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{{#Wiki_filter:Document Control Desk | {{#Wiki_filter:Document Control Desk LR-N96291 LCR S95-02 SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT ISOLATION VALVES MARKED UP TECHNICAL SPECIFICATION PAGES The following Technical Specification for Facility Operating License Nos. DPR-70 and DPR-75 are affected by this License Change Request Unit 1 Unit 2 Technical Specification Page Page | ||
: 1. 0 3/4.6.1.1 3/4 | : 1. 0 1-2 1-2 3/4.6.1.1 3/4 6-1 3/4 6-1 3/4.6.1.2 3/4 6-2 3/4 6-2 3/4.6.3.1 3/4 6-12 3/4 6-14 3/4 6-13 3/4 6-15 3/4 6-14 3/4 6-16 3/4 6-14a 3/4 6-16a 3/4 6-15 3/4 6-17 3/4 6-16 3/4 6-18 3/4 6-17 3/4 6-19 B3/4.6.3 B3/4 6-3 B3/4 6-4 9610020056 6~86~~72 | ||
~DR ADOCK PDR | |||
pEEwiaea iR Taa:i.. :J i + eii specification | |||
DEFINITIONS 0 CONTAINMEN'r INTEGRITY | |||
1.8 NOT USED 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. | .f:c: 1.7 CONTAINMENT INTEGRITY shall exist when: | ||
DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The SALEM -UNIT l 1-2 Amendment | Q tJ 1.7.1 All penetrations required to be closed during accident conditions are either: | ||
: a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or | |||
: b. Closed by manual valves, blind flange*, or deactivated automatic valves secured in their closed po*itions, except......,_ | |||
APPLICABILITY: | pEEwiaea iR Taa:i.. :J i + eii specification 3. 6. 3 .1. | ||
MOOES 1, 2, 3 and 4. ACTtQ!fT' | 1.7.2 All equipment hatches are closed and sealed, 1.7.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3, 1.7.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.7.5 The sealing mechanism associated with each penetration (e.g;, | ||
* | welds, bellows or 0-rings) is OPERABLE. | ||
* Hf thout prim&ry CONTAINMOO restore CONTAINMENT ITY on' nour orb(; in at leut HOT STAN09Y ._,.;tr.in the ne::t 6 nours anc ff, tl'lf following | 1.8 NOT USED I | ||
.. . | 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. | ||
4.5.1.1 Prini&ry INTEGRITY shall bt demonstrated: | DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The SALEM - UNIT l 1-2 Amendment No.~ | ||
autcmatic isolation valves and required ta Q) -0 .... C' accident conditions are closed by valves, | |||
3/4.6 CONTAINMENT SYSi8'1S 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CO~TAINMEi~T IN'i"~GRITY shall be maintained. | |||
0 c .l q-:::> o b. By verifying that each containment air lock is OPERABLE per 3.6.1.3. *Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containmnet, and (3) locked, sealed, o;-otherilfise seelJred in the clo*sed position *. These penetrations shall b* verified closed at least once per 92 days. SALEM | APPLICABILITY: MOOES 1, 2, 3 and 4. | ||
* UNIT 1 3/4 6-1 CONTAINMENT SYSTEMS CONTAINMENT Lp.KAGE LIMITING CONDITION FOR OPERATION | ACTtQ!fT' * | ||
: 3. 6 .1. 2 Containment leakage rates shal.l be limited to: a. An overall integrated leakage rate of s La, 0.10 percent by weight of the containment air per 24 hours at design pressure, (47. o psig) . b. A combined leakage rate of s 0.60 La for all penetrations and valves subject to Type Band C tests | * 0 t.. Hf thout prim&ry CONTAINMOO INTE~ITY, restore CONTAINMENT rNTEG~ ITY | ||
MODES 1, 2, 3 and 4. ACTION.: With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types Band C tests exceeding 0.60 La, restore the leakage rate(s) to within the limit(s) prior-to increasing the Reactor Coolant System temperature above 200°F. SURVEILLANCE REQUIREMENTS 4.6.l.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR SO using the methods and provisions of ANSI N45.4-l972: | ...-0 +- ~itMri on' nour orb(; in at leut HOT STAN09Y ._,.;tr.in the ne::t 6 nours v <:: anc ff, C0tf1Sr~.IT(>('l-!~1'~11.hi1i tl'lf following ~.O:.ho1*r..~. | ||
c v | |||
~ | |||
CJ tl.- | |||
0 a) | |||
~ | |||
(.. f=. | |||
d *a | |||
~ SURVE!LLANCF. | |||
============================== | |||
REQUIR~i::?fiS . | |||
T: j_<- ~ 4.5.1.1 Prini&ry Cl.ir!TAIMH~T INTEGRITY shall bt demonstrated: | |||
d -r --0 | |||
-'. ~ ,, a. At ltast C"*nca 1:1e,.. 31 days by vtri f'yi ng that: | |||
1 1- c:: t.l | |||
*" ~ i::::. 1. All 1:1~netrationsv not ca?able of being closed by O?::RABLS v* ~ ~ con~irliK?nt autcmatic isolation valves and required ta ~e Q) -0 .... C' cl.or~~ d*.~,.incz accident conditions are closed by valves, | |||
~ r1tnq**~ or deactivated al!tomatic valves se<:tJred in | |||
~ _j ~ b11m1 A"I d 0 ~ thf.lir positions, except 11 ~~~iQe4 iA r1~l1 3.6 l ef | |||
~ '> 0.-. ........---++------~;- Sp~1ficat1on 3. 6. 3. 1., and | |||
~ | |||
'I.. -c (/\ 2. All *At'lui__,.t | |||
't ......... | |||
natches are closed and sealed. | |||
0 c .l q- :::> o b. By verifying that each containment air lock is OPERABLE per Spec1fic~tion 3.6.1.3. | |||
*Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containmnet, and (3) locked, sealed, o;- otherilfise seelJred in the clo*sed position *. These penetrations shall b* verified closed at least once per 92 days. | |||
SALEM | |||
* UNIT 1 3/4 6-1 | |||
CONTAINMENT SYSTEMS CONTAINMENT Lp.KAGE LIMITING CONDITION FOR OPERATION | |||
: 3. 6 .1. 2 Containment leakage rates shal.l be limited to: | |||
: a. An overall integrated leakage rate of s La, 0.10 percent by weight of the containment air per 24 hours at design pressure, (47. o psig) . | |||
: b. A combined leakage rate of s 0.60 La for all penetrations and valves subject to Type Band C tests ? jd rtifi £ iw ;able* ' ~. | |||
2 0 0 when pressurized to Pa. | |||
APPLICABILITY: MODES 1, 2, 3 and 4. | |||
ACTION.: | |||
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types Band C tests exceeding 0.60 La, restore the leakage rate(s) to within the limit(s) prior-to increasing the Reactor Coolant System temperature above 200°F. | |||
SURVEILLANCE REQUIREMENTS | |||
=*************************************************************2=2***ssa==~=*== | |||
4.6.l.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR SO using the methods and provisions of ANSI N45.4-l972: | |||
: a. Three Type A tests (Overall Integrated Containment Leakage Ratel shall be conducted at 40 +/- lO month intervals during shutdown at design pressure (47.0 psig) during each 10-year service period.*(**) | : a. Three Type A tests (Overall Integrated Containment Leakage Ratel shall be conducted at 40 +/- lO month intervals during shutdown at design pressure (47.0 psig) during each 10-year service period.*(**) | ||
The third test of each set shall be conducted during the shutdown for the lO-year plant inservice inspection. | The third test of each set shall be conducted during the shutdown for the lO-year plant inservice inspection. | ||
*The second inservice Integrated Leak Rate Test shall be performed at the fifth refueling outage, but no later than May, 1984. **The fifth inservice Integrated Leak Rate Test (the second inservice Integrated Leak Rate Test during the second lO-year plant inservice inspection interval) shall be performed during the thirteenth refueling outage, but no later than June 1997. SALEM -UNIT 1 3/4 6-2 Amendment | *The second inservice Integrated Leak Rate Test shall be performed at the fifth refueling outage, but no later than May, 1984. | ||
**The fifth inservice Integrated Leak Rate Test (the second inservice Integrated Leak Rate Test during the second lO-year plant inservice inspection interval) shall be performed during the thirteenth refueling outage, but no later than June 1997. | |||
SALEM - UNIT 1 3/4 6-2 Amendment No.~ | |||
~~INMENT i.\!fi '-YfiHff9iWM'"HIP sYSTEMS | |||
.. , 3.1.J.1 | 'J/~.i.J CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION .., | ||
*a.1*1. *. * | 3.1.J.1 ~4-~ntaiwMholatfon OPEIAILE w4tt&'hoJ1Uo11 tt~,-~ =~.M ti\ T~hl *a.1*1. *. | ||
MODES 1, z. J Ind 4. M:flON: . | ~LICAIILilY:* MODES 1, z. | ||
v11../!.1c1ff"' | |||
J Ind 4. | |||
... | *~ *' . *. | ||
iR l811e Shall bl dl90n1tr1t1d OPERABL.£ prior to "t.u'rning t.hl valve to 1*rvic1 after .. int1nanc1, "pair or 1"9p1ac ... nt work ts perfor-..d*on the valve or fts associated actuator, control or power ci1"'Cuit by performance of a cycling test and verification of i1011tion tfH. | TU!oeolr.. I '111111 be | ||
* Normally closed or manual containment isolation valves may be opened on an intermittent basis under administrative control. SAL.EM | . . ~G..11"\Me" G M:flON: | ||
* UNIT 1 Amendment | ~t.h one Of'*" of tne"'fsolation valv1(s) 1*1.14f41,**'fft TU~Q laG1'1*4nop*rat)1t, 91int.ain at 1111t one f1ol1tion valve OPERABLE in 11ch affected penetration I | ||
S":"S':'!MS St."'RVE!:.:..ANCE (Continued) | ~t 11 ~n and 1i~r: * | ||
Con i"Cl..1 nm e () I 4.6.3.1.: | : a. Resto" tM f noperao 11 va1ve(1) to OPERAll.£ status wi thf n ' hours , | ||
valve iR *aQle J.G l*shall be demonstrated during the COLD SHUTDOWN or MCCE at least once per 18 | or | ||
:::y: a. 'lerifying that on a Phase A containment isolation test s:.gnal, each ?hase A isolation valve actuates to its isolation pcs:.::.on. | : b. Isolate Heh affected penetration within 4 houn by &111 of at l111t one deactivated automatic valve secured fn tM i1ola~ion position, or | ||
