ML20044B990
| ML20044B990 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/10/1993 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20044B989 | List: |
| References | |
| NUDOCS 9303160074 | |
| Download: ML20044B990 (37) | |
Text
{{#Wiki_filter:-- g-3 i-ENCLOSURE 1 PROPOSED TECHNICAL' SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 and 50-328 (TVA-SQN-TS-93-02) LIST OF AFFECTED PAGES Unit i VII 1-2 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-11 3/4 6-12 3/4 6-15 3/4 6-23 B 3/4 6-1 Unit 2 VII 1-2 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-11 3/4 6-12 3/4 6-15 3/4 6-23 B 3/4 6-1
- 9303160074 930310 C PDR ADOCK 05000327_ 1
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS A SECTION PAGE f 3/4.5 EMERGENCY.. CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS i Cold Leg Injection Accumulators........................... 3/4 5-l' 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 than350*F.................... 3/4 5-8 R144 3/4.5.4 DELETED................... '
............................... 3/4 5 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.....................................
, seen&r C 3/4 6-1 .b- - Centai=3 ,.dJ~d dess ent-Leakage.......................................
- - 3/4 6-2 Containment Air Locks..................................... 3/4 6 Internal Pressure......................................... 3/4.6 Air Temperature........................................... [t 3/4 6 a Containment Vessel Structural Integrity................... 3/4 6-11 Shield Building Structural Integrity......................- 3/4 6
- Emergency Gas. Treatment System (Cleanup Subsystem)........ .3/4 6-13 Containment Ventilation System............................ 3/4'6-15 5 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS '
Containment Spray Subsystems.............................. 3/4 6-16: uS; ; Lower Containment Vent ~ Coo 1ers............................. 3/4 6-16b
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SEQUOYAH - UNIT 1 VII Amendment No. 67, 69, 116,-140 150 MAR 181991 . . _ a
y - m * " g . 4 DEFINITIONS' CHANNEL FUNCTIONAL TEST l'. 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.
- c. Digital channels - the injection of a simulated signal'into the channel as close to the sensor input to the process racks as R145-practicable to verify OPERABILITY including alarm and/or. trip functions.
CONTAINMENT INTEGRITY 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' Table 3.6-2 of Specification 3.6.3. -
- b. All equipment hatches are closed and sealed. '
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- c. Each air lock is in compliance with the requirements of -
Specification 3.6.1.3, asa{anedin The containment leakage rates are within the limits of / "
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d. Specification 3.6.1.f, and
- e. The sealing mechansim associated with each penetration.(e.g.,
welds,. bellows, or 0-rings) is OPERABLE. 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
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1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that R15 9 ~ ~ provides core operating limits for the current operating reload cycle. These: , cycle-specific core' operating limits shall be determined.for each reload cycle-in accordunce with Specification'6.9.1.14. Unit operation within these - '(h.Y operating limits is addressed in individual specifications.- SEQUOYAH - UNIT 1 1-2 Amendment No. 12, 71, 130_, 141, 155. OCT 231991
U - _ s ferbem re vored suel emwn ons an la<kege-
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77 e as mool$ed #3 Aff re Ve g 3/4.6.1 PRIMARY CONTAINMENT mg y,-y m a//,w,6 /e, /e e rehe ,1, 4 ,# CONTAINMENT INTEGRITY C,26 % of tendneo-vend 4'Y u')JN@ a-l Oe. Calcule}cc) fer W c*onNmmnb f*&f~C LIMITING CONDITION FOR OPERATION f#'l .. j 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 _i SHUTDOWN within the following 30 hours. - SURVEILLANCE REQUIREMENTS t 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
.Qp 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. ha each closing of each penetration subject to Type B testingf except the ton ainment air locks, if opened followin ype'A or R16 B test, by leak rate ing the seal with s at P,, 12 psig, and verifying that when the measure akage rate for these seals is
> I added to the leakage r e determined pur nt to Specification l 4.6.1.2.d fo other Type B and C penetrations, combined pue ge rate is less than or equal to 0.60 L a* '
*Except valves, blind flanges, and deactivated automatic valves which are I located inside the annulus or containment and are lock.ed, sealed or otherwise sh secured in the closed position. These penetrations shall be verified closed
! during each COLD SHUTDOWN except that such verification need:not be performed I more often than once per 92 days. '
I SEQUOYAH - UNIT 1 3/4 6-1 Amendment No. 12) 130 February 16, 1990 I
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CONTAINMENT SYSTEMS _ p .CCNTAIN"ENTkAKAGE EC# OA W
\ LIMITING CONDITION FOR OPERATION Sec Arg bgpss ,
3.6.1.2 Containment leakage rates shall be. limited to@ 4
% all integrated leakage rate of less than or equal to La '
O.25 peh t by weight of the containment air per 24 h at Pa ' I2 Psig.
