ML20245L215
| ML20245L215 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/02/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245L220 | List: |
| References | |
| NUDOCS 8905050329 | |
| Download: ML20245L215 (18) | |
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8 UNITED STATES l
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NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20066
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva-Power and Light Company and Atlantic City Electric Company (the licensees) dated July 23, 1987 as supplemented by letter dated March 16, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and l
L safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; i.
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Consission's regulations and all applicable requirements have been f
satisfied.
l
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2.
Accordingly, the license is amended by changes to the Technical Specifica-L tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
8905050329 890502 i
PDR ADOCK 05000272 P
PDC l
L-._____..-_____-_--_-__-___..-...-__
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 94
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate.1-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 2, 1989 P
JStone:mr A Yo#0 WButler
/g /89 y//f/89 g / /89 4
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, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 94
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Spet rications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: May 2, 1989 e
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ATTACHMENT TO LICENSE AMENDNENT NO. 94 l
FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix-A as follows:
Remove Pages Insert Paces 3/4 5-3 3/4 5-3 3/4 5-4 3/4 5-4 3
3/4 5-6 3/4 5-6
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i B 3/4 5-1 B 3/4 5-1 B 3/4 5-la B 3/4 5-la i
i
EMERGENCY ' CORE COOLING SYST35
.' ECCS SUBSYSTEMS - T h 350*F' LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following injection systems:
One OPERABLE centrifugal charging pump and associated flow path
.a.
capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into each Reactor Coolant System (RCS) cold leg.
b.
One OPERABLE safety injection pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into each RCS cold leg, and; upon manual initiation, 2.
Discharging into its two associated RCS hot legs.
c.
One OPERABLE residual heat removal pump and associated residual heat removal heat. exchanger and flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recircu~1ation phase of operation and; 1.
. Discharging into each RCS cold leg, and; upon manual initiation, 2.
Discharging into two RCS hot legs.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With one ECCS subsystem inoperable,.restors the inoperabia subsystem a.
to OPERABLE' status within 72 hourr or be' in HO?' SHUTDOWN within the nest 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i b.
In the event the ECCS is actuated and injects water into the Reactor-Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total l
accumulated actuation cycles to date, c.
With both ECCS subsystems inoperable for surveillance testing, restore at least one subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at least COLD SHUTDCW within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SALEM - UNIT 1 3/4 5-3 Amendment No. 94 l-
A EMERGENCY CORE COOLfNG SYSTEMS l
SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying that the following valves are in the indicated positions
(
l with power to the valve operators removed:
Valve Number Valve Function Valve, Position a.
1 SJ 69
- a. RHR pump suction
- a. open b.
1 SJ 30
- b. SI pump suction b, open
- c. 11 SJ 40
- c. SI discharge to
- c. closed hot legs
- d. 12 SJ 40
- d. SI discharge to
- d. closed hot legs e.
1 RH 26
- e. RHR discharge to
- e. closed hot legs
- f. 11 SJ 49
- f. RHR discharge to
- f. open cold legs
- g. 12 SJ 49
- g. RHR discharge to
- g. open cold legs h.
1 CS 14#
- h. Spray additive
- h. open l
tank discharge i.
1 SJ 135
- 1. SI discharge to
- i. open cold legs J.
1 SJ 67
- j. SI recire. line J. open isolation k.
1 SJ 68
- k. SI recire. line
- k. open isolation
- 1. 11 SJ 44
- 1. Containment sump
- 1. closed isolation valve m.
12 SJ 44
- m. Containment sump
- m. closed isolation valve 2.
Verifying that the following valves are in the indicated positions:
Valve Number Valve Function Valve Position
- a. 11 RH 19
- a. RHR crosstie valve
- a. open
- b. 12. RE 19
- b. RHR crosstle-valva-
- b. open -
i b.
At least once per 31 days by:
1 1
1.
Verifying tnat each vab e (manual, power operaced or automatic) in the flow path that i:: not locked, sealed, or otherwise secured in position, is in its correct position.
)
2.
Verifying that the ECCS piping is full of water by venting the ECCS l
pump casings and accessible discharge piping high points.
)
j
- If inoperable, the applicable Technical Specification is 3.6.2.2.
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l SALEM - UNIT 1 3/4 5-4 Amendment No. 94
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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T
< 3 50 *J.
LIMITING CONDITION FOR OPEP ATION 3.5.3 As a minimum, one ECCS subsystem # comprised of the following shall be OPERABLE:
I a.
One OPERABLE centrifugal charging pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into each Reactor Coolant System (RCS) cold leg.
i b.
