ML20091C866
| ML20091C866 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/30/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091C869 | List: |
| References | |
| NUDOCS 9204060368 | |
| Download: ML20091C866 (12) | |
Text
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Y UNITED STATES
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NUCLEAR REGULATORY COMMISSION g,
.j WASHINGTON. o.C. 20565 o,
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CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET N0. 50-325 BRUNSWICK STEAM ELECTR'C PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amerc' ment No.157 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated October 16, 1991, complies with the standards and requirerents 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; 3
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the oublic, and (ii) that such activities will be conducted in compliance witn the Commission's reguletions;
~
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 requirements have been satisfied.
2.
Accordingly, the license is amended by changes to tae Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
1 9204060368 920330 PDR ADOCK 05000324 PDR
I i
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I (2)
Technical _Soeci ficat ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No.157, are hereby incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Tect.nical Specifications Date of Issuance: March 30, 1992
s' AITACHMENT TO LICENSE AMENDMENT NO.157 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
k Remove Paaes insert Paaes 3/4 5-1 3/4 5-1 B 3/4 5-1 B 3/4 5-1 F
c f
B 3/4 5-la
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1
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3/4.5 EVERGENCY CCRE CLOLING SYSTEMS 3/4.5.1 HIGH PRESSURE COCLANT INJECTION SYSTEM LIMITIN'; CCNDITICN FOR OPEFATICN 3.5.1 The High Pressure Coolant In]ection (HPCI) system shall bo CPEPABLE with:
a.
One CPERABLE high pressure coolant injection pump, and b.
An CPERABLE flow path capable of taking suction from the suppression pool and transferring the water to the pressure vessel.
APPLICABILITY:
CCNDITIONS 1, I,
and 3 with reactor vessel steam dome pressure greater than 150 psig.
l ACTION:
a.
With the HPCI system inoperable, POWER OPERATION may continue provided the ADS, CSS, and LPCI systems are OPEPAELE; restore the inoperable HPCI system to CPERABLE scatus within 14 days or be in at least HOT SHtTTOCWU within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHtTTDOWN within the following I4
- hours, b,
With the surveillance requirements of Specification 4.5.1 not performed at the required f requencies due to low reactor steam pressure, the provisions of Specification 4.0.4 are not applicable provided the appropriate surveillance is performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reactor steam pressure is adequate to perform the tests.
SURVEILLANCE REOUIRFMENTS 4.5.1 The HPCI shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying that the system piping from the pump dischargo valve to the system isolation valve is filled with water.
BRUNSWICK - UNIT 1 3/4 51 Amendment No. 157
5 3/4.5 FMERGENCY CORE COOLING SYSTEM BASES
[
3/4.5.1 HIGH FRESSURE CQOLANT INJECTICN SYSTEM BACYOROUND:
The High Pressure Coolant In]ection (HPCI) system consists of a steam driven turbine-pump unit, piping and valves to provide steam to the turbine, and piping and valves to transfer water from the suction source to the core via the feedwater system line where the coolant is distributed within the reactor vessel through the feedwater sparger.
Suction piping for the system is provided frem the condensate storage tank (CST) and the suppression pool.
Pump suction for the HPCI system is normally aligned to the CST source to minimize injection of suppression pool water into the reactor vessel.
~
However, if the CST water supply is low or if the suppression pool level is high, an automatic transfer to the suppression pool water source assures a water supply for continuous operation of the HPCI system. The steam supply to the HPCI system turbine is piped from the main steam line upstream of the associated inboard main steam line isolation valve.
The HPCI system is designed to provide core cooling at reactor pressures between 1120 psig and 150 psig.
Upoa receipt of an initiation signal, ths HPCI system turbine stop valves and turbine control valves open simultaneously and the turbine accelerates to a specified speed. As the HPCI system flow increases, the turbine governor valve is automatically adjusted to maintain design flow.
Exhaust steam from the HPCI system turbine is discharged to the suppression pool.
A full flow test line is provided to route water from and to the CST to allow testing of the HPCI system during norral operation without injecting water into the reactor vessel.
The High Pressure Coolant Injection (HPCI) system is provided to assure that the reactor core is adequately cooled to limit fuel cladding temperature in the event of a small break in the nuclear system and loss of coolant which does not result in rapid depressurization of the reactor vessel.
The HPCI system permits the reacter to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. The HPCI system continues to operate until reactor pressure
.4 below the pressure at which Low Pressure Coolant Injection (LPCI) system operation or Core Spray system operation maintains core cooling.
APPLICABILITY:
The HPCI system is required to be OPERABLE during OPERATIONAL CONDITIONS 1, 2,
and 3 when there is considerable energy in the reactor core and core cooling would be required to prevent fuel damage in the event of a break in the primary system piping.