- b. A combined leakage rat less than or al to 0.60 L f r all a
penetratio nd valves subject to Type B and C tes when essurized to Pa* h # Eombined bypass leakage rate of less than or equal to 0.25 L, for all penetrations identified in Table 3.6-1 as secondary containment BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to R75 - r ' (~ P'a W APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With either ed overall integrated containment leaka e e ing 0.75 L,, or (b) with the measured to Kage r and vgres -s c .to Types B and C tests exceeding 0.60 aL , r (c) Yiththe combined bypass leakage rate exceeding 0.25 L, for BYPASS LEAKAGE PATHS TO THE R75 AUXILIARY BUILDING, restore the cvtroll integrated leckage rete to le;; than er equal to 0.75 L,, the ccmbined lea hge rate for 21' penetration: ~ end velve; subject-tc Typc 3 and C test; to Ic;; than cr equal tc C.50 L,, the combined bypass leakage rate from BJILASS LEAKAGE PA_THS TO THE_ AUXILIARY BUILDING to less R75 than or equal to 0.25 L ft.uatCn , pr cFtc4ncre k7tsmar_be na the&Ee6cter af has cc-_lar+ f McT_ sTANO8D
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f s k SEQUOYAH - UNIT 1 3/4 6-2 Amendment No. 12 71 May 18, 1988
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/ CONTAINHENT SYSTEMS SEccaDAR'r' QnJTMmEa7 BYPASS WME SURVEILLANCE REQUIREMENTS sec Ar bysss
- 4. 6.1. 2 The containment leakage rates shall be demonstrated;at the fellcaing i test schedule end chc14-4>e-deterrined in conformence ith the criteric speci - '
fied " Appendh J cf 10 CFR 50 using the methods end previsien; cf ^NSI N45.4-1972; however, thc mctheds of ANSI /ANS 55.S-1987 fer me;; point det3 R106 cnalysi: cy be used ir lica of the method; ;pecified in ANSI N25.4-14M-- ,
\ a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals
- during shutdown at Pa R131 x (12 psig) during each 10 year service period.
b \ If any periodic Type A test fails to meet 0.75 L a, the test schedule
'fqr subsequent Type A tests shall be reviewed and approvep[y the Cohqission. IftwoconsecutiveTypeAtestsfailtomyt0.75L' e a ,
a Typb A test shall be performed at least every 18 mpffths until two consecu' ve Type A tests meet 0.75 aL at which timjVthe above test schedule y be resumed.
- c. The accuracy each Type A test shall be ve fied by a supplemental test which:
[N 1. Confirms the curacy of the Type difference betw n supplemental test by verifying that the d Type A test data is within 0 0.25 La '
- 2. Has a duration suffi 'ent t establish accurately the change in leakage rate between t jpe 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 (12 psig).
- d. Type B and C test shall be conducted wi gas at P3 (12 psig) at i intervals no g ater than 24 months except tests involving:
- 1. Air 1 ks,
- 2. P .etrations using continuous leakage monitori systems, and ,
- 3. Valves pressurized with fluid from a seal system.
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*A one me extension of the test interval is allowed for the third Ty A ithin the first 10 year service period provided unit shutdown occ s no RI3I tes e 1 r than May 1, 1990 and performance of Type A testing occurs prior to it-start following Unit 1 Cycle 4 refueling. -
r' i SEQUOYAH - UNIT 1 3/4 6-3 Amendment No. 102 , 127 September 29, 1989 j
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a p'. The combined bypass leakage rate to the auxiliary building shall be R75 determined to be less than or equal to 0.25 L, by applicable Type B 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 P, (12 psig)
; during each Type A test.
[ By verif9T6gheebcontainment a4" 4ock h in compliance with - R134 the r+miir+mentnfTpecification 3.6.1.4. 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 provided the seal system and valves are pressurized to at least 1.10 P, (13.2 g psig) and the seal system capacity is adequate to maintain system l pressure (or fluid head for the containment spray system and RHR R105 spray system valves at penetrations 48A, 488, 49A and 498) for at least 30 days. .
- h. tests for penetrations employing a continuous Ie -
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monitoring shall be conducted at P (12 at intervals no greater than once pe ars.
- i. All test leakage r s all be calcu a . ing observed data convert solute values. Error analyses s erformed to a balanced integrated leakage measurement system. '
] g jf. The provisions of Specification 4.0.2 are not applicable. l R106 I SEQUOYAH - UNIT 1 3/4 6-4 Amendment No. 12, 71, 101 102,130 February 16,~1990
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i 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. i ACTION: ! With the structural integrity of the containment vessel not conforming to the I above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F. ; i 1 h SURVEILLANCE REQUIREMENTS ! t
, .. 4.6.1.6 The structural integrity of the containment vessel shall be determined ;
y"*N during the shutdown for each Type A containment leakage rate test (Spccification i t 1.5.1.2) by a visual inspection of the exposed accessible interior 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 degradation of the . containment vessel detected during the above required inspections shall be > reported to the Commission pursuant to. Specification 6.6.1. R40 f l fi i t f f November 23, 1984 i SEQUOYAH - UNIT 1 3/4 6-11 Amendment No. 36 } i
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CONTAINMENT SYSTEMS [ SHIELD BUILDING STRUCTURAL INTEGRITY (. s- / LIMITING CONDITION FOR OPERATION
- 3. 6.1. 7 The structural integrity of the shield building shall be maintained 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, ;
y SURVEILLANCE REQUIREMENTS 4.6.1.7 The structural integrity of the shield building shall be determined hggj.gg
'during the shutdown for each Type A containment leakage rate test (reference . _ .
-- Speci'ication ".5.1.2) 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 Specification 6.6.1. R40 m.
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;SEQUOYAH - UNIT 1 3/4 6-12 Amendment No. 36 9
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[ , i bONTAINMENTSYSTEMS: ., E, CONTAINMENT VENTILATION SYSTEM i {k : LIMITING CONDITION'FOR OPERATION' j
- 3. 6.1. 9 One pair-(one purge supply line and one' purge exhaust line) of--
-l containment purge system lines may be open;.the containment purge supply and i exhaust isolation valves in all other containment purge lines shall be closed.- i Operation with purge supply or exhaust isolation valves open for either purging 4 or venting shall be limited to less than or equal to 1000 hours per 365 days. I The 365 day cumulative time period will begin every January 1. d22' APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION: 1
- a. With a purge supply or exhaust isolation valve open in. excess of the 12C above cumulative limit, or with more than one pair of containment ;
purge system lines open, close the isolation valve (s) in the purge H line(s) within one hour or be in at-least HOT STANDBY within the next- 1 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 !
