ML18102A429: Difference between revisions

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{{#Wiki_filter:Document Control Desk Attachment 3 SALEM GENERATING STATION LR-N96291 LCR S95-02 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 Technical Specification  
{{#Wiki_filter:Document Control Desk Attachment 3 SALEM GENERATING STATION LR-N96291 LCR S95-02 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 Technical Specification
: 1. 0 3/4.6.1.1 3/4.6.1.2 3/4.6.3.1 B3/4.6.3 ----9610020056 ADOCK PDR Unit 1 Page 1-2 3/4 6-1 3/4 6-2 3/4 6-12 3/4 6-13 3/4 6-14 3/4 6-14a 3/4 6-15 3/4 6-16 3/4 6-17 B3/4 6-3 Unit 2 Page 1-2 3/4 6-1 3/4 6-2 3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-16a 3/4 6-17 3/4 6-18 3/4 6-19 B3/4 6-4 0 .f: c: Q tJ
: 1. 0 3/4.6.1.1 3/4.6.1.2 3/4.6.3.1 B3/4.6.3 ----9610020056 ADOCK PDR Unit 1 Page 1-2 3/4 6-1 3/4 6-2 3/4 6-12 3/4 6-13 3/4 6-14 3/4 6-14a 3/4 6-15 3/4 6-16 3/4 6-17 B3/4 6-3 Unit 2 Page 1-2 3/4 6-1 3/4 6-2 3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-16a 3/4 6-17 3/4 6-18 3/4 6-19 B3/4 6-4 0 .f: c: Q tJ
* DEFINITIONS CONTAINMEN'r INTEGRITY  
* DEFINITIONS CONTAINMEN'r INTEGRITY  
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INTEGRITY shall exist when: 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......,_
INTEGRITY shall exist when: 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  
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.
: 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 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.
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.
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.. . -: SURVE!LLANCF. . ==============================
.. . -: SURVE!LLANCF. . ==============================
4.5.1.1 Prini&ry INTEGRITY shall bt demonstrated: . . 1-'. ,, a. At ltast C"*nca 1:1e,.. 31 days by vtri f'yi ng that: 1-c:: t.l *" i::::. 1. All not ca?able of being closed by O?::RABLS v*
4.5.1.1 Prini&ry INTEGRITY shall bt demonstrated: . . 1-'. ,, a. At ltast C"*nca 1:1e,.. 31 days by vtri f'yi ng that: 1-c:: t.l *" i::::. 1. All not ca?able of being closed by O?::RABLS v*
autcmatic isolation valves and required ta Q) -0 .... C' accident conditions are closed by valves, _j A"I 0 b11m1 or deactivated al!tomatic valves se<:tJred in d thf.lir positions, except 11 iA 3.6 l ef '> 0.-. ........  
autcmatic isolation valves and required ta Q) -0 .... C' accident conditions are closed by valves, _j A"I 0 b11m1 or deactivated al!tomatic valves se<:tJred in d thf.lir positions, except 11 iA 3.6 l ef '> 0.-. ........
: 3. 6. 3. 1., and -c 2. All At'lui__,.t natches are closed and sealed. 'I.. (/\ *'t .........
: 3. 6. 3. 1., and -c 2. All At'lui__,.t natches are closed and sealed. 'I.. (/\ *'t .........
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
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
* UNIT 1 3/4 6-1 CONTAINMENT SYSTEMS CONTAINMENT Lp.KAGE LIMITING CONDITION FOR OPERATION  
* 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 2? jd 0 rtifi 0&#xa3; iw ;able* ' when pressurized to Pa. APPLICABILITY:
: 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 2? jd 0 rtifi 0&#xa3; iw ;able* ' 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&deg;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:  
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&deg;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:
: 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.  
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S":"S':'!MS St."'RVE!:.:..ANCE (Continued)
S":"S':'!MS St."'RVE!:.:..ANCE (Continued)
Con i"Cl..1 nm e () I 4.6.3.1.:
Con i"Cl..1 nm e () I 4.6.3.1.:
valve iR *aQle J.G l*shall be demonstrated during the COLD SHUTDOWN or MCCE at least once per 18  
valve iR *aQle J.G l*shall be demonstrated during the COLD SHUTDOWN or MCCE at least once per 18
:::y: a. 'lerifying that on a Phase A containment isolation test s:.gnal, each ?hase A isolation valve actuates to its isolation pcs:.::.on.  
:::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  
: b. '/er:.fying
:.hat on a Phase 3 containment isolati.on  
:.hat on a Phase 3 containment isolati.on
:.est si.gnal. each ?hase 3 isolation  
:.est si.gnal. each ?hase 3 isolation  
*.ral*.re ac:uates t:.o it:.s isolat:.cn posi.::.on.  
*.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.  
: 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.  
: e.
:hat the Containment Pressure-Vacuum Relief Isolation valves are limited to :s 60&deg; 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
:hat the Containment Pressure-Vacuum Relief Isolation valves are limited to :s 60&deg; 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
* actuates to its isolation position.
* actuates to its isolation position.
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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   
