ML17158B107

Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program.

ML17158B107
Person / Time
Site:	Susquehanna
Issue date:	02/12/1996
From:	PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17158B106	List: ML17158B105 ML17158B107 ML18026A462
References
NUDOCS 9602160131
Download: ML17158B107 (59)

Text

3/4.6 CONTAIHMEHT SYSTEMS 3/4.6.1 PRIMARY CONTAIHMEHT PRIMARY CONTAIHMEHT INTEGRITY LIMITIHG CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAIHMEHT INTEGRITY shall be maintained.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2" and 3.ACTION: Without PRIMARY CONTAIHMEHT INTEGRITY, restore PRIMARY CONTAIHMEHT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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'n COLO SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE RE UIREMEHTS 4.6.1.1 PRIMARY CONTAIHMEHT INTEGRITY shall be demonstrated:

a.b.c d.After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A Qs wn~r44y-iwgWhal~he~h~neasu~~aka added-ta-8>e

-1~keg'su ant-to-Surve+1-1-anee-Aequi-'eae-her-Type-B-and-C

-penetrat4ons

-,the-At least once per 31 days by verifying tha4 all primary containment penetrations~

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.3-1 of Specification 3.6.3.By verifying each primary containment air lock OPERABLE per Specification 3.6.1.3.By verifying the suppression chamber OPERABLE per Specification 3.6.2.1..See Special Test Exception 3.10.1""Except valves, blind flanges, and deactivated automatic valves which are located insi'de the containment, and are locked, sealed or otherwise secured in the closed position.These penetrations shall be verified closed during each COLO SHUTDOWN except such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once per 92 days.SUSQUEHANNA

-UNIT 1 9602i60i3i, 9602i2 PDR ADQCK 05000387 P PDR 3/4 6-1

~IN~)~T B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

l 0 CONTAINMEHT SYSTEMS PRIMARY CONTAIHMEHT LEAKAGE LIMITING CONOITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to: (Vij C.A&>+)a.An overall integrated leakage rate penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves", main steam line d'rain valves" and.'alves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests.v I c."Less than or equal to 46 scf per hour foi all four main steam lines through the isolation valves when tested at Pt, 22.5 pstg.d."-Less than or equal to 1.2 scf per...hour for any one main steam line drain valve when tested.'-Q6 e.A combined leakage rate of less than or equal to 3.3 gpm for all containment isolation valves in hydrostatically tested lines which APPLICABILITY:

When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.l.l.ACTION: With: a.b.e.I The measured overall integrated primary containment leakage rate bye<>~>)'exceed-., or Tl0+The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3"1,'except for main steam line isolation'alves", main steam line drain valves" and valves which are hydro-statically leak tested per Table 3.6.3-1, subject to Type 8 and C tests exae , or no+C.$a'he measured I'eakage rate exceeding 46 scf per hour for all four main steam lines through the isolation valves, or The measured leak rate exceeding 1.2 scf per hour for any one main steam line drain valve, or The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 3.3 gpm, emption to Appenctix"J" of 10 CFR,50.SUSQUEHANNA

-UNIT 1 3/4 6-2 Amendment'o.

29 jNSI~T B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.,n C in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, NTAINM Y TEM LIMITIN NDmON FOR OPERATION Continued~AT~I (Continued) i'Bstore: 8s b.C.b (C)The overall integrated leakage rate to kess-than-or-equal-to-OP5-L-and t(syph.4~>3 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 and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests to I, r-equal-to-0-.60-L

-and The leakage rate to less than or equal to 46 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 200 F.URVEILLANCE REQUIREIVIENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated

+C=fbe-following-test-dul inc&shel AMBtef ml ne&~nfofmanefHtvith4le-CAte A8-specifi BN AAp J of 10 CFR 50,using the methods and provisions of ANSI N45.4-1972: 80 ree Type A Overall Integrated Containment Leakage Rate tests shall b onducted at Q a 10 month intervals during shutdown at P45.0 psig, duri each 10-year service p riod.~If any periodic e A test fails to meet.75 Lthe test s dule for subsequent Type A tests shall be revi d and approved by the Comm'on.If two consecutive Type A tests fail to meet.75 Type A test shall be rformed at least every 18 months until two consecutive Type A meet.75, at which time the above test schedule may be resumed.C.The accuracy of each Type A te hall b erified by a supplemental test which: Confirms the accy cy of the test by verify that the difference between the supplemental 1ta and the Type A test data is'thin 0.25 I.2.Hasp ration sufficient to establish accurately the c ge in leakage rate b tween the Type A test and the supplemental test.Requires the quantity of gas injected into the containment or ble m the containment during the supplemental test to be equivalent to at lees 5 percent of the total measured leakage at P45.0 psig.~Exemptio~PAppend~

