ML20063D771
| ML20063D771 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/31/1994 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20063D767 | List: |
| References | |
| NUDOCS 9402080296 | |
| Download: ML20063D771 (29) | |
Text
{{#Wiki_filter:'- - - ' 3 .
! .)
~,, .1 4
i r ENCLOSURE- l i REVISED PAGES FOR TECHNICAL SPECIFICATION CHANGE 93-02 r LIST OF AFFECTED PAGES ! Unit 1 -- VII. 1-2 3/4 6-1 i 3/4 6-2 l 3/4 6-3 3/4 6-4 1 3/4 6-8 , 3/4 6-11 ; 3/4 6-12 3/4 6-15 ; 3/4 6-23 B 3/4 6-1 ; Unit 2 5 r VII ! 1-2 ! 3/4 6-1 3/4 6-2 3/4 6-3 i
'I 3/4 6-4 3/4 6-8 l 3/4 6-11 : l 3/4 6-12 ;
3/4 6-15 e 3/4'6-23 . B 3/4 6-1 l [ P l i i 94020B0296 940131 h" : ADOCK 05000327 ) PUR p PDR $[ . e -
(1 . I
- s. .. . !
;s
\
i INDEX- ' LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTE SECTION t PAGE
-3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUNULATORS l
Cold Leg Injection Accumulators........................... 3/4 5-1 Deleted................................................... 3/4 5-3 ' 3/4.5.2 ECCS SUBSYSTEMS - T,yg greater than or equal to 350*F..... 3/4 5-4 3/4.5.3 ECCS SUBSYSTEMS - T,yg less than 350*F.................... 3/4 5-8 1144 3/4.5.4 DELETED................................................... 3/4 5-10 3/4.5.5 REFUELING WATER STORAGE TANK.............................. 3/4 5-11 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity..................................... 3/4 6-1 i
%;+nk -
f - hd r3 C.A.:~d 8#ss
%-Centa4nment Leakage....................................... 3/4 6-2 Containment Air Locks..................................... 3/4 6 Internal Pressure......................................... 3/4 6-9 Air Temperature........................................... 3/4 6-10 Containment Vessel Structural Integrity................... 3/4 6-11 Shield Building Structural Integrity...................... 3/4 6-12 1
l Emergency Gas Treatment System (Cleanup Subsystem). . . . . . . . 3/4 6-13 Containment Ventilation System............................ 3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ! Containment Spray Subsystems.............................. 3/4 6-16 115-Lower Containment Vent Coo 1ers............................ 3/4 6-16b l 1 i l l SEQUOYAH - UNIT 1 VII Amendment No. 67, 69, 116, 140 150 h4AJR 181991
., a DEFINITIONS CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be: ,
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions. ;
- c. Digital channels - the injection of a simulated signal into the '
channel as close to the sensor input to the process racks as R145 a practicable to verify OPERABILITY including alarm and/or trip functions. ; CONTAINMENT INTEGRITY 4
- 1. 7 CONTAINMENT INTEGRITY shall exist when: ;
- a. All penetrations required to be closed during accident conditions-are either: '
- 1) Capable of being closed by an OPERABLE containment automatic isolation valve system, or .
- 2) Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in l Table 3.6-2 of Specification 3.6.3.
- b. All equipment hatches are closed and sealed.
-{
f
- c. Each air lock is in compliance with the requirements of i Specification 3.6.1.3,
- d. The containment leakage rates are within the limits of l Specificati .6.1.E
- e. The sealin mechansim associated with each penetration (e.g.,
l{ welds, bellows, or 0-rings) is OPERABLE) ancL
- 4. See.ndary cada-,.,& yss Ic%e. is uk k I,,ts of Qc[e;[,,n 3 g,1,2, .j CONTROLLED LEAKAGE :
1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals. CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component > within the reactor pressure vessel with the vessel head removed and fuel. in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position. CORE OPERATING LIMIT REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that R159 provides core operating limits for the current operating reload cycle. These-cycle-specific core operating limits shall be determined for each reload cycle , in accordance with Specification 6.9.1.14. Unit operation within these , operating limits is addressed in individual specifications. SEQUOYAH - UNIT 1 1-2 Amendment No. 12, 71, 130, 141, 155 00T 23 E91 :
r Pe d w re red vasvel 2%nahon ; T ,. *nd Inh
- inq u G n" * * - " -- "~
~. a 1 . ru,c h l % **,., aQm e J,& to crR sh,4 a"Ex ff T. i l 3/4.6 -CONTAINMENT SYSTEMS j.M -'77' " 1, ro ve N 4 * "/b' "'I - ([ 3/4.6.1 PRIMARY CONTAINMENT N a x , 4 v +1 allo.a4b C /e e rak, k 3 .# CONTAINMENT INTEGRITY I O. M % o[ Gnb N " b[ d 8,i calculA J pak' coa]a-~a P"" \ LIMITING CONDITION FOR OPERATION - 3 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours and in COLD-SHUTDOWN within the following 30 hours. - - SURVEILLA'NCE REQUIREMENTS
- 4. 6.1.1 Primary C0'NTAINMENT INTEGRITY shall be demonstrated:
- a. At least once per 31 days by verifying that all penetrations ^ not capable of being closed by OPERABLE containment automatic isolation ,
valves and required to be closed during accident conditions are R16 j closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of-Specification 3.6,3.
- b. By verifying that each containment air lock is in compliance with' R134 the requirements of Specification 3.6.1.3.
- c. A each closing of each penetration subject to Type B testi ,
except the ainment air locks, if opened followin ype'A or R16 ' B test, by leak rate h +ing the seal with s at P,, 12 psig, and verifying that when the measure 2 te for these seals is added to the leakage r determined pur., nt to Specification 4'6.1.2.d fo
. . other Type B and C penetrations, t combined leaktrge ~ rate is less than or equal to 0.60 L,.