R124' [". m 7 inoperable valve to OPERABLE status within 24' hours, otherwise be-in :) at least HOT STANDBY- within the next 6 hours and in COLD SHUTDOWN l! within the following 30 hours. 1 SURVEILLANCE-REOUIREMENTS I a i 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
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4.6.1.9.2 The cumulative time that the purge' supply and exhaust isolation. valves are open over a 365 day period shall be determined at least'once per 7 days. i i. 4.6.1.9.3 At least once per 3 months, each containment purge supply and exhaust isolation valve shall be demonstrated.0PERABLE by verifying that the ~ ~ l measured leakage rate is less than or equal to 0.05 L, and by verifying .that when the measured leakage rate is added to the leakage rates deter 'ned - l per:e nt tc Specificatic: " 5.1.2.d for all other type B and C' penetrations, the combined leakage rate is less than or equal to 0.60 L,. ; J l t P
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SEQUOYAH - UNIT 1 3/4 6-15 Amendment No.18, .120 July 5, 1989
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- y TABLE 3.6-2 (Continued) y CONTAINMENT ISOLATION VALVES '
y 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 4* O 14. FCV-30-51 Upper Compt Purge Air Exh 4*
- 15. FCV-30-52 Upper Compt Purge Air Exh 4^
- 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*
- 20. FCV-30-59 Inst Room Purge Air Exh 4*
- 21. FCV-90-107 Cntmt Bldg LWR Compt Air Hon 5* R74
- 22. FCV-90-108 Cntml 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*
M* 2 5.- 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-Il4 Cntmt Bldg UPR Compt Air Mon 5* O 28. FCV-90-ll5 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
$3T 1. FCV-30-46 Vacuum Relief Isolation Valve 25 g8 2. FCV-30-47 Vacuum Relief Isolation Valve 25 gE 3. FCV-30-48 Vacuum Relief Isolation-Valve 25 N@ 4. FCV-62-90 Normal Charging Isolation Valve 12 R105 toCFRfo,Aud*Y3}~ ff g ^ Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed
@ - and under leakage kresuves. ts of Su.f 4cMlancc limiRep.'remn 6. I. 9.3Rc n.qu e s'1rement
, qiso b e.".saf C.s3.-+
4;'<d,are satis fied. For porge valves, le4Fge. tidfs g41-E '// 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 operable. 8 ' This valve is required after completion of the associated modification. R86 S
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. i 3/4. 6 CONTAINMENT SYSTEMS
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BASES 3/4.6.1 PRIMARY CONTAINMENT i 3/4.6.1 PRIMARY CONTAINMENT
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CONTAINMENT INTEGRITY ensures that the release of ra * % gf materials from i ' ment atmosphere will be res o those leakage ~ paths and associated leak ra e i + c1 dent analyses. This
.A restriction, in conjunction eakage ~ itation, will limit the i site boundary r oses to within the limits of 1 r
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ring i cg a,c_cids noitions. stcoaogY coa %MEpT SYPASS 3/4.6.1.2 CC"' O HEF LEAKAGE ' The limitations on containment leakage rates ensure that the total
.. conta' ent leakage volume will not exceed the value assumed in the.ac ~ ent f
analyses a .e peak accident pressure, P . As an added conserv +'sm, the ,
'/ a .,
measured overall tegrated leakage rate is further limited less than or j
,44# equal to 0.75 L, durin erformance of the periodic t s to account.for- l possible degradation of the tainment leakage riers between leakage l RT tests. -
h . h The surveillance testing for
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asuring akage rates are consistent with [ the requirements of Appendi " of 10 CFR 50 wi the following exemption.
- The third Type A test each 10 year service period n not be conducted R131 when the plant ic 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 o be R106 in lieu of the methods described in ANSI N45.4-1972.
l .? 3/4.5.1.3 CONTAINMENT AIR LOCKS l 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 during the intervals between air lock leakage tests. . 3/4.6.1;4 INTERNAL PRESEURE I The limitations on containment internal pressure ensure that 1) the ' containment structure is prevented from exceeding its design negative pressure i differential with respect to the annulus atmosphere of 0.5 psig and 2) the
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SEQUOYAH - UNIT 1 B 3/4 6-1 Amendment No. 102, 127 September 29, 1989
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l INSERT A ' 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. , 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 i
'(REA). In addition, release of significant fission product '
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 containmeat leakage rate at the calculated peak containment internal pressure (P,) resulting from-the limiting DBA. The
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allowable leakage rate represented by L,. forms the basis for the acceptance criteria imposed on all containment' 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. i 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 , (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. i l l l i 1
v INSERT B The safety design basis for containment leakage assumes that 75 percent of the leakage from the primary containment enters the shield building annulus for filtration by the emergency gas 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 j 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 i boundary radiation doses remain valid. i 8 [ s i
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. INDEX em. -
I I LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
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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,yg greater than or equal to 350*F. . .. . 3/4 5-4 3/4.5.3 R131 ECCS SUBSYSTEMS - T,yg less than350*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
,- Containment Integrity.....................................
( GatonLegGk.sment 8 gass 3/4 6-1
\ ,),/ (*-Gont-ainment Le a kage . . . . . . . . . . . . . . . . . . . . . .3/4
. . 6-2 Containment Air Locks..................................... 3/4 6-7 I
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 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 R140 Lower Containment Vent Coo 1ers............................. 3/4 6-16b R61 7- ss SEQUDYAH - UNIT 2 VII Amendment No. 59, 61, 131 140 h4AR 181991
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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 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 practi- R132 cable to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT INTEGRITY R63 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 auto-matic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.