SUSQUEHANNA

-UNIT 1 3/4 6-3 Amendment No.121

~p 0 C in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, D in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, for the following:

a.Type A Test b.Type B and C Tests (including air locks and purge supply and exhaust isolation valves)c.Air Locks d.Main Steam Line Isolation Valves e.Hydrostatically Tested Containment Isolation Valves f.Purge Supply and Exhaust Isolation Valves 0

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.Type B and C'ests shall be conducted with gas at P , 45;0 psig," intervals no greater than 24 months except for testI involving:

Air locks, 2.ain steam line isolation valves and main steam 1 e drain v ves, 3.Contas ent isolation valves in hydrostati lly tested lines which pe trate the primary containment and Purge supply d exhaust isolation.ives with resilient material seals.e.'.Air locks shall be tested nd de strated OPERABLE per Surveillance Requirement 4.6.1.3.Main steam line isolation ives nd main steam line drain valves'hall be leak tested at east once r 18 months.I'Containment isoIati valves in hydrant ically tested 1ines which penetrate the pr ary containment shall be eak tested at'east once per 18 months.Purge sup and exhaust isolation valves with re lient material seals s 1 be tested and demonstrated OPERABLE per urveillance

!Requi ment 4.6.1.8.2.

e provisions of Specification 4.'0.2 are not applicable t Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, 4.6.1.2.d, an 4.6.1.2.e.SUSQUEHANNA

-UNIT 1 3/4 6-4 Amendment No.36

s ,', r"p<a s,rut$h CONTAIHMEHT SYSTEMS PRIMARY COHTAIHMEHT AIR LOCKS LIMITING CONOITION FOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERABLE with: a.Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and 5 b.An overall air lock leakage rate n~~q APPLICABILITY:

OPERATIONAL CONDITIONS 3., 2" and 3.ACTION: ygs r)s i)s'ps ae b.Mfth one primary containment afr:lock door inoperable:

s'1.Maintain at least the OPERABLE air lock door closed and efther-".;,"

restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the.OPERABLE air lock door closed.2.Operation may then continue until performance of the next requfred-overall afr lock leakage test provide'd that the OPERABL'E air lock" door fs verified to be locked closed at least once per 31 days.-3.Otherwise, be in at least HOT SHUTGSO within the next X2 hours and in COLD SHUTDOWN wfthin the followfng 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Mfth the or<nary containnent air 1och$noperah'le, escape as a resn1t of an inoperable air lock door, maintain at least one air lock door closed;restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.or be fn 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 COLO SHUTDOWN within thel'ollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.p"See Special Test Exception 3.10.1.SUSQUEHANNA

" UNIT 1 3/4 6-5 ,g I Amendment Ho.,;;~78,(i

~').':.(v"",

1~~~y INSERT B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

CONTAINMEHT SYSTBlS SURVEILLANCE RE UIRBIEHTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:~~g h-a a~~~y verifying seal leakage rate Ass-tNhan-o~q e-qap&atween-the-doo~al-s

-fx-pea b.By conducting an overall air lock leakage test'e%4ying-that-th akag c gh p~h-1 C p XS th~d 4-I'H~l I~-makltenafice-has-been-pePAFmed-on

-tahe-ale-"l4ck-'that-colAd-4l 4-N 4W~~~At least once per 6 months by verifying that only.one,'door in each air lock can be opened at a t$ae.~-Vh.~i-Sp i&M-ldl.'M Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested upon initial entry after the primary containment has been de-inerted.

SUSQUEHANNA

-UNIT 1 3/4 6-6 Amendment No.29 NS RT B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

CONTAINMENT SYSTEMS PRO'.ARY CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONOITION FOR OPERATION 3.6.1.5 The structural integrity of the primary containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.3..5.APPLICABILITY:

OPERATIONAL CONOITIONS 1, 2 and 3.ACTION: '.lith the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTOOWN within the next i2 hours and in COLO SHUTGOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE RE UIREMENTS 4.6.1.5.1 The.structural integrity of the exposed accessible interior and exterior surfaces of the primary containment, including the liner plate, shall be detenNoed-during-th~utdow'n-fo~ch-Type-A-coataQment-'t-eakage-mate-

