ML20217A152
| ML20217A152 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/12/1998 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20217A158 | List: |
| References | |
| DPR-70-A-208, DPR-75-A-189 NUDOCS 9803240291 | |
| Download: ML20217A152 (14) | |
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UNITED STATES s
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. SegeHe01 PUBLIC SERVICE FI FCTRIC & GAS COMPANY PHILADELPHIA FI FCTRIC COMPANY -
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY FLFCTRIC COMPANY DOCKET NO 50-272 SALEM NUCLEAR GENERATING STAT 10N. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 208 License No. DPR-70
- 1. ' The Nuclear Regulatory Commission (the Commission 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 March 4,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the i
Commission'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-i i
C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirerr ents have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
9003240291 980312 PDR ADOCK 05000272 P
t.
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.208, 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 to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION P
/3o F. Stolz, Director oject ' rectorate 1-2 Division of Reactor Projects -l/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 12,1998
ATTACHMENT TO LICENSE AMENDMENT NO. 9n8 FACILITY OPERATING LICENSE NO, DPR-70 DOCKET No. 50-272 Revise Appendix A as follows:
Remove Paoes insert Paaes 3/4 5 5a 3/4 5-5a 3/4 5-5b 3/4 5-5b B 3/4 5-2 B 3/4 5 2 B 3/4 5 3 8 3/4 5-3 1
r EMERGENCY CCetE COOLING SYSTSMS SURVEILLANCE REQUIREMENTS (Continued) f.
By verifying that each of the following pumps develops the
. indicated Total Dynamic Bead (TDE) when tested at the test flow point pursuant to Specification 4.0.5:
1.
Centrifugal charging pump 2 2338 pai TDE 2.
Safety Injection Pusp 1 1369 psi TDE 3.
Residual heat removal pump 2 165 psi TDE g.
By verifying the correct position of each of the following ECCS throttle valves:
1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
2.
At least once per 18 months.
EPSI SYSTEM LPSI SYSTEM VALVE NUMBER VALVE MIBdBER 11 SJ 16 11 SJ 130 12 SJ 16 12 SJ 138 13 SJ 16 13 SJ 138 14 SJ 16 14 SJ 138 11 SJ 143 12 SJ 143 13 SJ 143 14 SJ 143 h.
By performing a flow balance test, during shutdown, following completion of modiN oations to the ECCS subsystems that alter the subsystem. flow characteristics and verifying that:
1.
For Safety Injection pumps, with a single pump running:
a)
The sum of the injection line flow rates, excluding the l
highest flow rate, is 2 453 gym; and b)
The total' flow rate through all four injection lines is 5 647 gym, and c)
The difference between any pair of injection line flow rates is s 12.0 gym, and d)
The total pusy flow rate is 5 654 gym in the cold leg alignment, and e)
The total pusy flow rate is 5 654 gym in the hot leg alignment.
SALEM --UNIT 1 3/4 5-5a Amendment No.N3,208 l
EMERGENCY CORE COOLING SYSTEMS SDRVEILLANCE REQUIREMENTS (Continued)
==
2.
For Centrifugal Charging pumps, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is 2 306 gym, and b)
The total flow rate through all four injection lines is s 444 gpaa, and c)
The difference between any pair of injection line flow rates is s 10.5 gym, and d)
The total pump flow rate is 5 554 gym.
1.
The automatic interlock function of the RER System shall be verified within the seven (7) days prior to placing the RER System in service for cooling of the Reactor Coolant System. This shall be done by verifying with a test signal corresponding to a reactor coolant pressure of 375 psig or greater, that the IRB1 and 1RB2 valves cannot be opened.
l l
l SALEM - UNIT 1 3/4 5-5b Amendment No. 70, 208
l m maeuCY CORE COOLING SYSTEMS BASES
(
i I
ECCS SUBSYSTEMS (Continued)
With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is neceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
h surveillance requirements, which are provided to ensure the OPERABILITY of each component, ensure that, at a mind==, the assumptions used in the safety analysis are met and that subsystem OPERABILITY is maintained, h safety analyses make assumptions with respect to:
- 1) both the==w4==
and minimum total system resistance, and 2) both the==w4==
and minimman branch injection line resistance. h oe resistances, in conjunction with the ranges of potential pump performance, are used to calculate the
w4
and miniamma ECCS flow assumed in the safety analyses.
The==w4==
and minismen flow surveillance requirements in conjunction with the==wi= =
and min 4== pug performance curves ensures that the assumptions of total system resistance and the distribution of that system resistance among the various paths are met.
h maximaan total pump flow surveillance requirements ensure the pump runout limits of 560 gym for the centrifugal charging pumps and 675 gym for the safety injection pumps are not exceeded. Due to the effect of pump suction boost alignment, the runout limits for the surveillance criteria are s 554 gym for C/SI pumps, s 664 gym for SI pumps in cold leg alignment, and s 654 gym for SI pumps in hot leg alignment.
