ML20093L736

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Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys
ML20093L736
Person / Time
Site: River Bend Entergy icon.png
Issue date: 10/24/1995
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20093L719 List:
References
NUDOCS 9510260056
Download: ML20093L736 (16)
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Text

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Definitions '

1.1-1.1': DefinitionsL (continued)

' EMERGENCY CORE C00 LING' The ECCS RESPONSE TIME shall 'be that time interval .:

SYSTEM (ECCS) RESPONSE ~from when-the monitored parameter exceeds.its ECCS l TIME initiation setpoint at.the channel sensor until '

t the ECCS equipment is= capable of performing its.

safety function (i~.e., the valves travel.to'their i required positions, pump < discharge pressures reach their' required values, etc.). Times shall' include -

diesel generator' starting and. sequence loading >

delays, where applicable. The' response time.may t be measured by means of any series of sequential, j overlapping, or total steps so that the entire response time is measured.

END OF CYCLE. The E0C-RPT SYSTEM RESPONSE TIME shall be that

- RECIRCULATION PUMP TRIP time interval from initial movement of the (E0C-RPT) SYSTEM RESPONSE- associated turbine stop valve or the turbine TIME control valve to complete suppression of-the ,

electric arc between the fully open contacts of '

the recirculation pump _ circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.  ;

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall 'be that RESPONSE TIME time interval from when the monitored parameter i exceeds its isolation initiation setpoint at the .

channel sensor until the isolation valves travel to;their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that i the entire response time is measured. j 1

la Ih0 000i C Oll0%;bl0 PII 0TY 000I0iU 00t l00kO90 rate. L , 0h:11 be 0.25% cf pri=:ry cent:inment 1 cir =0i"ht per d:y :t the q:l=10ted p0:k j containmentoressure(P}vy g i

(continued) ]

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RIVER BEND 1.0-3 j Amendment'No.8FRLATER i 9510260056 951024 PDR ADOCK 05000458 P. .

..PDR

Primary Containment-Operating 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and NOTE leakage rate testing except for primary &R 3.0.2 is net containment air lock testing,. in . . _ _ .

applicable

.accordance withitheLPH marysCont'ainment leakageJRatslTesting? Pro Ap;fdhdii~J,"n?^M5diffEd~gramFM bi 'djipreved CFR" In 50,accordance exemption:. withithy Primary The leakage-rate cceptance criteri; is Containment es-1.0 La . Hewever, during the first Leakage 1 Rats..

unit startup fellowing testir.g perfer cd TestingtProgr,am ~

+ ,

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. . u..i.n. c. r. o., .e.n , ,n,-

ry m a 4. ., i n. ' e...r o.

. ..,en-

=cdified by appreved exemptions, the Appendix J, ::

leakage rate acceptance criteria 1: modified by ,

< 0.6 L afor the Type B and Type C test + cpproved l and < 0.75 L, for the Type A test. OXOPtiOD; l

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,~ RIVER BEND 3.6-2 AmendmentNo.84?1LATER

Primary Containment Air Locks 3.6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------NOTES------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.
2. During MODES 1, 2, and 3, results shall be evaluated against acceptance

, criteria of SR 3.6.1.1.1 in

accordance with the7 Primary Rate Testin t

NOTE

- ContsinmentTeak' Pr69ramT40"CFR~ 50, age [AppcEdiM,s c: SR 3.0.2 is not rediffbd by cpproved exc=ption:. cppliccble Perform required primary containn;ent air In accordance lock leakage rate testing in accordance withithe with thelPriisaff!C6ntaihment? Leakage ^Rste Ppimary; ..

Testing?ProgramO10~CFR'50,'AppbEdiiJ, Containment c:hsdiffEdb"3pprovedexc=ptions. Le_akage(Rats _

Testing Program Verify the combined leakage rate is 10"CFR 50,

s 13,500 cc/hr for all required annulus Appendix ', es bypass leakage paths when pressurized to = edified by aP-a PPr0"ed

. cxc=ption:

SR 3.6.1.2.2 Verify primary containment air lock seal 7 days air flask pressure is a 90 psig.

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SR 3.6.1.2.3 -

NOTE-------------------

Only required to be performed upon entry or exit through the primary containment air lock.

Verify only one door in the primary 184 days containment air lock can be opened at a

, time.

(continued)

RIVER BEND 3.6-7 AmendmentNo.8QLATER 4

PCIVs >

3.6.1.3

' SURVEILLANCE REQUIREMENTS (continued) ,

SURVEILLANCE FREQUENCY ..