~e i 1'I M~~p~~As performed-prio~o-the-Type-A-co~ment

-l-eakzge-rate-to-v~3-fino-appareiK

~nges-Q-appearance-o~~bnom~e gradation 4.6.1.5.2 Re orts Any abnormal degradation of the primary containment structure detecte during the required inspection shall be reported in a Special Report to the Commission pursuant to Specification

6.9.2 within

30 days.This report shall'nclude a description of the condition of the concrete, the inspection proi.dure, the tolerances on cracking, and the corrective actions taken.,'HCt:l:A-UNIT 1 3/4 6-8 Amendment No."c

~INSE T B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

~~e CONTAINMENT SYSTEMS ORYMELL ANO SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONOITION FOR OPERATION 3.6.1.8 The drywell and suppressian chamber purge system may be in operation far up to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> each 365 days with the supply and exhaust isolation valves in one suppIy line and one exhaust line open for inerting, deinerting or pressure control.".

I APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.acTiaih a.Nth a drywell and/or suppression chamber purge supply and/or exhaust'solation valve open, except as permitted abov6, close the valve(s)within.four hours or be in at least HOT SHUTQOMN 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 COLO SHUTGOWN within the fallowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />., b.Mith a containment purge supply and/or exhaust isolation valve(s).with.resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.8.2, restore the inoperable valve(s)to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ar be in't least HOT SHUTOOMN within the next XZ hours and in COLO SHUTOOMN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />', SURVEILLANCE RE UIREMENTS 4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust, butterfly isolatian valves shall be verified not to have been open.fot more than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in the previous 365 days." l'.;4.6.1.8.2 Each 18 inch and 24 inch drywell and suppression chamber purge.supply and exhaust with resilient material seals shall be demonstrated OPERABLE by ,t ver ifying that the measured leakage rate is u~o-(hA)5-L

-when-,y,~ssur4zed-to~

at least once per 6 months.1 3/4 6"U.e~I"Valves open for pressure control are not subject to,the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per',365 day': 1iait presided the 2-inch bypass line is being utilized.SUSQUEHANNA

-UNIT 1 tg s~~~+)'

k I B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

4, BA E 4 4..1 P MA Y AINMENT INTE Rl 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.

4..1 2 P I ARY NTAINME LEAKA The limitations on primary containment leakage rates ensure that the to containment leakage volume will not exceed the value assumed in the accident analyses at the pressure of 45.0 psig, P,.As an added conservatism, the measured overall integrated leakage rate s further limited to less than or equal to 0.75 I during performance of the periodic tests to accoun for possible degradation of the containment leakage barriers between leakage tests.Crypt.A+esH3 Operating experience with main steam line 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.Q The surveillance.

testing for measuring leakage rates is consistent with th~quiremen~Mppendix.'"J-"o ith-the-exception-of-exemptions-granted-for-main-steam-isolation-and-drain--valve-leak-testi rid-testiri e-airiocks-after-each-o enin ng-a g-th p g (a3 The frequency for performing the Type A tests is consistent withPhe-mquiremente-of-4OQFR69-

• ppendix-J

-whh-the-exception-of-the-exemption-gmntedtothe-scheduler-requimmentsoMectionr, I-II-.GAfeI-.4..1;RIIVIARY NTAI MME AI L K The limitations on closure and leak rate for the primary contain e t air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and th peeiTieatiorva-8-.6-.'I+~n~-.68~

The-speeiTieation-rnakemilowanoes-for-the4aotthawhero-may-be-Iong-periods-of-time-when-the-eir-locke-will-be-in-a-closed-and-secured-position-during-reactor-mperatioa Only one closed door in each air lock is required to maintain the integrity of the containment.

4 14 IVI I EA E Calculated doses resulting from the maximum leakage allowance for the main steamline isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided the main steam line system from the isolation valves up to and including the turbine condenser remains intact.Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.

The requirement for the leakage control system will reduce the untreated leakage from the MSIVs when isolation of the primary system and containment is required.SUSQUEHANNA

-UNIT 1 B 3/4 6-1 Amendment No.Jgl r t i x

[NSE T F design basis LOCA maximum peak containment O G Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

t' CONTAINMENT SYSTEMS-BASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY~This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit.Structural, integrity is required to ensure that the containment will withstand the maximum pressure of 45.0 psig in the event of a LOCA..A visual i'nspection i~onjunction ype-A-leakage

-&sos-is sufficient to demonstra e this capability.

