ML20086P757
| ML20086P757 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 12/03/1991 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086P760 | List: |
| References | |
| NUDOCS 9112270186 | |
| Download: ML20086P757 (7) | |
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UNITED 5TATES NUCLE AR REGULATORY COMMISSION
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GULF STATES UTILITIES COMPANY h
DOCKET NO. 50-458 i
RIVER BEND STATION, UNIT 1 l
AMENDMENT'f0 FA'CILITY OPERATING LICENSE
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Amendaent No. 62
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License No. NPF-47 1.
The Nuclear Re0ulatory Commission (the Commission) has found that:
A.
The application for amendment by Gulf States Utilities Company (the licensee) dated June 26, 1991,. complies with the standards and requirements of. the Atomic Energy Act-.of 1954,: as t amended
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(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 app 1'ication as.
amended, 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 safety of the public, and (ii)..that'such activities will be conducted in compliance with the Commission's regulations; t:
D..
The issuance of-this~ license amendment will not be inimical"to the l
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 Ma Commission's regulations and all; applicable requirements 'have-been satisfied.
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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 *.icense No. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Envi_ronmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 62 and the Environmental Protection Plan contained in Appendix B, are hereby incorporatted in the license.
GSU 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 and to be implemented within 60 days of date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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+M Suzanne Black, Director Project Directorate IV 2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 3, 1991 t
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ATTACHMENT TO LICENSE AMENDMENT NO 62 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment nLaber and contain vertical lines indicating the area of change.
The overleaf pages are 1
provided to maintain document completeness.
REMOVE INSERT 3/4 8-10 3/4 8-10 3/4 8-11 3/4 8 11 B 3/4 8-2 8 3/4 8-2 0 3/4 8-3 B 3/4 8 3 f
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4 ELICTRICAL POWER SY$TEMS
$URVEILLANCE RIOUIREMENTS (Continued) 10.
Verifying the diesel generator's capability to a)
Synchronize with the effsite power source, while the gener-ator is loaded with its emergency leads, won a simulated restoration of offsite power, b)
Transfer its loads to the offsite power source, and c)
Se restored to its standby status.
11.
Verifying that, with'the diesel generator operating in a test l
mode and connectori to its bus, a simulated ECC$ actuation signal-overrides the test. node by (1) returning the diesel generator to standby opetStion and (2)'automatica ly energizing the emer-gency loads with effsite. power.
12.
Verifying that the autom84c lead sequence timers arc OPERABLE
-l with the interval betweep e&ch load block within i 10E of its design interval for ciott) generators 1A, la and IC.
13.
Verifying that the following diesel generater lockout features -
prevent diesel generator starting only when required a)
For Diesel Generators 1A and 18:
1)-
Less of. control power to diesel control panel.
2 Starting air pressure below 150 psi.
3 Stop solenoid energized.
i 4
Diesel in the maintenance mode (includes barring device engaged).
5)
Overspeed trip device actuated.;
l 6)
Generator backup protection lockout relay tripped.
b)
For Diesel Generator IC:
1)
Diesel generator lockout relays not reset.
2)
Diesel engine mode switch not in "AUT0" position.
3)
Diesel dissel. generator output breaker closed before start of 4)
Diesel Der. orator Loutput bceaker Lin rackeddout position.
5) tDiesel-generater regulator' mode switch not in."AUT0" position..
6)
Insufficient-starting air pressure.'
7)_
Loss of de power.to diesel. generator controls, g.
By verU ving the Division 111 diesel generator ambient room temperature to be 9 0'F:
1.
At t once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the-last reported room temperature t! tem 5) does not electrically block diesel generator-from emergency starting;'
however, it will' affect the loading and operation of the diesel.
RIVER BEND - UNIT 1 3/4'B-9l Amendment. No. L, 43 '
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUJ3rMEt(15 (Continued)
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At her',.tnce per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with the last reported room temperature
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At 10a9t abn per 10 years, or af ter any modifications which could af fect (1449) (tenerator interdependence, by starting all three diesel generett r4 ritav'staneously, during shutdown, and verifying that all three di$1el geoorators accelerate to at least 450 rpm for diesel generet+rs.1k and 18 and'900 rpm for diesel generator 1C in less than or egy4) to 10 seconds, i
At least'ohmt per 10 years by:
1.
Drainino each fuel oil' storage tank, removing the accumulated sediment, and cleaning the tank using a sodium hypochlorite or equivalent solution, and 2.
Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection N0 of the ASME Code, in accordance with ASME Code Section XI Article IWD-5000.
4.8.1.1.3 Rentet;[ - All diesel generator failures, valid or non-valid, shall be reported to thn Conmission, pursuant to Specification 6.9.2, ion recom within 30 days.
Reports of diesel generator failures shall include the informat in Regulatory Position P.3.b of Regulatory Guide 1.108, Revision 1, August 1977.
If the number of failures in the last 100 valid tests of any diesel generator, is greater then or equal to 7, the report shall be supplemented to include the additional infonnation recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, IRevision 1, August 1977.
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- RIVER BEND - UNIT 1 3/4 8-10 Amendment No. ' 62_
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_ TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE Number of failures Number of failures in in Last 100 Valid Last 20 Valid lests*
Tests
- Test frequency 5 1 14 Once per 31 days 32 15 Once per 7 days **
" Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, but determined on a per diesel generator basis.