SR 3.6.1.3.8 Verify in-leakage rate of 5; 340 scfh for 18 months each of the following valve groups when ,

tested at 11.5 psid for MS-PLCS valves '

and 33 psid for PVLCS sealed valves.

a. Division I MS-PLCS valves and Division I PVLCS valves.
b. Division II MS-PLCS valves and Division II PVLCS valves.
c. Division I MS-PLCS valves and all first outboard PVLCS valves.

SR 3.6.1.3.9 -----------------NOTE--------------------

Only required to be met in MODES 1, 2, and 3.

Verify the combined leakage rate for all NOTE secondary containment bypass leakage SR 3.0.2 is net paths equipped with PVLCS is s 170,000 cppliceb10.

cc/hr when pressurized to 2: P- a In accordance withEthe Primaryl_.

Containment Leakage: Rate TestinsfProgpam 10'CFR 50~,~ i Appendix J, es mcdified by apprcved exempticn:

(continued) l 1

RIVER BEND 3.6-18 AmendmentNo.81TiLAT.ER 1

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY j SR 3.6.1.3.10 -----------------NOTE-------------------- l Only required to be met in MODES 1, 2, '

and 3. l NOTE Verify leakage rate through the valves SR 3.0.2 i: ,

served by each division of MS-PLCS is net cpplicible s 150 scfh per division when tested at ~

aP-a In accordance with ths PFimary~

Containnsnt~

Lsakage Rate .

Tes. ting!ProgFam gg fppendix J, c '

mcdified by  ;

cpproved  ;

exc=ption  ;

SR 3.6.1.3.11 ------------------NOTE-------------------

Only required to be met in MODES 1, 2, '

and 3.

NOTE Verify combined leakage rate of I gpm SR 3.0.2 is not j times the total number of PCIVs through cppl iccble.- -

hydrostatically tested lines that penetrate the primary containment is not exceeded when these isolation valves are In accordance ,

tested at a 1.1 Pa . with thi PFimirf~

C6ntainsent Leak'ge a Rate TestingiProgrsm- i 40'cFR 50,~

f.ppendix J, c:

med4fied by cpproved exc=ptions (continued)

~ RIVER BEND 3.6-19 AmendmentNo.8QLATER

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY -

SR 3.6.1.3.12 Verify the combined leakage rate is NOTE ,

s 13,500 cc/hr for all required annulus SR 3.0.2 i: nct bypass leakage paths when pressurized to cppliccble ,

2: Pa-In accordance with ths .

Primirf;;

Containment Leakage 7 Rate TestingiProgram 10~CFR 50,

^

,ppendix J, c mcdified by ,

cpproved exemption i

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RIVER BEND 3.6-20 AmendmentNo.&ly[LATER I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Technical Specifications (TS) Bases Control Proaram (continued)

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.
d. Proposed changes that do not meet the criteria of either Specification 5.5.ll.b.1 or Specification 5.5.ll.b.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.12 Biofoulina Prevention and Detection A program, which will include the procedures to prevent biofouling of safety-related equipment, to assure detection of Corbicula in the intake embayment and the clarifier influent, and to monitor and survey safety-related equipment to detect bicfouling. Changes to this program will be submitted to and approved by the NRC (both the Region and NRR) prior to implementation.

5.5.13 Primary' Containment Lsakage7 Rats Tustina:Psoaram A program shallLbe'. established lto Limplement'..the leakage: rate

~

testing of the containment. as required by;10 CFR 50.54(o)c andL10 CFR 50,cAppendix'J, Option'B,7as-modified byfapprovedLexemptions.

This program.shall.be fin accordance with the guidelines contained in Regulatory Guide 1.163, '" Performance-Based-Containment: Leak-Test Program,"' as) modified by approved' exceptions.

The peak calculated containment 71nternal' pressure fori.the ' design basis loss of coolant accident, 'P a6 1s 7.6:psig.

1 Th'e Eaximtim allowableTleak' age rate, La, shall bs10.26%L of, primary con.tainment.. air weight per day;at' the-calculated ' peak containment pressure _.(P)-

a The provisionsLof SR 3 0'2ldoLnot' apply;;:toftes't f.requencies 1

specified in the: Primary. Containment : Leakage, Rate. Testing; Program.