3/4.6.1.6 ORWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression in chamber internal pressure ensure that the containment peak pressure of 45.0 psig does not exceed the design pressure of 53 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5 psid.The limit of 2.0 psig for initial positive containment pressure will limit the total pressure to 45.0 psig which is less than the design pressure and is consistent with the safety analysis.3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340 F during LOCA conditions and is consistent with the safety analysis.3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM'he drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting;de-inerting and pressure control.Until these valves have been demonstrated capable of closing during a LOCA or steam line break accident, they shall be blocked so as not to open more than 504.Until these valves have been demonstrated capable of closing within the times assumed in the safety analysis, they shall not be open more than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in any consecutive 365 days.Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.The 0.60 L leakage limit shall not be exceeded when the leakage rates determined 8y the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.SUS(UEHANNA

-UNIT 1 8 3/4 6-2'mendment'o.

29

~INS RT C in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, I J k T ADMINl TRATlV NTR 6.7 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a.The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.The Vice President-Nuclear Operations and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.b.A Safety Limit Violation Report shall be prepared.The report shall be reviewed by the PORC.This report shall describe (1)applicable circumstances preceding the violation, (2)effects of the violation upon unit components.

systems or structures, and (3)corrective action taken to prevent recurrence.

c.The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Vice President-Nuclear Operations within 14 days of the violation.

'd.Critical operation of the unit shall not be resumed until authorized'by the Commission.

6.8 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below: a.The applicable procedures recommended in Appendix"A" of Regulatory Guide 1.33, Revision 2, February 1978.b.Refueling operations.

c.Surveillance and test activities of safety related equipment.

d.Security Plan implementation.

e.Emergency Plan implementation.

f.Fire Protection Program implementation.

g..PROCESS CONTROL PROGRAM implementation.

h.Offsite Dose Calculation Manual implementation.

i.Quality Assurance Program for effluent and environmental monitoring, using the guidance of Rej~latory Guthrie.4.1,5+egruary'.1979:

I 6.8.2 Each procedure of 6.8.1(a)through (g)above, and changes thereto, shall be reviewed in accordonce with Specifications 6.5.1.6 or 6.5.3, as, appropriate, and approved by the Superintendent of Rant-Susquehanna prior to-implementation and shall be reviewed periodically as set forth in administrative procedures.

Each procedure of 6.8.1, above, and changes thereto, that is established to implement those portions of the radiological effluent and environmental monitoring programs and those portions of the ODCM that are the responsibility of Nuclear Technology shall be approved by the Manager-Nuclear Technology.

SUSQUEHANNA

-UNlT 1 6-15 Amendment No.117 r l I s ADMINISTRATIVE CONTROLS PROCEOURES AND PROGRAMS (Continued}

6.8.3 Temporary

changes to procedures of 6.8.1 above may be made provided: a.b.C.The intent of the original procedure is not altered.The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.The change is documented, reviewed in accordance with Specfffcation 6.5.1.6 or 6.5.3, as appropriate, and approved by the Superintendent of Plant-Susquehanna within 14 days of implementation.

6.8r4 The following programs shall be established, implemented, and maintained:

a.Primar Coolant Sources Outside Containment b.A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious, transient or accident to as low as pract'ical',r'.'levels.

The syst'ems include the core spray, high pressure coolant injection, reactor'ore isolation cooling, reactor water cleanup,.standby gas treatment, serac discharge, residual heat removal, past accident sampling and containment air monitoring systems.The program shall include the following:

1.Preventive maintenance and periodic visual inspection requirements, and 2.Integrated leak test requirements for each systim at refueling cycle intervals or less.In-Plant Radiation Nonitorin C.A program which will ensure coolant, radioactive iodine and containment atmosphere shall include the following 1.Training of personnel.

2.Procedure for sampling 3.Provisions for mainten the capability to obtain and analyze reactor s and partfculatis in plant gaseous effluents, samples under accident conditions.

The program and analysis, ance of sampling and analysis equipment.

r A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas,undid accident conditions.

This program shall include the followi'ng:

1.Training of personnel, 2.Procedures for monitoring, and 3.'rovfsfons for maintenance of sampling and analysis equipment.

Post-accident 5 lin 6-16, a n Amendment No.82 AUG',3 0 198 lEREBj ai A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10 CFR 50.54(o)and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163,"Performance-Based Containment Leak-Test Program", dated September 1995.The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 45.0 psig.The maximum allowable primary containment leakage rate, La, at Pa, shall be 1%of the primary containment air weight per day.Leakage Rate Acceptance Criteria are: a.Primary Containment leakage rate acceptance criterion is<1.0 La.During each unit startup following testing in accordance with this program, the leakage rate acceptance criteria are<0.60 La for Type B and Type C tests and<0.75 La for Type A tests;b.Air lock testing acceptance criteria are: 1)Overall air lock leakage rate is<0.05 La when tested at>Pa, 2)For each door, leakage rate is<5 scfh when pressurized to>10 psig.The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.The provisions of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

I-.3/4.6 CONTAIHMEHT SYSTEMS 3/4.6.1 PRIMARY CONTAINMEHT PRIMARY CONTAINMEHT INTEGRITY LIMITIHG CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAIHMEHT IHTEGRITY shall be maintained.