"Except valves, blind flanges,'and deactivated automatic valves which are located inside the annulus or containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified cl6 sed during each COLD SHUTDOWN except that such verification need:not be performed more often than once per 92 days. '
l SEQUOYAH - UNIT 1 3/4 6-1 Amendment No. 12) 130
- 7ebruary 16, 1990 t i
~ ly.; *
- a CGNTAINMENT SYSTEMS _-
CCNT ^ I""PGkAKAGE 6ECc8J I## LIMITING CONDITION FOR OPERATION Secubr3 b p ss , 3.6.1.2 Containment leakage rates shall be limited ta@ 4 An' overall integrated leakage rate of less than or equal to La' O.25 per: t by weight of the containment air per 24'h at Pa ' I2 psig,
- b. A combined leakage ra than or al to 0.60 L, for all penetratio nd valves subject to Type B and C tess when essurized to Pa '
- ~ _ --
@ Y Eombined bypass leakage rate of less than or equal to 0.25 La fI all penetrations identified in Table 3.6-1 as secondary containment BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to R75 t
Q
~
I P,. -- %2w. _- _ _ - . APPLICABILITY: MODE 5 1, 2, 3 and 4. , ACTION: W integrated containment leaka- . . . see ing 0.75 L , r (b) with the measured com- age r- .1 L1 qenetrations a
' ; et to Types B and C tests exceeding 0.60 L,, or (c) Yith the combined bypass leakage rate exceeding 0.25 L foraBYPASS LEAKAGE PATHS TO THE R75 AUXILIARY BUILDING, restore th: overcl' ntegrated leak;;c r;t t; 10;; thar Or md ic 0 75 '.,, the cce! ed '^:kage rat: ': al' pc :tration and valec; W .:t ic Type 3 ; H test to le:: than er : qual t; 0.50 L , the a combined R75 bypass leakage rate from BY ASS LEAKAGE PATHS TO THE AUXILIARY BUILDING to less wd;a 4 hoTrS or be m 4f leasT Hor sTAAOd Q -
than or ecual to 0.25 gL , acer te_n i cr^5 m t- "e ct-h*AS 'n quHe& uth.f t%Efue~ m ir p ;cte-c te &
.l i -
$EQUOYAH - UNIT 1 3/4 6-2 Amendment No. 12 71 May 18, 1988 P
b
~,.N. .
.s .
- m. ,
/,
CONTAINMENT SYSTEMS ggg,gg4py c3;gmggy AyPA55 4EARAGE
^
SURVEILLANCE REOUIREMENTS
}
^
seemkr ?
- 4. 6.1. 2 The containment le . hall be demonstrated;;t the fchet tc t sc Mdule 2nd chal' be s ;
" conformance it " the criteri :peci -
#ied 4a ippendi' 2 c' 10 C 9-the method; nd provi:icn: cf "!$I fM5. > 107:; h; cycr, th; ; - :.95 / INS 55.5-1937 for :::: peint d t: R106 n !yti: :y bc =ed " '.e thod: :pecified in ,"'5I t"'5. F1972. ,
\ a. Three Type A tests (Ove,all Integrated Containment Leakage Rate) .
shall be conducted at 40 + 10 month intervals
- during shutdown at P lg13 ~3 (12 psig) during each 10 year service period. 1
- b. If any periodic Type A test f ails to meet 0.75 L3 , the test edule for subsequent Type A tests shall be reviewed and approve y the -
Co'. ission. If two consecutive Type A tests fail to mje - 0.75 La ' a Typ A test shall be performed at least every 18 m ths until two consecuyveTypeAtestsmeet0.75La at which tim the above test
- schedule !r,4y be resumed.
N
- c. The accuracy each Type A test shall be ve fied by a supplemental test which:
, 1. Confirms the curacy of the Type test by verifying that +5e Qj ference betw n supplemental d Type A test data is wit..in a
- 2. Has a duration suffi *ent t establish accurately the change in leakage rate between t. pe A test and the supplemental test.
- 3. Requires the quantity s injected into the containment or bled from the contai .ent d ing the supplemental test to be equivalent to at I st 25 per nt of the total measured leakage at Pa (I2 PSI9 )*
- d. Type B and C test shall be conducted wie gas at Pa (12 psig) at intervals no g _ater than 24 months except , r tests involving:
- 1. Air 1 ks,
- 2. P etrations using continuous leakage monitori systems, and
- 3. Valves pressuri::ed with fluid from a seal system.
*A one + me extension of the test interval is allowed for the third Ty A R131 test ithin'the first 10 year service period provided unit shutdown occ s no r than May 1, 1990 and performance of Type A testing occurs prior to it l la)s tart following Unit 1 Cycle 4 refueling.
l 3/4 6-3 Amendment No. 102 , 127 SEQUOYAH - UNIT 1 September 29, 1989 l l l
~, _ ._ _. _.
CONTAINMENT SYSTEMS ' m SURVEILLANCE REQUIREMENTS (Continued) a.
- d. / The combined bypass leakage rate to the auxiliary building shall-be = ^
determined to be less than or equal to 0.25 L, by applicable Type B R 75_- ; and C. tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable . shall be determined to have no detectable leakage when tested with
.during soap bubbles each Type while the containment is pressurized to P* (12 psig)
A test.* ,
-+
- f. By verWdiai.,eeh-. containment 24" lcck != in compliance with A
_- the ram!irementa vi apecification D . R134 g ,g. Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J, Section III.C.3, when determining the combined leakage rate p'rovided the seal system and valves are pressurized to at least 1.10 Pa (13.2~ psig) and the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray system and RHR RIOS spray system valves at penetrations 48A, 488, 49A and 498) for at least 30 days.