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   
":A3LE
":A3LE
* ISOLATION VAL 1* Fl TN CT ION ISOLATION TI!'iE (S A. "A" ISOLATION  
* ISOLATION VAL 1* Fl TN CT ION ISOLATION TI!'iE (S A. "A" ISOLATION
: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. l l l w'R l CV l CV 4 1 CV 5 l CV 7 l CV 68 1111 l CV 69 1111 l CV 284 1 CV 116 1 cc 215 l cc 113 l WL 96* 1 WL 97* l WL 98* l WL 99* 1 WL 108* 1 WL 12* l WL 13* 1 NT 32* 1 SJ 123* l SJ 60* 1 SJ 1 s 1 s SS SS SALEH -UNIT 1 Pressurizer Tk. -Gas Analyzer Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -N? Connectio Pressurizer Relief Tk. -Primary W er Conn. CVCS Letdown Line CVCS Letdown Line CS Letdown Line CV Letdown Line eves Charging Line CVCS harging Line CVCS R Seals eves RCP Comp . Coolin Comp. Cooling RC Drain Tk RC RC Dra* RC. D RC Tk. Tk. tk. N., Connec Tank.Pumps Drain Tank Pumps Accumulator Supply SI Test Line SI Test Line SI Test Line Accumulator Sampling Accumulator Sampling RC Sampling RC Sampling .SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. .SlO Sec. SlO Sec. SlO Sec. HO Sec. SlO Sec. SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec .. SlO Sec. SlO Sec. 10 Sec. 3/4 6-14 Amendment
: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. l l l w'R l CV l CV 4 1 CV 5 l CV 7 l CV 68 1111 l CV 69 1111 l CV 284 1 CV 116 1 cc 215 l cc 113 l WL 96* 1 WL 97* l WL 98* l WL 99* 1 WL 108* 1 WL 12* l WL 13* 1 NT 32* 1 SJ 123* l SJ 60* 1 SJ 1 s 1 s SS SS SALEH -UNIT 1 Pressurizer Tk. -Gas Analyzer Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -N? Connectio Pressurizer Relief Tk. -Primary W er Conn. CVCS Letdown Line CVCS Letdown Line CS Letdown Line CV Letdown Line eves Charging Line CVCS harging Line CVCS R Seals eves RCP Comp . Coolin Comp. Cooling RC Drain Tk RC RC Dra* RC. D RC Tk. Tk. tk. N., Connec Tank.Pumps Drain Tank Pumps Accumulator Supply SI Test Line SI Test Line SI Test Line Accumulator Sampling Accumulator Sampling RC Sampling RC Sampling .SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. .SlO Sec. SlO Sec. SlO Sec. HO Sec. SlO Sec. SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec .. SlO Sec. SlO Sec. 10 Sec. 3/4 6-14 Amendment
* TABLE 3.6-1 CONTAINXENT ISOLATION VALVES VALVE NUMBER FUNCTION PHASE "A" ISOLATION (Continued)  
* TABLE 3.6-1 CONTAINXENT ISOLATION VALVES VALVE NUMBER FUNCTION PHASE "A" ISOLATION (Continued)
: 30. SS 31. s 32. s 33. SS 34. vc 35. 1 vc 8 36. 1 VC 11 37. 1 VC 12 38. 11 CA 330 39. 12 CA 330 40. 1 DR 29 41. 1 WL 16 42. 1 WL 17 43. 1 FP 147* Pressurizer Liquid Sampling Pressurizer Llquid Sampling Pressurizer Steam Sampling Pressurizer Sampling Containment Radiation Sampling Containment Radiation Sampling Containment Radiation Samplin Containment Radiation Sampl" g nstrument Air Supply I trument Air Supply Dem eralized Water S ply ent Sump Di harge nt Sump scharge Fire Prot tion ystem B. PHASE "B" ISOLATION  
: 30. SS 31. s 32. s 33. SS 34. vc 35. 1 vc 8 36. 1 VC 11 37. 1 VC 12 38. 11 CA 330 39. 12 CA 330 40. 1 DR 29 41. 1 WL 16 42. 1 WL 17 43. 1 FP 147* Pressurizer Liquid Sampling Pressurizer Llquid Sampling Pressurizer Steam Sampling Pressurizer Sampling Containment Radiation Sampling Containment Radiation Sampling Containment Radiation Samplin Containment Radiation Sampl" g nstrument Air Supply I trument Air Supply Dem eralized Water S ply ent Sump Di harge nt Sump scharge Fire Prot tion ystem B. PHASE "B" ISOLATION
: l. l cc 118 2. 1 cc 187 3. l cc 136 4. 1 cc 190 s. l cc 131 c. 11 MS 711 12 MS 7 13 MS II 14 711 l 1811 2 MS 1811 13 MS 1811 14 MS 1811 SALEM -UNIT 1 Compone Compo nt ComP, nent Co ponent Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Bypass Main Steam Bypass Main Steam Bypass Main Steam Bypass 3/4 6-l4a Sec. SlO Sec. SlO Sec. Sec. HO Sec. Sec. SlO Sec. Sec. Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. *SlO Sec. SlO Sec. SlO Sec. Sec. Sec. Sec. Sec. Sec. Sec. Amendment No.,,
: l. l cc 118 2. 1 cc 187 3. l cc 136 4. 1 cc 190 s. l cc 131 c. 11 MS 711 12 MS 7 13 MS II 14 711 l 1811 2 MS 1811 13 MS 1811 14 MS 1811 SALEM -UNIT 1 Compone Compo nt ComP, nent Co ponent Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Bypass Main Steam Bypass Main Steam Bypass Main Steam Bypass 3/4 6-l4a Sec. SlO Sec. SlO Sec. Sec. HO Sec. Sec. SlO Sec. Sec. Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. *SlO Sec. SlO Sec. SlO Sec. Sec. Sec. Sec. Sec. Sec. Sec. Amendment No.,,
* TABLE 3.6-:
* TABLE 3.6-:
CONTAINMENT  
CONTAINMENT
:scLAT:ON VAI.VES FUNCTION D. NOT :JSED E. STEAM GENERATOR ISOLATION  
: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  
: 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.&#xa5;   
-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.&#xa5;   
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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. / ISALE:-1 -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:  