: b. '/er:.fying | : c. Isolate each affected penetration within 4 hours by use of at l111t on* closed ..nual valve or blin4 flange; or | ||
:.hat on a Phase 3 containment isolati.on | : d. 81 in at least HOT STAHDIY within the nut 6 hours and in CCL.D SHUTDOWN within t.hl following 30 haul"I. | ||
:.est si.gnal. each ?hase 3 isolation | SURVEILLANCE REQUIREMENTS fc...c..h ccnta.'" (')le";- . | ||
*.ral*.re ac:uates t:.o it:.s isolat:.cn posi.::.on. | 4.6,3. 1. l~isolatiOft valYl~l ... lifil~ iR l811e Jal-~ Shall bl dl90n1tr1t1d OPERABL.£ prior to "t.u'rning t.hl valve to 1*rvic1 after .. int1nanc1, "pair or 1"9p1ac... nt work ts perfor-..d*on the valve or fts associated actuator, control or power ci1"'Cuit by performance of a cycling test and verification of i1011tion tfH. | ||
: c. Not Used. d. VerifT...ng that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates t:.o its isolation position. | * Normally closed or manual containment isolation valves may be opened on an intermittent basis under administrative control. | ||
: e. | SAL.EM | ||
:hat the Containment Pressure-Vacuum Relief Isolation valves are limited to :s 60° opening angle. 4.6.3.l.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve iR *aQla 4 i | * UNIT 1 Amendment No.~ | ||
:~N":"A:~ S":"S':'!MS e - | |||
St."'RVE!:.:..ANCE REQU!REME.~S (Continued) | |||
==========~=*================================================================= | |||
Con i"Cl..1 nm e () I 4.6.3.1.: Each~solation valve e~eeifia~ iR *aQle J.G l*shall be demonstrated | |||
:~ERAE:.E during the COLD SHUTDOWN or REFL"E:L:~G MCCE at least once per 18 | |||
:nonc~s :::y: | |||
: a. 'lerifying that on a Phase A containment isolation test s:.gnal, each ?hase A isolation valve actuates to its isolation pcs:.::.on. | |||
: b. '/er:.fying :.hat on a Phase 3 containment isolati.on :.est si.gnal. | |||
each ?hase 3 isolation *.ral*.re ac:uates t:.o it:.s isolat:.cn posi.::.on. | |||
: c. Not Used. | |||
: d. VerifT...ng that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates t:.o its isolation position. | |||
: e. Verifyi...~g :hat the Containment Pressure-Vacuum Relief Isolation valves are limited to :s 60° opening angle. | |||
4.6.3.l.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve ~**ifiea iR *aQla 4 i | |||
* actuates to its isolation position. | * actuates to its isolation position. | ||
4.6.3.l.4 The isolation time of each J 9 1 shall be determined to be Specification 4.0.5. | Co n-t~1nrnenT *so Jo.,,T1on 4.6.3.l.4 The isolation time of each power operated or automaticAvalv~ | ||
~aala J 9 1 shall be determined to be within its limit when tested pursuant to . | |||
for all other Type 8 and C the combined leakage rate is less than or equal to 0.60La. 4.6.3.1.6 A pressure drop test to identify excessive degradation of resilient val*1e seals shall be conducted on the: a. Containment Purge Supply and Exhaust Valves at least once per 6 months. b. Deleted. SALEM -'C.JN!T l 3/4 6-13 Amendment No. Y | Specification 4.0.5. | ||
4.6.3.1.5 Each containment purge isolation valve shall be demonstrated OPERABLE within 24 hours after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours, by verifying that when the measured leakage rate is added to the leakage races determined pursuant to Specification 4.6.l.2d. for all other Type 8 and C penetra~ions, the combined leakage rate is less than or equal to 0.60La. | |||
4.6.3.1.6 A pressure drop test to identify excessive degradation of resilient val*1e seals shall be conducted on the: | |||
: a. Containment Purge Supply and Exhaust !solatio~ Valves at least once per 6 months. | |||
: b. Deleted. | |||
SALEM - 'C.JN!T l 3/4 6-13 Amendment No. Y | |||
BASES 3/4.6.2 DEPRESSURIZATION ANO COOLING SYSTEMS 3/4.6.2.l CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses. | ":A3LE J.~-~ | ||
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized. | * CON'I'AI~~T ISOLATION VAL 1* | ||
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. | FlTN CT ION ISOLATION TI!'iE (S A. "A" ISOLATION | ||
These assumptions are sistent with the iodine removal efficiency assumed in the accident analyses. | : 1. Pressurizer Re~ief Tk. - Gas Analyzer .SlO Sec. | ||
: 2. l Pressurizer Relief Tk. - Gas Analyzer .SlO Sec. | |||
: 3. l Pressurizer Relief Tk. - N? Connectio .SlO Sec. | |||
: 4. l w'R Pressurizer Relief Tk. - Primary W er Conn. SlO Sec. | |||
: 5. l CV CVCS Letdown Line .SlO Sec. | |||
: 6. l CV 4 CVCS Letdown Line .SlO Sec. | |||
: 7. 1 CV 5 CS Letdown Line .SlO Sec. | |||
: 8. l CV 7 CV Letdown Line .SlO Sec. | |||
: 9. l CV 68 1111 eves Charging Line .SlO Sec. | |||
: 10. l CV 69 1111 CVCS harging Line SlO Sec. | |||
: 11. l CV 284 CVCS R Seals SlO Sec. | |||
: 12. 1 CV 116 eves RCP SlO Sec. | |||
: 13. 1 cc 215 Comp . Coolin SlO Sec. | |||
: 14. l cc 113 Comp. Cooling .SlO Sec. | |||
: 15. l WL 96* RC Drain Tk SlO Sec. | |||
: 16. 1 WL 97* RC SlO Sec. | |||
: 17. l WL 98* RC Dra* Tk. HO Sec. | |||
: 18. l WL 99* RC. D Tk. SlO Sec. | |||
: 19. 1 WL 108* RC tk. N., Connec SlO Sec. | |||
: 20. 1 WL 12* Tank.Pumps .SlO Sec. | |||
l WL 13* Drain Tank Pumps .SlO Sec. | |||
1 NT 32* Accumulator ~ Supply SlO Sec. | |||
1 SJ 123* SI Test Line 2 SlO Sec. | |||
l SJ 60* SI Test Line SlO Sec. | |||
1 SJ SI Test Line SlO Sec. | |||
1 s Accumulator Sampling SlO Sec.. | |||
1 s Accumulator Sampling SlO Sec. | |||
SS RC Sampling SlO Sec. | |||
SS RC Sampling 10 Sec. | |||
SALEH - UNIT 1 3/4 6-14 Amendment _No.~ | |||
VALVE NUMBER | |||
* TABLE 3.6-1 (Contd.~ | |||
CONTAINXENT ISOLATION VALVES FUNCTION PHASE "A" ISOLATION (Continued) | |||
: 30. SS Pressurizer Liquid Sampling ~10 Sec. | |||
: 31. s Pressurizer Llquid Sampling SlO Sec. | |||
: 32. s Pressurizer Steam Sampling SlO Sec. | |||
: 33. SS Pressurizer S~eam Sampling ~10 Sec. | |||
: 34. vc Containment Radiation Sampling HO Sec. | |||
: 35. 1 vc 8 Containment Radiation Sampling ~10 Sec. | |||
: 36. 1 VC 11 Containment Radiation Samplin SlO Sec. | |||
: 37. 1 VC 12 Containment Radiation Sampl" g ~10 Sec. | |||
: 38. 11 CA 330 nstrument Air Supply ~10 Sec. | |||
: 39. 12 CA 330 I trument Air Supply SlO Sec. | |||
: 40. 1 DR 29 Dem eralized Water S ply SlO Sec. | |||
: 41. 1 WL 16 ent Sump Di harge SlO Sec. | |||
: 42. 1 WL 17 nt Sump scharge SlO Sec. | |||
: 43. 1 FP 147* Fire Prot tion ystem SlO Sec. | |||
B. PHASE "B" ISOLATION | |||
: l. l cc 118 Compone SlO Sec. | |||
: 2. 1 cc 187 Compo nt SlO Sec. | |||
: 3. l cc 136 ComP, nent *SlO Sec. | |||
: 4. 1 cc 190 Co ponent SlO Sec. | |||
: s. l cc 131 SlO Sec. | |||
c. | |||
11 MS 711 Main Steam Drain Sec. | |||
12 MS 7 Main Steam Drain Sec. | |||
13 MS II Main Steam Drain Sec. | |||
14 711 Main Steam Drain Sec. | |||
l 1811 Main Steam Bypass Sec. | |||
2 MS 1811 Main Steam Bypass Sec. | |||
13 MS 1811 Main Steam Bypass 14 MS 1811 Main Steam Bypass SALEM - UNIT 1 3/4 6-l4a Amendment No.,, | |||
* TABLE 3.6-: *~cntinued) | |||
CONTAINMENT :scLAT:ON VAI.VES FUNCTION D. NOT :JSED E. STEAM GENERATOR ISOLATION | |||
: 1. 11 GB 4# slOSec. | |||
: 2. 12 GB 4# Steam slOSec. | |||
: 3. 13 GB 4# Steam slOSec. | |||
: 4. J.4 GB 4# Steam slOSec. | |||
: 5. 11 SS 94# SG slOSec. | |||
: 6. 12 SS 94# SG slOSec. | |||
: 7. 13 SS 94# SG slOSec. | |||
: a. 14 SS 94# slOSec. | |||
F. CONTAINMENT - VACUUM Purge Supply s2Sec. | |||
Purge Supply s2Sec. | |||
Purge Exhaust s2Sec. | |||
Purge Exhaust s2Sec. | |||
Pressure - Vacuum Relief s2Sec. | |||
Pressure - Vacuum Relief SALEM - UNIT 1 3 I 4 6 -*1s _,,dment No.¥ | |||
'<., 7A3:....E ;.iS-~ I:.:~:~., | |||
CONTAI~'ME..VI' rso~TION VA.ls FUNCTION G. | |||
: l. l s 90011 Pressurizer De&d-Weight Calibrator plicable | |||
: 2. l SS 111 Pressurizer Dead-Weight Calibrator Applicable J. ll CV 9 1 eves - RCP Se:-.ls ot Applicable | |||
: 4. 12 CV 9oll eves - RCP Seals Not Applicable S. 13 CV 9811 CVCS - RCP Seals Not Applicable | |||
: 6. 14 CV 9811 CVCS - RCP Seals Not Applicable | |||
: 7. 1 SJ 711# CS Flushin1 eonnaction Not Applicable | |||
: 8. 1 SA 118 C ressad Air Supply Not Applicable | |||
: 9. 1 WL 190 Ref lina Canal Supply Not Applicable | |||
: 10. 1 SF 36 Rafua n1 C&n&l Supply Not Applicable | |||
: 11. 1 WL 191 Refuali Canal Disc rg* Not Applicable | |||
: 12. 1 SF 22 Raf ualin1 l D h&r1* Not Applicable | |||
: 13. 1 Ve 9* | |||
* Containment d | |||
* tion Samplin1 Not Applicable | |||
: 14. 1 ve 10* Containment iation Samplin1 Not Applicable | |||
: 15. 1 ve 13* d tion Samplin1 Not Applicable | |||
: 16. 1 Ve 14* t Radia 'on Samplin1 Not Applicable | |||
: 17. II fer Tuba Not Applicable | |||
: 18. 1 cs 900 Instrumen tion Fill Conn. Not Applicable | |||
: 19. 1 cs 901 Instrument& on Fill Conn. Not Applicable | |||
: 20. 1 cs 902 Instrumentati Fill Conn. Not Applicable | |||
: 21. 1 cs 903 Containmant Instrumentation ill *conn. Not Applicable | |||
: 22. 1 SA 262 Containmant Pressure Test Co Not Applicable | |||