The provisions of SR 3.0.3 arelapplicableito Primary;. Containment I Leakage Rate Testing' Program testLfrequencies. l The' Primary Containmentf oyerallLleak'agef ratsLacceptance LcriteFia is :s; 1.0 La . .During-theifirst unitLstartup following; testing in I accordance withithis: program,ithe leakage" rate a'cceptance criteria l are <' 0;6 L 'afor the Type Bf:and' Type:.C.;; tests: and'.<. 0.-75l1.s for

. Type'A-tests.

RIVER BEND 5.0-16 Amendment No. M ,fLATER l

l

5.5.13 ' Primary Containment Leakage Rate Testing Program A program shall be established to implement 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, l

"Perfonnance-Based Containment Leak-Test Program," as modified by 1 approved exceptions.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 7.6 psig.

+

The maximum allowable leakage rate, L., shall be 0.26% of primary containment air weight per day at the calculated peak containment pressure (P.).

The provisions of SR 3.0.2 do not apply to test frequencies specified in the Primary Conta'.nment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to Primary Containment Leakage Rate Testing Program test frequencies. 3 The Primary Containment overall leakage rate acceptance criteria is s 1.0 L..

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.6 L. for the Type B and Type C tests and < 0.75 L. for Type A tests.

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i Primary Containment-0perating  ;

B 3.6.1.1 -

BASES BACKGROUND 2. SR 3.6.1.1.1 leakage rate requirements are in (continued) conformancewith10CFR50,AppendixJf0ption]B(Ref.3),~

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, as modified by approved exemptions. ]

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APPLICABLE The safety design basis for the primary containment is that  ;

j SAFETY ANALYSES it must withstand the pressures and temperatures of the t limiting DBA without exceeding the design leakage rate.

The DBA that postulates the maximum release of radioactive material within primary containment is a LOCA. In the analysis of this accident, it is assumed that primary containment is OPERABLE'such that release of fission i products to the environment is controlled by the rate of primary containment leakage.

tnalytical methods and assumptions involving the primary

. containment are presented in References 1 and 2. The safety analyses assume a nonmechanistic fission product release following a DBA, which forms the basis for determination of offsite doses. The fission product release is, in turn, based on an assumed leakage rate from the primary containment. OPERABILITY of the primary containment ensures that the leakage rate assumed in the safety analyses is not exceeded.

4 The maximum allowable leakage rate for the primary containment (La ) is 0.26% by weight of the containment and drywell air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at the design basisfLOCAlmaximum peak containment pressure (P a ) of 7.6 p"sig'(Ref.~4).

Primary containment satisfies Criterion 3 of the NRC Policy Siatement.

LC0 Primary containment OPERABILITY is maintained by limiting  :

' verall o leakage to ys l.0.L ab DuringTtheLfirstistartup following:s. testing 11n:accordance with the? Primary Contai'nme~nt Leakage; Rate (Testing Program?(Ref3 5) R.the*1eakagetrate' acceptanceicriteria arel<LO.6; LaiforL theiTypelB.LandJype:C l

teststandL<j0,75 IJaiforlTypecAitestsi fi Sti t step efter performing require, d 10 CFR 50,except p'ris to th

. Appendix J, leckcge tc t. ^t this time, the combined Type B and C leakage must be < 0.6 L ai OCd th0 OVOI0ll IYPO A leakaoe must be < 0.75 yL r Compliance with this LC0 will ensure a primary containment configuration, including ,

(continued) ,

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RIVER BEND B 3.6-2 Revision No. LATER i

, s I

=

s l Primary Containment 4 perating B 3.6.1.1 1

BASES i SURVEILLANCE SR 3.6.1.1.1 (continued) ,

REQUIREMENTS ~ '

testrequirementsofth'e?Primarf*6C6ntainmestileakigelRats Testins Prop ami(RefD 5)U 10~CFR 50 D ppendi TJ"(Ref7 3)7 ::

inedified' bi pprcEdd ~5hc=jition:. Failure to meet air lock  :

leakage testing (SR 3.6.1.2.1 and SR 3.6.1.2.4) resilient i seal primary contaiinment purge valve leakage testing (SR 3.6.1.3.5), secondary containment bypass leakage (SR , 3.6.1.3.9), main steam positive leakage control system n '

(SR 3.6.1.3.10), hydrostatically tested ' valve leakage (SR 3.6.1.3.11), or annulus bypass leakage (SR 3.6.1.3.12) does not necessarily result in a failure of this SR. The impact of the failure to meet these SRs must be evaluated