One OPERABLE residual heat removal pump and associated residual heat removal heat exchanger and flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation and; 1.
Discharging into each RCS cold leg, and; upon manual 1
initiation, 2.
Discharging into two RCS hot legs.
APPLICABILITY: MODE 4 ACTION:
a.
With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the l
refueling water storage fank, restore at least one ECCS subsystem to l
OPERABLE status within I hour or be in COLD SHUTDOWN i<nin the next l
20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
f b.
Within no ECCS subsystem OPERABLE because of the inoperabilit's of l-either the residual heat removal heat exchanger or residual hav.
removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Re a tor Coolant System T**E less than 350'F by use of alternate heat removal methods.
c.
In the event the ECCS is actuated < and' injects water into, tha Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
- A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is le.ss than or equal to 312*F. NOTE: This particular restriction also applies in MODE 5 and 6.
SALEM - UNIT 1 3/4 5-6 Amendment No. 94
c__-_--_____--_
3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMULATORS The OPERABILITY of each RCS accumulator ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressur6 ensure that the assumptions used for accumulator injection in the safety analysis are met.
The accumulator power operated isolation valves are coesidered to be
" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met. In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.
The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA l
event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures. If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.
3/4.5.2 and 3/4.5.3' ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold les pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
The limitation for a maximum of one safety injection pump or centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all safety injection pumps except the allowed OPERABLE pump to be inoperable below 312*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single POPS relief valve.
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SALEM - UNIT 1 B 3/4 5-1 Amendment No. 94
D4ERGENCY CORE COOLRNG SYSTEMS BASES ECCS SUBSYSTDG (Continued)
With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that e
proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the Er.',-LOCA analyses.
Each ECCS subsystem supplies all four cold legs to satisfy minimum flow requirements.
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SALEM - UNIT 1 B 3/4 5-la Amendment No. 94 l
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UNITED STATES l
NUCLEAR REGULATORY COMMISSION n
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,I WASHWGTON, D. C. 20666
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PUBLICSERVICEELECTRICIGASCOMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY i
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensee') dated s
July 23,1987 as supplemented by letter dated March 16, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, i
as amendec (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by i
this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted
{
in compliance with the Comission's regulations set forth in 10 CFR l
Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of
)
the Comission's regulations and all applicable requirements have been j
satisfied.
l l
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
1
IL
- (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in.the license.. The. licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license' amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: May 2, 1989 h
PDI-2/PM OGC PDI-2/D P
I l
.en JStone:mr m Yo M WButler u
9 q/f/89 Y/[f/89
{/g/89 4
(2)' Technical Specifications and Environmental Protection Plan The Technical. Specifications contained in Appendices A and B as revised through Amendment No. 70, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/a&2&tL Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical i
Specifications
'Date.of Issuance:
May 2, 1989
ATTACHNENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 l
Revise Appendix A as follows:
Remove Paces Insert Pages 3/4 5-3 3/4 5-3 3/4 5-3a 3/4 5-4 3/4 5-4 3/4 5-7 3/4 5-7 8 3/4 5-2 B 3/4 5-2 i
c EMERGENCY CORE COOLXNG SYSTEMS ECCS SUBSYSTEMS - T 2 350*F_
i i
-e 1
LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following injection systems:
One OPERABLE centrifugal charging pump and associated flow path a.
capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removallpump discharge piping and; 1.
Discharging into each Reactor Coolant System (RCS) cold leg.
b.
One OPERABLE safety injection pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into each RCS cold leg, and; upon manual initiation, 2.
Discharging into its two associated RCS hot legs.
c.
One OPERABLE residual heat removal pump and associated residual heat removal heat exchanger and flow path capable of taking suction from the refueling water storage tank on a safety inje.ction signal and transferring suction to the containment sump during the
(
recirediation phase of operation and; 1.
Discharging into each RCS cold leg, and; upon manual initiation, I
2.
Discharging into two RCS hot legs.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
I a.
With one ECCS subsystem inoperable, restore the inoperable subsysten to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within.the next 11 hoarr.
l b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared'and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
SALEM - UNIT 2 3/4 5-3 Amendment No. 70 i
,4 EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T 2 350*F ACTION (Continued):
L c.
With both ECCS subsystems inoperabie for surveillance testing, restore at least one subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or i
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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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SALEM - UNIT 2 3/4 5-3a Amendment No. 70 o
EMERGENCY CORE COOLING SYSTEMS
, SURVEILLANCE REQUIREMENTS 4.S.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
l 1.
Verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position a.
