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{{#Wiki_filter:ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES LICENSE AMENDMENT APPLICATION SALEM GENERATING STATION -UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 REF: LR-N95081 LCR 95-08 LCR 85-18 The following Technical Specification pages have been revised to reflect the proposed changes: UNIT 1 3/4 4-3b 3/4 4-3c 3/4 9-8a B 3/4 4-1 B 3/4 9-2 UNIT 2 3/4 4-4a 3/4 4-4b 3/4 9-9 B 3/4 4-1 B 3/4 9-2 ( 9508080395 950622 PDR ADOCK 05000272 p PDR REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION  
{{#Wiki_filter:ATTACHMENT 2 REF: LR-N95081 LCR 95-08 MARKED-UP TECHNICAL SPECIFICATION PAGES         LCR 85-18 LICENSE AMENDMENT APPLICATION SALEM GENERATING STATION - UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 The following Technical Specification pages have been revised to reflect the proposed changes:
==============================================================================
UNIT 1 3/4 4-3b 3/4 4-3c 3/4 9-8a B 3/4 4-1 B 3/4 9-2 UNIT 2 3/4 4-4a 3/4 4-4b 3/4 9-9 B 3/4 4-1 B 3/4 9-2
3.4.1.4 Two# residual heat removal loops shall be OPERABLE*
( 9508080395 950622 PDR   ADOCK 05000272 p               PDR
and at least one RHR loop shall be in operation.**
 
APPLICABILITY:
REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION
MODE 5.## ACTION: a. With less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
==============================================================================
: b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
3.4.1.4         Two# residual heat removal loops shall be OPERABLE* and at least one RHR loop shall be in operation.**
SURVEILLANCE REQUIREMENTS  
APPLICABILITY: MODE 5.##
==============================================================================
ACTION:
4.4.1.4 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. # One RHR loop may be inoperable for up to two hours for surveillance testing, provided the other RHR loop is OPERABLE and in operation.
: a.         With less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5% (narrow range), may be substituted for one residual heat removal loop. ## A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 312°F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50°F above each of the RCS cold leg temperatures.
: b.         With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
* Systems supporting RHR loop operability may be excepted as follows: a. The normal or emergency power source may be inoperable.
SURVEILLANCE REQUIREMENTS
: b. One se vice er hea er may e equipment lipfed in, able 3_r4-3 __ _.,.._.. ___ _ provf the ** The residual heat removal pumps may be de-energized for up to 2 hours provided 1) no -operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) -core outlet temperature is maintained at least 10°F below saturation temperature.
==============================================================================
SALEM -UNIT_ 1 3/4 4-3b Amendment No. 72
4.4.1.4         At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.
/ REACTOR COOLANT SYSTEM ' / * / / / / ,TABLE 3. 4-3 MINIMUf( EQUIPMENT REQUIRED FOR DEci.Y HEAT REMOVAL WITH ONE ERVICE WITH HEADER OUT OF/ S.ERVICE / /
#   One RHR loop may be inoperable for up to two hours for           surveillance testing, provided the other RHR loop is OPERABLE and in operation.
Heat  
Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5%
/ redundant J(owpaths  
(narrow range), may be substituted for one residual heat removal loop.
/ / *** Two Coolin/Pumps, one c mponent Exchanger with *
## A reactor coolant pump shall not be started with one or more of             the RCS cold leg temperatures less than or equal to 312°F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50°F above each of the RCS cold leg temperatures.
* operab'le flowpath to each RHR H at Exchanger Wa er Pumps / Two Safety rade Pumps, in addition ta the RHR pumps,/capable of flow irito the corre any combination' of safety injecti n***,
* Systems supporting RHR loop operability may be excepted as follows:
or cont 'nment spray  
: a.         The normal or emergency power source may be inoperable.
/ / //' // *** On of the pumps ma_y"be removed ervice in to comply/with the require'ments of Secti7n;*.
__
: 5. 3 /footnote ( and 4. 5. 3. 2,,/ provide 7 d that the pump can be ade operabl within / / / / ' ; SALEM -UNIT 1 3/4 4-3c Amendment No. 72 i ); ' I / I I I I '
b.
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION  
_.,.._.. ____
==============================================================================
One se vice w~ er hea er may e equipment lipfed in, able 3_r4-3 provf the
3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*
** The residual heat removal pumps may be de-energized for up to 2             hours provided 1) no -operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) -core outlet temperature is maintained at least 10°F below saturation temperature.
APPLICABILITY: ,MODE 6 when water level above the top of the reactor pressure vessel flange is less than 23 feet. ACTION: a. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
SALEM - UNIT_ 1                             3/4 4-3b               Amendment No. 72
 