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 -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 conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
(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.
l(:-0. " . c: --::> '--0 QI 6.1 0-c: II\ LJ {) . -a.J 0 t.. += a ' -+j _c al +-: + V\ d t.. 2i-d V\ c &#xa3; -0 ';>..,. '-ti d ...D e e CEPINITIONS CQNIAINMIH'l' nrrmin l 7 CONTAINMJDn' INT!!GRin shall exist when: l.7.l "11 penetration*
l(:-0. " . c: --::> '--0 QI 6.1 0-c: II\ LJ {) . -a.J 0 t.. += a ' -+j _c al +-: + V\ d t.. 2i-d V\ c &#xa3; -0 ';>..,. '-ti d ...D e e CEPINITIONS CQNIAINMIH'l' nrrmin l 7 CONTAINMJDn' INT!!GRin shall exist when: l.7.l "11 penetration*
Line 104: Line 104:
containment automatic isolation valve syatem, or b. Cloaed by manual valve*, blind flange*, or deactivated automatic valve* secured in their clo*ed po*ition*.
containment automatic isolation valve syatem, or b. Cloaed by manual valve*, blind flange*, or deactivated automatic valve* secured in their clo*ed po*ition*.
except__...._
except__...._
prgH*ded in T1ble l ' 1 ef Specification 3.5.3.l. 1.1.2 All equipment hatches *re cloaed ..nd ***led, l.7.3 Each air lock is OPERABLB pur*U&nt to Specification 3.6.l.3, l.7.4 The containment leakage rate* are within the limit* of 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...  
prgH*ded in T1ble l ' 1 ef Specification 3.5.3.l. 1.1.2 All equipment hatches *re cloaed ..nd ***led, l.7.3 Each air lock is OPERABLB pur*U&nt to Specification 3.6.l.3, l.7.4 The containment leakage rate* are within the limit* of 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  
: 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!
*hall not preclude completion o!
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. \ l -0 QI Cl1 -ot:: c: -I :> t I\) I &#xa3; ll-I o d I 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 -ot:: c: -I :> t I\) I &#xa3; ll-I o d I 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.
APPLICABILITY:
APPLICABILITY:
MODES l, 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 detllOnstrated:  
MODES l, 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 detllOnstrated:
: a. At least once per 31 days by verifying that all penetrations*
: 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*
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*
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These penetrations shall be verified closed at least once per 92 days. SALEM -UNIT 2 3/4 6-1 -------------------------
These penetrations shall be verified closed at least once per 92 days. SALEM -UNIT 2 3/4 6-1 -------------------------
CONIAINMENI 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 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:
CONIAINMENI 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 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 Coolant System temperature above SURVEILLANCE REQUIREMENTS G 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:  
MODES l, 2, 3 and 4. ACTION: ( S") ontainment leakage rate Coolant System temperature above SURVEILLANCE REQUIREMENTS G 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*
: 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.
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.
Line 127: Line 127:
within the following 30 hours. SURVEILLANCE REQUIREMENTS .ea..e;,h t) me,,*;-4. 6. 3. l 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.
within the following 30 hours. SURVEILLANCE REQUIREMENTS .ea..e;,h t) me,,*;-4. 6. 3. l 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)
* 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)
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.  
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 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&deg; 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 main steam iA Tagle 316 1 actuates to its isolation position.  
: e. Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to 60&deg; 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 main steam iA Tagle 316 1 actuates to its isolation position.  
/So /Q..+1of\
/So /Q..+1of\
Line 135: Line 135:
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.
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.
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!
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!
ISOLATION FUNCTION A. "A" ISOLATION  
ISOLATION FUNCTION A. "A" ISOLATION
: 1. 2 2. 2 PR 3. 2 NT 25 4. 2 WR 80* 5. 2 CV 3 6. 2 CV 4 7. 2 CV 5 8. 2 CV 7 9
: 1. 2 2. 2 PR 3. 2 NT 25 4. 2 WR 80* 5. 2 CV 3 6. 2 CV 4 7. 2 CV 5 8. 2 CV 7 9
