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 ML18026A448 ML18026A535
References
NUDOCS 9411290140
Download: ML17164A435 (23)

Text

ATTACHMENTTO PLA-4228 ENCLOSURE I TECHNICAL SPECIFICATION CHANGES 9411290140 941121 PDR ADQCK 05000387 P .PDR,

4 INDEX LIMITING CONOITIONS FOR OPERATION ANO SURVEILLANCE RE UIREMENTS PAGE

'ECTION 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 Orywe11 Average Air Temperature.............'......... 3/4 6-10 Orywell and Suppression Chamber Purge System,'........ 3/4 6-11 3/4: 6. 2 OEPRESSURIZATION SYSTEMS aJ Suppression Chajebero ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-12 Suppression Pool Sprayoo ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-15 Suppression Pool Cooling............................. 3/4 6-16 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES...............".. 3/4 6-17 3/4. 6. 4 VACUUM RELIEFo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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 6-34 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Orwell and S'uppr ession Chamber Hydrogen R ecoabi ner Systems................................. 3/4 6-37 0>el 1 Ai r flow Systemo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-38 Orywell and Suppression Chamber Oxygen Concentl ationo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4'6-39 SUSQUEHANNA - UNIT 1

INOEX BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 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 Integrf ty................... 8 3/4 6-1 Prfmary Contafnment Leakageo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 6-1 Prfmary Contafnment Afr Locks................... 8 3/4 6-1 Prfmary Contafnment Structural Integrfty..... 8 3/4 6-2 D~ll and Suppressfon Chaeber Internal P ressuree ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 6-2 Orpull Average Afr Temperature................. 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 VACUN RELIEF................................... 8 3/4 6-4 3/4. 6. 5 SECONDARY CONTAINENTo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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 sl rate ak "'56 CONTA!NNENT SYSTEHS PRIHARY CONTAINMENT LEAKAGE LIMITING CONOITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a. 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.

b. A combfned leakage rate of less than or equal to 0;60 L for and all valves lfstad fn Table 3.6.3-1, ax3apt for main all'enetratfons steam line isolation valves , main steam line drain valves" and valves which are hydrostatically leak tasted per Table 3.6.3-1, ect to T e B and C tests when pressurized to Pa, 45 0 psig.

'b C. ~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 a', 45.0 psfg.

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 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 C. 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

~e 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.

scf par Bur Par ~ay one nncaTn sfea~ 'bb 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. If any 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. If two 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:

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,.

2. 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.

TABLE 3.0W1 (Continued)

PRIMARY CONTAWNENT ISOLATION VALVES Madmum teoletion Volvo Function and Number isolation T(me Signal(e) (a)

(Second!)

Automatic isolation Valves (Continued) re i HV-15766 30 B,Z HV-16768 30 B,Z HV-156F076 15 LB, Z HV-155F079 16 LB, 2 R V HV-149 F062 10 KB,Z HV-149F084 10 KB,2 C51-J004 A, 8, C, 0, E A,Z SV-157'100 A, 8 N/A (f)

SV-157101 A, 8 N/A (f)

SV-167102 A, 8 N/A (f)

SV-167103 A, 8 NIA (f)

SV-157104 .NIA (f)

SV-1 57106 N/A (f)

SV-1 67106 NIA (f)

SV-167107 N/A (f)

b. M n II bCLCTC

~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& &0<

C

I 1

TA8LE 3.8.4.2. 1-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAO PROTECTION CONTINUOUS SYSTEM(S)

VALVE NUMBER AFFECTEO HV Ell lF0288 RHR HV Ell-1F0478 RHR HV-Ell 1F0168 RHR HV-Ell-1F0038 RHR HV-Ell 1F0178 RHR HV-E21-1F0318 CS HV-E21-1FOOIB CS HV-Ell-lF1038 RHR HV Ell-1F0758 RHRSM HV-Ell 1F0738 RHRSM HV-Ell-IF0060 RHR HV-Ell 1F0040 RHR .

HV Ell 1F0248 RHR HV-E21 1F0158 CS HV-E21 1F0048 CS HV E21-1F0058 CS HV E51 1F045 RCIC HV-E51 1F012 RCIC HV E51-1FOu RCIC HV 15012 RCIC HV ESI-lF046 RCIC HV-E51-lF008 RCIC HV-E51 lF031 RCIC HV-E51-1F010 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 will be restricted.to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the 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 will not 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 PRIMARY CONTAINMENTINTEGRITY and the primary containment leakage rate given in Specifications 3.8.1.1 and 3.8.1.2. The specification makes allowances for the 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 of the MSIV's fied leakage requ always been maintained continuou u~rement for the leakage control system wIII reduce 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 Prf aary Contafreent Integrf ty........................ 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 S uppressf on Ch&ro ~ ~ ~ i ~ ~ ~ ~ ~ ~ s ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-12 S uppressf on Pool Spray@ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ 3/4 6 i5 Suppressf on Pool Cool f nge ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6 16 3/4.6. 3 PRIMARY CONTAINBIT ISOLATION VALVES-"~ ~ "".-. ~ .~. ~ 3/4 6-17 3 /4.6. 4 VCN RELIEF........................................ 3/4 6-29 3/4.6. S SECONARY CONTAIN%IT Secondary Contaf IwC Integrf tye ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-31 Secondary 'Contaf neert Autoeatf c Isol atf on Daspors.... 3/4 6-34 Standby Gas Treatisoflt Sy544$ i ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ t ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ 3/4 6-36 3/4.6.6 NIMARY CGNTAIN%NT AT&SPHERE CONTROL Otywell and Suppressfon, Chaaber Hydrogen R ecoebfner Systel ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t~~~~~~~~ 3/4 6-39 OFpE l 1 Af'r F10 Systewo ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6 40 O~ll C