7 b. c. All equipment hatches are closed and sealed, Each air lock is in compliance with the requirements oh - W'
'Ril, Specification.3.6.'1.3, (wgrigggeTd g snhnad[
- d. The containment leakage rates are within the limits of7 Specification 3.6.1.7, and
- e. The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
CONTROLLED LEAKAGE 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. R1461 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 , cperating limits is addressed in individual specifications. ' SEQUOYAH'- UNIT 2 1-2 Amendment No.- 63, 117, 132, ! 146 l March 30, 1992 l
. . . . . y
; exam s'no ca Q.Q
, excef $ the Cen$e.inmenk At' ec N
~~~, , (afe t in teS{, , in accordance O S ID CfA $*,' NftY'X {
eenLA /nusam ; ena
.( ~3/4.6 CONTAINMENT SYSTEMS 45 r>wc/,6 k gro
' IE" ) '
3/4.6.1 PRIMARY CONTAINMENT d 08 W
*]C-CONTAINMENT INTEGRITY f a,, , 12 fSog.
fea k conta,'ne ne fressore ' LIMITING CONDITION FOR OPERATION WV 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. 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 i 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
'ky secured in their positions, except as provided in Table 3.6-2 of '
Speci fication 3.6.3.
- b. By verifying that each containment air lock is in compliance with R117 .
the requirements of Specification 3.6.1.3.
- c. each closing of each penetration subject to Type B testin ,
htehtthe excep ntainment air locks, if opened followin ype A or B., , test, by leak r 4 the seal with at Pa, 12 psig, and ' verifying that when the measurec akage rate for these seals is ; added to the leakage r s determine t to Specification 4.6.1.2.d fo 1 other Type B and C penetrations, % combined p ge rate is less than or equal to 0.60 L,. j l
*Except valves, blind-flanges, and deactivated automatic valves which are j
located inside the annulus or containment and are locked, sealed or otherwise ' secured in the closed position. These penetrations shall be ve'rified 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 , 4
. CONTAINMENT SYSTEMS C0"TAIN"[NT AKAGE Y CONTA 9mEdT SYM55 d LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment rates shall be limited t @ <
M n overall integrated leakage rate of less than or equal to L p . d pe eight of the containment air per 24 hour P,, 12 psig.
- b. A combined leakage ra less than or W al to 0.60 L for all penetratio nd valves subject to Type B a st n re ized to P a' h-h X combined bypass leakage rate of less than or equal to 0.25 La fUI all penetrations identified in Table 3.6-1 as secondary containment BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to R1
(, P. a APPLICABILITY: MODES 1, 2, 3 and 4 ACTION: Tiltre+ a) the measured overall integrated containment leaka (C' exceeding 0.75 La , r (b) witTi'Ttte-me ed-cc ined leakage rate for all penet at,i.o_nL-arwfmra ves subject to Types B and C tests excee (c)lWith the combined bypass leakage rate exceeding 0.25 L f r BYPASS LEAKAGE a R63 PATHS TO THE AUXILIARY BUILDING, restore the everal' 4 ;tegrated leakege-eate-te-4est than or equal to 0.75 L a, and-the-combined 4eakege-rete for 21' penetra-
-14em and valvcs subject to Type C sad C tests to less than or caucl to 0.50 L,,
-eftd- the combined bypass leakage rate f rom BYPASS LEAKAGE P_ATits T0_TH AUXIL R63
'n 4 hours or bc art o. e4s BhotILDING STM D to 6Y l_wQlth;northiequal nQ11 0.25 og L anf, pninerCoz.,b t~e *^cMarim fthe Deirbw.fYLle SHuToewiJ r S N'*fL mi ef+t syste.T temperature at;c,c 20, F
- - - - - n]' 30 -s g
SEQUOYAH - UNIT 2 3/4 6-2 Amendment tto. 63 May 18, 1988 l ni
, CONTAINHENT SYSTEMS S E Cc N OA RY coa Tw a rcaT B r'M 55 LEA KAGE D SURVEILLANCE REQUIREMENTS second Q @~
4.6.1.2 The containment leakage rates shall be demonstrated:at-the following-i 1
-te s t-s c hedule-and-s ha H-be-determined-i n-co nfo rma nc+-with-t he-c etteria-spech
-f4ed-i n-Append i x-J-o f-10-CFR u s i ng - t he-methods-and-prov4si ons-o f-AN S I-
-N45A -1972;-howeveer -the-methods-of-ANSI /ANS-5678-1987-foe-mass--point-data-
-enalysis-may be used-in-44eu-of -the-methods-spec 4f4cd in ANSI-N45A-1972- R91
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at x P,,12 psig, during each 10 year service period. R13-b If any periodic Type A test fails to meet 0.75 L, the test chedule N for subsequent Type A tests shall be reviewed and appro by the
'Epmmis s ion. If two consecutive Type A tests fail to t 0.75 L , a N a Type A test shall be performed at least every 18 mo hs until two consecutive Type A tests meet 0.75 L at which ti the above test i a
schedu y be resumed.* l R126
- c. The accuracy of each Type A test shall be v ified by a supplemental e test which:
(N,;p 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. Hasadurationsufkicient t establish accurately the change in leakage rate between e ype A test and the supplemental test.
- 3. Requires the quantity of as injected into the containment or bled from the contpinment uring the supplemental test to be equivalent to at east 25 percent of the total measured leakage at P,, 12 psig.
- d. Type B and C tes $ shall be conducted w h gas at 3P , 12 psig, at intervals no eater than 24 months except or tests involving:
- 1. Air locks,
- 2. Pp/etrations using continuous leakage monitoriqg systems, and
- 3. Values pressurized with fluid from a seal system.
*An [emptionfromthe18-monthacceleratedfrequencyrequirementisallowedfor t,be Type A test failures conducted during the Unit 2 Cycle 2 and Unit 2 C' le 3 R126 refueling outages.
SEQUOYAH - UNIT 2 3/4 6-3 Amendment No. 91, 126, 139
'JAN M 1991
,- . -- - a ..
