ML20106D929
| ML20106D929 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/02/1992 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20106D932 | List: |
| References | |
| NUDOCS 9210160125 | |
| Download: ML20106D929 (8) | |
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'o UNITEO STATES.
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1 NUCLEAR REGULATORY COMMISSION l
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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSI
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Amendment No. 65 License No. NPF-47 1.
The Nuclear Reguletory Commission (the Comission) has found that:
A.
The application for amendment.by Gulf States Utilities Company (the.
licensee) dated February 5, 1992, complies with the standards t.nd requirements of the Atomic Energy Act of 1954, as-amended (the-Act),
l and the Comission's rules and regulations set forth in 10 CFR Chapter '-
1 I;
B.
The facility will operate in conformity with the epplication, as-t amended, the provisions of the Act, and the rules'and regulations of a
the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by; l
this-amend.nent can be conducted without endangering-the health and
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safety of the public, and (i;) that such activities will-be conducted-in compliance with the Commission's regulations;.
D.
The issuance of this license amendment will not be = inimical: to the'.
common defense and security or to the-health:and safety of the public; and E.
The issuancc d this amendment is in accordance with 10-CFR'Part 51.0) the Commission, regulations and all applicable requirements.have been satisfied.
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1; ADOCK.05000458 [
'9210160125 921002 I;
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. 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. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 65 and the Environmental Protection Plan contained in Apoendix B, are hereby incorporated in the license.
CSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Suzanne C. Black, Director Project Directort.te l-2 Division of Reactor Projects lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 2, 1992-l 1
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AIJACHMENT TO LICENSE AMENDMENT NO. 65 fA(1LITY OPERATING LICENSE NO. NPF-41 DOCKET NO. 50-458 Replace the following page of the Appendix *A" Technical Specifications with the encicsed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
The overleaf page is provided to maintain document completeness.
REMOVE INSERT 3/4 5-5 3/4 5-5
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B 3/4 5-2 B'3/4 5-2 B 3/4 5-3 8 3/4 5-3 4
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) e.
At least once per 18 months for the ADS by:
1.
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
2.
Manually opening each ADS valve when the reactor steam dome pressure is greater than or eqt'Al to 100 psig* and observing that:
a)
The control valve or bypass valve position responds accordingly, or b)
There is a corresponding change in the measured steam flow, or c)
The acoustic monitoring system indicates the valve is open.
f.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the Division I and II ADS air supply systems, by verifying the associated ADS accumulator air supply header pressure is greater than or equal to the required minimum pressure of 131 psig.
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
RIVER BEND - UNIT 1 3/4 5-5 Amendment No. 65
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[MERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION
- 3. 5. 2 At least two of the following shall be OPERABLE:
a.
The low-pressur-core spray (LPCS) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.
b.
Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppres-sion pool and transferring the water to the reactor vessel.
c.
Low pressure coolant injection tLP01) subsystem "B" of the RHR system with a flow path capable Jf taking sottion from the suppres-sion pool and transferring the water to the reactor vessel.
d.
Low-pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of taking suction from the suppres-sion pool end transferring the water to the reactor vessel.
The high pressure core spray (HPCS) system with a flow path capable e.
of taking suction from the condensate storage tank or suppression pool, as applicable, when these sources of water are OPERABLE per Specification 3.5.3.b, and transferring the water through the spray sparger to the reactor vessel.
APPLICABILITY:
OPERATIONAL CONDITION 4 and 5*.
ACTION:
With one of the above required subsystems / systems inoperable, restore a.
at least two subsystems / systems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel.
b.
With both of the above required subsystems / systems inoperable, susoend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel.
Restore at least one subsystem / system to OPERABLE status-within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish PRIMARY CONTAINMENT INTEGRITY -FUEL HANDLING-within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- The ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the upper containment fuel pool gate is opened, and water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.
RIVER BEND - L' NIT 1 3/4 5-6
BASES _
3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN ECCS division I consists of the low pressure core spray system and low-pressure coolant injection subsystem "A" of the RHR system and the automatic depressurization system (ADS) as actuated by ADS trip system "A".
ECCS divia sion 11 consists of low pressure coolant injection subsystems "B" and "C" of the RHR system and the automatic depressurization system as actuated by ADS trip system "B".
The low pressure core spray (LPCS) system is provided to assure that the core is adequately cooled following a loss-of-coolant accident and, together with the LPCI system, provides adequate tore cooling capacity for all break sizes up to and including the double-ended reactor recirculation line break, and for smaller breaks following depressurization by the ADb.
The LPCS is a primary source of emergency core cooling after the reactor vessel is depressurized and a source for flooding of the core in case of accidental draining.
The surveillance requirements provide adequate assurance that the LPCS system will be OPERABLE when required.
Although all active components are testable and full flow can be demonstrated by recirculation t*ough a test loop during reactor operation, a complete functional test requires reactor shutdown.
The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.
The low pressure coolant injection (LPCI) mode of the RHR system is provided to assure that the core is adequately cooled following a loss-of-coolant accident.
The LPCI system, together with the LPCS system, provides adequate core flooding for all break sizes up to and including the double-ended reactor recirculation line break, and for small breaks following depressurization by the ADS.
The surveillar.ce "equirements provide adequate assurance that the LPCI system will be OPERABLE when required.
Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test requires reactor shutdown.
The pump discharge piping is maintained full to prevent water hamrer damage to piping and to start cooling at the earliest moment.
ECCS division III consists of the high pressure core spray system.
The high pressure core spray (HPCS) system is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the reactor cuolant system and loss of coolant which does not result in rapid depressurization of the reactor vessel.