'j against the Type A, B, and C acceptance criteria of the ( i Primary"ContainmentLeakage]RateiTsstinpProgiamMThe" \ 4 t Primary; Containment!overallileakige! rate 3cceptancicpitefia <

testingsiniaccordance;with?thisiprograshthel rs;te leakage;gis3:s;;1 acceptanceLcriteria: fare %0;61Lpon?a?Makimum:Pathwai' Le'akage LRatey(MXPLR)(forj thei Type 18? and 4TypeiC1.testsfaind

<0;75;Lpfor;TypelAlt'estsOTheMXPLRjfor;combipsdJype?B indCNieakagelisstheimeasuredfleakageShroughithelworst4f '

the ; two L i sol ati on1 val ve s J unlse' si al penetrati on1i s(i sol ated by!uselofcone:Tclosedjandideactivatedtautomatic%alvesiclosed+

manualWalvehor,blindiflange:' In: thistcaseMthe;MXPLR;of thefisolated : penetration)isiassumed :tol be the! measured ~

leakagelthroughJthefisolstion(device.10'CFR'50,?pp6ndixJ,

.  :: modifidd' by apprcV5d '6xbmptiens'(Ref. 3) . A: !cft ,

4eakage pricr tc the first startup after perfor=ing  !

required 10 CFR 50, Appendix J, leakage test i required to be < 0.6 L 7 or f

combined Tyne B and C leakage. and < 0.75 L,g for ever:1 Type A leakage. At all other ti=c: between D required 100k;ge r:tc tests, the acceptance criteric is b :cd en an ever:11 Type A leakage limit of s 1.0 L,gr At s 1.0 L the a offsite dose consequences are bounded by the  ;

assumptions of the sa fety analysis. The Frequency is y required by the Primary! Containment}lsaka sLTesting g Progra'mJ10 CFR 50;'AppcEdif], YEdifi'6gib) ~h;slFeved

exc=ptions. Thus, SR 3.0.2 (which 2110w: Frequency extension:) dec nct apply.

REFERENCES 1. USAR, Section 6.2.

2. USAR, Section 15.6.5.
3. 10CFR50,AppendixJd0ptijohlB_. .
4. USAR, Section 6.2.6. .

SJ 3Regislatory Guideil2163dPerfopmance BasedfContai.nment I Leak;TestiProgram,";datediSeptemberJ1995; I

< , I RIVER BEND B 3.6-4 Revision No. LATER n  !

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Primary Containment Air Locks B 3.6.1.2 ;

BASES l ACTIONS E.1. E.2. and E.3 (continued) of a component to a safe position. Also, if applicable, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Action must continue until OPDRVs are suspended.

SURVEILLANCE SR 3.6.1.2.1 REQUIRGENTS Maintaining primary containment air locks OPERABLE requires compliance with the leakage rate test requirements of the ~

Primary C6ntainmentELeakage1 Rate" Testing Program

.(Re_f.J5)(10" CFR' 50; 'Appchdix 1 (R6f. ' 2), ' himbdified by cpproved exemptions when in MODES 1, 2, end 2. This SR reflects the leakage rate testing requirements with regard to air lock leakage (Type B leakage tests). The acceptance criteria (i.e., s13,500 cc/hr for the combination of all annulus bypass leakage paths that are required to be meeting leak tightness) ensures that the combined leakage rate of annulus bypass leakage paths is less than the specified leakage rate. This provides assurance in MODES 1, 2, and 3 that the assumptions in the radiological evaluations are met. The leakage rate of each bypass leakage path is assumed to be the maximum pathway leakage (e.g., leakage through the air lock door with the highest leakage) unless the penetration is isolated by use of (for this Specification) one closed and locked air lock door. The leakage rate of the isolated bypass leakage path is assumed to be the actual pathway leakage through the isolation devices (e.g., air lock door). If both air lock doors are closed, the actual leakage rate is the lesser leakage rate of the two barriers (doors). This method of quantifying maximum pathway leakage _is only to be used for this SR (i.e., Appendix J,f0ptioniBi maximum pathway leakage limits used to evaluate Type A,'B'and C. limits are to be quantified in.accordance with Appendix J, OptioniB).