: 23. l SA 264 Containmant hessure Test Conn. Not Applicable | |||
: 24. 1 SA Containment Pre*sur* Test Conn. Not Applicable | |||
: 25. l s 267 Cont&inmant hessure Test Conn. Not Applicable | |||
: 26. 1 A 268 Cont&inmant hessure Test Conn. Not Applicable | |||
: 27. SA 270 Containment hessure Test Conn. ot Applicable | |||
* 1 CA 1714 Cont&imDant Air Lock I.nstrumuit Conn. Applicable 1 CA 1715 Cont&inmant Air Lock Instrumant Conn. Not pplicable | |||
/ | |||
SALEM - UNIT 1 3/4 6-16 Amandmant No.~ | |||
TABLE 3.6-l jContinuedl CONTAINME?~ ISOLATION VALVES FUNCTION ISOLATION TIME G. MANUAL | |||
: 30. l l SS Post LOCA Sampling plicable | |||
: 31. 11 SS 182* Post LOCA Sampl:ng plicable | |||
: 32. 11 SS 188* LOCA Sampling Applicable | |||
: 33. 11 SS 189* LOCA Applicable | |||
: 34. 13 SS 181* LOCA Applicable | |||
: 35. 13 SS 182* Not Applicable | |||
: 36. 13 SS 184* Not Applicable | |||
: 37. 13 SS 185* Post Not Applicable | |||
: 38. 11 VC 17* Post Not Applicable | |||
: 39. 11 VC 18* Post Not Applicable | |||
: 40. 11 VC 19* Post Not Applicable | |||
: 41. 11 SF 20* Post Not Applicable | |||
: 42. 12 VC 1 7* Post LOCA Not Applicable | |||
: 43. 12 VC 18* Post LOCA Not Applicable | |||
: 44. 12 vc 19* Post L'JCA Not Applicable | |||
: 45. 12 VC 20* Post LOCA Not Applicable | |||
: 46. 11 cs 2+ Containment Not Applicable | |||
: 47. 12 cs 2+ Containment Spra Not Applicable H. CHECK | |||
: 1. 1 CV 74 CVCS-Char ng Line Not Applicable | |||
: 2. 1 CV 296 CVCS-RCP Seals Not Applicable | |||
: 3. 1 cc 119 Compon nt Cooling t~ RCP Not Applical.le | |||
: 4. 1 cc 186 ent Cooling to RCP Not Applicable | |||
: s. 1 cc 208 anent Cooling to RCP Not Applicable | |||
: 6. llCS 48 C ntainment Spray Not Applicable | |||
: 7. 12CS 48 ontainment Spray Applicable | |||
: 8. 1 DR 30 Demineralized Water System Applicable | |||
: 9. l FP 14 8 Fire Protection System Applicable | |||
: 10. l NT 26 Pressurizer Relief Tk. - Nitrogen Conn. ~plicable | |||
: 11. l NT Accumulator Nitrogen Supply plicable | |||
: 12. l SA Compressed Air Supply Ap licable | |||
: 13. l WR Pressurizer Relief Tank - Primary App 'cable Water Conn. | |||
: 14. 360 Instrument Air Supply Not Applic le | |||
.15. 360 Instrument Air Supply Not Applicab 22# Main Feedwater Not Applicable 12BF 22# Main Feedwater Not Applicable 13BF 22# Main Feedwater Not Applicable | |||
: 19. 14BF 22# Main Feedwater Not Applicable | |||
* May be opened on an intermittent basis under administrative control. | |||
# Not subject to Type C leakage test3. | |||
## Either valve 1CV68 or 1CV69 must be OPERABLE. | |||
+ Normally closed motor operated containment isolation valve. Valves open on Phase B isolation. | |||
SALEM - UNIT 1 3/4 6-17 Amendment No .ft' | |||
CONiA!~ME~YSi:MS BASES 3/4.6.2 DEPRESSURIZATION ANO COOLING SYSTEMS 3/4.6.2.l CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses. | |||
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. These assumptions are c:n-sistent with the iodine removal efficiency assumed in the accident analyses. | |||
3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits .during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions. | 3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits .during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions. | ||
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. | 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radi:active material to the environment will be consistent with the assumptions used in the analyses for a LOCA. | ||
Containment isolation within the time limits specified ensures that the release of radi:active material to the environment will be consistent with the assumptions used in the analyses for a LOCA. / ISALE: | / | ||
(1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment. | ISALE: UNIT 1 B 3/4 6-3 The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that envir~mmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment. | ||
l(:-0. | |||
l(:-0. | |||
* | e e 1 | ||
-g~ | |||
c: -- | |||
::> ~ CEPINITIONS | |||
-0 QI 6.1 0-c: II\ | |||
*hall | CQNIAINMIH'l' nrrmin LJ CONTAINMJDn' INT!!GRin shall exist when: | ||
-+= | |||
{) . | |||
l 7 a.J 0 l.7.l "11 penetration* required to be cloaed during accident condition. | |||
. | t.. *re either: | ||
a' a. Capabl* of being clo**d by an OPIRASX.. containment automatic | |||
-+j ~ isolation valve syatem, or | |||
: | _c al | ||
+- +: b. Cloaed by manual valve*, blind flange*, or deactivated automatic valve* secured in their clo*ed po*ition*. except__...._ | |||
V\ d prgH*ded in T1ble l ' 1 ef Specification 3.5.3.l. | |||
~ t.. | |||
2i- 1.1.2 All equipment hatches *re cloaed ..nd ***led, d V\ | |||
~ c l.7.3 Each air lock is OPERABLB pur*U&nt to Specification 3.6.l.3, | |||
£ | |||
~ -0 ';>..,. l.7.4 The containment leakage rate* are within the limit* of | |||
'-ti d ...D Specification 3.6.l.2, and l.7.5 The sealing meeh&nism aaaoeiated with each penetration (e.g., | |||
welda, bellow* or o-ring*l i1 OPZRASX... | |||
: l. 8 NOT t1SEO CORI ALTERATION l.9 CORB ALTERATION shall be the movement or manipulation of any component within the reactor pr***ur* v****l with the v****l head removed and fuel in the vea1el. Su1pen9ion of CORS ALTKJtATIOH *hall not preclude completion o! | |||
movemen~ o! & component to a **!* con9ervative po*ition. | |||
DOSE EOtlIVU.M I* l l l l.lO DOSB EQUIVAI.EHT I-131 *hall be that concentration o! I-131 (microcurie* | |||
per gram) which alone would produce the sa.me thyroid do** ** the quantity and isotopic mixture o! I*lll, I-132, I*lll, I-134, and I-135 actually pre*ent. ~he SALEM - UNIT 2 l-2 Amendment No~ | |||
. \ | |||
3/4.6 CONTAINMENT SYSTEMS 3/4.6.l PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be main.tained. | |||
l -0 QI Cl1 APPLICABILITY: MODES l, 2, 3 and 4. | |||
-ot:: | |||
c: - ACTION: | |||
I :> t I\) ~ Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within | |||
£ ll-one hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. | |||
I ~"l I o d I SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be detllOnstrated: | |||
: 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 closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except H provided* iR TiQll 3,i-1 ef 1----=>- Speci fi cat i.on 3. 6. 3.1, and a 11 equipment hatches are closed and sealed. | |||
: b. By verifying that each containment air lock is OPERABLE per Specification 3.6.l.3. | |||
: c. After each closing of a penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at Pa (47 psig) and verifying that when the ..asured leakage rate for these seals is added to the leakage rates deteMlined pursuant to Specification 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to | |||
: 0. 60 La. | |||
*Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days. | |||
SALEM - UNIT 2 3/4 6-1 | |||
CONIAINMENI SYS~ | |||
CONIAINHENI LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage ;ates shall be limited to: | |||
: a. An overall integrated leakage rate of less than ~r equal to ta, 0.10 percent by weight of the containment air per 24 hours at design pressure (47.0 psig). | |||
: b. A combined leakage rate of less than or equal to 0.60 I.a for all penetrations and valves subject to Type B and C tests as identified in Table 3.6*1, when pressurized to Pa. | |||
APPLICABILITY: MODES l, 2, 3 and 4. | |||
ACTION: ( S") | |||
ontainment leakage rate G | |||
Coolant System temperature above SURVEILLANCE REQUIREMENTS 4.6.l.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: | |||
: a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 +/- 10 month intervals* during shutdown at design pressure (47.0 psig) during each 10-year service period. | |||
The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection. | |||
* The test interval for conducting a Type A test shall be extended from 40 +/- 10 months to allow the third Type A test, within the first 10-year service period, to be completed during the 10-year plant in-service inspection outage (6th refueling outage). This extension expires upon completion of the 6th refueling outage. | |||
SALEM | |||
* UNIT 2 3/4 6-2 Amendment No. 85 | |||
' *~ | |||
.e CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION Ga.ch _,.... | |||
3.6.3 ~containment isolation valve1.*£13eeifie8 iR Tasl~ ~.e-1 shall be OPERABLE wHR i&elatieR ti111es as SR8\/R lA Taele 3.e l. ~ | |||
APPLICABILITY: MODES 1, 2, 3 and 4. | |||
ACTION: | |||
c;o .... tQ.,1;Hoen t-With one or more of theAisolation valve(s) -s~eeifiea iR Taele ~-~-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either: | |||
: a. Restore the inoperable valve(s) to OPERABLE status within 4 hours, or | |||
: b. Isolate each affected penetration within 4 hours by use of at least one deactivated automatic valve secured in the isolation position, or | |||
: c. Isolate each affected penetration within 4 hours by use of at least one closed manual valve or blind flange; or | |||