P.APPLICABILITY:

OPERATIOHAL COHOITIONS 1, 2" and 3.ACTION: Without PRIMARY CONTAINMENT IHTFGRITY, i estore PRIMARY CONTAIHMEHT INTEGRITY within 1 h'our or be in at least HOT SHUTOOWN 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 COLO'SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE RE UIREMEHTS~(4.6.1.1 a.b.c d.PRIMARY COHTAIHMEHT INTEGRITY seal l.be demonstrated:

After each closing of each penetration subject=to Type 8 testing, except the primary coninment air lock's, if'opened following Type A*'or B test, by leak rate testing th IM Nt-added-4o-@he-keakageratM-'detemmed-pursuance-t~SuvvH-1-lance 4eq~ement-her-Type-B-and-G-penetraÃon~e-At least once per 31 days by'verifying that all'primary containment penetrations"" not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident'conditions.are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table'.6.3-1 of Specification 3.6.3.By verifying each primary qontainment air lock OPERABLE per Specification 3.6.1.3.By verifying the suppression chamber OPERABLE per Specification 3.6.2.1.""Except valves, blind flanges, and deactivated automatic valves which are located inside the containment, and are locked, sealed or otherwise secured in the closed position.These penetrations shall be verifi'ed closed during each COLO SHUTOOWN except such verification need not be performed when the primary containment has not been de"inerted since the last verification or more.often than once per 92 days.SUSQUEHANNA

" UNIT 2 3/4:6-.1 B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

3.6.1.2 Primary containment leakage rates shall be limited.to: (Yypt k I-cs>')a.An overall integrated leakage rate)b.A combined leakage rate ef-less-tharI-or-equal-te-QAQ-~

for all penetrations and all~~valves listed in Table 3A.3-1, except for main steam line isolation valves, main steam line'drain valves'nd valves which are hydros'tatically leak tested per Table 3.6'.3-1, subject to Type 8 and C tests.~r c.Less than or equal to 100 scf per hour for any one main steam isolation valve and a combined'aximum pathway leakage rate of 5 300 scf per hour for all four main, steam lines through the isolation valves when tested at P22.5 psig.d.'Less than or equal to 1.2 scf~er hour for any one main steam line drain valve 5V 0-e.A combined leakage rate of less than or equal to 3.3 gpm for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 P-49-.6-peig-.

• 3.6.1.1'.With: (~<~~A mph')no+(D a.The measured overall integrated primary containment leakage'rate

~eeeding-O~-

+;,or.b.The measured combined leakage rate for all penetrations and all valves listed in, Table 3.6.3-1, exce'pt for main steam line isolation valves', main steam line drain valves and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C testes'WOJ or no+c.The measured leakage rate exceeding 100 scf per hour for any one main steam isolation valve or a total maximum pathway leakage rate of)300 scf per hour for all four main steam lines through the isolation valves, or d.The measured leak rate exceeding 1.2 scf per Itour for any one main steam.line drain valve, or'.The measured combined leakage rate for all containment isolation valves in hydrostatically tested line's which penetrate the primary containment exceeding 3.3 gpm, 0 Exemption to Appendix"J" of 10 CFR 50.SUSQUEHANNA

-UNIT 2 3/4 8-2 Amendment No.121

O B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.C in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, LIMmNG CONDITION FOR OPERATION (Cononuedl

~gfgg IContlnuedl restore:~, a.The overall integrated leakage rata to Iess-than-or-equaH~-.75-LI, and (7yf~A kess3.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, mairr steam line drain valves and valves which ara hydrostatically leak tested par Table 3.6.3-1, subject to Type B and C tests to 3eaa-thep-or-

.squa~MBtu, and'I c.The leakage rate to less than or equal to 11.5 scf par hour for any main steam'isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage rate to 5300 scf par 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 tasted lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200'F.SURVEILLANCE REQUIREMENTS

~D 4.6.1.2 The primary.containment leakage rateS shall be demonstrated et-the-foeowin~esmchad~nd-the.methods and provisions.

of ANSI N45A-1972: a.ee Type A Overall Integrated.