In OPERATIONAL CONDITIONS 1, 2, and 3 when reactor steam dome pressure is less than or equal to 150 psig, the MPCI system is not req 11 red to be OPERABLE because the low pressure ECCS systemc can provide sufficient flow below this pressure.
BRUNSWICK - UNIT 1 B 3/4 5-1 Amendment No.157
f 3/4.5 EMERGENCY CCRE COOLING SYSTEM EAS.ES 3/4.5.1 HIGH PPE,15URE COOLANT INJECTION SYSTEM (Continued)
ACTICNS:
With the HPCI system inoperable, adequate core cooling is assured by the demonstrated operability of the redundant and diversified Automatic Depressurization system and the low pressure cooling systems.
In additica, the Reactor Core Isolation Cooling (RCIC) system, a system for which no credit is taken in the safety analysis, will automatically provide makeup at reactor pressures on a reactor Icw water level condition.
The out of-service reriod of 14 days is based on the demonstrated operability of redundant and diversified low presoure core cooling systems.
SURVEILLANCE REOUIRT' "G.S:
The surveillance requirements provide adequate assurance that the HPCI system will be OPERABLE when required.
Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complet0 functional test requires reactor shutdown.
The pump discharge piping is maintained full to prevent water hammer damage and to provide cooling at the earliest moment.
REFE?ENCES:
1.
Brunswick Steam Electric Plant Updated FSAR, Section 6.3.2.2,1.
2.
Brunswick Steam Electric Plant Updated FSAR, Section 15.1.3.
3.
Brunswick Steam Electric Plant Updated FSAR, Section 15.2.5.
4.
Brunswick Steam Electric Plant Updated FSAR, Section 15.2.6.
5.
Brunswick Steam Electric Plant Updated FSAR, Section 15.5.2.
3/4.5.2 AUTCMATIC DEPRESSURI".ATICN SYSTEM (ADS)
Upon failure of the HFCIS to function properly after a small break loss-of-coolant accident, the ADS automatically causes the safety-relief valves to open, depressurizing the reactor ao that flow from the low pressure cc"'ing system can enter the core in time to limit fuel cladding temperature to less than 2200*F.
ADS is conservatively required to be CFERABLE whenever reactor vessel pressure exceeds 113 psig even though low pressure cooling systems provide adequate core cooling up to 150 psig.
BRUNSWICK - UNIT 1 B 3/4 5-la Amendment No. 157
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UNITED STATES 3
NUCLEAR REGULATORY COMMISSION c, k' f
WASHINGTON, D C. 20056
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CAROLINA POWER & LIGHT COMPANY. el_al DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LLCENSE Amendment No. 188 License No.DPR-62 1
1.
The Nuclear Regulatory Commission (the Commission) has f ound that:
A.
The application for amendment filed by Carolina Power &
Light Company (the licensee), dated October 16, 1991, 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; 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 appiicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the ettachment to this license amendment; and paragraph 2.C.(2) of Fe.cility Operating License No. DPR-62 is hereby amended to read as follows:
)
4~ (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.188, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This lieerise amendment is effective as of the date of its issuane.e and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/ll Of fice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 30, 1992
s ATTACHMENT TO LICENSE AMENDMENT NO.188 FACILITY OPERATING LICENSE NO. OPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 5-1 3/4 5-1 B 3/4 5-1 B 3/4 5-1 B 3/4 5-la i
I 3'
L 3/4.5 EMERGENCY CCRE COOLING SYSTEMS M4.5.1 HIGH PRESSURE COOLANT IN RCTION SYSTEM LIMITING COtGITION FOR OPERATION 3.5.1 The High Pressure Coolant In]ection (HPCI) system shall be OPERABLE with:
a.
One OPERABLE high pressure coolant iniection pump, and b.
An OPERABLE flow. path capable of taking suction from the suppression pool and transferring the water to the pressure vessel.
APPLICABILITY: CONDITIONS 1, 2, and 3 with reactor vessel steam dome pressure greater than 150 psig.
l ACTION:
a.
With the HPCI system inoperable, POWER OPERATION may continue provided the ADS, CSS, and LPCI systems are OPERABLE; restore the inoperable HPCI system to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next-12 hours and in COLD SHUTDOWN within 1.nts following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With the surveillance requirements of Specification 4.5.1 not performed at the required frequencies due to low reactor steam. 9ressure, the provisions of Specification 4.0.4 are not applicable provided the appropriate surveillance ir performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter reactor steam pressure is adequate to perform the tests.
SURVEILLANCE REOUIREMENTS 4.5.1 The HPCI shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1, Verifying that the system piping from the pump discharge valve to the system isolation valve is filled with water.