                                                                                      /
REACTOR COOLANT SYSTEM '
              /
                                                ,TABLE 3. 4-3
            /
        /                  /
MINIMUf( EQUIPMENT REQUIRED FOR DEci.Y HEAT REMOVAL WITH ONE ERVICE WITH HEADER OUT OF/
S.ERVICE i
                  /                                                /             /             '
                                                                                                  ); I
                                                                                              /      I
  *        /B~:h Residua~~at Remov~~;umps,              Heat E~~angers, a~d''associated
      /     redundant J(owpaths           /         ~                    /
  ***       Two   Com~nent  Coolin/Pumps, one c mponent       Cool~Heat Exchanger with operab'le flowpath to each RHR H at Exchanger                                         I
  *          ~rvice          Wa er Pumps     /                                               /~  I I
                                                                                                    '
* Two Safety     rade Pumps, in addition ta the RHR pumps,/capable of injectin~akeup      flow irito the corre any combination' of safety injecti n***, chargi~** or cont 'nment spray pu~s)
                                    /               /               //'             //
  ***     On     of the avail~e      pumps ma_y"be   administra~{~ely  removed   f~m ervice in or.~r to comply/with the require'ments of Secti7n;*. 5. 3 footnote ( ~Y and 4. 5. 3. 2,,/ provide d that the pump can be ade operabl
'/
within l~minutes.
                      /
                        /
                                    ;
                                      /
                                        /
                                          ~
7 SALEM - UNIT 1                                   3/4 4-3c                 Amendment No. 72
 
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION
==============================================================================
3.9.8.2   Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*
APPLICABILITY: ,MODE 6 when water level above the top of the reactor pressure vessel flange is less than 23 feet.
ACTION:
: a. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
: b. The provisions of Specification 3.0.3 are to applicable.
: b. The provisions of Specification 3.0.3 are to applicable.
SURVEILLANCE REQUIREMENTS  
SURVEILLANCE REQUIREMENTS
==============================================================================
==============================================================================
4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.S.
4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.S.
* Systems supporting RHR loop operability.may be excepted as follows: a. The normal or emergency power source may be inoperable.  
* Systems supporting RHR loop operability.may be excepted as follows:
/ b. //one seri'ice w. er header may e out o servic equipfuent in ,'f'able 3 4-3 is
: a. The normal or emergency power source may be inoperable.
* PERABLE/ DELETC provi d the / ,/ / SALEM -UNIT 1 3/4 9-8a Amendment No. 72
  /   b. //one seri'ice w. er header may e out o servic     provi  d the  /
... 3/4.4 REACTOR COOLANT SYSTEM BASES ==============================================================================
equipfuent l~ted in ,'f'able 3 4-3 is
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.
* PERABLE/     ,/       /
In MODES 1 and 2 with less than all coolant loops in operation, this specification requires that the plant be in at least HOT
DELETC SALEM - UNIT 1                   3/4 9-8a             Amendment No. 72
* STANDBY within 1 hour. In MODE 3, a single reactor coolant loop provides sufficient heat removal for removing decay heat; but, single failure considerations require all loops. be in operation whenever the rod control system is energized and at least one loop be in operation when the rod control. system is deenergized.
 