: d. Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN* within the following 30 hours. | |||
SURVEILLANCE REQUIREMENTS | |||
.ea..e;,h <:..~.-;ta,. me,,*;- | |||
t) | |||
: 4. 6. 3. l ~isolation valvefspeeifiea iii. Taele 3.6 1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit.by performance of a cycling test and verification of isolation time. | |||
* Normally closed or manual containment isolation valves may be opened on an intermittent basis under administrative control. | |||
SALEM - UNIT 2 3/4 6-14 | |||
e CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) | |||
:azasa:a***mzz===z=====2z=~**s:aaz****======*=s==z=====zzs======*============= | |||
C"o n io..1 nm e fl -f- | |||
: 4. 6. 3. 2 EachAieolation valve sp&&kfkaa iA Ta.lilla l i 1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per lS*months by: | |||
: a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position. | |||
: b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position. | : b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position. | ||
: c. NOT USED d. Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position. | : c. NOT USED | ||
: e. Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to 60° opening angle. 4.6.3.3 At lea.at once per 18 months, verify that on a. isolation teat signal, ea.ch main steam valve | : d. Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position. | ||
/So /Q..+1of\ | : e. Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to ~ 60° opening angle. | ||
4.6.3.4 The isolation time of ea.ch power operated or automaticl-valve-e+- | 4.6.3.3 At lea.at once per 18 months, verify that on a. main steam isolation teat signal, ea.ch main steam i~ola.tion valve s~*~itiea iA Tagle 316 1 actuates to its isolation position. | ||
4ai l shall be determined to be within its limit when tested pursuant to Specification 4.0.5. 4.6.3.S Ea.ch containment purge isolation valve shall be demonstrated OPERABLE within 24 hours after ea.ch closing of the valve, except when the valve is being used for mult.iple cyclings, then at lea.st once per 72 hours, by verifying that when the measured leakage rate is added to th* leakage rates determined pursuant to Specification 4.6.l.2d. | Con-t~anmet'li- /So /Q..+1of\ | ||
for all other Type B and c penetrations, the combined leakage rate is less than or equal to 0.60La. 4.6.3.6 A pressure drop teat to identify excessive degradation of resilient valve seals shall be conducted on the: a. Containment Purge Supply and Exhaust Isolation at least once per 6 month*. b. Containment Pressure -Vacuum Relief Isolation Valves at least once per 3 month*. SALEM -UNIT 2 3/4 6-15 Amendment TABLE 3.6-1 CONTAINME.V! | 4.6.3.4 The isolation time of ea.ch power operated or automaticl-valve-e+- | ||
~~le 4ai l shall be determined to be within its limit when tested pursuant to Specification 4.0.5. | |||
: 1. 2 | 4.6.3.S Ea.ch containment purge isolation valve shall be demonstrated OPERABLE within 24 hours after ea.ch closing of the valve, except when the valve is being used for mult.iple cyclings, then at lea.st once per 72 hours, by verifying that when the measured leakage rate is added to th* | ||
* 2 CV 6 8 fl fl 10 . | leakage rates determined pursuant to Specification 4.6.l.2d. for all other Type B and c penetrations, the combined leakage rate is less than or equal to 0.60La. | ||
4.6.3.6 A pressure drop teat to identify excessive degradation of resilient valve seals shall be conducted on the: | |||
: a. Containment Purge Supply and Exhaust Isolation Valve~ at least once per 6 month*. | |||
: b. Containment Pressure - Vacuum Relief Isolation Valves at least once per 3 month*. | |||
SALEM - UNIT 2 3/4 6-15 Amendment No~ | |||
TABLE | |||
: | TABLE 3.6-1 CONTAINME.V! ISOLATION VALVE~ | ||
: | FUNCTION A. "A" ISOLATION | ||
: 1. 2 Pressurizer Relief Tk. - Gas Analyzer ~10 Sec. | |||
. | : 2. 2 PR Pressurizer Relief Tk. - Gas Analyzer ~10 Sec. | ||
* 2 CA 1715 | : 3. 2 NT 25 Pressurizer Relief Tk. - N Connectio ~10 Sec. | ||
Pressurizer Relief Tk. 2 | |||
- Primary W er Conn. ~10 Sec. | |||
' | : 4. 2 WR 80* | ||
: 5. 2 CV 3 - Letdown Line ~10 Sec. | |||
: 6. 2 CV 4 - Letdown Line ~10 Sec. | |||
: 7. 2 CV 5 - Letdown Line .SlO Sec. | |||
: 8. 2 CV 7 ~10 Sec. | |||
9* 2 CV 6 8 fl fl ~10 Sec. | |||
10 . 2 CV 6 9 f111 ~10 Sec. | |||
: 11. 2 CV 284 ~10 Sec. | |||
: 12. 2 CV 116 ~10 Sec. | |||
: 13. 2 cc 215 o Excess Letdown Hx ~10 Sec. | |||
: 14. 2 cc 113 to Excess Letdown Hx ~10 Sec. | |||
: 15. 2 WL 96* - Gas Analyzer Conn. ~10 Sec. | |||
: 16. 2 WL 97* s Analyzer Conn. ~10 Sec. | |||
: 17. 2 WL 98* - Ve Header Conn. ~10 Sec. | |||
: 18. 2 WL 99* - Vent eader Conn. ~10 Sec. | |||
: 19. 2 WL 108* - N Con ~10 Sec. | |||
2 ~10 Sec. | |||
: 20. 2 WL 12* Drain Tank Pumps | |||
: 21. 2 WL 13* Drain Tank Pumps ~10 Sec. | |||
: 22. 2 NT 32 Accumulator N Supply ~10 Sec. | |||
2 ~10 Sec. | |||
: 23. 2 SJ 3* SI Test Line | |||
: 24. 2 60* SI Test Line ~10 Sec. | |||
: 25. SJ 53* SI Test Line ~10 Sec. | |||
26 SS 103* Accumulator Sampling ~10 Sec. | |||
. 2 SS 27* Accumulator Sampling ~10 Sec. | |||
2 SS 104* RC Sampling ~10 Sec. | |||
2 SS 33* RC Sampling ~10 Sec. | |||
SALEM - UNIT 2 3/4 6-16 Amendment No. ~ | |||
TABLE 3. 6-1 (Contd. ) e CONTAINMENT ISOLATION VALVES FUNCTION A. "A" ISOLATION (Contd.) | |||
: 30. 2 107* Pressurizer Liquid Sampling SlO Sec. | |||
: 31. 2 SS 4 | |||
* Pressurizer Liquid Sampling SlO Sec. | |||
: 32. 2 SS 11 Pressurizer Steam Sampling SlO Sec. | |||
: 33. 2 SS 64* Pressurizer Steam Sampling SlO Sec. | |||
: 34. 2 vc 7 Containment Radiation Sampling SlO Sec. | |||
JS. 2 VC 8 Radiation Sampling SlO Sec. | |||
: 36. 2 vc 11 Radiation Samplin SlO Sec. | |||
37 . .., VC 12 Sampl. g SlO Sec. | |||
: 38. 21 CA 330 SlO Sec. | |||
: 39. 22 CA 330 SlO Sec. | |||
: 40. 2 DR 29 SlO Sec. | |||
: 41. 2 WL 16 SlO Sec. | |||
: 42. 2 WL 17 SlO Sec. | |||
: 43. 2 FP 147* SlO Sec. | |||
B. PHASE "B" ISOLATION | |||
: 1. 2 cc 118 Comp one Cooling SlO Sec. | |||
: 2. 2 cc 187 Compo nt Cooling SlO Sec. | |||
: 3. 2 cc 136 Com onent Cooling to SlO Sec. | |||
: 4. 2 cc 190 C ponent Cooling to SlO Sec. | |||
: 5. 2 cc 131 omponent Cooling to ~10 Sec. | |||
c. | |||
21 MS Main Steam Drain S~c. | |||
22 M Main Steam Drain Sec. | |||
23 s Main Steam Drain Sec. | |||
MS Main Steam Drain Sec. | |||
21 MS Main Steam Bypass Sec. | |||
22 MS Main Steam Bypass 23 MS Main Steam Bypass 24 MS Main Steam Bypass SALEM - UNIT 2 3/4 6-16a Amendment No. 67 | |||
TABLE 3.6-1 (Contd.) e CONTAINMENT ISOLATION VALVES NUMBER FUNCTION o. | |||
E. STEAM SLOWDOWN ISOLATION | |||
: 1. 21 GB 4# Blowdown - SlO Sec. | |||
: 2. 22 GB 4# SlO Sec. | |||
J. 23 GB 4# SlO Sec. | |||
: 4. 24 GB 4# SlO sec. | |||
: s. 21 SS 94# SlO Sec. | |||
: 6. 22 SS 94# SG SlO Sec. | |||
: 7. 23 SS 94# SG SlO Sec. | |||
: a. 24 SS 94# SG SlO Sec. | |||
P'. CONTAINMENT | |||
: 1. 2 vc l Purge Supply S2 Sec. | |||
: 2. 2 vc Purge Supply S2 sec. | |||
: 3. 2 Purge Exhau*t S2 sec., | |||
: 4. Purge Exhau*t Sec. | |||
: s. S* Pre1111ure - Vacuum Relief 6* Pressure - Vacuum Relief 3/4 6-17 Amendment Mo. 128 SALEM - UNIT 2 | |||
TABLE J.6-1 <Contd.) | |||
CONTAINMENT ISOLATION VALVES FUNCTION G. | |||
: l. Oil Pressurizer Dead-Weight Calibrator AP, icable | |||
: 2. 90 Pressurizer Dead-Weight Calibrator pplicable | |||
: 3. 21 9811 eves ~ RCP Seals Applicable | |||
: 4. 22 CV 9811 eves RCP Seals Applicable | |||
: 5. 23 CV 9811 CVCS - RCP Seals Applicable | |||
: 6. 24 CV 9811 CS - RCP Seals Not Applicable | |||
: 7. 2 SJ 7 ltl S Flushing Connection Not Applicable | |||
: 8. 2 SA 118 Comp essed Air Supply Not Applicable | |||
: 9. 2 WL 190 "Refue *ng Canal Supply Not Applicable | |||
: 10. 2 SF 36 Refueli Canal Supply Not Applicable | |||
: 11. 2.WL 191 Refueling anal Supply Not Applicable | |||
: 12. 2 SF 22 Refueling C l Supp Not Applicable | |||
: 13. 2 vc 9* Containment iat n Sampling Not Applicable | |||
: 14. 2 VC 10* Containment Rad tion Sampling Not Applicable | |||
: 15. 2 VC 13* ia *on Sampling Not Applicable | |||
: 16. 2 VC 14* Containment diati Sampling Not Applicable | |||
: 17. II far Tube Not Applicable | |||
: 18. 2 cs 900 Contai t Instrument& on Conn. Not Applicable | |||
: 19. 2 cs 901 Con inment Instrumentati Conn. Not Applicable | |||
: 20. 2 cs 902 C tainment Instrumentation Conn. Not Applicable | |||
: 21. 2 cs 903 ontainment Instrumentation Conn. Not Applicable | |||
: 22. 2 SA 262 Containment PTessure Te*t Conn. Not Applicable | |||
: 23. 2 SA 264 Containment Pressure Test Conn. Not Applicable | |||
: 24. 2 SA 265 Containment Prtssure Test Conn. Not Applicable | |||
: 25. 2 SA 2 Containment Pressura Test Conn. Not Applicable | |||
: 26. 2 s 68 Containment Pressure Test Conn. ot Applicable | |||
: 27. 2 "A 270 Containment Pressure Test Conn. N Applicable | |||
: 28. CA 1714 Containm'ent Airlock Instrument Conn. Not plicable | |||
* 2 | |||
* 2 CA 1715 Containment Airlock Instrument Conn. Not A licable SALEM - UNIT 2 3/4 6-18 Amendment No. 67 | |||
G. ~~~ :::ntd. .' | |||