* 2 CV 6 8 fl fl 10 . 2 CV 6 9 f 111 11. 2 CV 284 12. 2 CV 116 13. 2 cc 215 14. 2 cc 113 15. 2 WL 96* 16. 2 WL 97* 17. 2 WL 98* 18. 2 WL 99* 19. 2 WL 108* 20. 2 WL 12* 21. 2 WL 13* 22. 2 NT 32 23. 2 SJ 3* 24. 2 60* 25. SJ 53* 26 SS 103* . 2 SS 27* 2 SS 104* 2 SS 33* SALEM -UNIT 2 Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -N 2 Connectio Pressurizer Relief Tk. -Primary W er Conn. -Letdown Line -Letdown Line -Letdown Line o Excess Letdown Hx to Excess Letdown Hx -Gas Analyzer Conn. s Analyzer Conn. -Ve Header Conn. -Vent eader Conn. -N 2 Con Drain Tank Pumps Drain Tank Pumps Accumulator N 2 Supply SI Test Line SI Test Line SI Test Line Accumulator Sampling Accumulator Sampling RC Sampling RC Sampling Sec. Sec. Sec. Sec. Sec. Sec. .SlO Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. 3/4 6-16 Amendment No.
* 2 CV 6 8 fl fl 10 . 2 CV 6 9 f 111 11. 2 CV 284 12. 2 CV 116 13. 2 cc 215 14. 2 cc 113 15. 2 WL 96* 16. 2 WL 97* 17. 2 WL 98* 18. 2 WL 99* 19. 2 WL 108* 20. 2 WL 12* 21. 2 WL 13* 22. 2 NT 32 23. 2 SJ 3* 24. 2 60* 25. SJ 53* 26 SS 103* . 2 SS 27* 2 SS 104* 2 SS 33* SALEM -UNIT 2 Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -N 2 Connectio Pressurizer Relief Tk. -Primary W er Conn. -Letdown Line -Letdown Line -Letdown Line o Excess Letdown Hx to Excess Letdown Hx -Gas Analyzer Conn. s Analyzer Conn. -Ve Header Conn. -Vent eader Conn. -N 2 Con Drain Tank Pumps Drain Tank Pumps Accumulator N 2 Supply SI Test Line SI Test Line SI Test Line Accumulator Sampling Accumulator Sampling RC Sampling RC Sampling Sec. Sec. Sec. Sec. Sec. Sec. .SlO Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. 3/4 6-16 Amendment No.
TABLE 3. 6-1 (Contd. ) e CONTAINMENT ISOLATION VALVES FUNCTION A. "A" ISOLATION (Contd.) 30. 2 107* 31. 2 SS 4
TABLE 3. 6-1 (Contd. ) e CONTAINMENT ISOLATION VALVES FUNCTION A. "A" ISOLATION (Contd.) 30. 2 107* 31. 2 SS 4
* 32. 2 SS 11 33. 2 SS 64* 34. 2 vc 7 JS. 2 VC 8 36. 2 vc 11 37 . .., VC 12 38. 21 CA 330 39. 22 CA 330 40. 2 DR 29 41. 2 WL 16 42. 2 WL 17 43. 2 FP 147* Pressurizer Liquid Sampling Pressurizer Liquid Sampling Pressurizer Steam Sampling Pressurizer Steam Sampling Containment Radiation Sampling Radiation Sampling Radiation Samplin Sampl. g B. PHASE "B" ISOLATION  
* 32. 2 SS 11 33. 2 SS 64* 34. 2 vc 7 JS. 2 VC 8 36. 2 vc 11 37 . .., VC 12 38. 21 CA 330 39. 22 CA 330 40. 2 DR 29 41. 2 WL 16 42. 2 WL 17 43. 2 FP 147* Pressurizer Liquid Sampling Pressurizer Liquid Sampling Pressurizer Steam Sampling Pressurizer Steam Sampling Containment Radiation Sampling Radiation Sampling Radiation Samplin Sampl. g B. PHASE "B" ISOLATION
: 1. 2. 3. 4. 5. c. 2 cc 118 2 cc 187 2 cc 136 2 cc 190 2 cc 131 21 MS 22 M 23 s MS 21 MS 22 MS 23 MS 24 MS SALEM -UNIT 2 Comp one Compo nt Com onent C ponent omponent Cooling Cooling Cooling to Cooling to Cooling to Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Bypass Main Steam Bypass Main Steam Bypass Main Steam Bypass 3/4 6-16a SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO SlO SlO SlO Sec. Sec. Sec. Sec. Sec.
: 1. 2. 3. 4. 5. c. 2 cc 118 2 cc 187 2 cc 136 2 cc 190 2 cc 131 21 MS 22 M 23 s MS 21 MS 22 MS 23 MS 24 MS SALEM -UNIT 2 Comp one Compo nt Com onent C ponent omponent Cooling Cooling Cooling to Cooling to Cooling to Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Bypass Main Steam Bypass Main Steam Bypass Main Steam Bypass 3/4 6-16a SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO SlO SlO SlO Sec. Sec. Sec. Sec. Sec.
Sec. Sec. Sec. Sec. Amendment No. 67 : .
Sec. Sec. Sec. Sec. Amendment No. 67 : .
TABLE 3.6-1 (Contd.) e CONTAINMENT ISOLATION VALVES NUMBER FUNCTION o. E. STEAM SLOWDOWN ISOLATION  
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. 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  
: 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 SALEM -UNIT 2 3/4 6-17 Amendment Mo. 128   
-Vacuum Relief 6* Pressure -Vacuum Relief SALEM -UNIT 2 3/4 6-17 Amendment Mo. 128   
Line 164: Line 164:
Either recombiner unit is capable of the expected hydrogen generation associated with 1) zirconium-water  
Either recombiner unit is capable of the expected hydrogen generation associated with 1) zirconium-water  
*reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment.
*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 tions in Containment Following a LOCA, 11 March 1971. The opening of locked or sealed closed containment isolation on an intermittent basis under administrative control includes the following considerations:  
These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas tions in Containment Following a LOCA, 11 March 1971. The opening of locked or sealed closed containment isolation on an intermittent basis under administrative control includes the following considerations:
(1) stationing a dedicated individual, who is in 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 the valves and that this will prevent the release of rad1oact1v1ty outside the containment.
(1) stationing a dedicated individual, who is in 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 the valves and that this will prevent the release of rad1oact1v1ty outside the containment.
_. SALEM -UNIT 2 B 3/4 6-4   
_. SALEM -UNIT 2 B 3/4 6-4   