In MODE 4, a single reactor coolant loop or RHR loop provides sufficient heat removal for removing decay heat; but, single failure considerations require that at least 2 loops be OPERABLE.
...
Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two RHR loops be OPERABLE.
3/4.4   REACTOR COOLANT SYSTEM BASES
In MODE 5, single failure considerations re ire that two RHR loops be OPERABLE.
      ==============================================================================
The sions of ections 3 4.1.4 and .9.8.2 ( of ootnote *)] whic permit ervi , are b sed on t e followi oper tions r y upon e provis'ons of th' lative 5 days f any si le outag , and e Gas .T bac up to the diesel ge erators,.
3/4.4.1   REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with less than all coolant loops in operation, this specification requires that the plant be in at least HOT
* n the ev supply t e applica e loads. he basis for OPE tartup o the Gas rbine no ore than 4 days rior to begi ning of e Unit o tage. The operation of one R actor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of operator recognition and control. The restrictions on starting a Reactor Coolant Pump below P-7 with one or more RCS cold legs less than or equal to 3l2°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to lOCFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each steam generator is less than 50°F above each of the RCS cold leg temperatures.
* STANDBY within 1 hour.     In MODE 3, a single reactor coolant loop provides sufficient heat removal for removing decay heat; but, single failure considerations require all loops. be in operation whenever the rod control system is energized and at least one loop be in operation when the rod control.
WrTi; IITTEP-T \ SALEM -UNIT 1 B 3/4 4-1 Amendment No. 72 INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be Note that one piping path of SW and CC is adequate if it supports both RHR loops.
system is deenergized. In MODE 4, a single reactor coolant loop or RHR loop provides sufficient heat removal for removing decay heat; but, single failure considerations require that at least 2 loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two RHR loops be OPERABLE. In MODE 5, single failure considerations re ire that two RHR loops be OPERABLE. The pro~ sions of ections 3 4.1.4 and .9.8.2
. REFUELING OPERATIONS BASES ==============================================================================
(   of ootnote *)] whic permit ervi , are b sed on t e followi oper tions r     y upon   e provis'ons of th' lative 5 days f     any si le outag , and         e Gas .T bac up to the diesel ge erators,.
3/4.9.6 MANIPULATOR CRANE The requirements for the cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
* n the ev supply t e applica e loads. he basis for OPE tartup o the Gas     rbine no ore than 4 days rior to begi ning of     e Unit o tage. The operation of one R actor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of operator recognition and control. The restrictions on starting a Reactor Coolant Pump below P-7 with one or more RCS cold legs less than or equal to 3l2°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to lOCFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each steam
3/4.9.7 CRANE TRAVEL -SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control r.od assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
    ~ generator is less than 50°F above each of the RCS cold leg temperatures.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
R.SPL.f\C~ WrTi;     IITTEP-T \
A minimum flow rate of 1000 gpm is required.
SALEM - UNIT 1                         B 3/4 4-1                 Amendment No. 72
Additional flow limitations are *,specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown.
 
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.
INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operabl~. Note that one piping path of SW and CC is adequate if it supports both RHR loops.
Th pr6visio s of Sect" ns 3.4.1. and 3.9 .2 [para aph (b) f foot ote (*)] which pe it one se vice wate header be out o service,_, are d on thEt" followin : / / /, . . I 1. /{he periqd of time wh 'h plant  
 
!e1y upon/the I provisi.o'ns of thi footnote shall be imited t a cumulative 45 da s for apY single tage, an /' / Thela'as Turb e shall b operabl , as a ba up to t /diesel /1 1 1 Arierators, in the ev t of a ss of of ite powe , to supply the 1
~ .
* pplicabl loads. T e basis or OPERAB LITY is o e succes ful / startup f the Gas urbine 14 days rior to he beginni g of the nit outa e. {2E:PLAC.E wrrt-t I I SALEM -UNIT 1 B 3/4 9-2 Amendment No. 109 INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operable.
REFUELING OPERATIONS BASES
Note that one piping path of SW and CC is adequate if it supports both RHR loops.
        ==============================================================================
REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.4 Two# residual heat removal loops shall be OPERABLE*
3/4.9.6     MANIPULATOR CRANE The OPERABIL~TY requirements for the manip~lator cranes ensure that:
and at least one RHR loop shall be in operation.**
: 1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are
APPLICABILITY:
    ~  protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
MODE 5.## ACTION: a. With less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
3/4.9.7     CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control r.od assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8     RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. A minimum flow rate of 1000 gpm is required. Additional flow limitations are
      *,specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. Th pr6visio s of Sect" ns 3.4.1. and 3.9 .2 [para aph (b)               f foot ote (*)] which pe it one se vice wate header             be out o service,_, are d on thEt" followin :           /                   /         /,
                        .                     .                                       I
: 1.   /{he periqd of time   ~ring wh 'h plant   ~rations  !e1y upon/the
              /~.
I   provisi.o'ns of thi footnote shall be imited t for apY single     tage, an a cumulative 45 da s Thela'as Turb e shall b operabl , as a ba up to t /diesel /
                                                                                /'
1
                                                                                            /
1 Arierators, in the ev t of a           ss of of ite powe , to supply the 1
1
* pplicabl   loads. T e basis or OPERAB LITY is o e succes ful
      /               startup f the Gas urbine                   14 days rior to he beginni g of the nit outa e.
{2E:PLAC.E     wrrt-t   I N8~[2_T I SALEM - UNIT 1                       B 3/4 9-2           Amendment No. 109
 
INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operable. Note that one piping path of SW and CC is adequate if it supports both RHR loops.
 
REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION
  =========================~====================================================
3.4.1.4  Two# residual heat removal loops shall be OPERABLE* and at least one RHR loop shall be in operation.**
APPLICABILITY: MODE 5.##
ACTION:
: a. With less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
: b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
: b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
SURVEILLANCE REQUIREMENTS  
SURVEILLANCE REQUIREMENTS
==============================================================================
==============================================================================
4.4.1.4 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. # One RHR loop may be inoperable for up to two hours for surveillance testing, provided the other RHR loop is OPERABLE and in operation.
4.4.1.4   At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.
Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5% (narrow range), may be substituted for one residual heat removal loop. ## A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 312°F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50°F above each of the RCS cold leg temperatures.
#     One RHR loop may be inoperable for up to two hours for surveillance testing, provided the other RHR loop is OPERABLE and in operation.
* Systems supporting loop operability may be excepted as follows: ** The residual heat removal pumps may be de-energized for up to 2 hours provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10°F below saturation temperature.
Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5% (narrow range), may be substituted for one residual heat removal loop.
SALEM -UNIT 2 3/4 4-4a Amendment No. 46
##   A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 312°F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50°F above each of the RCS cold leg temperatures.
/ / REACT R COOLANT S TEM r / / / * * * *** M TABLE 3.4-3 !MUM SERVICE WATER s VICE QUIRED FOR WITH ONE ===========  
* Systems supporting ~R  loop operability may be excepted as follows:
-=================  
**   The residual heat removal pumps may be de-energized for up to 2 hours provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10°F below saturation temperature.
/ ,/ Both Res'tlual Heat Remov redund t flowpaths Pumps, Heat Exchangers, and asso iated // Exchanger Two Component Cooli g Pumps, one Compbnent Cooling He w' h operable flo aths to each R.!ilV'Heat Exchanger  
SALEM - UNIT 2                       3/4 4-4a                 Amendment No. 46
/ / / / Two Service W er Pumps // , Two Safety rade Pumps, in to the pumps, makeup flow into/the core (any c mbination of ea tfty n***,
 
or containment spray pumps) / ne of the may b administrativel removed from / service in order to comply wit the requirement of Section 3.5 footnote (#) ,-a"nd 4.5.3.2, pr ided that the p p can be made operable within 15 minutes / / SALEM -UNIT 2 3/4 4-4b Amendment No. 46 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION  
                                                                                        /
==============================================================================
                                          /                        /
                                                                /
                                                              /
REACT R COOLANT S     TEM                                 r TABLE 3.4-3 M  !MUM                 QUIRED FOR WITH ONE SERVICE WATER s   VICE
                            =========== -=================
                                                                /
                                                          ,/
Pumps, Heat Exchangers, and asso iated Both Res'tlual Heat Remov redund t flowpaths                             //
* Two Component Cooli g Pumps, one Compbnent Cooling He               Exchanger w' h operable flo aths to each R.!ilV'Heat Exchanger
                                              /                                         /
                                            /                                       /
* Two Service W     er Pumps         //                                       ,
* Two Safety rade Pumps, in       a:ef~ition  to the makeup flow into/the core (any c mbination of ea pumps, capabl~
tfty n***, charging*~' or containment spray pumps)
                              /
***    ne of the   avail~pumps
                        /
may b     administrativel service in order to comply wit the requirement of Section 3.5 removed from footnote (#) ,-a"nd 4.5.3.2, pr ided that the p p can be made operable within 15 minutes
              /
                /
SALEM - UNIT 2                             3/4 4-4b                     Amendment No. 46
 
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION
==============================================================================
3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*
3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*
APPLICABILITY:
APPLICABILITY: MODE 6 when water level above the top of the reactor pressure vessel flange is less than 23 feet.
MODE 6 when water level above the top of the reactor pressure vessel flange is less than 23 feet. ACTION: a. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
ACTION:
: a. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
: b. The provisions of Specification 3.0.3 are to applicable.
: b. The provisions of Specification 3.0.3 are to applicable.
SURVEILLANCE REQUIREMENTS  
SURVEILLANCE REQUIREMENTS
==============================================================================
==============================================================================
4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.5.
4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.5.
* Systems supporting RHR loop operability may be excepted as follows: a. The normal or emergency power source may be inoperable.
* Systems supporting RHR loop operability may be excepted as follows:
se/vice waij/r be oitf of l / equ9'ent listed in T_;ble 3. 4-:yis OPERA 1 BLE. SALEM -UNIT 2 3/4 9-9 prov'ded the Amendment No. 46 3/4.4 REACTOR COOLANT SYSTEM BASES ==============================================================================
: a. The normal or emergency power source may be inoperable.
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION  
J~~e          se/vice waij/r hea~e~may be oitf of se~rlce prov'ded the l /     equ9'ent listed in T_;ble 3. 4-:yis OPERABLE.
' The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.
1 SALEM - UNIT 2                     3/4 9-9                 Amendment No. 46
In MODES 1 and 2 with less than all coolant loops in operation, this specification requires that the plant be in at least HOT STANDBY within 1 hour. In MODE 3, a single reactor coolant loop provides sufficient heat removal fqr removing decay heat; but, single failure considerations require all loops be in operation whenever the rod control system is energized and at least one loop be in operation when the rod control system is deenergized.
 