- h. tests for penetrations employing a continuous l'e monitoring
- shall be conducted at P, (12 - '
at intervals no greater than once pe ars. *
- i. All test leakag pe r all be calcut 2
ging observed data converte + IFsolute values. Error analyses sh7 W b cerformed to
. a balanced integrated leakage measurement system. ,
]
g f. The provisions of Specification 4.0.2 are not applicable. d t
$ des.Mc shd he evaLJed aps4 L awghnce adaca. J '
5'ge bedw a 9. L, I. I. c. m a ceerdenee id -lo CFA $6, Agendix 3~f R106
't S mc> d$ed b a aved eve 4kn s . '
SEQUOYAH - UNIT 1 #/4 6 '* .mendment A No. 12, 71, 10 rIO7,130 l bbruary 16, ~ 190 ;
)
~~' CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS ;
\
- 4. 6.1. 3 Each containment air lock shall be demonstrated OPERABLE:
- a. After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours, by verifying seal leakage less than or equal to 0.01 L, as determined by precision flow measurements when measured for at least two minutes with the volume RS2 between the door seals at a pressure greater than or equal to 6 psig,
- b. By conducting an overall air lock leakage test at not less than P a (12 psig) and by verifying the overall air lock leakage rate is wi y limit:#
- 1. At least nce per six months, and
- 2. Prior establishing CONTAINMENT INTEGRITY if opened when CONTA iMENT INTEGRITY was not required when maintenance has been erformed on the air lock that could affect the air lock seal ng capability.*
- c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
~. -
of 3.6.I.3.b and 4Lc. resulks ev<l.de) ;n etccord anc e. wNL laCfA S, A x 'T,
i SURVEILLANCE REQUIREMENTS !
- 4. 6.1. 6 The structural integrity of the containment vessel shall be determined
-"', ) during the' shutdown for each Type A-containment leakage rate test (Specification 4.6.1.JS by a visual inspection of_the exposed'6ccessible interior and exterior
?
i surta'ces of the vessel. This inspection shall be performed prior to the Type, f.c A containment leakage rate test to verify no apparent changes -in appearance of
~
the surfaces or other abnormal degradation. Any abnormal degradation'of the containment vessel detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.6.1. R40 i f i 1 l 1 i November 23, 1984 SEQUOYAH - UNIT 1 3/4 6-11 Amendment No. 36 l
9 CONTAINMENT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.7 The structural integrity of the shield building shall be maintained i at a level consistent with the acceptance criteita in Specification 4.6.1.7. ! APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits , prior to increasing the Reactor Coolant System temperature above 200 F. ' SURVEILLANCE REQUIREMENTS
- 4. 6.1. 7 The structural integrity of the shield building shall be determined h$;sj.
during the shutdown for each Type A containment leakage rate test (eefeeense- .
)*g Specification 4.6._1./f) by a visual inspection of the exposed accessible interior and exterior surfaces of the shield building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation. Any abnormal degradation of the shield building detected during the above required inspections shall be reported to the Commission pursuant to e Specification 6.6.1. lR40 s
/ i\
November 23, 1984 SEQUOYAH - UNIT 1 3/4 6-12 Amendment No. 36
CONTAINMENT SYSTEMS *
\ ,
I I CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION
- 3. 6.1. 9 One pair (one purge supply line and one purge exhaust line) of I containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.
Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 hours per 365 days. The 365 day cumulative time period will begin every January 1. R22 APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: '
- a. With a purge supply or exhaust isolation valve open in excess of the R124 ,
above cumulative limit, or with more than one pair of containment purge system lines open, close the isolation valve (s) in the purge line(s) within one hour or be in at least HOT STANDBY within the r. ext 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With a containment purge supply and/or exhaust isolation valve '
having a measured leakage rate in excess of 0.05 L,, restore the [ /) inoperable valve to OPERABLE status within 24 hours, otherwise be in R124
- at least HOT STANDBY within the next 6 hours and in COLD SHUTOOWN within the following 30 hours.
SURVEILLANCE RE001REMENTS ' 4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days. i 4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation E valves 7 days. are open over a 365 day period shall be determined at least once per 4.6.1.9.3 At least once per 3 months, each containment purge supply and ' exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.05 La,.and by verHyi9 + hat
-when the reasured leakage " ate is addad to the leakage ratet determinad. 24
-pur4uaro te SpecificatJer A.6.1_2 d fe" 211 ether type E nd C penetratient,
-the-combined-4eakage-eate i 1000 ther ~ equal to 0.60 L
- a ,
- Resdhs s V\ he en kked ay,as4- % accykee e,% o f Spec.Ccd;,a 4'. L . 1. f.c. m a.ecorJa cc e wdL to era a,tyy,J;g'
) ac <rl$cd I a grw l a e q L as.
SEQUOYAH - UNIT 1 3/4 6-15 Amendment No. 18, 120 July 5, 1989
~
(y.. s . m TABLE 3.6-2 (Continued) y CONTAlte!ENT ISOLATION VALVES { VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) 7 C. PHASE "A" CONTAINMENT VENT ISOLATION (Cont.)