Revision as of 14:00, 25 April 2019

Proposed Tech Specs Re Containment Isolation Valves
ML18102A429
Person / Time
Site: Salem  PSEG icon.png
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 Attachment 3 SALEM GENERATING STATION LR-N96291 LCR S95-02 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 Technical Specification

1. 0 3/4.6.1.1 3/4.6.1.2 3/4.6.3.1 B3/4.6.3 ----9610020056 ADOCK PDR Unit 1 Page 1-2 3/4 6-1 3/4 6-2 3/4 6-12 3/4 6-13 3/4 6-14 3/4 6-14a 3/4 6-15 3/4 6-16 3/4 6-17 B3/4 6-3 Unit 2 Page 1-2 3/4 6-1 3/4 6-2 3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-16a 3/4 6-17 3/4 6-18 3/4 6-19 B3/4 6-4 0 .f: c: Q tJ
  • DEFINITIONS CONTAINMEN'r INTEGRITY

1.7 CONTAINMENT

INTEGRITY shall exist when: 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 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 I

,_ 0 t.. ...-0 v <:: c v CJ tl.-0 a) (.. f=. d *a T: j_<-d -r --0 3/4.6 CONTAINMENT SYSi8'1S 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION

  • 3.6.1.1 Primary shall be maintained.

APPLICABILITY:

MOOES 1, 2, 3 and 4. ACTtQ!fT'

  • 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

.. . -: SURVE!LLANCF. . ==============================

4.5.1.1 Prini&ry INTEGRITY shall bt demonstrated: . . 1-'. ,, a. At ltast C"*nca 1:1e,.. 31 days by vtri f'yi ng that: 1-c:: t.l *" i::::. 1. All not ca?able of being closed by O?::RABLS v*

autcmatic isolation valves and required ta Q) -0 .... C' accident conditions are closed by valves, _j A"I 0 b11m1 or deactivated al!tomatic valves se<:tJred in d thf.lir positions, except 11 iA 3.6 l ef '> 0.-. ........

3. 6. 3. 1., and -c 2. All At'lui__,.t natches are closed and sealed. 'I.. (/\ *'t .........

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

  • 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 2? jd 0 rtifi 0£ iw ;able* ' 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 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

sYSTEMS i.\!fi '-YfiHff9iWM'"HIP CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION

.. , 3.1.J.1 v11../!.1c1ff"' TU!oeolr .. I '111111 be OPEIAILE w4tt&'hoJ1Uo11 ti\

  • a.1*1. *. *' . * ..

MODES 1, z. J Ind 4. M:flON: ...

G one Of'*" of tne"'fsolation valv1(s) 1*1.14f41,**'fft laG1'1*4nop*rat)1t, I 91int.ain at 1111t one f1ol1tion valve OPERABLE in 11ch affected penetration 11 and

  • a. Resto" tM f noperao 11 va 1ve(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 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.

...

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.

  • Normally closed or manual containment isolation valves may be opened on an intermittent basis under administrative control. SAL.EM
  • UNIT 1 Amendment e -

S":"S':'!MS St."'RVE!:.:..ANCE (Continued)

Con i"Cl..1 nm e () I 4.6.3.1.:

valve iR *aQle J.G l*shall be demonstrated during the COLD SHUTDOWN or MCCE at least once per 18

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.
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
  • 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

  • so Jo.,, T1on power operated or within its limit when tested pursuant to . 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 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