In MODE 4, a single reactor coolant loop or RHR loop provides sufficient heat removal for removing decay heat; but, single failure considerations require that at least 2 loops be OPERABLE.
3/4.4   REACTOR COOLANT SYSTEM BASES
Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two RHR loops be OPERABLE.
      ==============================================================================
W tit+-1 N5*:\,'2.\  
3/4.4.1     REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed' to operate with all reactor coolant loops   in operation, and maintain DNBR above 1.30 during all normal operations       and anticipated transients. In MODES 1 and 2 with less than all coolant       loops in operation, this specification requires that the plant be in at least     HOT STANDBY within 1 hour.
\ In MODE 5, single failure considerations require that two RHR loops be OPERABLE.
In MODE 3, a single reactor coolant loop provides sufficient heat removal fqr removing decay heat; but, single failure considerations require all loops be in operation whenever the rod control system is energized and at least one loop be in operation when the rod control system is deenergized.
The p ovisions o Sections*  
In MODE 4, a single reactor coolant loop or RHR loop provides sufficient heat removal for removing decay heat; but, single failure considerations require that at least 2 loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two RHR loops be OPERABLE.
.4.1.4 and .9.8.2 [par raph (b) o footn e (*)] ich permit one servi e water hea r to be ou bas
p.£PL-~ W tit+- 1N5:\,'2.\ \
: 1. The time ring which ant *operat' ns rely u n the pr visions o this foot ote shall b limited to cumulativ 45 days single utage, an /2. Th Gas Turbi e shall be erable, as backup t the diesel gener ors, int event of loss of of "ite power, to supply e appl'cable load . The bas' for OPERAB LITY is on successfu st tup of th Gas Turbin no more th n 14 days ior to th beginni the Unit utage. are The operation of one Reactor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of operator recognition and control. The restrictions on starting a Reactor Coolant Pump below P-7 with one or more RCS cold legs less than or equal to 312°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits ;-of Appendix G. to lOCFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) *restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each steam generator is less than 50°F above each of the RCS cold leg temperatures.
In MODE 5, single failure considerations require that two RHR loops be OPERABLE. The p ovisions o Sections* .4.1.4 and .9.8.2 [par raph (b) o footn e (*)]       ich permit one servi e water hea r to be ou                 are bas     on~heollowing:~
SALEM -UNIT 2 B 3/4 4-1 Amendment No. 46 INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be Note that one piping path of SW and CC is adequate if it supports both RHR loops.
: 1. The perio~f time     ring which   ant *operat' ns rely u n the pr visions o this foot ote shall b limited to         cumulativ 45 days
REFUELING OPERATIONS BASES ==============================================================================
            ~y single utage, an
3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
: 2. Th Gas Turbi e shall be     erable, as   backup t   the diesel gener ors, int     event of   loss of of "ite power, to supply     e
3/4.9.7 CRANE TRAVEL -SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
  /        appl'cable load . The bas'     for OPERAB LITY is on successfu st tup of th Gas Turbin no more th n 14 days         ior to th beginni the Unit utage.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
  *-----'----------'----------'------*----r--------r---------r-------~=--t The operation of one Reactor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of operator recognition and control.
A minimum flow rate of 1000 gpm is required.
The restrictions on starting a Reactor Coolant Pump below P-7 with one or more RCS cold legs less than or equal to 312°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits ;-of Appendix G. to lOCFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) *restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each steam generator is less than 50°F above each of the RCS cold leg temperatures.
Additional flow limitations are specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown.
SALEM - UNIT 2                          B 3/4 4-1                Amendment No. 46
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.
 