,e . =
. CONTAINMENT SYSTEMS '
c ., SURVEILLANCE REQUIREMENTS (Continued) L q: j . The combined bypass leakage rate to the auxiliary building shall be R63 ; determined to be less than or equal to 0.25 Laby applicable Type B t 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 P,, 12 psig,- i during each Type'A test. ,
- f. By veriffi~ng~t7Fai, 6g ced '
t a b h d l= in compliance with the Rll7 requiremen+c of SphiiicatToli 3.6.1.3. i bpy: 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 f the seal system and valves are pressurized to at least 1.10 P,,13.2 psig, and the seal system capacity is adequate to maintain system } l pressure (or fluid head fo'r the containment spray system,and PJiR : i , spray system valves at penetrations 48A, 488, 49A and.'498) for at f
! least 30 days.
f .; p sts for penetrations employing a continuou's 1 monitoring s shall be conducted at P , 1 ' , at' intervals no greater than once per s. ,
- i. All test leakage r all be calcula observed data converted solute values. Error analyses sha erformed to
=
a balanced integrated leakage measurement system.
.j C ff The provisions of Specification 4.0.2 are not applicable.
i L l R126 SEQUOYAH - UNIT 2 3/4 6-4 Amendment No. 63, 90, 104, 117, 126 (Correction Letter of 7-11-88) j August 27. 1990
w- .? { (p). CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY l 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 requirements, restore the structural integrity to within the limits-prior to increasing the Reactor Coolant System temperature above 200 F. l f r SURVEILLANCE REQUIREMENTS LJ 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 (referer.se-
-Spee+f4 eat 4en 4.5.1.2) by a visual inspection of the exposed accessible interior i and exterior surfaces of the vessel, This inspection shall be performed prior I 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- I dation of the containment vessel detected during the above required inspec-tions shall be reported to the Commission pursuant to Specification 6.6.1. lR28 i i O %s , November 23, 1934 SEQUOYAH - UNIT 2 3/4 6-11 Amendment No. 28 ;
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. ,.-3
#~
- - CONTAINMENT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.7 The structural integrity of the shield building shall be maintained !
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
,m
./
) [6thJhilld 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 Specificatien 1.5.1.2) 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 Specification ' 6.6.1. l R28 f P
/~N l
November 23, 1984 SEQUOYAH - UNIT 2 3/4 6-12 Amendment No. 28
- ~
- a. .
t O CONTAINMENT SYSTEMS A - CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION
- 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. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:
- a. With a purge supply or exhaust isolation valve open in excess of the above cumulative limit, or with more than one pair of containment lR109 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 having a measured leakage rate in excess of 0.05 L , restore the 3 R109' !
( j inoperable valve to OPERABLE status within 24 hours, otherwise be in i LJ at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN ' within the following 30 hours. SURVEILLANCE RE0VIREMENTS 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. 4.6.1.9.2 The cumulative. time that the purge supply and exhaust isolation 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 exhaust isolation valve shall be demonstrated OPERABLE by verifying that the R109 measured leakage rate is less than or equal to 0.05 L, and by verifying that when the measured leakage rate is added to the leakage rates .detemied- ' pursu=t to Spect'icatier d.E.1.2.d for all other type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,. t h A SEQUOYAH - UNIT 2 3/4 6-15 Amendment No. 9,109 July 5, 1989 ,
c .
- ;q - .e
.m TABLE 3.6-2 (Continued) g CONTAINMENT ISOLATION VALVES h, VALVE NUMBER FUNCTION 2
MAXIMUM ISOLATION TIME (Seconds) I C. PliASE "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* ,
w 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* y 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. OTilER
- 1. FCV-30-46 Vacuum Relief Isolation Valve 25
- 2. FCV-30-47 Vacuum Relief Isolation Valve 25 Q
![g 3.
4. FCV-30-48 FCV-62-90 Vacuum Relief Isolation Valve 25 Normal Charging: Isolation Valve 12 R90 ca hh to CFR So[Affee ( o
- Provisions'of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power' lea R29 removed uaa g sav.kage
;na,ee.limits of Survcillr.cc a &.1. Requirement 1.5.3.1 s,um.are satisfied. For ge valas, Ic&ge.
Q Qe e<p.a-eat s.3 -st ats, he
# 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 operable. " q **The valve is required af ter completion of the associated modification. R73 O
m l . .
'3/4.6 CONTAINMENT SYSTEMS .
f) - N. M ' BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1 PRIMARY CONTAINMENT Drimary CONTAINMENT INTEGRITY ensures that the releasc of ra fr5 ggt materials fr h ntainment atmosphere will be re cted o those leakage
'p. paths and associated leak raf6?ntss cci ent analyses. This-restriction, in conjunction t tation, will limit the-M site bour'ary radjatierrd ses to within the limits o 1TtFfMOCLduring accident--conditions. _
CSEcoHDAW CcMTAt9 MENT BYPhSS [ 3/4.6.1.2 -GONTAINMENT- LEAKAGE N The limitations on containment leakage rates ensure that the total fjMg containatent leakage volume will not exceed the value assumed in the i ent .., g analyses at4he peak accident pressure, P,. As.an.added conser ti m, the. ' f measured overalhntegrated leakage rate is further limi d less than or l equal to 0.75 L, during1 rformance of the periodic .s to account for ;
-possible degradation of.the to tAinment leakagedfarriers between leakage tests.
l The surveillance testing p measuring e rates are consistent with the requirements .of Appendix"J" of 10 CFR 50 wi 'following exemption: -i the third Type - A tesjaf'each 10 year inservice interv eed not be conducted R139R when the plant yihut down for the 10 year plant inservichnspection. Due to the increased accuracy of the mass point method for. containment hte< grated
'leakagpt(sting,- the mass point method. referenced in ANSI /ANS_56.8-19B M an.be R91 l ujad in. lieu of the methods described in ANSI N45.4-1972.