The surveillance requiremnant for the
w4
difference between the==w4==
and minimum individual inject.lon line flows ensure that the minimum individual injection line resistance asetuned for the spilling line following a LOCA is met.
3/4.5.4 SEAL INJECTION FLOW The Reactor Coolant Pump (RCP) seal injection flow restriction limits the amount of ECCS flow thatt would be diverted frosa the injection path following an ECCS actuation. This limit is based on safety analysis assumptions, since RCP seal injection flow is not isolated during Safety Injection (SI).
The LCO is not strictly a flow limit, but rather a flow limit based on a flow line resistanoe. Line pressure and flow must be known to establish the proper line resistanoe.
Flow line resistance is determined by asetuning that the RCS pressure is at normal operating pressure, and that the centrifugal charging pump discharge pressure is greater than or equal to 2430 psig.
Charging pump header pressure is used instead of RCS pressure, since it is more representative of flow diversion during an accident. The additional LCO modifier, charging flow control valve full open, is required since the valve is designed to fail open. With the LCO specified discharge pressure and control valve position, a flow limit is established. This flow limit is used in the accident analysis.
A prevision has been added to exempt surveillance requirement 4.0.4 for entry into MODE 3, since the surveillance cannot be performed in a lcwer mode.
The eresytion is permitted for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the RCS pressure has stabilised within i 20 psig of normal operating pressure. h RCS pressure SALEN - UKIT 1 5 3/4 5-2 Amendment No/1//S,208
wwarm CY CORE COOLING SYSTEMS BASES requirement produces the conditions necessary to correctly set the saanual throttle valves. The exemption is limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to ensure timely surveillance completion once the necessary conditions are established.
3/4.5.5 REFDELING WATER STORAGE TANK The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in ',he event of a LOCA.
The limits on RWST seinismaa voltras and boron concentration ensure that:
(1) sufficient water is available within containment to permit recirculation cooling flow to the core, (2) the reactor will remain suberitical 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 contro2-assembly (ARI-1), and (3) the reactor will remain suberitical in the cold condition following a large break LOCA (break flow area > 3.0 sq. ft.)
assuming complete mixing of the RNST, RCS, and ECCS 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 baron concentration also ensure a pH value of between 8.5 and 11.0 for the solucion recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect 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.
i l
SALEN - UNIT 1 B 3/4 5-3 Amendment No. US, 208 l
- (*:0 g
i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 300864 201 Y+9 ** * * *,o PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO, 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. R AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.189 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission 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 March 4,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment v.ill not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating 1.icense No. DPR-75 is hereby amended to read as follows:
2-(2) Technical Soecifications and Environmental Proter 41an Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.189 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 to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION 0
A Jo n.htolz, Director P o et Directorate I-2 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 12, 1998
1 4
ATTACHMENT TO LICENSE AMENDMENT NO.189 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes insert Paaes 3/4 5-6 3/454 3/4 54a 3/4 54a 1 3/4 5-2 B 3/4 5-2 B 3/4 5-3 B 3/4 5-3
N N umCY CORE COOLING SYSTEMS SURVEILLANCE DEQUIREMENTS (Continued) f.
By verifying that each of the following pumps develops the indicated Total Dynamic Bead (TDE) when tested at the test flow point pursuant to Specification 4.0.5:
1.
Centrifugal charging pump 2 2338 pai TDI 2.
Safety Injection pump k 1369 psi TDE 3.
Residual Beat Removal pu g 2 165 psi TDI g.
By verifying the correct position of each of the following ECCS throttle valves:
1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
2.
At least once per 18 months.
IPSI System 113I System Valve Number Valve Number 21 SJ 16 21 SJ 138 22 SJ 16 22 SJ 138 23 SJ 16 23 SJ 138 24 SJ 16 24 SJ 138 21 SJ 143 22 SJ 143 23 SJ 143 24 SJ 143 h.
By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
1.
For Safety Injection pumps, with a single pump running:
a) The sum of the injection line flow rates, emoluding the highest flow rate, is 2 453 gym, and b) The total flow rate through all four injection lines is s 647 gym, and c) The difference between any pair of injection line flow rates is s 12.0 gym, and d) The total pump flow rate is s 664 gyn in the cold leg alignment, and e) The total pump flow rate is 5 654 gym in the hot leg alignment.
SALEM - UNIT 2 3/4 5-6 Amenchment No. 779, 189
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)-
2.