The revisions of Sections 3.4.1.4 and 3.9.8.2 [pa graph (b) footnote )] wh'ch permit one service ater heade to be out o service, e based on he cl lowing: 1. 2. / The of time d ing which p of this ootnote sha ou ge, and nt operati s rely upo the be limite to a cumul tive 45 day Th Gas shall be o erable, as the event f a loss o loads. he basis f success&#xa3; startup o the Gas Tu ine no mer to the eginning of the Unit o age. he diesel er, to sup y Y is one than 14 da s prior With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is -provided to initiate emergency procedu<.res to cool the core. SALEM -UNIT 2 B 3/4 9-2 Amendment No. 87 P&#xa3;.PLAUZ lf.-J ilH' I N 0
INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operabl~. Note that one piping path of SW and CC is adequate if it supports both RHR loops.
\
 
INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operable.
REFUELING OPERATIONS BASES
Note that one piping path of SW and CC is adequate if it supports both RHR loops.}}
      ==============================================================================
3/4.9.6    MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7   CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8   RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140&deg;F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. A minimum flow rate of 1000 gpm is required. Additional flow limitations are specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown. The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.
The revisions of Sections 3.4.1.4 and 3.9.8.2 [pa graph (b)             footnote   )]
wh'ch permit one service ater heade to be out o service,             e based on he cl lowing:
                                          /
: 1. The         of time d ing which p nt operati s rely upo the of this ootnote sha      be limite to a cumul tive 45 day ou ge, and
: 2. Th  Gas            shall be o erable, as               he diesel the event f a loss o               er, to sup y loads. he basis f             Y is one success&#xa3;     startup o the Gas Tu ine no mer     than 14 da s prior to the eginning of the Unit o age.
With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is -provided to initiate emergency procedu<.res to cool the core.
SALEM - UNIT 2                             B 3/4 9-2              Amendment No. 87 P&#xa3;.PLAUZ lf.-J ilH' I N 0 ~P-T \
 
INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operable. Note that one piping path of SW and CC is adequate if it supports both RHR loops.}}

Revision as of 09:10, 21 October 2019

Proposed Tech Specs 3.4.1.4 & 3.9.8.2,deleting Footnotes & Associated Info Re SW Header Operation to RHR Operation to Be Consistent W/Current Regulations & Sts,Deleting Previous Amends 72 & 46
ML18101A869
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Site: Salem  PSEG icon.png
Issue date: 06/22/1995
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To:
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ML18101A868 List:
References
NUDOCS 9508080395
Download: ML18101A869 (15)
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Text

ATTACHMENT 2 REF: LR-N95081 LCR 95-08 MARKED-UP TECHNICAL SPECIFICATION PAGES LCR 85-18 LICENSE AMENDMENT APPLICATION SALEM GENERATING STATION - UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 The following Technical Specification pages have been revised to reflect the proposed changes:

UNIT 1 3/4 4-3b 3/4 4-3c 3/4 9-8a B 3/4 4-1 B 3/4 9-2 UNIT 2 3/4 4-4a 3/4 4-4b 3/4 9-9 B 3/4 4-1 B 3/4 9-2

( 9508080395 950622 PDR ADOCK 05000272 p PDR

REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION

==================================================================

3.4.1.4 Two# residual heat removal loops shall be OPERABLE* and at least one RHR loop shall be in operation.**

APPLICABILITY: MODE 5.##

ACTION:

a. With less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.

SURVEILLANCE REQUIREMENTS

==================================================================

4.4.1.4 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

  1. One RHR loop may be inoperable for up to two hours for surveillance testing, provided the other RHR loop is OPERABLE and in operation.

Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5%

(narrow range), may be substituted for one residual heat removal loop.

    1. A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 312°F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50°F above each of the RCS cold leg temperatures.
  • Systems supporting RHR loop operability may be excepted as follows:
a. The normal or emergency power source may be inoperable.

__

b.

_.,.._.. ____

One se vice w~ er hea er may e equipment lipfed in, able 3_r4-3 provf the

    • The residual heat removal pumps may be de-energized for up to 2 hours provided 1) no -operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) -core outlet temperature is maintained at least 10°F below saturation temperature.

SALEM - UNIT_ 1 3/4 4-3b Amendment No. 72

/

REACTOR COOLANT SYSTEM '

/

,TABLE 3. 4-3

/

/ /

MINIMUf( EQUIPMENT REQUIRED FOR DEci.Y HEAT REMOVAL WITH ONE ERVICE WITH HEADER OUT OF/

S.ERVICE i

/ / / '

); I

/ I

  • /B~:h Residua~~at Remov~~;umps, Heat E~~angers, a~dassociated

/ redundant J(owpaths / ~ /

      • Two Com~nent Coolin/Pumps, one c mponent Cool~Heat Exchanger with operab'le flowpath to each RHR H at Exchanger I
  • ~rvice Wa er Pumps / /~ I I

'

  • Two Safety rade Pumps, in addition ta the RHR pumps,/capable of injectin~akeup flow irito the corre any combination' of safety injecti n***, chargi~** or cont 'nment spray pu~s)

/ / //' //

      • On of the avail~e pumps ma_y"be administra~{~ely removed f~m ervice in or.~r to comply/with the require'ments of Secti7n;*. 5. 3 footnote ( ~Y and 4. 5. 3. 2,,/ provide d that the pump can be ade operabl

'/

within l~minutes.