: 30. :! l SS ~l" Post :.oCA Sampl'ng Applicable | |||
: 31. 21 SS 13':\ Post LOCA Sampling Applicable | |||
: 32. SS 188" Post ~OCA Sampling Not Applicable | |||
: 33. 21 SS Post LOCA Sampling Not Applicable | |||
: 34. 23 SS 181" Post LOCA Sampling Not Applicable | |||
: 35. 23 SS 182* LOCA Sampling Not Applicable | |||
: 36. 23 SS l84. LOCA S amp l ing Not Applicable | |||
: 37. 23 SS 135* LOCA Sampling Not Applicable 38 . .::: 1 ''- Sampl!ng Not Applicable | |||
: 39. :1 ~ | |||
.; '- * :l Sa!r.pl :..ng Not Applicable | |||
: 40. : l. ~:c :.9 .. ?est Sampl:..ng Not Applicable | |||
.., SF '"" | |||
: 41. .:. | |||
- '- ?ost Not Applicable 42. | |||
..*- ?est Applicable | |||
~ | |||
~lot 43 :2 ,.. :3* ?ost Not Applicable | |||
: 44. ..... | |||
'.., ~.ic .:. 9" ?est :.oc.:.. Not Appli.cable | |||
: 45. :2 *:c :a .. ?est Not Applicable | |||
: 46. .::: 1 :s .... Conc:ainment Not Applicable | |||
: 47. 22 :-s :::!+ Not Applicable H. CHECK | |||
: 1. ..,., C\" 74 Line Not Applicable | |||
., CV 296 Not Applicabl? | |||
3 . .. cc 119 Compo Cooling to RCP Not Applicable | |||
: 4. 2 cc l86 Comp nent Cocl:..ng ~o RCP Not Applicable | |||
: 5. 2 cc 2'.l8 Co anent Cooling to RCP Not Applicable | |||
: 6. .::: 1 cs 48 tainrnent Spray Not Applicable | |||
: 7. 22 cs 48 ontainrnent Spray Applicable | |||
: 8. ..., DR 30 Demineralized Water System Applicable | |||
: 9. 2 FP 14 8 Fire Protection System Applicable | |||
: 10. 2 NT 26 Pressurizer Relief Tk. - Nitrogen Applicable | |||
: 11. 2 NT 34 Accumulator Nitrogen Supply Applicable | |||
: 12. 2 SA Compressed Air Supply Applicable | |||
: 13. 2 WR Pressurizer Relief Tank - Primary plicable Water Conn. | |||
: 14. 360 Instrument Air Supply Not App cable | |||
: 15. 360 Instrument Air Supply Not Appli able | |||
: 16. BF 22# Main Feedwater Not Applica: le BF ..::........ | |||
..... Main Feedwater Not Applicab e 23 BF 2"' .. ..... Main Feedwater Not Applicable 24 BF 22# Main reedwater Not Applicable May be opened on an intermittent basis under administrative control. | |||
# Not subject to Type C leakage tests. | |||
## Either valve 2 CV 68 or 2 CV 6~ must be OPERABLE. | |||
~ Normally closed motor operated containment isolation valve. Valve opens on Phase B isolation. | |||
SAL.EM - UNIT 2 :!/4 6-19 Amendment No. 139 | |||
' (, .. | |||
CONTAINMENT SYSTEMS BASES 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation*within the time limits specifiea ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA. ~ | |||
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that tnis equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit is capable of con~rolling the expected hydrogen generation associated with 1) zirconium-water | |||
*reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentra-tions in Containment Following a LOCA, 11 March 1971. | |||
The opening of locked or sealed closed containment isolation valve~ on an intermittent basis under administrative control includes the following considerations: (1) stationing a dedicated individual, who is in ~nstan~ | |||
communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude acc~ss t~ ~lose the valves and that this ~ction will prevent the release of rad1oact1v1ty outside the containment. | |||
SALEM - UNIT 2 B 3/4 6-4 | |||
' Document Control Desk Attachment 4 LR-N96291 LCR S95-02 SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT ISOLATION VALVES TABLE This attachment provides the changes that have been identified to Technical Specification (TS) Table 3.6-1 as a result of the review of the Containment Penetrations. The information contained in this attachment will be relocated to the UFSAR as proposed in the License Change Request. The changes to the TS Table 3-6.1 are separated into three categories: | |||
The information contained in this attachment will be relocated to the UFSAR as proposed in the License Change Request. The changes to the TS Table 3-6.1 are separated into three categories: | |||
Valves Removed/Replaced Valves Corrected The list below provides the reasons for each of the changes that have been identified. | Valves Removed/Replaced Valves Corrected The list below provides the reasons for each of the changes that have been identified. | ||
Valves Removed/Replaced 11-14(21-24)CV98 | Valves Removed/Replaced 11-14(21-24)CV98 - eves - RCP seals These are manual throttle valves and are being replaced by 11-14(21-24)CV99 Check Valves. | ||
-eves -RCP seals These are manual throttle valves and are being replaced by 11-14(21-24)CV99 Check Valves. 1(2)SJ71 -CVCS Flushing Connection Valve has been removed from the system. Fuel Transfer Tube This is not a Containment Isolation Valve. 1(2)CS903 | 1(2)SJ71 - CVCS Flushing Connection Valve has been removed from the system. | ||
-Containment Radiation Sampling Valve is not within the penetration isolation valves. Valves Corrected 11(2l)VC20 | Fuel Transfer Tube This is not a Containment Isolation Valve. | ||
-Post LOCA Sampling Valve Valve designator changed previously designated as 11(2l)SF20 This change corrects typographical error from TS Amendment 92/67. 1(2)CV68 and 1(2)CV69 -Normal Charging to the RCS These valves are incorrectly identified as Phase A Isolation valves. These valves receive a Safety Injection Signal, but not a Phase A Isolation. | 1(2)CS903 - Containment Radiation Sampling Valve is not within the penetration isolation valves. | ||
These valves are correctly identified in the UFSAR Table as Safety Injection only.}} | Valves Corrected 11(2l)VC20 - Post LOCA Sampling Valve Valve designator changed previously designated as 11(2l)SF20 This change corrects typographical error from TS Amendment 92/67. | ||
1(2)CV68 and 1(2)CV69 - Normal Charging to the RCS These valves are incorrectly identified as Phase A Isolation valves. These valves receive a Safety Injection Signal, but not a Phase A Isolation. These valves are correctly identified in the UFSAR Table as Safety Injection only.}} |
Latest revision as of 04:27, 3 February 2020
ML18102A429 | |
Person / Time | |
---|---|
Site: | Salem |
Issue date: | 09/25/1996 |
From: | Public Service Enterprise Group |
To: | |
Shared Package | |
ML18102A428 | List: |
References | |
NUDOCS 9610020056 | |
Download: ML18102A429 (24) | |
Text
Document Control Desk LR-N96291 LCR S95-02 SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT ISOLATION VALVES MARKED UP TECHNICAL SPECIFICATION PAGES The following Technical Specification for Facility Operating License Nos. DPR-70 and DPR-75 are affected by this License Change Request Unit 1 Unit 2 Technical Specification Page Page
- 1. 0 1-2 1-2 3/4.6.1.1 3/4 6-1 3/4 6-1 3/4.6.1.2 3/4 6-2 3/4 6-2 3/4.6.3.1 3/4 6-12 3/4 6-14 3/4 6-13 3/4 6-15 3/4 6-14 3/4 6-16 3/4 6-14a 3/4 6-16a 3/4 6-15 3/4 6-17 3/4 6-16 3/4 6-18 3/4 6-17 3/4 6-19 B3/4.6.3 B3/4 6-3 B3/4 6-4 9610020056 6~86~~72
~DR ADOCK PDR
DEFINITIONS 0 CONTAINMEN'r INTEGRITY
.f:c: 1.7 CONTAINMENT INTEGRITY shall exist when:
Q tJ 1.7.1 All penetrations required to be closed during accident conditions are either:
- a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or
- b. Closed by manual valves, blind flange*, or deactivated automatic valves secured in their closed po*itions, except......,_
pEEwiaea iR Taa:i.. :J i + eii specification 3. 6. 3 .1.
1.7.2 All equipment hatches are closed and sealed, 1.7.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3, 1.7.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.7.5 The sealing mechanism associated with each penetration (e.g;,
welds, bellows or 0-rings) is OPERABLE.
1.8 NOT USED I
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.
DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The SALEM - UNIT l 1-2 Amendment No.~
3/4.6 CONTAINMENT SYSi8'1S 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CO~TAINMEi~T IN'i"~GRITY shall be maintained.
APPLICABILITY: MOOES 1, 2, 3 and 4.
ACTtQ!fT' *
- 0 t.. Hf thout prim&ry CONTAINMOO INTE~ITY, restore CONTAINMENT rNTEG~ ITY
...-0 +- ~itMri on' nour orb(; in at leut HOT STAN09Y ._,.;tr.in the ne::t 6 nours v <:: anc ff, C0tf1Sr~.IT(>('l-!~1'~11.hi1i tl'lf following ~.O:.ho1*r..~.
c v
~
CJ tl.-
0 a)
~
(.. f=.
d *a
~ SURVE!LLANCF.
==================
REQUIR~i::?fiS .
T: j_<- ~ 4.5.1.1 Prini&ry Cl.ir!TAIMH~T INTEGRITY shall bt demonstrated:
d -r --0
-'. ~ ,, a. At ltast C"*nca 1:1e,.. 31 days by vtri f'yi ng that:
1 1- c:: t.l
- " ~ i::::. 1. All 1:1~netrationsv not ca?able of being closed by O?::RABLS v* ~ ~ con~irliK?nt autcmatic isolation valves and required ta ~e Q) -0 .... C' cl.or~~ d*.~,.incz accident conditions are closed by valves,
~ r1tnq**~ or deactivated al!tomatic valves se<:tJred in
~ _j ~ b11m1 A"I d 0 ~ thf.lir positions, except 11 ~~~iQe4 iA r1~l1 3.6 l ef
~ '> 0.-. ........---++------~;- Sp~1ficat1on 3. 6. 3. 1., and
~
'I.. -c (/\ 2. All *At'lui__,.t
't .........
natches are closed and sealed.
0 c .l q- :::> o b. By verifying that each containment air lock is OPERABLE per Spec1fic~tion 3.6.1.3.
- Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containmnet, and (3) locked, sealed, o;- otherilfise seelJred in the clo*sed position *. These penetrations shall b* verified closed at least once per 92 days.
SALEM
- UNIT 1 3/4 6-1
CONTAINMENT SYSTEMS CONTAINMENT Lp.KAGE LIMITING CONDITION FOR OPERATION
- 3. 6 .1. 2 Containment leakage rates shal.l be limited to:
- a. An overall integrated leakage rate of s La, 0.10 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at design pressure, (47. o psig) .
- b. A combined leakage rate of s 0.60 La for all penetrations and valves subject to Type Band C tests ? jd rtifi £ iw ;able* ' ~.
2 0 0 when pressurized to Pa.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION.:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types Band C tests exceeding 0.60 La, restore the leakage rate(s) to within the limit(s) prior-to increasing the Reactor Coolant System temperature above 200°F.
SURVEILLANCE REQUIREMENTS
*************************************************************2=2***ssa==~=*=
4.6.l.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR SO using the methods and provisions of ANSI N45.4-l972:
- a. Three Type A tests (Overall Integrated Containment Leakage Ratel shall be conducted at 40 +/- lO month intervals during shutdown at design pressure (47.0 psig) during each 10-year service period.*(**)
The third test of each set shall be conducted during the shutdown for the lO-year plant inservice inspection.
- The second inservice Integrated Leak Rate Test shall be performed at the fifth refueling outage, but no later than May, 1984.
- The fifth inservice Integrated Leak Rate Test (the second inservice Integrated Leak Rate Test during the second lO-year plant inservice inspection interval) shall be performed during the thirteenth refueling outage, but no later than June 1997.
SALEM - UNIT 1 3/4 6-2 Amendment No.~
~~INMENT i.\!fi '-YfiHff9iWM'"HIP sYSTEMS
'J/~.i.J CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION ..,
3.1.J.1 ~4-~ntaiwMholatfon OPEIAILE w4tt&'hoJ1Uo11 tt~,-~ =~.M ti\ T~hl *a.1*1. *.
~LICAIILilY:* MODES 1, z.
v11../!.1c1ff"'
J Ind 4.
- ~ *' . *.
TU!oeolr.. I '111111 be
. . ~G..11"\Me" G M:flON:
~t.h one Of'*" of tne"'fsolation valv1(s) 1*1.14f41,**'fft TU~Q laG1'1*4nop*rat)1t, 91int.ain at 1111t one f1ol1tion valve OPERABLE in 11ch affected penetration I
~t 11 ~n and 1i~r: *
- a. Resto" tM f noperao 11 va1ve(1) to OPERAll.£ status wi thf n ' hours ,
or
- b. Isolate Heh affected penetration within 4 houn by &111 of at l111t one deactivated automatic valve secured fn tM i1ola~ion position, or
- c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at l111t on* closed ..nual valve or blin4 flange; or
- d. 81 in at least HOT STAHDIY within the nut 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CCL.D SHUTDOWN within t.hl following 30 haul"I.
SURVEILLANCE REQUIREMENTS fc...c..h ccnta.'" (')le";- .
4.6,3. 1. l~isolatiOft valYl~l ... lifil~ iR l811e Jal-~ Shall bl dl90n1tr1t1d OPERABL.£ prior to "t.u'rning t.hl valve to 1*rvic1 after .. int1nanc1, "pair or 1"9p1ac... nt work ts perfor-..d*on the valve or fts associated actuator, control or power ci1"'Cuit by performance of a cycling test and verification of i1011tion tfH.
- Normally closed or manual containment isolation valves may be opened on an intermittent basis under administrative control.
- UNIT 1 Amendment No.~
- ~N":"A:~ S":"S':'!MS e -
St."'RVE!:.:..ANCE REQU!REME.~S (Continued)
====~=*===========================================================
Con i"Cl..1 nm e () I 4.6.3.1.: Each~solation valve e~eeifia~ iR *aQle J.G l*shall be demonstrated
- ~ERAE:.E during the COLD SHUTDOWN or REFL"E:L:~G MCCE at least once per 18
- nonc~s :::y:
- a. 'lerifying that on a Phase A containment isolation test s:.gnal, each ?hase A isolation valve actuates to its isolation pcs:.::.on.
- b. '/er:.fying :.hat on a Phase 3 containment isolati.on :.est si.gnal.
each ?hase 3 isolation *.ral*.re ac:uates t:.o it:.s isolat:.cn posi.::.on.
- c. Not Used.
- d. VerifT...ng that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates t:.o its isolation position.
- e. Verifyi...~g :hat the Containment Pressure-Vacuum Relief Isolation valves are limited to :s 60° opening angle.
4.6.3.l.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve ~**ifiea iR *aQla 4 i
- actuates to its isolation position.
Co n-t~1nrnenT *so Jo.,,T1on 4.6.3.l.4 The isolation time of each power operated or automaticAvalv~
~aala J 9 1 shall be determined to be within its limit when tested pursuant to .
Specification 4.0.5.
4.6.3.1.5 Each containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to the leakage races determined pursuant to Specification 4.6.l.2d. for all other Type 8 and C penetra~ions, the combined leakage rate is less than or equal to 0.60La.
4.6.3.1.6 A pressure drop test to identify excessive degradation of resilient val*1e seals shall be conducted on the:
- a. Containment Purge Supply and Exhaust !solatio~ Valves at least once per 6 months.
- b. Deleted.
SALEM - 'C.JN!T l 3/4 6-13 Amendment No. Y
":A3LE J.~-~
- CON'I'AI~~T ISOLATION VAL 1*
FlTN CT ION ISOLATION TI!'iE (S A. "A" ISOLATION
- 1. Pressurizer Re~ief Tk. - Gas Analyzer .SlO Sec.
- 2. l Pressurizer Relief Tk. - Gas Analyzer .SlO Sec.
- 3. l Pressurizer Relief Tk. - N? Connectio .SlO Sec.
- 4. l w'R Pressurizer Relief Tk. - Primary W er Conn. SlO Sec.
- 5. l CV CVCS Letdown Line .SlO Sec.
- 6. l CV 4 CVCS Letdown Line .SlO Sec.
- 7. 1 CV 5 CS Letdown Line .SlO Sec.
- 8. l CV 7 CV Letdown Line .SlO Sec.
- 9. l CV 68 1111 eves Charging Line .SlO Sec.
- 10. l CV 69 1111 CVCS harging Line SlO Sec.
- 11. l CV 284 CVCS R Seals SlO Sec.
- 12. 1 CV 116 eves RCP SlO Sec.
- 13. 1 cc 215 Comp . Coolin SlO Sec.
- 14. l cc 113 Comp. Cooling .SlO Sec.
- 15. l WL 96* RC Drain Tk SlO Sec.
- 16. 1 WL 97* RC SlO Sec.
- 17. l WL 98* RC Dra* Tk. HO Sec.
- 18. l WL 99* RC. D Tk. SlO Sec.
- 19. 1 WL 108* RC tk. N., Connec SlO Sec.
- 20. 1 WL 12* Tank.Pumps .SlO Sec.
l WL 13* Drain Tank Pumps .SlO Sec.
1 NT 32* Accumulator ~ Supply SlO Sec.
1 SJ 123* SI Test Line 2 SlO Sec.
l SJ 60* SI Test Line SlO Sec.
1 SJ SI Test Line SlO Sec.
1 s Accumulator Sampling SlO Sec..
1 s Accumulator Sampling SlO Sec.
SS RC Sampling SlO Sec.
SS RC Sampling 10 Sec.
SALEH - UNIT 1 3/4 6-14 Amendment _No.~
VALVE NUMBER
- TABLE 3.6-1 (Contd.~
CONTAINXENT ISOLATION VALVES FUNCTION PHASE "A" ISOLATION (Continued)
- 30. SS Pressurizer Liquid Sampling ~10 Sec.
- 31. s Pressurizer Llquid Sampling SlO Sec.
- 32. s Pressurizer Steam Sampling SlO Sec.
- 33. SS Pressurizer S~eam Sampling ~10 Sec.
- 34. vc Containment Radiation Sampling HO Sec.
- 35. 1 vc 8 Containment Radiation Sampling ~10 Sec.
- 36. 1 VC 11 Containment Radiation Samplin SlO Sec.
- 37. 1 VC 12 Containment Radiation Sampl" g ~10 Sec.
- 38. 11 CA 330 nstrument Air Supply ~10 Sec.
- 39. 12 CA 330 I trument Air Supply SlO Sec.
- 40. 1 DR 29 Dem eralized Water S ply SlO Sec.
- 41. 1 WL 16 ent Sump Di harge SlO Sec.
- 42. 1 WL 17 nt Sump scharge SlO Sec.
- 43. 1 FP 147* Fire Prot tion ystem SlO Sec.
B. PHASE "B" ISOLATION
- l. l cc 118 Compone SlO Sec.
- 2. 1 cc 187 Compo nt SlO Sec.
- 3. l cc 136 ComP, nent *SlO Sec.
- 4. 1 cc 190 Co ponent SlO Sec.
- s. l cc 131 SlO Sec.
c.
11 MS 711 Main Steam Drain Sec.
12 MS 7 Main Steam Drain Sec.
13 MS II Main Steam Drain Sec.
14 711 Main Steam Drain Sec.
l 1811 Main Steam Bypass Sec.
2 MS 1811 Main Steam Bypass Sec.
13 MS 1811 Main Steam Bypass 14 MS 1811 Main Steam Bypass SALEM - UNIT 1 3/4 6-l4a Amendment No.,,
- TABLE 3.6-: *~cntinued)
CONTAINMENT :scLAT:ON VAI.VES FUNCTION D. NOT :JSED E. STEAM GENERATOR ISOLATION
- 1. 11 GB 4# slOSec.
- 2. 12 GB 4# Steam slOSec.
- 3. 13 GB 4# Steam slOSec.
- 4. J.4 GB 4# Steam slOSec.
- a. 14 SS 94# slOSec.
F. CONTAINMENT - VACUUM Purge Supply s2Sec.
Purge Supply s2Sec.
Purge Exhaust s2Sec.
Purge Exhaust s2Sec.
Pressure - Vacuum Relief s2Sec.
Pressure - Vacuum Relief SALEM - UNIT 1 3 I 4 6 -*1s _,,dment No.¥
'<., 7A3:....E ;.iS-~ I:.:~:~.,
CONTAI~'ME..VI' rso~TION VA.ls FUNCTION G.