Containmeftt Leakage.Rate tests'shall be cond~ed at 40 a 10 m h intervals during shutdown ht P45.0 p'sig, during each 10-year s Mica period.b.If any p'eriodic a A test fails to meet.75 Ltha test schedule r subsequent Type A tests shall be reviewed an proved by tha Commission.

If tw onsacutive Type'A tests fail to~meat.)5 I, a Type,A tes ball be performed at least ry 18 months until two consecutive Type A tests meet.75 I, at h time the abov st schedule may be resumed.c.'he accuracy of each Type A test shall erified by a supplemental test which: 1.Confirms the accuracy'he'est by ve ng that the difference between the supplemental data a e Type A test data is withi 25 L2.Has durati sufficient to establish accurately the change in akaga rate between the Ty est and tha supplemental test.Requires the quantity of gas injected into the containment or bled from the tainment.during the supplemental test to be equivalent to at least 25 percent of the total m ured leakage at P'45.0 psig.<<SUSQUEHANNA

-UNIT 2 3/4 6-3 Amendmant No.09>

~SF~T C in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, D in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, for the following:

a.Type A Test b.-Type B and C Tests (including air locks and purge supply and exhaust isolation valves)c.Air Locks d.Main Steam Line Isolation Valves e.Hydrostatically Tested Containment Isolation Valves f.Purge Supply and Exhaust Isolation Valves t'I CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.Type B and C tests shall be conducted with gas at P , 45.0 psig,>>a intervals no greater than 24 months except for.test involving:

l.Air locks, 2.n steam line isolation valves and main steam li drain val Containme isolation'alves in hydr'ostati-ly tested lines which penetr e the primary containment nd 4.Purge supply and haust isolation ives with resilient material seals.e.'ir locks shall be tested and Requirement 4.6.1.3.nstrated OPERABLE per Surveillance f..Main steam line isolatio alves and in steam line drain valves shall be leak tested.a east once per 1 months.h.Containment isola on valves in hydrostatical tested lines which penetrate the mary containment shall.be leak sted.at least once per 18 month.1.Purge'ply and exhaust isolation valves, with resilien a'terial seal shall be tested and demonstrated OPERABLE per Survei ance.Re irement 4.6;1~8.2.The provisions of Specification 4.0.2 are not applicable to Speci'-tions 4..6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, 4.6.1.2d and 4.6.1.2e.SUSQUEHANNA

-UNIT 2 3/4 6-4 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERABLE with: a.Both doors closed except when the air lock is being used for normal transit entry and exit through the containment,.

then at least one air lock door shall be closed, and b.An overall air lock leakage rate APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2" and 3.ACTION: a.With one primary containment air lock door inoperable:

a b.1.Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.2.Operation may then continue until per'formance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.3.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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.With the primary'containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed;restore'he inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 />.pPP E*M SUSQUEHANNA

" UNIT 2 3/4 6-5 Amendment No.43 B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE: b.C.~hm-72-hour.McRWw4ag-each-&es4n~xce~be~hemi.~oc~z-d-a verifying seal leakage rate Less-tha~p-beCween-the-d ia 5/By conducting an overall air lock leakage test 4-im44;-AA 4 p 4 h~~~8-sCaN-iong-PIQHARY

-CONTAL4ME~NTEGRI1-Y-when-eaintenan~as-been-peA~e

'C-coAd-~cC-th parity~At least once per 6 months by verifying that only one door.in each air lock can be opened at a time.""-CP AM%44'.pt'ption-to-AypenCQ~of CFR-Part-50

""Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment, is inerted, provided that the inner door interlock is tested upon initial entry after the primary containment has been deinerted.

SUS(UEHANNA

-UNIT 2.3/4 6-6 B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

CONTAIHHENT'YSTEHS PRIMARY CONTAINMENT STRUCTURAL INTEGRITY.,LIHITING CONOITION FOR OPERATION 3.6.1.5 The structural integrity of the primary containment shall be~intai'~

at a level consist~nt with the acceptance criteria in SPecification 4.6.1.5.s~~APPLICA8ILITY:

OPERATIONAL'CONOITIONS 4, 2 and 3.ACTION: With the structural integrity of the primary containment not conforming to t'h e abcve requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTOOWN 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 COLO SHUTGOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE RE VIREHENTS ,4.6.1.5.1 The structural integrity of the exposed accessible interior and.'xterior surfaces of the primary containment, including the liner plate, shall be 4etenn%eed-du~th~utdown-for-each~e-A-containment