.c 13. FCV-30-50 Upper Compt Purge Air Exh O 14. FCV-30-51 4*
- Upper Compt Purge Air Exh 4*
- 15. FCV-30-52 Upper Compt Purge Air Exh
- 16. FCV-30-53 4*
Upper Compt Purge Air Exh 4*
- 17. FCV-30-56 Lower Compt Purge Air Exh
- 18. FCV-30-57 4* l Lower Compt Purge Air Exh 4*
- 19. FCV-30-58 Inst Room Purge Air Exh
- 20. FCV-30-59 4*
Inst Room Purge Air Exh 4*
- 21. FCV-90-107 Cntmt Bldg LWR Compt Air Mon
- 22. 5* a74 FCV-90-108 Cntmt Bldg LWR Compt Air Mon
- 23. 5^
FCV-90-109 Cntmt Bldg LWR Compt Air Mon
- 24. 5*
FCV-90-Il0 Cntmt B1dg LWR Compt Air Mon 5* R 25. FCV-90-lli Cntmt Bldg LWR Compt Air Mon
- 26. 5*
FCV-90-Il3 Cntml Bldg UPR Compt Air Mon 5* T 27. 'FCV-90-il4 Cntmt Bldg UPR Compt Air Mon O 28. 5* FCV-90-ll5 Cntmt Bldg UPR Compt Air Mon 5*
- 29. FCV-90-116 Cntmt Bldg UPR Compt Air Mon
- 30. 5*
FCV-90-117 Cntmt B1dg UPR Compt Air Mon 5* D. OTHER
$ET 1. FCV-30-46 ;3 2.
Vacuum Relief Isolation Valve 25 FCV-30-47 Vacuum Relief Isolation Valve 25 4& 3. FCV-30-48 Vacuum Relief Isolation Valve 25 '<@ 4. FCV-62-90 Normal Charging Isolation Valve s ~ -- 12 R105 ?g S eEc.k.en q. 6. I.Q
@g
- Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated positirn with power removed and Saceleakage limits of 4.
nla.,ce RayMent* St 4.1.
- c. _i'l=cc Pcquirement 4.3 rnest i.C.3.4 are satisfied. For gorp velves , le.k.3c 1,LYs under alsa be s-flsRal. g41 U # Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed co and either FCV-62-73 or FCV-62-74 is maintained operable.
**This valve is required after completion of the associated modification . R86
. t a
{. 3/4.6 CONTAINMENT SYSTEMS t
- (
BASES . 3/4.6.1 PRIMARY CONTAINMENT ! 3/4.6.1 PRIMARY CONTAINMENT l 4 M *4- CONTAINMENT INTEGRITY ensures that the release of ra * .. jd6gf materials from t. e .
+ -
' ment atmosphere will be res*% uo those leakage paths and associated leak rate -
- i. ' . ucident analyses. This A' restriction,inconjunction '"
teakage itation, will limit the M site boundary ra - .. ooses to within the limits of 1 v. '^ _ ring acci - enoitions. 52 coa 0ARY CouTA&&T SYPhs'$ i 3/4. 6.1. 2 [CC'!' LEAKAGE P"'O!T I The limitation; on containment leakage rates ensure that the total / l _. conta scent leakage volume will not exceed the value assumed in the ac# ent
/ -
N analyses a. 5e peak accident pressure, P . As an added conserv *;sm, the
- a
[.o . measured overall ,tegrated leakage rate is further limited less than or ; V equal to 0.75 L, durin erformance of the periodic t es to account for possible degradation of the tainment leakage - riers between leakage i RT tests. > I h The surveillance testing for . asuring akage rates are consistent with 7 the requirements of Appendix ' " of 10 CFR 50 wi . the following exemption. The third Type A test - - each 10 year service period nes not be conducted R131 l when the plant i< , utdown for the 10 year plant inservice 1. ection. Due to the increas accuracy of the mass point method for containment 1. rated leaka testing, the mass point method referenced in ANSI /ANS 56.8-198/ n be R105 ed in lieu of the methods described in ANSI N45.4-1972. \ i 1 i 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CCNTAINMENT INTEGRITY and containment i leak rate. Surveillance testing of the air lock seals provide assurance that i the overall air lock leakage will not become excessive due to seal damage I during the intervals between air lock leakage tests. 3/4.5.1.3 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the
, containment structure is prevented from exceeding its design negative pressure
! diff erential witn resoect to the' annulus atmospnere of 0.5 psig and 2) tne SEQUOYAH - UNIT 1 3 3/4 6-1 Amencment No. 102, 127 Sepcamber 29, 1989 s---- ,
. L.*
4 INSERT A . i
'l The safety design basis for primary containment is that the containment must withstand the pressures and temperatures of the i limiting design basis accident (DBA) without exceeding the design i leakage rates.
The DBAs that result in a challenge to containment OPERABILITY- , from high pressures and temperatures are a loss of coolant-
- accident (LOCA), a steam line break, and a rod ejection accident (REA). In addition, release of significant fission product H radioactivity within containment can occur from a LOCA or REA. i In the-DBA analyses, it is assumed that the containment is !
OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage. This leakage rate limitation will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions. The containment.was designed with an allowable' leakage rate of 0.25 percent of , containment air weight per day. This leakage rate, used in the ! evaluation of offsite doses resulting from accidents, is defined in 10 CFR 50, Appendix J, as L,: the maximum allowable containment leakage rate at the calculated-peak containment internal pressure ( P,) resulting from the limiting DBA. The allowable leakage rate represented by L, forms the basis for the i acceptance criteria imposed on all containmemt leakage rate testing. L, is assumed to be 0.25 percent per day in the safety .. analysis at P, = 12.0 psig. As an added conservatism, the measured overall integrated leakage rate is further limited to > less than or equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between tests. Primary containment INTEGRITY or operability is maintained by limiting leakage to within the acceptance criteria of 10 CFR 50, Appendix J. i Individual leakage rates specified for the containment air lock (LCO 3.6.1.3), purge valves (LCO 3.6.1.9) and secondary bypass ! leakage (LCO 3.6.1.2) are not specifically part of.the acceptance ! criteria of 10 CFR 50, Appendix J. Therefore, leakage rates + exceeding these individual limits do not result in~the primary-containment being inoperable unless the leakage, when combined _.,
^
with other Type B and C test leakages, exceeds the acceptance criteria of Appendix J. 1 1
}
5
4 . ':. ,; - INSERT B , 'l The safety design basis for containment leakage assumes that ll 75 percent of the leakage from the primary containment enters the 1; shield building annulus for filtration by the emergency gas- l treatment system. The remaining 25 percent of the primary- j containment leakage, which is considered to be bypassed to the j auxiliary building, is assumed to exhaust directly to the ! atmosphere without filtration during the first 5 minutes of~the accident. After 5 minutes, any bypass leakage to the auxiliary 'j building is filtered by the auxiliary building gas treatment j system. A tabulation of potential secondary containment bypass l leakage paths to the auxiliary building is provided in ; Table 3.6-1. Restricting the leakage through the bypass leakage paths in Table 3.6-1 to 0.25 L, provides assurance that the leakage fraction assumptions used in the evaluation of site- .; boundary radiation doses remain valid.
- 2 i
T i i Ej i I I
~
l 1 1 J
l c . .. .. ,. . ,
~
.INDEX' LIMITING CONDITIONS FO'R OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Injection Accumulators........................... 3/4 5-1 Deleted................................................... 3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T gg greater than or equal to 350*F..... 3/4 5--4 3/4.5.3 R131 ECCS SUBSYSTEMS - T ,g less than 350*F.................... 3/4 5-8 3/4.5.4 DELETED................................................... 3/4 5-10 3/4.5.5 REFUELING WATER STORAGE TANK..............................
3/4 5-11 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT S Containment Integrity..................................... 3/4 6-1
.Ga ed egg A ,sment 8 gass yv (Cent:i
> nment Lea kage. . . . . . . . . .. . .........................
3/4 6-2 Containment Air Locks..................................... 3/4 6-7 Internal Pressure......................................... 3/4 6-9 A i r Te mp e r a t u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-10 Containment Vessel Structural Integrity................... 3/4 6-11 Shield Building Structural Integrity...................... 3/4 6-12 Emergency Gas Treatment System (Cleanup Subsystem)........ 3/4 6-13 Containment Ventilation System............................ 3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray Subsystems.............................. 3/4 6-16 R14C Lower Containment Vent Coo 1ers............................ 3/4 6-16b R61 SEQUOYAH - UNIT 2 VII Amendment No. 59, 61, 131 140 MAR 18 i991
.2.
.i
. DEFINITIONS
'\>
CHANNEL FUNCTIONAL' TEST Rc 1.6 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the ;
channel as close to the sensor as practicable to verify'0PERABILITY including alarm and/or trip functions. .
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip ' functions. e
- c. Digital channels - the injection of a simulated signal into the '
channel as close to the sensor input to the process racks as'practi- R132 l cable to verify OPERABILITY including alarm and/or trip functions. CONTAINMENT INTEGRITY R63
- 1. 7 CONTAINMENT INTEGRITY shall exist when:
r
- a. All penetrations required to be closed during accident conditions are either: 7
- 1) Capable of being closed by an OPERABLE containment automatic 1 isolation valve system, or
- 2) Closed by manual valves,' blind flanges, or deactivated auto-matic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3. ,
- b. All equipment hatches are closed and sealed, c.
- f. .'
Each air lock is in compliance with the' requirements of R117 Specification 3.6.1.3,
- d. The containment leakage rates are within the limits of Specification i 1.6.1.f
- e. l The sealing mechanism associated with each penetration (e.g., welds, J bellows or 0-rings) is OPERABLE n =L
-F. Sw.k CONTROLLEDLEAKAGkc-A&,merk pss lexd $ :, a4L;. L I'.-[s
,{ fd.., 3.L t.2. R63
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals. ,
CORE ALTERATION R63
- 1. 9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head. removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
CORE OPERATING LIMITS REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle. R14d These cycle specific core merating limits shall be determined for each reload ; cycle in accordance with secification 6.9.1.14. Unit operation within these '; operating limits is addressed in individual specifications. SEQUOYAH - UNIT 2 1-2 Amendment No. 63, 117, 132, ! 146 March 30 1992 ,
-_ -- ~ - <_, ,,. ,. ~
fctbrm r rN I'Sval C*** *N'E0 9ncl ICn 2 .& , &
- rde t u p4 % cA=-
nce G,5 to cf2. So, Appo{,y r
-+ + j g to accorda ~
, .'en s . I4e mer,,nm
/ 3/4.6 CONTAINMENT SYSTEMS a s- m e,l, E t d by g romd eren
# #> <- )
3/4.6.1 PRIMARY CONTAINMENT ctilewabIC- Ie* U t-
## " * ^ '" #
CONTAINMENT INTEGRITY resSofe (>l2f's,. fea.k conta.inmenE f LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUT 00WN within the following 30 hours. SURVEILLANCE REQUIREMENTS
- 4. 6.1.1 Primary . CONTAINMENT INTEGRITY shall be demonstrated:
- a. At least once per 31 days by verifying that all penet. rations
- 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 k
gf secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3.
- b. By verifying that each containment air lock is in compliance with Ell 7 the requirements of Specification 3.6.1.3.
- c. h v each closing of each penetration subject to Type B testine, except the ontainment air locks, if opened followinc . iype A or B.