- l. l s 90011 Pressurizer De&d-Weight Calibrator plicable
- 2. l SS 111 Pressurizer Dead-Weight Calibrator Applicable J. ll CV 9 1 eves - RCP Se:-.ls ot Applicable
- 7. 1 SJ 711# CS Flushin1 eonnaction Not Applicable
- 8. 1 SA 118 C ressad Air Supply Not Applicable
- 9. 1 WL 190 Ref lina Canal Supply Not Applicable
- 10. 1 SF 36 Rafua n1 C&n&l Supply Not Applicable
- 11. 1 WL 191 Refuali Canal Disc rg* Not Applicable
- 12. 1 SF 22 Raf ualin1 l D h&r1* Not Applicable
- 13. 1 Ve 9*
- Containment d
- tion Samplin1 Not Applicable
- 14. 1 ve 10* Containment iation Samplin1 Not Applicable
- 15. 1 ve 13* d tion Samplin1 Not Applicable
- 16. 1 Ve 14* t Radia 'on Samplin1 Not Applicable
- 17. II fer Tuba Not Applicable
- 18. 1 cs 900 Instrumen tion Fill Conn. Not Applicable
- 19. 1 cs 901 Instrument& on Fill Conn. Not Applicable
- 20. 1 cs 902 Instrumentati Fill Conn. Not Applicable
- 21. 1 cs 903 Containmant Instrumentation ill *conn. Not Applicable
- 22. 1 SA 262 Containmant Pressure Test Co Not Applicable
- 23. l SA 264 Containmant hessure Test Conn. Not Applicable
- 24. 1 SA Containment Pre*sur* Test Conn. Not Applicable
- 25. l s 267 Cont&inmant hessure Test Conn. Not Applicable
- 26. 1 A 268 Cont&inmant hessure Test Conn. Not Applicable
- 27. SA 270 Containment hessure Test Conn. ot Applicable
- 1 CA 1714 Cont&imDant Air Lock I.nstrumuit Conn. Applicable 1 CA 1715 Cont&inmant Air Lock Instrumant Conn. Not pplicable
/
SALEM - UNIT 1 3/4 6-16 Amandmant No.~
TABLE 3.6-l jContinuedl CONTAINME?~ ISOLATION VALVES FUNCTION ISOLATION TIME G. MANUAL
- 35. 13 SS 182* Not Applicable
- 36. 13 SS 184* Not Applicable
- 37. 13 SS 185* Post Not Applicable
- 38. 11 VC 17* Post Not Applicable
- 39. 11 VC 18* Post Not Applicable
- 40. 11 VC 19* Post Not Applicable
- 41. 11 SF 20* Post Not Applicable
- 44. 12 vc 19* Post L'JCA Not Applicable
- 46. 11 cs 2+ Containment Not Applicable
- 47. 12 cs 2+ Containment Spra Not Applicable H. CHECK
- 1. 1 CV 74 CVCS-Char ng Line Not Applicable
- 2. 1 CV 296 CVCS-RCP Seals Not Applicable
- 3. 1 cc 119 Compon nt Cooling t~ RCP Not Applical.le
- 4. 1 cc 186 ent Cooling to RCP Not Applicable
- s. 1 cc 208 anent Cooling to RCP Not Applicable
- 6. llCS 48 C ntainment Spray Not Applicable
- 7. 12CS 48 ontainment Spray Applicable
- 8. 1 DR 30 Demineralized Water System Applicable
- 9. l FP 14 8 Fire Protection System Applicable
- 10. l NT 26 Pressurizer Relief Tk. - Nitrogen Conn. ~plicable
- 11. l NT Accumulator Nitrogen Supply plicable
- 12. l SA Compressed Air Supply Ap licable
- 13. l WR Pressurizer Relief Tank - Primary App 'cable Water Conn.
- 14. 360 Instrument Air Supply Not Applic le
.15. 360 Instrument Air Supply Not Applicab 22# Main Feedwater Not Applicable 12BF 22# Main Feedwater Not Applicable 13BF 22# Main Feedwater Not Applicable
- 19. 14BF 22# Main Feedwater Not Applicable
- May be opened on an intermittent basis under administrative control.
- Not subject to Type C leakage test3.
- Either valve 1CV68 or 1CV69 must be OPERABLE.
+ Normally closed motor operated containment isolation valve. Valves open on Phase B isolation.
SALEM - UNIT 1 3/4 6-17 Amendment No .ft'
CONiA!~ME~YSi:MS BASES 3/4.6.2 DEPRESSURIZATION ANO COOLING SYSTEMS 3/4.6.2.l CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. These assumptions are c:n-sistent with the iodine removal efficiency assumed in the accident analyses.
3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits .during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radi:active material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
/
ISALE: UNIT 1 B 3/4 6-3 The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that envir~mmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
l(:-0.
e e 1
-g~
c: --
- > ~ CEPINITIONS
-0 QI 6.1 0-c: II\
CQNIAINMIH'l' nrrmin LJ CONTAINMJDn' INT!!GRin shall exist when:
-+=
{) .
l 7 a.J 0 l.7.l "11 penetration* required to be cloaed during accident condition.
t.. *re either:
a' a. Capabl* of being clo**d by an OPIRASX.. containment automatic
-+j ~ isolation valve syatem, or
_c al
+- +: b. Cloaed by manual valve*, blind flange*, or deactivated automatic valve* secured in their clo*ed po*ition*. except__...._
V\ d prgH*ded in T1ble l ' 1 ef Specification 3.5.3.l.
~ t..
2i- 1.1.2 All equipment hatches *re cloaed ..nd ***led, d V\
~ c l.7.3 Each air lock is OPERABLB pur*U&nt to Specification 3.6.l.3,
£
~ -0 ';>..,. l.7.4 The containment leakage rate* are within the limit* of
'-ti d ...D Specification 3.6.l.2, and l.7.5 The sealing meeh&nism aaaoeiated with each penetration (e.g.,
welda, bellow* or o-ring*l i1 OPZRASX...
- l. 8 NOT t1SEO CORI ALTERATION l.9 CORB ALTERATION shall be the movement or manipulation of any component within the reactor pr***ur* v****l with the v****l head removed and fuel in the vea1el. Su1pen9ion of CORS ALTKJtATIOH *hall not preclude completion o!
movemen~ o! & component to a **!* con9ervative po*ition.
DOSE EOtlIVU.M I* l l l l.lO DOSB EQUIVAI.EHT I-131 *hall be that concentration o! I-131 (microcurie*
per gram) which alone would produce the sa.me thyroid do** ** the quantity and isotopic mixture o! I*lll, I-132, I*lll, I-134, and I-135 actually pre*ent. ~he SALEM - UNIT 2 l-2 Amendment No~
. \
3/4.6 CONTAINMENT SYSTEMS 3/4.6.l PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be main.tained.
l -0 QI Cl1 APPLICABILITY: MODES l, 2, 3 and 4.
-ot::
c: - ACTION:
I :> t I\) ~ Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within
£ ll-one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I ~"l I o d I SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be detllOnstrated:
- 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 closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except H provided* iR TiQll 3,i-1 ef 1----=>- Speci fi cat i.on 3. 6. 3.1, and a 11 equipment hatches are closed and sealed.
- b. By verifying that each containment air lock is OPERABLE per Specification 3.6.l.3.
- c. After each closing of a penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at Pa (47 psig) and verifying that when the ..asured leakage rate for these seals is added to the leakage rates deteMlined pursuant to Specification 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to
- 0. 60 La.
- Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days.
SALEM - UNIT 2 3/4 6-1
CONIAINMENI SYS~
CONIAINHENI LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage ;ates shall be limited to:
- a. An overall integrated leakage rate of less than ~r equal to ta, 0.10 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at design pressure (47.0 psig).
- b. A combined leakage rate of less than or equal to 0.60 I.a for all penetrations and valves subject to Type B and C tests as identified in Table 3.6*1, when pressurized to Pa.
APPLICABILITY: MODES l, 2, 3 and 4.
ACTION: ( S")
ontainment leakage rate G
Coolant System temperature above SURVEILLANCE REQUIREMENTS 4.6.l.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 +/- 10 month intervals* during shutdown at design pressure (47.0 psig) during each 10-year service period.
The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
- The test interval for conducting a Type A test shall be extended from 40 +/- 10 months to allow the third Type A test, within the first 10-year service period, to be completed during the 10-year plant in-service inspection outage (6th refueling outage). This extension expires upon completion of the 6th refueling outage.
SALEM
- UNIT 2 3/4 6-2 Amendment No. 85
' *~
.e CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION Ga.ch _,....
3.6.3 ~containment isolation valve1.*£13eeifie8 iR Tasl~ ~.e-1 shall be OPERABLE wHR i&elatieR ti111es as SR8\/R lA Taele 3.e l. ~
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
c;o .... tQ.,1;Hoen t-With one or more of theAisolation valve(s) -s~eeifiea iR Taele ~-~-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:
- a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or
- c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or
- d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN* within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
.ea..e;,h <:..~.-;ta,. me,,*;-
t)
- 4. 6. 3. l ~isolation valvefspeeifiea iii. Taele 3.6 1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit.by performance of a cycling test and verification of isolation time.
- Normally closed or manual containment isolation valves may be opened on an intermittent basis under administrative control.
SALEM - UNIT 2 3/4 6-14
e CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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C"o n io..1 nm e fl -f-
- 4. 6. 3. 2 EachAieolation valve sp&&kfkaa iA Ta.lilla l i 1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per lS*months by:
- a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
- b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
- c. NOT USED
- d. Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.
- e. Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to ~ 60° opening angle.
4.6.3.3 At lea.at once per 18 months, verify that on a. main steam isolation teat signal, ea.ch main steam i~ola.tion valve s~*~itiea iA Tagle 316 1 actuates to its isolation position.
Con-t~anmet'li- /So /Q..+1of\
4.6.3.4 The isolation time of ea.ch power operated or automaticl-valve-e+-
~~le 4ai l shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.S Ea.ch containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ea.ch closing of the valve, except when the valve is being used for mult.iple cyclings, then at lea.st once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to th*
leakage rates determined pursuant to Specification 4.6.l.2d. for all other Type B and c penetrations, the combined leakage rate is less than or equal to 0.60La.
4.6.3.6 A pressure drop teat to identify excessive degradation of resilient valve seals shall be conducted on the:
- a. Containment Purge Supply and Exhaust Isolation Valve~ at least once per 6 month*.
- b. Containment Pressure - Vacuum Relief Isolation Valves at least once per 3 month*.
SALEM - UNIT 2 3/4 6-15 Amendment No~
TABLE 3.6-1 CONTAINME.V! ISOLATION VALVE~
FUNCTION A. "A" ISOLATION
- 1. 2 Pressurizer Relief Tk. - Gas Analyzer ~10 Sec.
- 2. 2 PR Pressurizer Relief Tk. - Gas Analyzer ~10 Sec.
- 3. 2 NT 25 Pressurizer Relief Tk. - N Connectio ~10 Sec.
Pressurizer Relief Tk. 2
- Primary W er Conn. ~10 Sec.
- 4. 2 WR 80*
- 5. 2 CV 3 - Letdown Line ~10 Sec.
- 6. 2 CV 4 - Letdown Line ~10 Sec.