2 SJ 69
- a. RHR pump suction
- a. open b.
2 SJ 30
- b. SI pump suction
- b. open
- c. 21 SJ 40
- c. SI discharge to
- c. closed hot legs
- d. 22 SJ 40
- d. SI discharge to
- d. closed hot legs e.
2 RH 26
- e. RHR dischtege to
- e. closed hot legs
- f. 21 SJ 49
- f. RHR discharge to
- f. open cold legs
- g. 22 SJ 49
- g. RHR discharge to
- g. open cold legs h.
2 CS 14#
- h. Spray additive
- h. open tank discharge 1.
2 SJ 135
- 1. SI discharge to
- i. open cold legs j., 2 SJ 67
- j. SI recirc. line J. open isolation I
k.
2 SJ 68
- k. SI recire. line
- k. open isolation
- 1. 21 SJ 44
- 1. Containment sump
- 1. closed isolation valve I
- m. 22 SJ 44
- m. Containment sump
- m. closed isolation valve 2.
Verifying that the following valves are in the indicated positions:
Valve Number Valve Function Valve Position
- a. 21 RH.19
- a. RER croastie val.ve
- a. Open
- b. 22 RE 19<
- b. RHR crosstia valve-
- b. Open-b.
At least once per 31 days by:
1.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
2.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points.
- If inoperable, the applicable Technical Specification is 3.6.2.2.
l SA1.EM - UNIT 2 3/4 5-4 Amendment No. 70
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EMERGENCY CORE COOLING SYSTEMS
.ECCS SUBSYSTEMS - T
<350'F LIMITING CONDITION FOR OPERATION 3.5.3.
As a minimum, one ECCS subsystemli comprised of the following shall be OPERABLE:
One OPERABLE centrifugal charging pump and associated flow path a.
capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into_each Reactor Coolant System (RCS) cold leg.
b.
One 01dRA3LE residual heat removal pump and associated residual heat removal hat enhanger and flow path capable of taking suction from tha refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation and; 1.
Discharging into each RCS cold leg, and; upon manual initiation, 2.
Discharging into two RCS hot legs.
APPLICABILITY: MODE 4.
ACTION:
With no ECCS subsystem OPERABLE because of the inoperability of a.
either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, b.
With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE-status or maintain tho' Reactor Coolant System T less than 350*F by use_
')
of alternate heat removal methods.
"#8 In the event the ECC5 tis actuated and injects water into the Reactor c.
l Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage f actor for each affected safety-injectiart nozzle.shall be l
provided in this Special Report whenever its value exceeds 0.70.
//A maximum of one safety injection pump or one centrifugal charging pump shall l be OPERALLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 312*F.
NOTE: This particular restriction also applies in MODES 5 and 6.
i SALEM - UNIT 2 3/4 5-7 Amendment No. 70
EMERGENCY CORE C00LfNG SYSTEMS
. BASES ECCS SUBSYSTEMS (Continued)
With the RCS temperature below 350*F, on OPERABLE ECCS subsystem is acceptable without single failure consideratic.n on the basis of the stable reactivity condition of the' reactor and the limited core cooling requirements.
The limitation for a maximum of one safety injection pump or one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all safety ir etion pumps except the allowed OPERABLE safety injection pump to be inoperable below 312*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single POPS relief valve.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures t.'at at a minimum, the assumptions used in the safety analyses are met and that subs:rstem OPERABILITY is maintained. Surveillance requirements for throttle valve posicion stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. : maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
Each ECCS subsystem supplies all four cold legs to satisfy minimum flow requirements.
3/4.5.4 REFUELING WATER STORAGE TANK The OPERABILITY of the RWST as a part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
The limits on RWST minimum volume and boron concentrations ensure that:
(1) sufficient water is available within containment to permit recirculation cooling flow to the core, (2) the reactor will remain subcritical in the cold condition following a small LOCA assuming complete mixing of the RWST, RCS, and ECCS water volumes with all control rods inserted except the most reactive control assembly (ARI-1), and (3) the reactor will remain suberitical in the cold condition following a large break LOCA (break flow area > 1.0 sq. f t.)
assuming' complets mixing of the RWST, RCF, and ECCY water and other sources of water that may eventually reside in the sump following a LOCA with all control rods assumed to be out (ARO). The limits on contained water volume and boron
]
concentration also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effset of chloride and caustic stress corrosion on mechanical systems and components. The contained water volume limit includes an allowance for water not usable because of tank discharge-line location or other physical characteristics.
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1 SALEM - UNIT 2 B 3/4 5-2 Amendment No. 70 i