-leakag~ate

'testy-e vi suallp inspectPR 6 ().'~efonaed-pA-or-t~e-Type-'A-containment

-leakag.'paint changes'-appear an~r-other-abnormal-degrad~ea'.6.1.S.2 Reports Any ahnonea1 degradation of the primary containment structure detected'during the required inspection shall he reported in a Special Report to the Coamission pursuant to Specification

6.9.2 within

3O days.This report, shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective actions taken.SUSqVEHANNA

-UNIT 2 3/4 6-8

~IIEET B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

CONTAINMENT SYSTEMS ORYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONOITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation for up to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> each 365 days with the supply and exhaust isolatioO.

valves in one supply line and one exhaust line open for fnerting, deinerting or pressure control." APPLICABILITY:

OPERATIONAL CONOITIONS 1, 2, and 3.ACTION:.With a drywell and/or suppression chamber purge supply and/or exhaust isolation valve open, except as permitted above, close the valve(s)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 the next 12 houis and in COLO SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.b.With a containment purge supply and/or exhaust, isolation valve(s)with resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.8.2, restore.the inoperable valve(s)to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTOOWN 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 COLO SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE RE UIREMENTS 4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust butterfly isolation valves shall be verified not to have been open for more than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in the previous 365 days." 4.6.1.8.2 Each 18-inch and 24-inch drywell and suppression chamber purge supply and exhaust with resilient material seals shall be demonstrated OPERABLE b~\tg~Mg when-pmssu~d-to~

at least once pet 6 months.a.Valves.open for pressure control are not subject to the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 day limit provided the 2-inch bypass line is being utilized.SUSQUEHANNA

-UNIT 2 3/4 6" 11

/1 0 B in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

BASES PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from.the containment atmosphere will be restricted to those leakage paths'nd associated leak'rates assumed in the accident analyses.This restriction, in conjunction with the leakage rate limitation,'ill 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 co inment leakage volume will not exceed the value assumed in the accident, analyses at the pressure g~VIE,A I-d>P of 45.0'psig, P,.As an added conservatism, the measured overall integrated leakage rate~is further limited to less th'an or equal to Os75 L, during performance of the periodic tests to accoLInt 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 tightness of the valves;therefore..the special requirement for testing these vafves.G The surveillance testing for measuring leakage rates-is consistent withe ulremaa~f isolatio~pcLdrain-valve-leak-testing-and-testing-alrlocks-atter-each-opening

.The frequency for per'forming the Type A tests is consistent with-the-requirernen~f-Q3-CFR-50 e-exception-cd-the-exemption-granted-to-the-schedule-requirements~f Wectie The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY.CONTAINMENT INTEGRITY and the-srtrnarY-aentainnrent-lssiraas-8-that-there-rRey-be-IoRg-periods-of-time-when-the-eir locks-will-be-In-e-closed-and-secured-pesltieR-duri'ea Only one closed door in each air lock is required to maintain the.Integrity of the'containment.

SUSQUEHANNA

-UNIT 2 B 3/4 6-1 Amendment No.Hg.1 p1 4 0 INSERT F design basis LOCA maximum peak containment O G Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

CONTAINMENT SYSTEMS BASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit.Structural integrity is required to ensure that the containment will withstand the maximum pressure of 45.0 psig in the event of a LOCA.A visual inspection i-n-conjunction-

'pe-Al-eakage-test is sufficient to demonstrate this capability.

3/4.6.1.6 DRYWELL AND SUPPRESSION'CHAMBER INTERNAL PRESSURc The limitations on drywell and suppression in chamber internal pressure ensure that the containment peak pressu're of 45;0 psig does not exceed the design pressut e of 53 psig during LOCA conditions or that the external pres'sure differ-ential does not exceed the design maximum external pressure differential of 5 psid.The limit of 2.0 psig for initial positive containment pressure will limit the total pressure to 45.0 psig which is less than the design pressure and is consistent with the safety analysis.3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does.not exceed the design temperature.

of 340'F...during LOCA conditions and is consistent with the safety analysis.(" 3/4.6.1.8'9RYMELL AND SUPPRESSION CHAMBER PURGE SYSTEM l r The drywe11 and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting and pressure control.The 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 day limit on purge valve.operation is imposed to protect the integrity of the SGTS filters.Analysis indicates that should a LOCA.occur while this pathway is being utilized, the associated pressure surge through the (18 or 24")purge lines will adversely affect the integrity of SGTS.This limit is not imposed, however, on the subject valves when pressure control is being performed through the 2-inch bypass line, sinch a pressure surge through this line does not threaten the OPERABILITY of SGTS.Leakage integrity tests with a maximum allowable.

leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops;The 0.60 L leakage limit shall not be.a exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.SUSQUEHANNA

-UNIT 2 B 3/4 6-2 C in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, 6.7 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a.The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.The Vice President-Nuclear Operations and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.b.A Safety Limit Violation Report shall be prepared.The report shall be reviewed by the PORC.This report shall describe (1)applicable circumstances preceding the violation, (2)effects of the violation upon unit components, systems or structures, and (3)corrective action taken to prevent recurrence.

c.The Safety Limit Violation Report shall be submitted to.the Commission, the SRC and the Vice President-Nuclear Operations within 14 days of the violation.

d.Critical operation of the unit shall not be, resumed until authorized by the Commission.

'6.8 p 6.8.1 Written procedures shalt be established, implemented and maintained covering the activities referenced below: a.The applicable procedures recommended in Appendix"A" of Regulatory Guide 1.33, Revision 2, February 1978.b.Refueling operations.

c.Surveillance and test activities of safety related equipment.

d.Security Plan implementation.

e.Emergency Plan implementation.

f.Fire Protection Program implementation.

g.PROCESS CONTROL PROGRAM implementation.

h.Offsite Dose Calculation Manual implementation.

i..Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory.

Guide 4.15, February 1979.6.8.2 Each procedure of 6.8.1(a)through (g)above, and changes thereto, shall be reviewed in accordance with Specifications 6.5.1.6 or 6.5.3, as appropriate, and approved by the Superintendent of Plant-Susquehanna prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

Each procedure of 6.8.1, above,.and changes thereto, that is established to implement those portions of the radiological effluent and environmental monitoring programs and those portions of the ODCM that are the responsibility of Nuclear Technology shall be approved by the Manager-Nuclear Technology.

SUSQUEHANNA

-UNIT 2 6-15 Amendment No.86 ANIHISTRATI VE CONTROLS PROCEGURfS AN PROGRAMS (Contf nued)6.8.3 Temporary changes to procedures of 6.8.1 above agr be sade provided: a.Th>>intent of the orfgfnal procedure fs not altered.b.The change fs approved by two aeabers of the unit aanageaent staff, at least one of whoa holds a Senfor Reactor Operator's License on the unit affected.c..The change is documented, reviewed fn accordance 4th Specification 6.5.1.6 or 6.5.3, as appropr fate, and approved by%he Superintendent of Plant-Susquehanna within 14 days of fapleaentatfon.

6.8.4 The following prograas shall be established, fapleatnted, and aafntafned:

Prfaa Coolant Sources Outside Contafnaent-A prograa to reduce leakage froa those portions of systems outside contafnaent that could contain highly radfoactfve fluids during a serious transient or accident to as low as practical levels.The systems include the core spray, high pressure coolant fn)ection, reactor core isolation cooling, reactor water clianup, standby gas treatment, scraa discharge, residual heat raeoval, post accident saaplfng and contafnaent afr aonftoring systems.The prograa shall include the following:

b.C.3..Preventive aafntenance and periodic visual inspection requirements, and 2.Integrated leak test requirements for each system at refueling cycle intervals or less.In-Plant Radiation Monitorin A prograa which will ensure the capability to accurately determine the airborne iodine concentration

'fn vital areas under accident conditions.

This program shall include th'e following:

1.Training of personnel, 2.Procedures for monitoring, and 3.Provisions for eafntenance of sampling and analysis equipment.

Post-accident Sam 1fn A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The prograa shall include the following:

1.Training of personnel.

2.Procedure for sampling and analysis, 3.Provisions for maintenance of sampling and analysis equipment.

SUSQUEHANNA

-UNIT 2 6-16 Amendment No.]7 OE 6.8.5 P a~MS~T i n Leaka e aeT o I A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10 CFR 50.54(o)and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163,"Performance-Based Containment Leak-Test Program", dated September 1995.The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 45.0 psig.The maximum allowable primary containment leakage rate, La, at Pa, shall be 1%of the primary containment air weight per day.Leakage Rate Acceptance Criteria are: a.Primary Containment leakage rate acceptance criterion is<1.0 La.During each unit startup following testing in accordance with this program, the leakage rate acceptance criteria are<0.60 La for Type B and Type C tests and<0.75 La for Type A tests;b.Air lock testing acceptance criteria are: 1)Overall air lock leakage rate is<0.05 La when tested at>Pa, 2)For each door, leakage rate is<5 scfh when pressurized to>10 psig.The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.The provisions of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

%~k l (0PI p'