'N :
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. l 1eak' rate. Surveillance testing of the air lock seals provide' assurance that- l the overall air lock leakage will not become excessive due to seal damage , during the intervals between air lock leakage tests. , ' 1 3/4.6.1.4 INTERNAL PRESSURE ! The limitations on containment internal pressure ensure that 1) the- ! p containment structure is' prevented from exceeding its design negative pressure differential with respect to'the annulus atmosphere of 0.5 psig and 2) the
'j.
- e
\ s. ,
SEQUOYAH - UNIT 2 B 3/4 6-1 Amendment No. 91, 139 JANP1199h !
q 1
. . l INSERT A The safety design basis for primary containment is that the containment must withstand the pressures and temperatures of the ;
limiting design basis accident (DBA) without exceeding the design ' 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 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 I 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 containment leakage rate testing. L, is assumed to be 0.25 percent per day in the uafety 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 (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.
4 9
. I INSERT B The safety design basis for containment leakage assumes that 75 percent of the leakage from the primary containment enters the s shield building annulus for filtration by the emergency gas !
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 i paths in Table 3.6-1 to 0.25 L, provides assurance that the < leakage fraction assumptions used in the evaluation of site l boundary radiation doses remain valid. 1 l l 1 l l I i l i i i 1
.a
4 4 . ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE I SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 and 50-328 (TVA-SQN-TS-93-02). - DESCRIPTION AND JUSTIFICATION FOR : REMOVING DETAILED CONTAINMENT TEST REQUIREMENTS FROM TSs P I l i 5 r t l 1 i
a . ENCLOSURE 2-Description of_ Change TVA proposes to modify the Sequoyah Nuclear Plant (SQN) Units 1 and 2 technical specifications (TSs) to delete detail containment test requirements that are governed by 10 CFR 50, Appendix J,'" Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors."' SQN's primary containment TS 3.6.1.1 and containment leakage TS 3.6.1.2 ; currently contain detailed containment leakage rate requirements, test requirements, test schedules, and test accuracies that are also required by 10 CFR 50, Appendix J. TVA's proposed change will remove the duplicate 10 CFR 50, Appendix J, requirements from TSs. In addition to , the specific changes to TSs 3.6.1.1 and 3.6.1.2, three other related TSs are being revised to remove references that will no longer be applicable. An unrelated. change to a footnote in TS Table 3.6-2 provides ; a needed clarification to correct an oversight from a previous TS change. The proposed changes are as follows: *
- 1. Revise definition for containment Item d references the current integrity (Definition 1.7, Item d) TS 3.6.1.2 that governs containment leakage rate criteria. Proposed changes to TS 3.6.1.2 required Item d to be revised to reference the 10 CFR 50, Appendix J, containment leakage rate criteria that are provided by reference in TS 3.6.1.1.
- 2. Revise Surveillance Requirement This SR currently contains (SR) 4.6.1.1.c containment. leak rate criteria for Types B and C penetrations following closure. The Types B and C penetration leak rates are
. governed by 10 CFR 50, Appendix J. This SR is being' revised to be consistent with standard requirements from NUREG-1431.
- 3. Revise Limiting Condition for The LCO currently limits Operation (LCO) 3.6.1.2 containment leakage rates in three categories:- (a) overall integrity leakage rate, (b) combined leakage for Types B and C tests, and (c) combined leakage for secondary.
containment bypass leakage rates to.the auxiliary building. The LCO is being revised to limit applicability to secondary containment bypass leakage rates (Category e only).
O. A J
- 4. . Delete LCO 3.6.1.2.a' The LC0 currently limits SQN's overall; integrated containment !
leakage rate to less than or equal to a maximum. allowable leakage rate (L,). The 10 CFR 50, Appendix J,. test-requirement referenced in SR 4.6.1.1.c maintains and " governs the L, limit.
- 5. Delete LCO 3.6.1.2.b The LCO currently limits the containment. combined leakage rate.to less than or equal to ,
0.60 La for all penetrations and valves subject to Types B and C' i testing.- The 10 CFR 50, Appendix J, test requirements referenced in SR 4.6.1.1.c maintain this 0.60 L, limit.
- 6. Revise LCO 3.6.1.2.c The LCO ctrrently. limits'the . l containment bypass leakage rate to less than or equal to 0.25 La for all penetrations identified in TS TableL3.6-1-(secondary containment bypass leakage paths to the auxiliary building). The ;
secondary containment bypass , leakage paths to the auxiliary building are specific to SQN'and~ are not addressed by 10 CFR 50, Appendix J; therefore, this LCO is being retained under LCO 3.6.1.2.
- 7. Revise action to LCO 3.6.1.2 The action for LCO 3.6.1.2 4 currently contains actions t associated with containment l 1eakage rates in three .
categories: (a) overall-integrated leakage rate, (b) combined-leakage rate'for Types B and C penetrations, and (c) combined leakage for secondary containment bypass
' leakage paths to the auxiliary building. The action'has been reformatted to' reflect applicability to Category c q only. Action. requirements forL leak rate Categories a and b are ,
maintained and governed by : 10 CFR 50, Appendix J (refer to SR 4.6.1.1.c).' , P
- s e
+' 7
- 8. Delete SR 4.6.1.2 The SR items are associated with d (Items a, b, c, d. containment leakage rate -
'f, h, and i) criteria, test schedules, and accuracy requirements that are maintained and governed by .;
10 CFR 50, Appendix J. Items (e), (g), and (j) are associated with combined bypass , leakage rates to SQN's auxiliary. building and are being retained in TSs.
- 9. Revise SR 4.6.1.6 SR 4.6.1.6 currently references SR 4.6.1.2 for Type A :
containment leakage _ rate testing. This reference will no longer be applicable following ' the proposed changes to SR 4.6.1.2.