For centrifugal charging pump, with a single pump runnings a)
The sunt of the injection line flow rates, excluding the highest flow rate, is lt 306 gpai, and b)
The total flow rate through all four injection lines is 4 444 gpat, and c)
The difference between any pair of injection line flow rates is s 10.5 gpan, and d)
The total pump flow rate is s 554 gym.
i.
The autonuttic interlock function of the RER System shall be verified within the seven (7) days prior to placing the RER Systemt in service for cooling of the Reactor Coolant Systent. This shall be done by verifying with a test signal correspond'.ng to a reactor coolant pressure of 375 psig or greater, that the 2RIl and 2RI2 valves cannot be opened.
l 1
l t
SALEM - UNIT 2 3/4 5-Ea Amendment No.1AN,189 i
l i
EMERGENCY CCRE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
With the RCS tagerature below 350*F, one OPERABLE ECCS subsystesa is soceptable without single failure ;onsideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
h limitation for a==w4==
of one safety injection pug or one centrifugal charging pump to be OPERABLE and the Surveillance requiremment to verify all safety injection 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.
h surveillance requirements, which are provided to ensure OPERASIL CTY of each component, ensure that, at a min 4==, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. h safety analyses snake the assumptions with respect to:
- 1) both the===4= =
. and miniumma total system resistance, and 2) both the==ri==
and minimum branch injection line resistance, h oe resistances, in conjunction with the ranges of potential pump performance, are used to calculate the==w4==
and minimum ECCS flow assumed in the safety analyses.
The==w4==
and min 4== flow surveillance requirements in conjunction with the==w4==
and minimman pump performance curves ensures that the assumptions of total system resistance and the distribution of that system resistance among the various paths are met.
The==w4==
total pump flow surveillance requirements ensure the pump runout limits of 560 gym for the centrifugal charging pumps and 675 gpsa for the safety injection pumps are not exceeded. Due to the effect of pump suction boost alignment, the runout limits for the surveillance criteria are s 554 gym for C/SI pumps, s 664 gym for SI pumps in cold leg alignment and s 654 gpsa for SI pumps in hot leg alignaant.
h surveillance requirement for the==wi== difference between the
w4
and min 4== individual injection line flows ensure that the min 4==
individual injection line resistance assumed for the syllling line following a i
14CA is met.
3/4.5.4 SEAL I3tJECTICat FLOW h Reactor Coolant Pump (RCP) seal injection flow zustriction limits the amount of ECCS flow that would be diverted fresa the injection path following an ECCS actuation. This limit is based on safety analysis assumptions, since RCP seal injection flow is not isolated during Safety Injection (SI).
j i
SALEM - UNIT 2 3 3/4 5-2 Amendment No.IIN 109 i
l
W N N*Y CORE COOLING SYSTEMS RASES h LCO is not strictly a flow limit, but rather a flott Mait based on a flow line resistance..Line pressure and flow sust be known to establish the proper line resistance.
Flow line resistance is determined by assuming that the RCS pressure is at normal operating pressure, and that the centrifugal
' charging pusy discharge pressure is greater than or equal to 2430 psig.
Charging pusy header pressure is used instead of RCS pressure, since it is more representative of flow diversion during an accident. The additional LCO modifier, charging flow control valve full open, is required since the valve is designed to fail open. With the LCO specified discharge pressure and control valve position, a f5nw limit is established. This flow limit is used in the sooident analysis.
A provision has been added to emesyt surveillance requirement 4.0.4 for entry into MODE 3, since the surveillance cannot be performed in a lower mode.
h emesytion is pairmitted for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the RCS pressure has stabilized within i 20 psig of normal operating pressure.
N RCS pressure requirement produces the conditions necessary to correctly set the manual throttle valves. h emesytion is limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to ensure timely surveillance completion once the necessary conditions are established.
3/4.5.5 REFUELING MATER STORAGE TANK h OPERABILITY of the RNST 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 14CA.
h limits on RNST min 4== volume and boron concentrations ensure thats (1) sufficient water is available within containment to permit recirculation cooling flow to the core, (2) the reactor will remain suboritical in the cold condition following a small LOCA assuming cosplete mixing of the RNST, RCS, and ECCS water volumes with all control rods inserted ezoopt the most reactive control assembly (ARI-1), and (3) the reactor will remain suboritical in the cold condition following a large break 14CA (break flow area > 3.0 sq. ft.)
assuming cosplete mixing of the RNST, RCS, and ECCS water and other sources of water that may eventually reside in the susy following a lOCA with all control rods assumed to be out (ARO). h 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 minimises the evolution of iodine and minimises the effect of chloride and caustic stress corrosion on mechanical systems and oosponents. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
SALEM - UNIT 2 3 3/4 5-3 Amendment No.II9,189