- 7. 2 CV 5 - Letdown Line .SlO Sec.
- 8. 2 CV 7 ~10 Sec.
9* 2 CV 6 8 fl fl ~10 Sec.
10 . 2 CV 6 9 f111 ~10 Sec.
- 11. 2 CV 284 ~10 Sec.
- 12. 2 CV 116 ~10 Sec.
- 13. 2 cc 215 o Excess Letdown Hx ~10 Sec.
- 14. 2 cc 113 to Excess Letdown Hx ~10 Sec.
- 15. 2 WL 96* - Gas Analyzer Conn. ~10 Sec.
- 16. 2 WL 97* s Analyzer Conn. ~10 Sec.
- 17. 2 WL 98* - Ve Header Conn. ~10 Sec.
- 18. 2 WL 99* - Vent eader Conn. ~10 Sec.
- 19. 2 WL 108* - N Con ~10 Sec.
2 ~10 Sec.
- 20. 2 WL 12* Drain Tank Pumps
- 21. 2 WL 13* Drain Tank Pumps ~10 Sec.
- 22. 2 NT 32 Accumulator N Supply ~10 Sec.
2 ~10 Sec.
- 23. 2 SJ 3* SI Test Line
- 24. 2 60* SI Test Line ~10 Sec.
- 25. SJ 53* SI Test Line ~10 Sec.
26 SS 103* Accumulator Sampling ~10 Sec.
. 2 SS 27* Accumulator Sampling ~10 Sec.
2 SS 104* RC Sampling ~10 Sec.
2 SS 33* RC Sampling ~10 Sec.
SALEM - UNIT 2 3/4 6-16 Amendment No. ~
TABLE 3. 6-1 (Contd. ) e CONTAINMENT ISOLATION VALVES FUNCTION A. "A" ISOLATION (Contd.)
- 30. 2 107* Pressurizer Liquid Sampling SlO Sec.
- 31. 2 SS 4
- Pressurizer Liquid Sampling SlO Sec.
- 32. 2 SS 11 Pressurizer Steam Sampling SlO Sec.
- 33. 2 SS 64* Pressurizer Steam Sampling SlO Sec.
- 34. 2 vc 7 Containment Radiation Sampling SlO Sec.
JS. 2 VC 8 Radiation Sampling SlO Sec.
- 36. 2 vc 11 Radiation Samplin SlO Sec.
37 . .., VC 12 Sampl. g SlO Sec.
- 38. 21 CA 330 SlO Sec.
- 39. 22 CA 330 SlO Sec.
- 40. 2 DR 29 SlO Sec.
- 41. 2 WL 16 SlO Sec.
- 42. 2 WL 17 SlO Sec.
- 43. 2 FP 147* SlO Sec.
B. PHASE "B" ISOLATION
- 1. 2 cc 118 Comp one Cooling SlO Sec.
- 2. 2 cc 187 Compo nt Cooling SlO Sec.
- 3. 2 cc 136 Com onent Cooling to SlO Sec.
- 4. 2 cc 190 C ponent Cooling to SlO Sec.
- 5. 2 cc 131 omponent Cooling to ~10 Sec.
c.
21 MS Main Steam Drain S~c.
22 M Main Steam Drain Sec.
23 s Main Steam Drain Sec.
MS Main Steam Drain Sec.
21 MS Main Steam Bypass Sec.
22 MS Main Steam Bypass 23 MS Main Steam Bypass 24 MS Main Steam Bypass SALEM - UNIT 2 3/4 6-16a Amendment No. 67
TABLE 3.6-1 (Contd.) e CONTAINMENT ISOLATION VALVES NUMBER FUNCTION o.
E. STEAM SLOWDOWN ISOLATION
- 1. 21 GB 4# Blowdown - SlO Sec.
- 2. 22 GB 4# SlO Sec.
J. 23 GB 4# SlO Sec.
- 4. 24 GB 4# SlO sec.
- s. 21 SS 94# SlO Sec.
P'. CONTAINMENT
- 1. 2 vc l Purge Supply S2 Sec.
- 2. 2 vc Purge Supply S2 sec.
- 3. 2 Purge Exhau*t S2 sec.,
- 4. Purge Exhau*t Sec.
- s. S* Pre1111ure - Vacuum Relief 6* Pressure - Vacuum Relief 3/4 6-17 Amendment Mo. 128 SALEM - UNIT 2
TABLE J.6-1 <Contd.)
CONTAINMENT ISOLATION VALVES FUNCTION G.
- l. Oil Pressurizer Dead-Weight Calibrator AP, icable
- 2. 90 Pressurizer Dead-Weight Calibrator pplicable
- 3. 21 9811 eves ~ RCP Seals Applicable
- 4. 22 CV 9811 eves RCP Seals Applicable
- 7. 2 SJ 7 ltl S Flushing Connection Not Applicable
- 8. 2 SA 118 Comp essed Air Supply Not Applicable
- 9. 2 WL 190 "Refue *ng Canal Supply Not Applicable
- 10. 2 SF 36 Refueli Canal Supply Not Applicable
- 11. 2.WL 191 Refueling anal Supply Not Applicable
- 12. 2 SF 22 Refueling C l Supp Not Applicable
- 13. 2 vc 9* Containment iat n Sampling Not Applicable
- 14. 2 VC 10* Containment Rad tion Sampling Not Applicable
- 15. 2 VC 13* ia *on Sampling Not Applicable
- 16. 2 VC 14* Containment diati Sampling Not Applicable
- 17. II far Tube Not Applicable
- 18. 2 cs 900 Contai t Instrument& on Conn. Not Applicable
- 19. 2 cs 901 Con inment Instrumentati Conn. Not Applicable
- 20. 2 cs 902 C tainment Instrumentation Conn. Not Applicable
- 21. 2 cs 903 ontainment Instrumentation Conn. Not Applicable
- 22. 2 SA 262 Containment PTessure Te*t Conn. Not Applicable
- 23. 2 SA 264 Containment Pressure Test Conn. Not Applicable
- 24. 2 SA 265 Containment Prtssure Test Conn. Not Applicable
- 25. 2 SA 2 Containment Pressura Test Conn. Not Applicable
- 26. 2 s 68 Containment Pressure Test Conn. ot Applicable
- 27. 2 "A 270 Containment Pressure Test Conn. N Applicable
- 28. CA 1714 Containm'ent Airlock Instrument Conn. Not plicable
- 2
- 2 CA 1715 Containment Airlock Instrument Conn. Not A licable SALEM - UNIT 2 3/4 6-18 Amendment No. 67
G. ~~~ :::ntd. .'
- 30. :! l SS ~l" Post :.oCA Sampl'ng Applicable
- 32. SS 188" Post ~OCA Sampling Not Applicable
- 39. :1 ~
.; '- * :l Sa!r.pl :..ng Not Applicable
- 40. : l. ~:c :.9 .. ?est Sampl:..ng Not Applicable
.., SF '""
- 41. .:.
- '- ?ost Not Applicable 42.
..*- ?est Applicable
~
~lot 43 :2 ,.. :3* ?ost Not Applicable
- 44. .....
'.., ~.ic .:. 9" ?est :.oc.:.. Not Appli.cable
- 45. :2 *:c :a .. ?est Not Applicable
- 46. .::: 1 :s .... Conc:ainment Not Applicable
- 47. 22 :-s :::!+ Not Applicable H. CHECK
- 1. ..,., C\" 74 Line Not Applicable
., CV 296 Not Applicabl?
3 . .. cc 119 Compo Cooling to RCP Not Applicable
- 4. 2 cc l86 Comp nent Cocl:..ng ~o RCP Not Applicable
- 5. 2 cc 2'.l8 Co anent Cooling to RCP Not Applicable
- 6. .::: 1 cs 48 tainrnent Spray Not Applicable
- 7. 22 cs 48 ontainrnent Spray Applicable
- 8. ..., DR 30 Demineralized Water System Applicable
- 9. 2 FP 14 8 Fire Protection System Applicable
- 10. 2 NT 26 Pressurizer Relief Tk. - Nitrogen Applicable
- 11. 2 NT 34 Accumulator Nitrogen Supply Applicable
- 12. 2 SA Compressed Air Supply Applicable
- 13. 2 WR Pressurizer Relief Tank - Primary plicable Water Conn.
- 14. 360 Instrument Air Supply Not App cable
- 15. 360 Instrument Air Supply Not Appli able
- 16. BF 22# Main Feedwater Not Applica: le BF ..::........
..... Main Feedwater Not Applicab e 23 BF 2"' .. ..... Main Feedwater Not Applicable 24 BF 22# Main reedwater Not Applicable May be opened on an intermittent basis under administrative control.
- Not subject to Type C leakage tests.
- Either valve 2 CV 68 or 2 CV 6~ must be OPERABLE.
~ Normally closed motor operated containment isolation valve. Valve opens on Phase B isolation.
SAL.EM - UNIT 2 :!/4 6-19 Amendment No. 139
' (, ..
CONTAINMENT SYSTEMS BASES 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation*within the time limits specifiea ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA. ~
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that tnis equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit is capable of con~rolling the expected hydrogen generation associated with 1) zirconium-water
- reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentra-tions in Containment Following a LOCA, 11 March 1971.
The opening of locked or sealed closed containment isolation valve~ on an intermittent basis under administrative control includes the following considerations: (1) stationing a dedicated individual, who is in ~nstan~
communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude acc~ss t~ ~lose the valves and that this ~ction will prevent the release of rad1oact1v1ty outside the containment.
SALEM - UNIT 2 B 3/4 6-4
' Document Control Desk Attachment 4 LR-N96291 LCR S95-02 SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT ISOLATION VALVES TABLE This attachment provides the changes that have been identified to Technical Specification (TS) Table 3.6-1 as a result of the review of the Containment Penetrations. The information contained in this attachment will be relocated to the UFSAR as proposed in the License Change Request. The changes to the TS Table 3-6.1 are separated into three categories:
Valves Removed/Replaced Valves Corrected The list below provides the reasons for each of the changes that have been identified.
Valves Removed/Replaced 11-14(21-24)CV98 - eves - RCP seals These are manual throttle valves and are being replaced by 11-14(21-24)CV99 Check Valves.
1(2)SJ71 - CVCS Flushing Connection Valve has been removed from the system.
Fuel Transfer Tube This is not a Containment Isolation Valve.
1(2)CS903 - Containment Radiation Sampling Valve is not within the penetration isolation valves.
Valves Corrected 11(2l)VC20 - Post LOCA Sampling Valve Valve designator changed previously designated as 11(2l)SF20 This change corrects typographical error from TS Amendment 92/67.
1(2)CV68 and 1(2)CV69 - Normal Charging to the RCS These valves are incorrectly identified as Phase A Isolation valves. These valves receive a Safety Injection Signal, but not a Phase A Isolation. These valves are correctly identified in the UFSAR Table as Safety Injection only.