOIO XV-243F011 XV-243F012 XV-243F040 XV-243F057 A,B A,B A,B,C,O A,B,C,O A,B,C,O A,B,C,O A,B,C,Q A,B Nuclear Boiler Vessel Instrument XV-242F041 XV-242F043 XV-242F045 XV-242F047 XV-242F051 XV-242F053 XV-242F055 XV-242F057 XV-242F059 XV-242F061 XV-24201 XV-24202 A,S A,B A,B A,B,C,D A,B,C,O AiBsCsO ~ EsFtG H L H N P R

S T U Nuclear Boil'er XV-24IF070 XV-241F071 XV-241F072 XV-241F073 XV-241F009 A,B,C,D A,B,C,O A,B,C,D A,B,C,D hEa.e TE'USQUEHANNA

- UNIT 2 3/4 6-27

~ +

1

'I

TABLE 3.8.4.2. 1-1 (Continued)

MOTOR-OPERATEO VALVES THERMAL OVERLOAO PROTECTION CONTINUOUS VALVE NUMBER HV-Ell-ZF0218 HV-. Ell"2F0108 HV-Ell-2F0048 HV-Ell"2F0078 HV-Ell-2F1048 HV-E11-2F0268 HV-Ell-2F0288 HV-El1-2F0478 HV-Ell-2F0168 HV-Ell-2F0038 HV-Ell-2F0178 HV-E21-2F0318 HV-E21-ZF0018 HV-Ell"2F 1038 HV-Ell-2F0758 HV-E11=2F0738 HV-E11-ZF0060 HV-Ell-2F0040 HV-Ell-2F0248 HV-E21-2F0158 HV-E21-2F0048 HV-E21-2F0058 SYSTEM(S)

AFFECTED RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR CS CS RHR RHRSW RHRSW RHR RHR RHR CS CS CS HV-E51-2F045 HV-E51-2F012 HV-E51-2F013 HV-25012 RCIC RCIC RCIC RCIC SUSQUEHANNA - UNfT 2 3/4 8-33 Amendment No. 59

PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere willbe restricted.to those leakage paths and associated leak rates assumed in the accident analyses.

This restriction, in conjunction with the leakage rate limitation, willlimitthe site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

The limitations on primary containment leakage rates ensure that the total containment leakage volume willnot exceed the value assumed in the accident analyses at the peak accident pressure of 45.0 pslg, P,. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 I during performance of the periodic teats to account for possible degradation of the containment leakage barriers between leakage teats.

Operating experience with main steam tine isolation valves and main steam line drain valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J

of 10 CFR Pan 50 with the exception of exemptions granted for main steam Isolation and drain valve leak testing and testing the airiocks after each opening.

The frequency for performing the Type A teats is consistent with the requirements of 10CFR50 Appendix "J'ith the exception of the exemption granted to the schedular requirements of Section III.D.1 la).

4 The limitations on closure and leak rate forthe primary containment air locks are required to meet the restrictions on PRIMARYCONTAINMENTINTEGRITYand the primary containment leakage rate given in Specificationa 3.B.1.1 and 3.8.1.2. The specification makes allowances forthe fact that there may be long periods of time when the air locks will be in a dosed and secured position during reactor operation.

Only one closed door in each air lock is required to maintain the integrity of the containment.

in the situations would be a small fraction of the 10 CFR 100 vlded the main steam line system valves up to and b

ters'ntact.

Operating experience has indicated has occasionally occurred In the leak tightness of the MSIV's such leakage requi always been maintained continuou wrement for the leakage control system wN reduce the u from SUSQUEHANNA - UNIT 2 8 3/4 6-1 Amendment No. 89