ML18101A869
| ML18101A869 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/22/1995 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18101A868 | List: |
| References | |
| NUDOCS 9508080395 | |
| Download: ML18101A869 (15) | |
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 />.
- 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.
- 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
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,TABLE 3. 4-3
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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.
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/
/
/
~
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 10CFR 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 />.
- 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.
- 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
===== -===========
/
,/
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.*
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
==================================================================
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 10CFR 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
==================================================================
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:
/
- 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.