":A3LE

  • ISOLATION VAL 1* Fl TN CT ION ISOLATION TI!'iE (S A. "A" ISOLATION
1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. l l l w'R l CV l CV 4 1 CV 5 l CV 7 l CV 68 1111 l CV 69 1111 l CV 284 1 CV 116 1 cc 215 l cc 113 l WL 96* 1 WL 97* l WL 98* l WL 99* 1 WL 108* 1 WL 12* l WL 13* 1 NT 32* 1 SJ 123* l SJ 60* 1 SJ 1 s 1 s SS SS SALEH -UNIT 1 Pressurizer Tk. -Gas Analyzer Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -N? Connectio Pressurizer Relief Tk. -Primary W er Conn. CVCS Letdown Line CVCS Letdown Line CS Letdown Line CV Letdown Line eves Charging Line CVCS harging Line CVCS R Seals eves RCP Comp . Coolin Comp. Cooling RC Drain Tk RC RC Dra* RC. D RC Tk. Tk. tk. N., Connec Tank.Pumps Drain Tank Pumps Accumulator Supply SI Test Line SI Test Line SI Test Line Accumulator Sampling Accumulator Sampling RC Sampling RC Sampling .SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. .SlO Sec. SlO Sec. SlO Sec. HO Sec. SlO Sec. SlO Sec. .SlO Sec. .SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec .. SlO Sec. SlO Sec. 10 Sec. 3/4 6-14 Amendment
  • TABLE 3.6-1 CONTAINXENT ISOLATION VALVES VALVE NUMBER FUNCTION PHASE "A" ISOLATION (Continued)
30. SS 31. s 32. s 33. SS 34. vc 35. 1 vc 8 36. 1 VC 11 37. 1 VC 12 38. 11 CA 330 39. 12 CA 330 40. 1 DR 29 41. 1 WL 16 42. 1 WL 17 43. 1 FP 147* Pressurizer Liquid Sampling Pressurizer Llquid Sampling Pressurizer Steam Sampling Pressurizer Sampling Containment Radiation Sampling Containment Radiation Sampling Containment Radiation Samplin Containment Radiation Sampl" g nstrument Air Supply I trument Air Supply Dem eralized Water S ply ent Sump Di harge nt Sump scharge Fire Prot tion ystem B. PHASE "B" ISOLATION
l. l cc 118 2. 1 cc 187 3. l cc 136 4. 1 cc 190 s. l cc 131 c. 11 MS 711 12 MS 7 13 MS II 14 711 l 1811 2 MS 1811 13 MS 1811 14 MS 1811 SALEM -UNIT 1 Compone Compo nt ComP, nent Co ponent Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Bypass Main Steam Bypass Main Steam Bypass Main Steam Bypass 3/4 6-l4a Sec. SlO Sec. SlO Sec. Sec. HO Sec. Sec. SlO Sec. Sec. Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. *SlO Sec. SlO Sec. SlO Sec. Sec. Sec. Sec. Sec. Sec. Sec. Amendment No.,,
  • TABLE 3.6-:

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.¥

'<., / G. l. l s 90011 2. l SS 111 J. ll CV 9 1 4. 12 CV 9oll S. 13 CV 9811 6. 14 CV 9811 7. 1 SJ 711# 8. 1 SA 118 9. 1 WL 190 10. 1 SF 36 11. 1 WL 191 12. 1 SF 22 13. 1 Ve 9* 14. 1 ve 10* 15. 1 ve 13* 16. 1 Ve 14* 17. II 18. 1 cs 900 19. 1 cs 901 20. 1 cs 902 21. 1 cs 903 22. 1 SA 262 23. l SA 264 24. 1 SA 25. l s 267 26. 1 A 268 27. SA 270

  • 1 CA 1714 1 CA 1715 SALEM -UNIT 1 7A3:....E VA.ls FUNCTION Pressurizer De&d-Weight Calibrator Pressurizer Dead-Weight Calibrator eves -RCP Se:-.ls eves -RCP Seals CVCS -RCP Seals CVCS -RCP Seals CS Flushin1 eonnaction C ressad Air Supply Ref lina Canal Supply Rafua n1 C&n&l Supply Refuali Canal Disc rg* Raf ualin1 l D h&r1*
  • Containment d
  • tion Samplin1 Containment iation Samplin1 d tion Samplin1 t Radia 'on Samplin1 fer Tuba Instrumen tion Fill Conn. Instrument&

on Fill Conn. Instrumentati Fill Conn. Containmant Instrumentation ill *conn. Containmant Pressure Test Co Containmant hessure Test Conn. Containment Pre*sur* Test Conn. Cont&inmant hessure Test Conn. Cont&inmant hessure Test Conn. Containment hessure Test Conn. Cont&imDant Air Lock I.nstrumuit Conn. Cont&inmant Air Lock Instrumant Conn. plicable Applicable ot Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable ot Applicable Applicable Not pplicable 3/4 6-16 Amandmant G. MANUAL 30. ll SS 31. 11 SS 182* 32. 11 SS 188* 33. 11 SS 189* 34. 13 SS 181* 35. 13 SS 182* 36. 13 SS 184* 37. 13 SS 185* 38. 11 VC 17* 39. 11 VC 18* 40. 11 VC 19* 41. 11 SF 20* 42. 12 VC 1 7* 43. 12 VC 18* 44. 12 vc 19* 45. 12 VC 20* 46. 11 cs 2+ 47. 12 cs 2+ H. CHECK 1. 1 CV 2. 1 CV 3. 1 cc 4. 1 cc s. 1 cc 6. llCS 7. 12CS 8. 1 DR 9. l FP 10. l NT 11. l NT 12. l SA 13. l WR 74 296 119 186 208 48 48 30 14 8 26 14. 360 .15. 360 22# 12BF 22# 13BF 22# 19. 14BF 22# TABLE 3.6-l jContinuedl ISOLATION VALVES FUNCTION ISOLATION TIME Post LOCA Sampling Post LOCA Sampl:ng LOCA Sampling LOCA Post Post Post Post Post LOCA Post LOCA Post LOCA Post L'JCA Post LOCA Containment Containment Spra CVCS-Char ng Line CVCS-RCP Seals Compon nt Cooling RCP ent Cooling to RCP anent Cooling to RCP C ntainment Spray ontainment Spray Demineralized Water System Fire Protection System Pressurizer Relief Tk. -Nitrogen Conn. Accumulator Nitrogen Supply Compressed Air Supply Pressurizer Relief Tank -Primary Water Conn. Instrument Air Supply Instrument Air Supply Main Feedwater Main Feedwater Main Feedwater Main Feedwater plicable plicable Applicable Applicable Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applical.le Not Applicable Not Applicable Not Applicable Applicable Applicable Applicable plicable Ap licable App 'cable Not Applic le Not Applicab Not Applicable Not Applicable Not Applicable 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'