N test, by leak rate h , Qq the seal with o - t P . 12 Psig, and a verifying that when the me re . e rate for these seals is N added to the leakage rv5 determined purhaqt to Specification 4.6.1.2.d fo - 1 other Type B and C penetrati t combined Je3,agerateislessthanorequalto0.60L" a
*Except valves, blind flanges, and deactivated automatic vahes which are located inside the annulus or containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
SEQUOYAH - UNIT 2 3/4 6-1 Amendment. No.117 February 16, 1990
. CONTAINMENT SYSTEMS y n_ - ,- ONTA! W T LEAKAGE QCorJDARY CcNTAn a mtar 8Yh155 LIMITING CCNDITION FOR OPERATION 3.6.1.2 A Containment leaka e rates shall be limited t @ <
($eanM bdass DQ n overall integrated leakage rate of less than or equal to L , x [ perc eight of the containment air per 24 hour P , 12 3 psig_
- b. A combined leakage ra less than h al to 0.60 La f r all penetratic nd valves subject to Type B and C test when r ssurized to P a' r a.
@. X combined bypass leakage rate of less than or equal to 0.25 L a f#
all penetrations identified in Table 3.5-1 as secondary containment i BYPA$5 LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to :n< ' P. w,y a APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
~h r (a) the measured overall integrated containment leakar -
6~ exceeding 0.75 L , r (b) with v. . _. um ined leakage rate for all a penet ations-w -ni ves subject to Types B and C tests exceedW (c)lWiththecomninedbypassleakagerateexceeding0.25L f r BYPASS a LEAKAGE R53 i PATHS TO THE AUXILIARY BUILDING, restore the neral' ntcy+ted Icak 9c ratc te-l k:: "Mr 1 r rnte;! t o 0. 75 ' , a nd-thmbi ned l e # age-cat e f e r :! ' p e net r e tion; and calsc; :vbject ;; Tj;,e 3 er.d C tests to icas thar. or cqual to 0.E3 L a' w the combined bypass leakage rate from BYPASS LEAKAGE PATHS TO THE_A_UXI_LIA v ! 3 Laur_s [ *^e orke Irt[af cas d
, [I1 DING to IQor_ ecual to 0. 25 L g ~ ta ecr n '"a ,
. ,?.'. , _. . 7?.-f ,u
? - '
Y ? Y _ 1 SEQUOYAH - UNIT 2 3/4 6-2 Amendment No. 63 May 18, 1988
, . . . . _ . . . _ . . ..._....- ..janlik
, , ', 7. ;' * -
CCNTAINHENT SYSTEMS SEconc,q p,Y acmameaT BYPASS LEAKAGE , _ = - s SURVEILLANCE RE0VIREMENTS seci 'b
- 4. 6.1. 2 The ontainment rates shall be demonstrated:at the felle !ing
-test schedule and chal' be determined in confermence ith the criteria speci- ,
ficd in Appendix J cf 10 CFR-50 c:ing-the-sethod; and previ icn: cf ANSI- " N45.4-1972 H ewever, the method; of AN W ANS 55.8-1987 for :::: peint data
-analy i: may be used in lieu of the acthod: Specified in ANSI N?5.4-1972. E" '
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at ,
Pa ,12 psig, during each 10 year service period. 313
, If any periodic Type A test fails to meet 0.75 L the test,chedule f
horsubsequentTypeAtestsshallbereviewedandapprov by the mmission. If two consecutive Type A tests fail to m et 0.75 L , a N a Typ'gA test shall be performed at least every 18 me hs until two consecutive Type A tests meet 0.75 L at which ti the above test a schedu y be resumed.* R126
- c. The accura of each Type A test shall be v ified by a supplemental test which:
'qgy 1. Confirms th accuracy of the Type test by verifying that the difference be .een supplemental nd Type A test data is within 0.25 La '
- 2. Has a duration suf ' ient establish accurately the change in leakageratebetween%e ype A test and the supplemental test.
- 3. Requires the quantit of as injected into the containment or bled from the cont nment during the supplemental test to be equivalent to at east 25 pe ent of the total measured leakage i at Pa, 12 psig.
- d. Type 8 and C tes shall be conducted w h gas at Pa , 12 psig, at intervals no reater than 24 months except or tests involving:
- 1. Air 1 cks,
- 2. P etrations using continuous leakage monitor g systems, and
- 3. - Values pressurized with fluid from a seal system.
*An px/emption from the 18-month accelerated frequency requirement is allowed for the Type A test failures conducted during the Unit 2 Cycle 2 and Unit 2 C' le 3 2126
/efueling outages.
/
SEQUOYAH - UNIT 2 3/4 6-3 Amendment No. 91, 126, 139 JAN 29199'i
P CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) q sg. The combined bypass leakage rate to the auxiliary building shall be R63 determined to be less than or equal to 0.25 La by applicable Type B R104 and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to Pa , 12 psig, during each Type A test.+
~
- f. By verifyTng T? rat 7achwohun!._. air-Seek-tr T5 compliance with the R117
(-SpectiTn~3. 6.1 . pg' Leakage from isolation. valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J, Section III.C.3, when determining the combined leakage rate provided the seal .cystem and valves are pressurized to at least 1.10 P ,13.2 a , psig, and the seal system capacity is adequate to maintain system I pressure (or fluid head for the containment spray system and RHR i i l spray system valves at penetrations 48A, 488, 49A and 498) for at least 30 days. Nh. for penetrations employing a continuous 1 iyp ^g monitoring syste Ashall be conducted at P , 1.2.pe' , at intervals no greater than once pe W ear x
- i. All test leakage calc'25YP6usin observed data converted + values. Error analyses s 4 erformed to so' .. a balanced integrated leakage measurement system.
C ,-f The provisions of Specification 4.0.2 are not applicable. T 6.s,jf5 gL)! U c'ha ag O b a"' jnana- WN d akuolwnce
- Y '#
#'A 5% A'f'f k?