- i
- 10. Revise SR 4.6.1.7 SR 4.6.1.7 currently references SR 4.6.1.2 for Type A ,
containment leakage rate testing. This reference will no longer be applicable following , the proposed changes to- l SR 4.6.1.2.
- 11. Revise SR 4.6.1.9.3 SR 4.6.1.9.3 currently references SR 4.6.1.2.d that- i ensures the combined leakage '
rates for purge valves and all other Types B and C penetrations remain less than or equal-to 0.60'L,. This reference will no longer be applicable following the proposed deletion of' TS;4.6.1.2.d.
- 12. Revise footnote (*) to Table 3.6-2 A footnoted reference to -;
SR 4.6.3.4 in Table 3.6-2 is no longer applicable for defining the leakage limit on purge valves. Leakage' limits for
-valves in Table 3.6-2 are governed by 10 CFR- 50, s Appendix J. The leakage limits for SQN's purge valves are also-governed by SR 4.6.1.9.3.
l i
g- 4 6
- 13. Revise' Bases 3/4.6.1 The current' bases for primary containment integrity are being replaced to reference the containment. leakage limits -
governed by 10 CFR 50, Appendix J. The proposed bases change incorporates the NUREG-1431 wording to. reflect 10 CFR 50, Appendix J, leakage limits and acceptance criteria.
- 14. Revise Bases 3/4.6.1.2 The current bases for overall !
containment leakage are being revised to incorporate secondary containment bypass leakage limitations. Renann_for Change The purpose of 10 CFR 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," is to establish , containment leakage test requirements for ensuring that leakage. rates do not exceed those assumed in the evaluation of offsite dose limits following an accident. The maximum allowable containment leakage rate limit (L a) forms the basis for the acceptance' criteria for containment ' leak rate testing. The 10 CFR 50, Appendix J, requirements establish a 0.75 La leakage limit for the overall containment integrated leakage rate i during performance of periodic Type A tests (i.e., containment integrated , leak rate test [CILRT)). This 0.75 L, limit is consistent with the , philosophy of having a 25 percent margin for deterioration of containment ; integrity during the interval between periodic Type A' tests. A combined leakage rate limit (0.60 L ) for containment penetration'and containment- . isolation valves subject to Types B and C tests is also governed by 10 CFR 50, Appendix J. Other associated details for maintaining primary-containment integrity (i.e., testing requirements, test schedules,;and-test accuracies) are contained in 10 CFR 50, Appendix J. Since these leak rate limits and detail requirements are governed under Appendix-J, TVA proposes to remove duplicate requirements from SQN TSs. Previous TS amendments associated with SQN's Appendix J. Type A test schedules and test methodology have resulted in TS changes being processed in accordance with 10 CFR 50.90 along with Appendix.J exemptions being processed in accordance with 10 CFR 50.12. Deleting. duplicative requirements between 10 CFR 50, Appendix J, and TSs will reduce the administrative burden for processing TS changes in conjunction with 10 CFR 50, Appendix J, exemptions should this become necessary. Consistent with this described situation, TVA recently submitted an Appendix J exemption request on January 7,1993, to address the reported failure of a containment integrated leakage rate test (Type A test)
~
performed on SQN Unit 2 during the Unit 2 Cycle 5 refueling outage. A
a <. ,
- c-companion TS change would be necessary under the current TSs to reflect the same provisions of the exemption request. TVA is utilizing this- '
opportunity to permsnently' revise the related SQN TSs to eliminate the need for this and eay future exemption-related TS changes. One additional unrelated change to a footnote in TS Table 3.6-2 provides a needed correction to delete a reference to SR 4.6.3.4. SR 4.6.3.4 was deleted by a previous TS change (TS Change 88-06) and is no. longer : applicable. Since the footnoted reference to SR 4.6.3.4 was > inadvertently retained in TSs, the proposed change is needed to correct , the oversight, r Jus 11fication for Change SQN's primary containment design includes the provisions and features required to satisfy the testing requirements of 10 CFR 50, Appendix J. The design of SQN's containment penetrations and isolation valves _ permits periodic leakage rate testing at the pressure (Pa ) 8Pecified in 10 CFR 50, Appendix J. The specific test requirements for leak testing SQN's primary containment (Type A testing), containment penetrations ~ ' (Type B testing), and containment isolation valves (Type C testing) are : provided in Section III of 10 CFR 50, Appendix J. SQN's measured leakage rate acceptance criterion for Type A tests is defined in Section III.A.S.b.2 and is 0.75 L,. The leakage rate acceptance criterion for SQN's Types B and C tests is provided in Sections III.B.3.a-and III.C.3, respectively, and is 0.60 L,. The 0.60 L, limit serves as a combined leakage rate limit for all containment leakage paths subject to , Types B and C testing. These Appendix J containment leakage rate limits . (0.75 Laand 0.60 L,) are also contained in SQN TS 3.6.1.2. The subject i TS change proposes to remove the containment leakage rate criteria from the SQN TSs. Justification for this change is based on the fact that.the { same containment leakage rate criteria are prescribed and governed by , 10 CFR 50, Appendix J. Accordingly, the removal of this criteria from 6 TSs does not alter or affect the containment leakage rate. criteria for : SQN. In addition, the proposed change is consistent with guidance provided in the recently approved standard TSs for Westinghouse Electric'
- Corporation plants (NUREG-1431).