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.

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 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:-1 -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 conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

l(:-0. " . c: --::> '--0 QI 6.1 0-c: II\ LJ {) . -a.J 0 t.. += a ' -+j _c al +-: + V\ d t.. 2i-d V\ c £ -0 ';>..,. '-ti d ...D e e CEPINITIONS CQNIAINMIH'l' nrrmin l 7 CONTAINMJDn' INT!!GRin shall exist when: l.7.l "11 penetration*

required to be cloaed during accident condition.

  • re either: a. Capabl* of being clo**d by an OPIRASX..

containment automatic isolation valve syatem, or b. Cloaed by manual valve*, blind flange*, or deactivated automatic valve* secured in their clo*ed po*ition*.

except__...._

prgH*ded in T1ble l ' 1 ef Specification 3.5.3.l. 1.1.2 All equipment hatches *re cloaed ..nd ***led, l.7.3 Each air lock is OPERABLB pur*U&nt to Specification 3.6.l.3, l.7.4 The containment leakage rate* are within the limit* of 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!

o! & component to a **!* con9ervative po*ition.

DOSE EOtlIVU.M I* lll 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. SALEM -UNIT 2 l-2 Amendment 1

. \ l -0 QI Cl1 -ot:: c: -I :> t I\) I £ ll-I o d I 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.

APPLICABILITY:

MODES l, 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 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 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 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 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 Coolant System temperature above SURVEILLANCE REQUIREMENTS G 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 isolation valve1.*£13eeifie8 iR 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) iR Taele 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 t) me,,*;-4. 6. 3. l 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)

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. isolation teat signal, ea.ch main steam valve main steam iA Tagle 316 1 actuates to its isolation position.

/So /Q..+1of\

4.6.3.4 The isolation time of ea.ch power operated or automaticl-valve-e+-

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 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!

ISOLATION FUNCTION A. "A" ISOLATION

1. 2 2. 2 PR 3. 2 NT 25 4. 2 WR 80* 5. 2 CV 3 6. 2 CV 4 7. 2 CV 5 8. 2 CV 7 9
  • 2 CV 6 8 fl fl 10 . 2 CV 6 9 f 111 11. 2 CV 284 12. 2 CV 116 13. 2 cc 215 14. 2 cc 113 15. 2 WL 96* 16. 2 WL 97* 17. 2 WL 98* 18. 2 WL 99* 19. 2 WL 108* 20. 2 WL 12* 21. 2 WL 13* 22. 2 NT 32 23. 2 SJ 3* 24. 2 60* 25. SJ 53* 26 SS 103* . 2 SS 27* 2 SS 104* 2 SS 33* SALEM -UNIT 2 Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -Gas Analyzer Pressurizer Relief Tk. -N 2 Connectio Pressurizer Relief Tk. -Primary W er Conn. -Letdown Line -Letdown Line -Letdown Line o Excess Letdown Hx to Excess Letdown Hx -Gas Analyzer Conn. s Analyzer Conn. -Ve Header Conn. -Vent eader Conn. -N 2 Con Drain Tank Pumps Drain Tank Pumps Accumulator N 2 Supply SI Test Line SI Test Line SI Test Line Accumulator Sampling Accumulator Sampling RC Sampling RC Sampling Sec. Sec. Sec. Sec. Sec. Sec. .SlO Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. Sec. 3/4 6-16 Amendment No.

TABLE 3. 6-1 (Contd. ) e CONTAINMENT ISOLATION VALVES FUNCTION A. "A" ISOLATION (Contd.) 30. 2 107* 31. 2 SS 4

  • 32. 2 SS 11 33. 2 SS 64* 34. 2 vc 7 JS. 2 VC 8 36. 2 vc 11 37 . .., VC 12 38. 21 CA 330 39. 22 CA 330 40. 2 DR 29 41. 2 WL 16 42. 2 WL 17 43. 2 FP 147* Pressurizer Liquid Sampling Pressurizer Liquid Sampling Pressurizer Steam Sampling Pressurizer Steam Sampling Containment Radiation Sampling Radiation Sampling Radiation Samplin Sampl. g B. PHASE "B" ISOLATION
1. 2. 3. 4. 5. c. 2 cc 118 2 cc 187 2 cc 136 2 cc 190 2 cc 131 21 MS 22 M 23 s MS 21 MS 22 MS 23 MS 24 MS SALEM -UNIT 2 Comp one Compo nt Com onent C ponent omponent Cooling Cooling Cooling to Cooling to Cooling to Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Drain Main Steam Bypass Main Steam Bypass Main Steam Bypass Main Steam Bypass 3/4 6-16a SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO Sec. SlO SlO SlO SlO Sec. Sec. Sec. Sec. Sec.