The HPCS system permits
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the reactor to be shut down while maintaining sufficient reactor vessel water inventory until 1 i vessel is depressurized. The HPCS system operates over a range of 0 to 1177 psi differential pressure between reactor vessel and HPCS suction source.
RIVER BEND - UNIT 1 B 3/4 5-1
3/4.5 JMERGENCY CORE C00LIN_LSL7JB BASES ECCS - OPERATING and SHVTDOWN_!fl,ontinued)
The capacity of the HPCS rystem is selected to provide the rettuired core cooling. The HPCS pump is designed to deliver greater than or equal to 467/1400/5010 gpa at differential pressures of 1177/1147/200 psid.
Initially, water from the condensate sto7 age tank is used instead of injecting water from the suppression pool into the reactor, but no credit is taken in the safety analyses for the condensate 'itorage tank water.
With the HPCS systen inoperable, adequate core cooling is assured by the OPERABILITY of the redundant and diversified automatic depressurization system and both the LPCS and LPCI systems.
In addition, the reactor core isolation cooling (RCIC) system will automatically provide makeup, at reactor operating pressures, on a reactor 1r,w water level condition. The HPCS out-of-service period of 14 days is based on the demonstrated OPERABILITY of redund:nt and diversified low pressure core cooling sys; ems.
The surveillance requirements provide adequate assurance that the HPCS system will be OPERABLE when required. Although all attive compnnents are testable and full flow can be demonstrated by r+culation through a test loop during reactor operation, a complete fur-
' test with reactor vessel injection requires reactor shutdown.
The pump narge piping is maintained full to prevent water hammer damage and to prov.Je cooling at the earliest moment.
Upon failure of the HPCS system to function properly after a small break loss-of-coolant cccident, the automatic depressurization system (ADS) automatically causes selected safety / relief valve; to open, depre:,surizing the reactor so that flow from the low pressure core cooling systems can enter the core ir time to limit fuel cladding temperature to less than 2200*F. AD5 is conser.atively required to be OPERABLE whenever reactor vessel pressure exceeds 100 psig. This pressure is substantially below that for which the low pressure core cooling systems can provide adequate core cooling for events requiring ADS.
ADS automatically controls seven selected safety / relief valves although the safety analysis only takes credit for six valves.
It is therefore appropriate to permit one valve to be out-of-service for up to 14 days without materially reducing systes reliability.
During normal plant operations, ADS and non-ADS safety / relief valve (SRV) accumulator pressure is maintained by the non-safety related SVV compressors.
Post-accident air pressure for SRV actuation is supplie<' by the afety-related Penetration Valve Leakage Control System (PVLCS) co y.e!. sors. Since PVLCS compressors are not loaded on to the safety-related, divisional electrical buses until 10-20 minutes after the start of an accident, the pneumatic force for any ADS SRV actuations required during the-initial stage of an accident must be providad by ADS accumulator air pressure.
l RIVER BEND - UNIT 1 B 3/4 5-2 Amendment Ns. 65
e 3/4.5 EMERGENCY CORE COOLING SYSTEM BASES ECCS - OPERATING and SHUTDOWN (Continued)
The required minimum ADS' accumulator air supply header pressure must be greater than or equal to 131 psig during normal plant y arations to ensure that the design and licensing basis requirements are satisfied (2 ADS actuations with drywell pressure at 70% of drywell design pressure or 4-5 actuations at atmo;pheric pressure w.thout makeup air).
Long-term, post-accident operability of ADS is assured with the PVLCS supplying air at a pressure greater than or equal 1: 101 psig.
Pressure indication and 'ev
..sure alarm channels are provided in the Main Contr,1 Room for both di
.onal ADS SRV accumulator air supply headers.
3/4.5.3 SUPPRESSION POOL The suppression pool is required to be OPERABLE as part of the ECCS to ansure that a sufficient supply of v0er is available to the HPCS, LPCS and LPCI systems in the event of a LOCA. This limit on suppression pool minimum water volume ensures that sufficient water is available to permit recirculation cooling flow to the core.
The OPERABILITY of the suppression pool in OPERATIONAL CONDITIONS 2 or 3 is required by Specification 3.6.3.1.
Repair work might require making the suppression pool inoperable.
This specification will permit those repairs to be made and at the same time give assurance that the irradiated fuel has an adequate cooling water supply when tht suppressiun pool must be made inoperable, including draining, in OPERATIONAL CONDITION 4 or 5.
In OPERATIONAL CONDITIONS 4 and 5 the suppression pool minimum required water volume is reduced because the reactor coolant is maintained at or below 200'F.
Since pressure suppression is not required below 212*F, the minimum required water volume is based on NPSH, recircu~ tion volume, vortex prevention, and a 2' 6" safety margin fo* conservatism.
The suppression pool pumpback system (5
) is a subsystem designed to ensure suppression pool level; therefore the OPERABILITY of the Suppression Pici can be maintained in the event of a passive ECCS failure. _The ECCS p, ring compon1nts which may experience passive failures will not result in flooding of the ECCS equipment cubicles because the rooms are located in waterticht cubicles. The system design basis is for a maximum unisolatable ieak into the auxiliary building crescent room of 50 gpm.
Each of the manually operated SPPS subsystems consists of two crescent room sumps each with two 100% capacity pumps.
In the event one subsystem becomes inoperabie, a functional test of the operable subsystem is performed in lieu of a full-(92 day) surveillance test because of the difficulty in performing the full test and the pumps are used in~ normal plant operation.
This will provide the plant staff additional awareness of the systems condition.
RIVER BEND - UNIT 1 B 3/4 5-3 Amendment No. 7S, 65