During the operational conditions of moving irradiated fuel assemblies in the primary containment, CORE ALTERATIONS, or OPDRVS, the only annulus bypass path leakage required to be met is through the two primary containment airlocks; therefore the entire 13,500 cc/hr limit can be applied to the air locks. In these operational conditions the reactor coolant system is not pressurized and specific primary containment leakage limits are not imposed. However, due to the size of the air lock penetration, leakage limits are (continuedl RIVER BEND B 3.6-12 Revision No. LATER

Primary Containment Air Locks B 3.6.1.2 BASES SURVEILLANCE SR 3.6.1.2.1 (continued)

REQUIREMENTS imposed to assure an OPERABLE barrier. In these conditions the leakage limits are not related to radiological evaluations, but only reflect engineering judgment of. an acceptable barrier. The periodic testing requirements verify that the air lock leakage does not exceed the allowed fraction of the overall primary containment. leakage rate. .

TheFrequencyisrequiredbytheliPhimarf7CbntiinmentVleakags RutblTesti 4 Proghm710 CFR 50Tf,5fEEdi X hi~hibdifibf b.9 hppF5!!bd hem;itions. Thus, SR 3.0.2 (which cllcx Frequenc-y exten;ien ) decs not cpply.

The SR has been modified by two Notes. Note 1-states that an inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

This is considered reasonable since either air lock door is capable of providing a fission product barrier in the event of a DBA. Note 2 has been added to this SR, requiring the results to be evaluated against the acceptance criteria of SR 3.6.1.1.1 during operation in MODES 1, 2, and 3. This ensures that air lock leakage is properly accounted for in determining the overall primary containment leakage rate.

Since the overall primary containment leakage rate is only applicable in MODE 1, 2, and 3 operation, the Note 2 requirement is imposed only during these MODES.

SR 3.6.1.2.2 The seal air flask pressure is verified to be at 2: 90 psig every 7 days to ensure that the seal system remains viable.

It must be checked because it could bleed down during or following access through the air lock, which occurs regularly. The 7 day Frequency has been shown to be acceptable through operating experience and is considered adequate in view of the other indications available to operations personnel that the seal air flask pressure is low.

SR 3.6.1.2.3 The air lock interlock mechanism is designed to prevent simultaneous opening of both doors in the air lock. Since both the inner and outer doors of an air lock are designed to withstand the maximum expected post accident primary containment pressure (Ref. 3), closure of either door will (continued)

RIVER BEND B 3.6-13 Revision No. LATER

Primary Containment Air Locks B 3.6.1.2

' BASES SURVEILLANCE SR 3.6.1.2.3 (continued) l REQUIREMENTS i support primary containment OPERABILITY. Thus, the interlock feature supports primary containment OPERABILITY while the air lock. is being used for personnel transit in -

and out of the containment. Periodic testing of this interlock demonstrates that the interlock will function as  ;

designed and that simultaneous inner and outer door opening will not inadvertently occur. Due to the nature of this-interlock, and given that the interlock mechanism is only challenged when the primary containment _ airlock door is opened, this test is only required to be performed upon entering or exiting a primary containment air lock, but is ,

not required more frequently than once per 184 days. The 184 day Frequency is based on engineering judgment and is.

considered adequate in view of other administrative controls.

SR 3.6.1.2.4 A seal pneumatic system test to ensure that pressure does not decay at a rate equivalent to > 1.28 psig for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from an initial pressure of 90 psig is an effective leakage rate test to verify system performance.

The 18 month Frequency is based on the fact that operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

I REFERENCES 1. USAR, Section 3.8.

2. 10 CFR 50, Appendix Jg0ptioniB.
3. USAR, Table 6.2-1.
4. USAR, 15.7.4
5. ~LJ RegelitoVi? Gu i del 11163 M PeFfofmahde7 Bhedicontii nineh t 1995f'~~~'~~^~~'

l

. RIVER BEND B 3.6-14 Revision No. LATER

PCIVs B 3.6.1.3 BASES SURVEILLANCE SR 3.6.1.3.9 (continued)

REQUIREMENTS evaluations of Reference 4 are met. The leakage rate of each bypass leakage path is assumed to be the maximum pathway leakage (leakage through the worse of the two isolation valves) unless the penetration is isolated by use of one closed and de-activated automatic valve, closed manual valve, or blind flange. In this case, the leakage rate of the isolated bypass leakage path is assumed to be the actual pathway leakage through the isolation device. If both isolation valves in the penetration are closed, the actual leakage rate is the lesser leakage rate of the two valves. This method of quantifying maximum pathway le_akage is only to be used for this SR (i.e., Appendix Jy0ptic' nib maximum pathway leakage limits are to be quantified 'in~ ~

accordance with Appendix idOpt16 nib)s.

required by th'e?Priinary;"ContainmsntK The Frequency is aksisTRit'eWestini 5

Pro.g f.aml

g. (Re f?]g)] ! 0 ^ C FR 50, "fsheEd l iT ( RcC~i }T~is' Eid i f Frcquency extencicn:) dec: not cpplyr A note is added to this SR which states that these valves are only required to meet this leakage limit in MODES 1, 2 and 3. In the other conditions the Reactor Coolant System is not pressurized and primary containment leakage limits are not required.