Sfa.[ek cn 'l 4. l. I c m as w],U ] $ ( affwe even.f acn s, R125 SEQUCYAH - UNIT 2 3/4 6-4 Amendment No. 53, 90, 104, a 7, 125 (Corre tion Letter of 7-11-88) Augu 2 7, 1990
~
,,, CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS r - - - 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE: a. After each opening, except when the air lock is beir'g used for multiple entries, then at least once per 72 hours, by verifying seal leakage less than or equal to 0.01 L, as determined by precision flow measurements when measured for at least two minutes with the volume R40 between the door seals at a pressure greater than or equal to 6 psig, b. By conducting an overall air lock leakage test at not less than P (12 psig) and by verifying the overall air lock leakage rate is a withi3 4 h limit:#
- 1. At least ce per six months, and
- 2. Prior to establishing CONTAINMENT INTEGRITY ff opened when CONTAINM NT INTEGRITY was not required when maintenance has been per ormed on the air lock that could affect the air lock sealing capability.*
- c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
^
N o f 3. &. I. 3. b ancl -lhe resa l+s evaluda) en a.cenden ec w$ la CFR So , ffA enkh I, as n,J. -[&L agrue) exemfOr. r The provisions of Specification 4.0.2 are not applicable.
- Exemption to Appendix "J" of 10 CFR 50.
October 2, 1986 SEQUOYAH - UNIT 2 3/4 6-8 Amendment No. 40
=.
I o *.
~w CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY ,
LIMITING CONDITION FOR OPERATION
- 3. 6.1. 6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6. .
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the structural integrity of the containment vessel not conforming to the above iequirements, restore the structural integrity to within the limits .e prior to increasing the Reactor Coolant System temperature above 200'F. f SURVEILLANCE REQUIREMENTS k 4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (reference *
'g __ Specification 4.6.1]) by a visual inspection of the exposed accessible interior
- 1. c and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance of the surfaces or other abnormal degradation. Any abnormal degra-dation of the containment vessel detected during the above required inspec-tions shall be reported to the Commission pursuant to Specification 6.6.1. l R28 l
'l e, :
l November 23, 1984 i SEQUOYAH - UNIT 2 3/4 6-11 Amendment No. 28 i i l l
j - CONTAINMENT SYSTEMS I"A4]/}, 3 SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.7 The structural integrity of the . shield building shall be maintained , i at a level consistent with the acceptance criteria in Specification 4.6.1.7. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200 F. SURVEILLANCE REQUIREMENTS 4.6.1.7 The structural integrity of the shield building shall be determined during the shutdown for each Type A containment leakage rate test (reference O, jg Specification 4.6.1.,2) by a visual inspection of the exposed accessible interior , and exterior surTaf'es of the shield building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation. Any abnormal degradation of the shield building detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.6.1. l R28 , L b 2 E November 23, 1984 ' SEQUOYAH - UNIT 2 3/4 6-12 Amendment No. 28
- l CONTAINMENT SYSTEMS -
CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION
, i i
- 3. 6.1. 9 One pair (one purge supply line and one purge exhaust line) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed. ;
Operation with purge supply or exhaust isolation valves open for either purging ' or venting shall be limited'to'less than or equal to 1000 hours per 365 days .R9 The 365 day cumulative time period will begin every January 1. APPLIChBILITY: MODES 1, 2, 3, and 4. 6 ACTION: i
- a. With a purge supply or exhaust isolation valve open in excess of the 3 R109 above cumulative limit, or with more than one pair of containment :
purge system lines open, close the isolation valve (s) in the purge line(s) within one hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With a containment purge supply and/or exhaust isolation valve i
having a measured leakage rate in excess of 0.05 L , restore the a R109
# inoperable valve to OPERABLE status within 24 hours, otherwise be in /2 at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REOUIREMENTS i 4 6.1.9.1 The position of the containment purge supply and exhaust isolation L valves shall be determined at least once per 31 days. 4.6.1.9.2 The cumulative. time that the purge supply and exhaust iso'ation i valves are open over a 365 day period shall be determined at least once per R9 7 days. ' 4.6.1.9.3 At least once per 3 months, each containment purge supply and i exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.05 L a
.cnd by ver fying that i R109
-when--the measured leakagwate is added to th" leakage rates detere%ed-
-p. - ,nt-to4pesification A.S.I.2.d for !' ether type B and C penetrations, 4
-t) * .+embined-4eakage-rate 4s-less th= cr caucl to 0. 50 L
- a !