and Suppressfon Chaaber Oxygen oncantratfon...................................... 3/4 6-41 SUS/UEHANNA' UNIT 2 vff

INOEX BASES SECTION PAGE 3/4.5 EHERGENCY CORE COOLING SYSTENS 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 Integrf ty................... 8 3/4 6-1 Prfwary Contafrment Leakage..................... 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 P ressuree ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 6-2 Orwell Average Afr Teeperature................. 8 3/4 6 2 Orywell and Suppressfon Chaaber Purge Systea.... 8 3/4 6-2 3/4.6.2 OEPRESSURIZATION SYSTEMS..................... 8 3/4 6-3 3/4.6.3 PRINARY CONTAINMENT ISOLATION VALVES......... 8 3/4 6-4 3/4.6.4 VACUN RELIEF..................--...-.".... 8 3/4 6-4 3/4.6. 5 SECONARY CONTAINMENT....... ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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 cNE i300 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 The aeasured overall fntegrated pr faary contafraent leakage rate exceedfng 0.75 L, or

b. 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 Ci 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

I I.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, 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 Co 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 with the 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. If any 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. If two consecutive Type A tests fail to 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:

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,.

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

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 SUSQUEHANNA - UNIT 2 3/4 6-7

IIKXILhlI Mes(mum (so)at(on Valve Function and Number Time (Seconds) lsofatlon Signal(s)

AUToMATIC ISOLATION VALvaa (CONTINUEoi SUPPREssfoN PooL CLEANUI' HV-2578 S 35 Bg;"

HV-25788 30 B,Z HPCI VAcUUM BAEAKol HV-255F075.,;. .15'5 LB,Z ~:

HV-255F079 LB.Z RCIC VAcUUM BaEAxEIt HV-249 F062 10 KBg.

HV-249 F084 10 KB,Z TIP BALL VALVES I+

C514004 A B C D E A 2' CONTAINMENT RAOIATION DETECTION SYSTEM SV 257100 A,B NIA w i, (f)

SV-257101 A,B N/A SV-257102 A,B NIA SV-257103 A,B N/A lf)

N/A W SV-257104'V-257105 NIA lf)

SV-257108 N/A ., (f).

SV-257107 N/A (f)

b. MANUAL IsoLATION VALvsa bEL 8 Tc=

FEEowATEa(e)

HV-241F032 A B RWCU Ries HV-24182 A B'CIC IILIEcTION HV-249F013 2%9<20 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 A,B XV-243F004 A,B XV-243F009 A,B,C,O XV-243FOIO A,B,C,O XV-243F011 A,B,C,O XV-243F012 A,B,C,O XV-243F040 A,B,C,Q XV-243F057 A,B Nuclear Boiler Vessel Instrument XV-242F041 XV-242F043 A,S XV-242F045 A,B XV-242F047 A,B XV-242F051 A,B,C,D XV-242F053 A,B,C,O XV-242F055 XV-242F057 XV-242F059 AiBsCsO ~ EsFtG H L H N P R S T U XV-242F061 XV-24201 XV-24202 Nuclear Boil'er XV-24IF070 A,B,C,D XV-241F071 A,B,C,O XV-241F072 A,B,C,D XV-241F073 A,B,C,D XV-241F009 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 SYSTEM(S)

VALVE NUMBER AFFECTED HV-Ell-ZF0218 RHR HV-. Ell"2F0108 RHR HV- Ell-2F0048 RHR HV- Ell"2F0078 RHR HV-Ell-2F1048 RHR HV-E1 1-2F0268 RHR HV- Ell-2F0288 RHR HV- El 1-2F0478 RHR HV-Ell-2F0168 RHR HV- Ell-2F0038 RHR HV- Ell-2F0178 RHR HV-E21-2F0318 CS HV- E21-ZF0018 CS HV- Ell"2F 1038 RHR HV-Ell-2F0758 RHRSW HV-E11=2F0738 RHRSW HV-E11-ZF0060 RHR HV-Ell-2F0040 RHR HV-Ell-2F0248 RHR HV-E21-2F0158 CS HV- E21-2F0048 CS HV- E21-2F0058 CS HV- E51-2F045 RCIC HV-E51-2F012 RCIC HV-E51-2F013 RCIC HV-25012 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 will be restricted.to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the 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 will not 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 for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENTINTEGRITY and the primary containment leakage rate given in Specificationa 3.B.1.1 and 3.8.1.2. The specification makes allowances for the 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 Operating experience has indicated has occasionally occurred In the leak ters'ntact.

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