Individual leakage rate limits specified for the containment air locks, purge valves, and secondary containment bypass leakage are not specifically part of the acceptance criteria of 10 CFR 50, Appendix J. Therefore, these individual leakage rate limits are being retained in SQN TSs. The TS operability requirements for SQN's containment air lock and , containment purge valves are contained in LCO 3.6.1.3 and 3.6.1.9, respectively. SQN's secondary containment bypass leakage limits are being retained under the current LCO 3.6.1.2. ! t In addition to the proposed changes associated with containment leakage , limits. TVA is proposing to remove Types A, 3, and C test schedules and accuracy requirements from SQN TSs. 'Thes<, test schedules and accuracy requirements are identical to the requirzements contained in 10 CFR 50,- Appendix J. This proposed change thereby reduces duplicate requirements between TSs and Appendix J and is consistent with the guidance provided : in NUREG-1431.
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i - . O One other area involving proposed changes involves a footnote found in Table 3.6-2, " Containment Isolation Valves Function," that provides an exemption to LCO 3.0.4. The exemption to LCO 3.0.4 is applicable to designated containment isolation valves shown with an asterisk (*) in Table 3.6-2. The exemption allows entry into an operational mode when the valve (s) is: (1) secured in its isolation position with power removed, and (2) containment leakage limits are satisfied. The. footnote ' currently contains a reference to the leakage limits of SR 4.6.3.4 that. was specific only to purge valves. However, the footnote to Table 3.6-2 may be applicable to either a purge valve or a containment isolation valve having isolation capability. TVA's proposed change clarifies the footnote to ensure that the leakage limits are properly defined for either application. It should be noted that the current footnote reference to SR 4.6.3.4 is no longer applicable. SR 4.6.3.4, which provided purge valve test and leakage limit requirements, was superseded by SR 4.6.1.9.3 (reference TS Change 88-06, NRC letter to TVA dated July 5, 1989, TAC R00518/R00519). The footnoted reference to SR 4.6.3.4 in Table 3.6-2 should have been revised under TS Change 88-06, but was inadvertently retained. TVA's proposed TS change corrects this oversight. Environmantal_ Impact Evaluation The proposed change request does not involve an unreviewed environmental question because operation of SQN Units 1 and 2 in accordance with this change would not:
- 1. Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or decisions ,
of the Atomic Safety and Licensing Board.
- 2. Result in a significant change in effluents or power levels.
- 3. Result in matters not previously reviewed in the licensing basis for SQN that may have a significant environmental impact.
t
i' 4 4 Enclosure 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PIANT UNITS 1 AND 2 DOCKET NOS. 50-327 and 50-328 (TVA-SQN-TS-93-02) DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION I i
J: 4 . - t 1 ENCLOSURE 3~ r Significant Hazards Evaluation - ; t TVA has evaluated the proposed technical specification (TS) change and
~
has determined that it does not represent a significant hazards , consideration based on criteria established in 10 CFR 50.92(c). > Operation of Sequoyah Nuclear Plant (SQN) in accordance with the proposed ! amendment will not:
- 1. Involve a significant increase in the probability or consequences of -
an accident previously evaluated. , SQN's primary containment design includes the provisions and features ! required to satisfy the testing requirements of 10 CFR 50, Appendix J. TVA's proposed TS change continues to require that SQN-containment integrity be maintained in accordance with 10 CFR'50, i Appendix J. The evaluation for determining containment leakage rate- , limits and offsite dose limits following an accident is not affected. SQN's current acceptance criteria governing containment leakrate test limits (0.75 L, for periodic Type A testing and 0.60 L, , for Types B and C testing) remain unchanged. Detailed test requirements, test schedules, and test accuracies that are being deleted from SQN TSs will be governed by reference under 10 CFR 50, i Appendix J. TVA's proposed amendment does not affect the individual TS leakage rates associated with SQN's containment air lock, purge valves, or secondary bypass leakage to the auxiliary building since these leakage rate limits are not specifically part.of the acceptance criteria of 10 CFR 50, Appendix J. These individual leakage limits remain unchanged and are retained in SQN TSs. All other proposed changes are clarifications, including the revised wording for the footnote to TS Table 3.6-2. These clarifications do not impact'the intent of the affected specifications. In conclusion, TVA's proposed TS change will not affect containment test criteria, system conditions, or plant configurations, and will not affect SQN's accident analysis. The proposed change is considered by TVA to be a TS improvement that is consistent with the j guidance contained in the recently approved NUREG-1431. Consequently, this change will not increase the probability or ; consequences of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident f rom any previously analyzed.
No physical modification is being made to any plant hardware, plant ; operating setpoints, limits, or operating procedures as a result of j this change. TVA's proposed TS amendment is designed to remove detailed containment test requirements from TSs and maintain these- : containment test requirements under 10 CFR 50, Appendix J. The ; proposed change does not alter any accident analysis or any F
h'! p .
- . t
. e assumptions used to support the accident analysis. Censequently, the containment leakage assumptions used to determine offsite dose limits for compliance with 10 CFR 100 are not affeated. All other proposed '
changes are clarifications, including the r~a v.1 wording for the-footnote to TS Table 3.6-2. These clarifit.r. io not impact the intent of the affected specifications. Acco.c gly, this change will not create the possibility of a new or different kiad.of accident from any previously analyzed.
- 3. Involve a significant reduction in a margin of safety.
The margin of safety provided by SQN's allowable containment leakage i rate test limits (0.75 L, for periodic Type A testing and 0.60 L, for Types B and C testing) remains unchanged. TVA's proposed change removes detailed requirements such as containment test requirements, < test schedules, and test accuracies from TSs.. These detailed requirements are governed by 10 CFR 50, Appendix J, and have not been - affected by TVA's proposed change. Individual leakage limits . i associated with SQN's containment air locks, purge valves, or secondary bypass leakage to the auxiliary building are site specific (not specifically part of the acceptance criteria of 10 CFR 50 Appendix J) and are_ retained in SQN TSs. All other proposed changes are clarifications and do not affect the intent of the affected specifications. Consequently, TVA's proposed change will not affect the margin of safety. l i i l l l 1}}