N Reshc shall he avakbeN a,nsh 4Le acc Me crkerla. ofng,fQ -- Spec.Q.m L j % 6. l. l. e a n a ccord- nce. J to efR Ag,cdlx 4, ag ' affroveA exe f n S. SEQUOYAH - UNIT 2 3/4 6-15 Amendment No. 9,109 July 5, 1989
o fN M )
~
V .. m TABLE 3.6-2 (Continued) p CONTAlf4 met 4T ISOLATION VALVES h VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) N C. PHASE "A" CONTAINMENT VENT ISOLATION (Cont.) h 13. FCV-30-50 Upper Compt Purge Air Exh 4* 5
- 14. FCV-30-51. Upper Compt Purge Air Exh 4*
- 15. FCV-30-52 Upper Compt Purge Air Exh 4*
N
- 16. FCV-30-53 Upper Compt Purge Air Exh 4*
- 17. FCV-30-56 Lower Compt Purge Air Exh 4*
- 18. FCV-30-57 Lower Compt Purge Air Exh 4*
- 19. FCV-30-58 Inst Room Purge Air Exh 4* R62
- 20. FCV-30-59 Inst Room Purge Air Exh 4*
- 21. FCV-90-107 Cntmt Bldg LWR Compt Air Mon 5*
- 22. FCV-90-108 Cntmt Bldg LWR Compt Air Mon 5*
- 23. FCV-90-109 Cntmt Bldg LWR Compt Air Mon 5*
- 24. FCV-90-110 Cntmt Bldg LWR Compt Air Mon 5*
y 25. FCV-90-111 Cntmt Bldg LWR Compt Air Mon 5*
- 26. FCV-90-113 Cntmt Bldg UPR Compt Air Mon 5*
T 27. FCV-90-114 Cntmt Bldg UPR Compt Air Mon 5* N
- 28. FCV-90-115 Cntmt Bldg UPR Compt Air Mon 5*
- 29. FCV-90-116 Cntmt Bldg UPR Compt Air Mon 5*
- 30. FCV-90-117 Cntmt Bldg UPR Compt Air Mon 5*
D. OTHER
- 1. FCV-30-46 Vacuum Relief Isolation Valve 25
- 2. FCV-30-47 Vacuum Relief Isolation Valve 25 '
- 1p 3. FCV-30-48 Vacuum Relief Isolation Valve 25 gg 4. FCV-62-90 Normal Charging Isolation Valve 12 Cg -
R90
. 5c.bd..n4.6.I.Ic.)
( o
- Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power R29 rem veds unayerdleakagkneee limits of 2eIv.ree. ur-f %
cill=cc 4 1. 1."cquirem^nt i.E.5%Ns 3.1 ge satisfied. 6e p-rge valves, /e4Mye. J la.; Serve: em 3 mesi also be go # Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with . power removed and either FCV-62-73 or FCV-62: 74 is maintained operabic. y ' **The valve is required af ter completion of the associated modification. R73
'e
.f.*>.?;"-, o_ , 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1 PRIMARY CONTAINMENT MggT 'N CONTAINMENT INTEGRITY ensures that the release of ra ' c-materials from . ment atmosphere will be rest - o those leakage p paths and associated leak rate in N 1 ent analyses. This restriction, in conjunction wi Meakag t "mitation, will limit the M site boundary radi ses to within the limits of during accideEt e ions. __ SEccNDMY' CcM7AuMMEMT BYPASS 3/4.6.1.2 CONTAINMEN7 LEAKAGE N The limitations on containment leakage rates ensure that the total Sy co h ent leakage volume will not exceed the value assumed in the a M ent g analyses'at4he peak accident pressure, Pa . As an added conserv sm, the f measured cveral equal to 0.75 L duri rated leakage rate is further limit pqrformance of the periodic s to o less than or account for a possible degradation of the co inment leaka arriers between leakage tests. The surveillance testing measuring age rates are consistent with the requirements of Appen ~ J" of 10 CFR 50 wit e following exemption: the third Type A tes each 10 year inservice interva eed not be conducted R139 when the plant i ut down for the 10 year plant inservice ' gection. Due to , the increa accuracy of the mass point method for containment W1 rated leaka ing, the mass point method referenced in ANSI /ANS 56.8-191 an be . R91 u,s # 1n lieu of the methods described in ANSI N45.4-1972. 1 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment-air locks , are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage curing the intervals between air lock leakage tests. 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psig and 2) the B 3/4 6-1 Amendment No. 91, 139 SEQUOYAH - UNIT 2 JAN 231991
1 u.
..> .ep .*
o .. - l r l INSERT A , J The safety design basis for primary containment is that the ; containment must withstand the pressures and temperatures of the i limiting design basis accident (DBA) without exceeding the design leakage rates. - 1 The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a loss of coolant , accident (LOCA), a steam line break, and a rod ejection accident l (REA). In addition, release of significant fission product l radioactivity within containment can occur from a LOCA or REA. In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage. This leakage rate limitation will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions. The containment was designed with an allowable leakage rate of 0.25 percent of containment air weight per day. This leakage rate, used in the evaluation of offsite doses resulting from accidents, is defined in 10 CFR 50, Appendix J, as L,: the maximum allowable containment leakage rate at the calculated peak containment internal pressure ( P,) resulting from the limiting DBA. The allowable leakage rate represented by L, forms the basis for the acceptance criteria imposed on all containmemt leakage rate testing. L, is assumed to be 0.25 percent per day in the safety analysis at P, = 12.0 psig. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment , leakage barriers between tests. Primary containment INTEGRITY or operability is maintained by limiting leakage to within the acceptance criteria of 10 CFR 50, Appendix J. Individual leakage rates specified for the containment air lock (LC0 3.6.1.3), purge valves (LCO 3.6.1.9) and secondary bypass leakage (LCO 3.6.1.2) are not specifically part of the acceptance criteria of 10 CFR 50, Appendix J. Therefore, leakage rates exceeding these individual limits do not result in the primary containment being inoperable unless the leakage, when combined .; with other Type B and C test leakages, exceeds the acceptance criteria of Appendix J.
h.*.h:*4
^
i INSERT B , i The safety design basis f or containment leakage assunas that 75 percent of the leakage from the primary containmenu enters the shield building annulus for filtration by the emergency gas i treatment system. The remaining 25 percent of the primary containment leakage, which is considered to be bypassed to the auxiliary building, is assumed to exhaust directly to the atmosphere without filtration during the first 5 minutes of the accident. After 5 minutes, any bypass leakage to the auxiliary building is filtered by the auxiliary building gas treatment system. A tabulation of potential secondary containment bypass leakage paths to the auxiliary building is provided in Table 3.6-1. Restricting the leakage through the bypass leakage paths in Table 3.6-1 to 0.25 L, provides assurance that the leakage fraction assumptions used in the evaluation of site boundary radiation doses remain valid. I h t P f f}}