BRUNSWICK - UNIT 2 3/4 51 Amendment No.1M8
-. _ ~..
n i-L.
3/4.5 EMERGENCY CORE COOLING SYSTEM BASES 3/4.5.1 HIGH PRESSURE COCLANT INJECTION SYSTEM BACMGROUND:
The High Pressure Coolant injection (HPCI) System consists of a steam driven turbine pump unit, piping and valves to provide steam to the turbine, and piping and valves to transfer water from the suction source to the core via tae feedwater system line where the coolant is distributed within the reactor vessel through the feedwater sparger.
Suction piping for the system is provided from the condensate storage _ tank (CST) and the suppression pool.
Pump suction for the HPCI system is normally aligned to the CST source to minimize injection of suppression pool water into the reactor vessel.
However, if the CST water supply is low or if the suppression pool level is high, an automatic transfer to the suppression pool water source assures a water supply for continuous operation of the HPCI system. The steam supply to the HPCI system turbine is piped from the main steam line upstream of the associated inboard main steam line isolatien valve.
The HPCI system is designed to provide core cooling at reactor pressures between 11IO psig and 150 pstg.
Upon receipt of an initiation signal, the HPCI system turbine stop valves and turbine control valves open simultaneously and the turbine accelerates to a specified speed. As the HPCI system flow increases, the turbine governor velve is automatically adjusted to maintain design flow.
Exhaust steam from the HPCI system turbine is discharged to the suppression pool.
A full flow test line is provided to route water from and to the CST to allow testing of the HPCI system during normal operation without injecting water into the reactor vessel.
The High Pressure Coolant Injection (HPCI)' system is provided to assure that the reactor core is adequately cooled to limit fuel cladding temperature in the event of a small break in the nuclear system and loss of coolant which does not result in rapid depressurization of the reactor vessel.
The HPCI system permits the reactor to be shut down while maintaining
. sufficient reactor vessel water level inventory until the vessel is-depressurized.
The HPCI syctem continues to operate until reactor pressure is below the pressure at which Low Pressure Coolant Injection (LPCI) system operation or Core Spray system operation maintains core cooling.
APPLICABILITY:
The HPCI system is required to be OPERABLE during OPERATIONAL CONDITIONS 1, 2,
and 3 when there is considerable energy in the reactor core and core cooling would be required to prevent fuel damage in the event of a break.in the primary system piping.
In OPERATIONAL CONDITIONS 1, 2, and 3
~
when reactor steam dome pressure is less than or equal to 150 psig, the-HPCI system is not required to be OPERABLE because the low pressure ECCS systems can provide sufficient flow below this pressure.
BRUNSWICK - UNIT 2 B 3/4 5-1 Amendment No. 1C0
p t
3/4.5 EFERGENCY CORE C0 CLING SYSTEM ILASIS 3/4.5.1 HIGH PRESSUPE CCOLANT INJEC'"@ SYSTEM (Continued)
ACTICNS:
With the HPCI system inoperable, adequate core cooling is assured by the demonstrated cperability of the redundant and diversified Automatic Depressuritation system and the low pressure cooling systems.
In addition, the Reactor Core Iselation Cooling (RCIC) system, a system for which no credit is taken in the safety analysis, will automatically provide makeup at reactor pressures on a reactor low water level condition. The out-of-service period of 14 days is based on the demonstrated operability of redundant and diversified low pressure core cooling systems.
SUP'.'EILLANCE PEOUIREMEq1:
The surveillance requirements provide adequate assurance that the HPCI system will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculatien during reactor cparation, a complete functional test requires reactor shutdown.
The pump discharge piping is maintained full to prevent water hammer damage and to provide cooling at the earliest moment.
REFERENCES:
1.
Brunswick Steam Electric Plant Updated FSAR, Section 6..) 2.2.1.
2.
Brunswick Steam Electric Plant Updated FSAR, Section 15.1.3.
3.
Brunswick Steam Electric Plant Updated FSAR, Section 15.2.5.
4.
Brunswick Steam Electric Plant Updated FSAR, Section 15.2.6.
r 5.
Brunswick Steam Electric Plant Updated FSAR, Section 15.5,2.
3/4.5.2 AUTOMATIC DEPRESSURI'4ATICN SYSTEM (ADS)
Upon f ailure of the HPCIS to function properly af ter a small break loss of-coolant accident, the ADS automatically causes the safety relief valves to open, depressurizing the reactor so that flow from the low pressure cooling system can enter the core in time to limit fuel cladding temperature to less than 2200'F.
ADS is conservatively required to be OPERABLE whenever reactor vessel pressure exceeds 113 psig even though low pressure cooling systems provide adequate core cooling up to 150 psig.
BRUNSWICK - UNIT 2 B 34 5 la Amendment No.1CE
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