/

/

/

/

~

7 SALEM - UNIT 1 3/4 4-3c Amendment No. 72

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION

==================================================================

3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*

APPLICABILITY: ,MODE 6 when water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
b. The provisions of Specification 3.0.3 are to applicable.

SURVEILLANCE REQUIREMENTS

==================================================================

4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.S.

  • Systems supporting RHR loop operability.may be excepted as follows:
a. The normal or emergency power source may be inoperable.

/ b. //one seri'ice w. er header may e out o servic provi d the /

equipfuent l~ted in ,'f'able 3 4-3 is

  • PERABLE/ ,/ /

DELETC SALEM - UNIT 1 3/4 9-8a Amendment No. 72

...

3/4.4 REACTOR COOLANT SYSTEM BASES

==================================================================

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with less than all coolant loops in operation, this specification requires that the plant be in at least HOT

  • STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. In MODE 3, a single reactor coolant loop provides sufficient heat removal for removing decay heat; but, single failure considerations require all loops. be in operation whenever the rod control system is energized and at least one loop be in operation when the rod control.

system is deenergized. In MODE 4, a single reactor coolant loop or RHR loop provides sufficient heat removal for removing decay heat; but, single failure considerations require that at least 2 loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two RHR loops be OPERABLE. In MODE 5, single failure considerations re ire that two RHR loops be OPERABLE. The pro~ sions of ections 3 4.1.4 and .9.8.2

( of ootnote *)] whic permit ervi , are b sed on t e followi oper tions r y upon e provis'ons of th' lative 5 days f any si le outag , and e Gas .T bac up to the diesel ge erators,.

  • n the ev supply t e applica e loads. he basis for OPE tartup o the Gas rbine no ore than 4 days rior to begi ning of e Unit o tage. The operation of one R actor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of operator recognition and control. The restrictions on starting a Reactor Coolant Pump below P-7 with one or more RCS cold legs less than or equal to 3l2°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to lOCFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each steam

~ generator is less than 50°F above each of the RCS cold leg temperatures.

R.SPL.f\C~ WrTi; IITTEP-T \

SALEM - UNIT 1 B 3/4 4-1 Amendment No. 72

INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operabl~. Note that one piping path of SW and CC is adequate if it supports both RHR loops.

~ .

REFUELING OPERATIONS BASES

==================================================================

3/4.9.6 MANIPULATOR CRANE The OPERABIL~TY requirements for the manip~lator cranes ensure that:

1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are

~ protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control r.od assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. A minimum flow rate of 1000 gpm is required. Additional flow limitations are

  • ,specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. Th pr6visio s of Sect" ns 3.4.1. and 3.9 .2 [para aph (b) f foot ote (*)] which pe it one se vice wate header be out o service,_, are d on thEt" followin : / / /,

. . I

1. /{he periqd of time ~ring wh 'h plant ~rations !e1y upon/the

/~.

I provisi.o'ns of thi footnote shall be imited t for apY single tage, an a cumulative 45 da s Thela'as Turb e shall b operabl , as a ba up to t /diesel /

/'

1

/

1 Arierators, in the ev t of a ss of of ite powe , to supply the 1

1

  • pplicabl loads. T e basis or OPERAB LITY is o e succes ful

/ startup f the Gas urbine 14 days rior to he beginni g of the nit outa e.

{2E:PLAC.E wrrt-t I N8~[2_T I SALEM - UNIT 1 B 3/4 9-2 Amendment No. 109

INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operable. Note that one piping path of SW and CC is adequate if it supports both RHR loops.

REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION

===================~==============================================

3.4.1.4 Two# residual heat removal loops shall be OPERABLE* and at least one RHR loop shall be in operation.**

APPLICABILITY: MODE 5.##

ACTION:

a. With less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.

SURVEILLANCE REQUIREMENTS

==================================================================

4.4.1.4 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

  1. One RHR loop may be inoperable for up to two hours for surveillance testing, provided the other RHR loop is OPERABLE and in operation.

Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5% (narrow range), may be substituted for one residual heat removal loop.

    1. A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 312°F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50°F above each of the RCS cold leg temperatures.
  • Systems supporting ~R loop operability may be excepted as follows:
    • The residual heat removal pumps may be de-energized for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10°F below saturation temperature.