Sec. Sec. Sec. Sec. 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 SALEM -UNIT 2 3/4 6-17 Amendment Mo. 128

. "* G. l. Oil 2. 90 3. 21 9811 4. 22 CV 9811 5. 23 CV 9811 6. 24 CV 9811 7. 2 SJ 7 ltl 8. 2 SA 118 9. 2 WL 190 10. 2 SF 36 11. 2.WL 191 12. 2 SF 22 13. 2 vc 9* 14. 2 VC 10* 15. 2 VC 13* 16. 2 VC 14* 17. II 18. 2 cs 900 19. 2 cs 901 20. 2 cs 902 21. 2 cs 903 22. 2 SA 262 23. 2 SA 264 24. 2 SA 265 25. 2 SA 2 26. 2 s 68 27. 2 "A 270 28. CA 1714 2

  • 2 CA 1715 SALEM -UNIT 2 TABLE J.6-1 <Contd.) CONTAINMENT ISOLATION VALVES FUNCTION Pressurizer Dead-Weight Calibrator Pressurizer Dead-Weight Calibrator eves RCP Seals eves RCP Seals CVCS -RCP Seals CS -RCP Seals S Flushing Connection Comp essed Air Supply "Refue *ng Canal Supply Refueli Canal Supply Refueling anal Supply Refueling C l Supp Containment iat n Sampling Containment Rad tion Sampling ia *on Sampling Containment diati Sampling far Tube Contai t Instrument&

on Con inment Instrumentati C tainment Instrumentation Conn. Conn. Conn. Conn. ontainment Instrumentation Containment PTessure Te*t Conn. Containment Pressure Test Conn. Containment Prtssure Test Conn. Containment Pressura Test Conn. Containment Pressure Test Conn. Containment Pressure Test Conn. Containm'ent Airlock Instrument Conn. Containment Airlock Instrument Conn. AP, icable pplicable Applicable Applicable Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable ot Applicable N Applicable Not plicable

  • Not A licable 3/4 6-18 Amendment No. 67

' G. :::ntd. 30. :! l SS 31. 21 SS 13':\ 32. ..,. ...... SS 188" 33. 21 SS 34. 23 SS 181" 35. 23 SS 182* 36. 23 SS l84. 37. 23 SS 135* 38 . .::: 1 ,.,.. -: ..... 39. :1 .,,.... .; '-. '* * :l 40. : l. :.9 .. 41. .., . SF '"" .:. . -'-42. ..,.., _ .. ..,... *-...... 43 :2 .. ,.. :3* 44. '..,

.:. 9" ..... 45. :2 *:c :a .. 46. .::: 1 :s .... 47. 22 :-s :::!+ H. CHECK 1. ., C\" 74 .. ., ., CV 296 ... .. 3 . .., cc 119 .. 4. 2 cc l86 5. 2 cc 2'.l8 6. .::: 1 cs 48 7. 22 cs 48 8. .., DR 30 .. 9. 2 FP 14 8 10. 2 NT 26 11. 2 NT 34 12. 2 SA 13. 2 WR 14. 360 15. 360 16. BF 22# BF ........ ..:: ..... 23 BF 2"' .. ..... 24 BF 22# .' Post :.oCA Sampl'ng Post LOCA Sampling Post Sampling Post LOCA Sampling Post LOCA Sampling LOCA Sampling LOCA S amp l ing LOCA Sampling Sampl!ng Sa!r.pl :..ng ?est Sampl:..ng

?ost ?est ?ost ?est :.oc.:.. ?est Conc:ainment Line Compo Cooling to RCP Comp nent Cocl:..ng RCP Co anent Cooling to RCP tainrnent Spray ontainrnent Spray Demineralized Water System Fire Protection System Pressurizer Relief Tk. -Nitrogen Accumulator Nitrogen Supply Compressed Air Supply Pressurizer Relief Tank -Primary Water Conn. Instrument Air Supply Instrument Air Supply Main Feedwater Main Feedwater Main Feedwater Main reedwater Applicable Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Applicable Not Applicable Not Appli.cable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicabl?

Not Applicable Not Applicable Not Applicable Not Applicable Applicable Applicable

Applicable Applicable

Applicable Applicable plicable Not App cable Not Appli able Not Applica: le Not Applicab e Not Applicable 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 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 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 tions in Containment Following a LOCA, 11 March 1971. The opening of locked or sealed closed containment isolation on an intermittent basis under administrative control includes the following considerations:

(1) stationing a dedicated individual, who is in 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 the valves and that this will prevent the release of rad1oact1v1ty outside the containment.

_. SALEM -UNIT 2 B 3/4 6-4

  • .. * ' Document Control Desk Attachment 4 SALEM GENERATING STATION LR-N96291 LCR S95-02 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.