SR 3.6.1.3.10 The analyses in References 2 and 3 are based on leakage out '

of the primary containment that is less than the specified leakage rate. Leakage !.hrough the valves sealed in each division of MS-PLCS must be s 150 scfh per division when tested at 2: P a, 7.6 psig. The leakage rate must be verified to be in accordance with the leakage test i requirements of Reference 4, as modified by approved exemptions.

A note is added to this SR which states that these valves are only required to meet this leakage limit in MODES 1, 2 i and 3. In the other conditions, the Reactor Coolant System is not pressurized and specific primary containment lea _kage limits are not required. The Frequency is required by the PrlsaryfC6ntaisme'ntjleakabelRat)MeptingIPropm{(Ref85);

10 CFR 50, fp:endii! ' (Ref.1), 0: =cdif f'ed .y cpproved exemption:; t =, SR 3.0.2 (which 0110w: Frequency extencien:) dec not cpply.

(continued)

RIVER BEND B 3.6-27 Revision No. LATE.R

.PCIVs B 3.6.1.3 BASES SURVEILLANCE SR 3.6.1.3.11 REQUIREMENTS (continued) Surveillance of hydrostatically tested lines at i 2: 1.1 Pa , 8.36 psig provides assurance that the calculation assumptions of References 2 and 3 are met. The combined  ;

leakage rates must be demonstrated at the frequency of the  !

leakage test requirements of thsIPhimaFylC6ntainnientRsakape RatBTestin#1EogFain hpp?b?Ed^620!pt'icn:;J(Refy thn , SR'3.0.2s)iRufeFeh25 i',~EE E difiEd V ^

(which ellcus Frcquency extensien ) dec: net cpply.

A note is added to this SR which states that these valves are only required to meet the combined leakage rate in MODES 1, 2, and 3 since this is when the Reactor Coolant System is pressurized and primary containment is required.  ;

In some instances, the valves are required to be capable of  ;

automatically closing during MODES other than MODES 1, 2, l and 3. However, specific leakage limits are not applicable in these other MODES or conditions.

I SR 3.6.1.3.12 This SR ensures that the combined leakage rate of annulus  !

bypass leakage paths is less than the specified leakage ,

rate. This provides assurance that the' assumptions in the i radiological evaluations of Refemnce 4 are met. The  ;

leakage rate of each bypass leakage pdb is assumed to be the maximum pathway leakage (leakage through the worse of ,

the two isolation valves) unless the penetration is isolated  !

by use of one closed and de-activated automatic valve, )

closed manual valve, or blind flange. In this case, the leakage rate of the isolated bypass leakage path is assumed to be the actual pathway leakage through the isolation l device. If both isolation valves in the penetration are I closed, the actual leakage rate is the lesser leakage rate of the two valves. This method of quantifying maximum i pathway leakage is only to be used for this SR (i.e., j Appendix J;ioptibhlB maximum pathway leakage. limits are to i bequantifiedin~accordancewithAppendixJj[ Option?B)._The

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Fre.quency is required by the PrimaryJContainmentdeakage RateTTeitiss$PrograinV(Refp5)iempticas; iT; "him5di f fed ^ bflpproved ^c thu:, SR 3.0.2i10~CFR (which ellew: Frequency extension:) dec: not cpply.

(continued)

RIVER BEND B 3.6-28 Revision No. LATE _R 1

l 1

PCIVs B 3.6.1.3 i BASES' (continued). l i

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REFERENCES 1. USAR, Chapter 15. I

2. USAR, Section 6.2.
3. USAR, Table 6.2-40.
4. 10CFR50,AppendixJg0pM6n{B.

51'(RegUlat'orf?Guidiili.163M"PEfOrmisce?Bised;C6htilhmeht LeakiTest;P ogram,."fdated.:;Septemberi1995l

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