SALEM - UNIT 2 3/4 4-4a Amendment No. 46

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REACT R COOLANT S TEM r TABLE 3.4-3 M !MUM QUIRED FOR WITH ONE SERVICE WATER s VICE

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Pumps, Heat Exchangers, and asso iated Both Res'tlual Heat Remov redund t flowpaths //

  • Two Component Cooli g Pumps, one Compbnent Cooling He Exchanger w' h operable flo aths to each R.!ilV'Heat Exchanger

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  • Two Service W er Pumps // ,
  • Two Safety rade Pumps, in a:ef~ition to the makeup flow into/the core (any c mbination of ea pumps, capabl~

tfty n***, charging*~' or containment spray pumps)

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      • ne of the avail~pumps

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may b administrativel service in order to comply wit the requirement of Section 3.5 removed from footnote (#) ,-a"nd 4.5.3.2, pr ided that the p p can be made operable within 15 minutes

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SALEM - UNIT 2 3/4 4-4b Amendment No. 46

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION

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3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*

APPLICABILITY: MODE 6 when water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
b. The provisions of Specification 3.0.3 are to applicable.

SURVEILLANCE REQUIREMENTS

==================================================================

4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.5.

  • Systems supporting RHR loop operability may be excepted as follows:
a. The normal or emergency power source may be inoperable.

J~~e se/vice waij/r hea~e~may be oitf of se~rlce prov'ded the l / equ9'ent listed in T_;ble 3. 4-:yis OPERABLE.

1 SALEM - UNIT 2 3/4 9-9 Amendment No. 46

3/4.4 REACTOR COOLANT SYSTEM BASES

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3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed' to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with less than all coolant loops in operation, this specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

In MODE 3, a single reactor coolant loop provides sufficient heat removal fqr removing decay heat; but, single failure considerations require all loops be in operation whenever the rod control system is energized and at least one loop be in operation when the rod control system is deenergized.

In MODE 4, a single reactor coolant loop or RHR loop provides sufficient heat removal for removing decay heat; but, single failure considerations require that at least 2 loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two RHR loops be OPERABLE.

p.£PL-~ W tit+- 1N5:\,'2.\ \

In MODE 5, single failure considerations require that two RHR loops be OPERABLE. The p ovisions o Sections* .4.1.4 and .9.8.2 [par raph (b) o footn e (*)] ich permit one servi e water hea r to be ou are bas on~heollowing:~

1. The perio~f time ring which ant *operat' ns rely u n the pr visions o this foot ote shall b limited to cumulativ 45 days

~y single utage, an

2. Th Gas Turbi e shall be erable, as backup t the diesel gener ors, int event of loss of of "ite power, to supply e

/ appl'cable load . The bas' for OPERAB LITY is on successfu st tup of th Gas Turbin no more th n 14 days ior to th beginni the Unit utage.

  • -----'----------'----------'------*----r--------r---------r-------~=--t The operation of one Reactor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump below P-7 with one or more RCS cold legs less than or equal to 312°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits ;-of Appendix G. to lOCFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) *restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each steam generator is less than 50°F above each of the RCS cold leg temperatures.

SALEM - UNIT 2 B 3/4 4-1 Amendment No. 46

INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operabl~. Note that one piping path of SW and CC is adequate if it supports both RHR loops.

REFUELING OPERATIONS BASES

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3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. A minimum flow rate of 1000 gpm is required. Additional flow limitations are specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown. The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.

The revisions of Sections 3.4.1.4 and 3.9.8.2 [pa graph (b) footnote )]

wh'ch permit one service ater heade to be out o service, e based on he cl lowing:

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1. The of time d ing which p nt operati s rely upo the of this ootnote sha be limite to a cumul tive 45 day ou ge, and
2. Th Gas shall be o erable, as he diesel the event f a loss o er, to sup y loads. he basis f Y is one success£ startup o the Gas Tu ine no mer than 14 da s prior to the eginning of the Unit o age.

With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is -provided to initiate emergency procedu<.res to cool the core.

SALEM - UNIT 2 B 3/4 9-2 Amendment No. 87 P£.PLAUZ lf.-J ilH' I N 0 ~P-T \

INSERT 1 For support systems; Service Water (SW) and Component Cooling (CC), component redundancy is necessary to ensure no single active component failure will cause the loss of RHR. Therefore, two SW pumps and two CC pumps, powered from two different vital buses, must be operable. Note that one piping path of SW and CC is adequate if it supports both RHR loops.

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