For the purposes of determining the required test frequency, the previous test failure count may be reduced to zero if a complete diesel overhaul to like-new condition is completed, provided that the overhaut, including appropriate post-maintenance operation and testing is specifically approved by the manufacturer and if acceptable reliability has been demonstrated.
The reliability criterion shall be the successful completion of 14 consecu-tive tests in a single series.
Ten of these tests shall be in accordance with the routine Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 and four tests in accordance with the 184-day testing requirement of Surve111-ance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5.
If this criterion is nst satisfied during the first series of tests, any alternate criterion to be used
- o trtnsvclue the failure count to zero requires NRC approval.
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- This test frequency shall Le maintained u til seven consecutive failure l
n free demands have been performed and the number of failures in the last 20 valid demands has been reduced to one or less.
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l RIVER BEND - UNIT 1 3/4 8-11 Amendment No. 62
ELECTRICAL POWER SYSTEMS A.C. SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
One circuit between the offsite transmission network and the onsite a.
Class 1E distribution system, and b.
Diesel generator lA or IB, and diesel generator 1C when the HPCS system is required to be OPERABLE, with each diesel generator having:
1.
A day fuel tank containing a minimum of 316.3 gallons of fuel, 2.
A fuel storage system containing a minimum of 45,495 gallons of fuel, and 3.
A fuel transfer pump.
APPLICABILITY:
OPERATIONAL CONDITIONS 4, 5, and *.
ACTION:
With less than the above required A.C. electrical power sources a.
OPERADLE, suspend CORE ALTERATIONS, handlin; of irradiated fuel in the primary or secondary containment, operations with a potential for draining.the reactor vessel, and crane operations over the spent fuel storage pool when fuel assemblies are therein.
In addition, when in OPERATIONAL CONDITION 5 with the water level less than 23 feet above the reactor pressure vessel flange, immediately initiate correc-tive action to restore the required power sources to OPERABLE status as soon as practical, b.
With diesel generator 10 of the above required A.C. electrical power sources inoperable, restore the inoperable diesel generator 1C 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 declare the HPCS system and the C SSW pump inoperable and take the ACTION required by.Specifica-tions 3.5.2, 3.5.3 and 3.7.1.1.
The provisions of Specification 3.0.3 are not applicable.
c.
- When handling irradiated fuel in the primary containment or Fuel Building.
RIVER BEND - UNIT 1 3/4 8-_12
e.
3/4.8 ELECTRICAL POWER SYSTEMS DASES 3/4.8.L 3/4.8.2 and 3/4.8.3 A.C. SOURCES. D.C. SOURCES and ONSITE POWER D151RIBUEdII~5iSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for the safe shutdown of the facility and the mitigation and control of accident condi-tions within the facility.
The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10 CFR Part 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility o)eration commen-surate with the level of degradation.
The OPERABILITY of tae power sources is consistent with the initial condition assumptions of the safety analyses and is based upon maintaining OPERABLE at least Division I or II of the onsite A.C. and D.C. power sources and associated distribution systems during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. or D.C. source.
Division III supplies the high pressure core spray (HPCS) system and the standby service water pump ISWP*P2C with its auxiliarien.
The A.C. and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, " Ave.11 ability of Electrical Power Sources," December 1974, as modified by plant-specific analysis and diesel generator manufacturer's recomendations.
When diesel generator IA or IB is inoperable, there is an additional ACTION requirement to verify that all required systems, subsystems, trains, components and devices that depend on the remaining OPERABLE diesel generator IA or 18 as a source,of emergency power, are also OPERABLE.
This requirement is intended to provide assurance that a loss of offsite power, during the period that diesel generator IA or IB is inoperable, will not result in a complete loss of safety function of critical systems.
The term verify, as used in this context, means to administrative 1y check, by exac.ining logs or other information, to determine if certain components are out of service for mainte-nance or other reasons.
It does not mean to perform the turveillance require-ments needed to demonstrate the OPERABILITY of the component.
l The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems, during shutdown and refueling, ensures that the facility can be maintained in the shutdown or refueling condition for extended time periods and sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.
The surveillance requirements, for demonstrating the OPERABILITY of the diesel generators, are in accordance with the recommendations of Regulatory Guide 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10, 1971, and Regulatory Guide 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977, as modified by diesel generator manufacturer's recommendations. plant-specific analysis and RIVER BEND - UNIT 1 B 3/4 8-1
t ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. rf,. SOURCES and DNSITE POWER DISTRIBUTION SYSTEMS (Continued)
Generic Letter 84-15 prescribed increasing the surveillance test frequency where previous testing indicated a reliability of less than or equal to 0.95/ demand until restored reliability was demonstrated.
It also
^
considered a prescriptive testing program which included seven consecutive successful demands without a failure of the DG.
The test frequency of Table 4.'8.1.1.2-1 is based on the criteria goals of an overall reliability of > 95% and to attain 3 90% prior to returning to monthly testing.
There is a requirement to return to weekly testing if the number of failures is greater than or equal to 2 in 20 or 5 in 100.
The note to the table (footnote """) explains that whenever failures in excess of one in 20 or five in 100 last valid tests an accelerated test frequency must be maintained.
This weekly (accelerated) test schedule is continued until-two conditions have been satisfied.
First, seven consecutive successful tests have been accumulated, and second, the failures in the most recent 20 tests have been reduced to one or lesse Seven successful tests indicate a reliability of at least 0.90/ demand.
Continuing the accelerated testing until the number of failures is one or less out of 20 adds further assurance that the DG reliability has not degraded below the 0.90/ demand level.
After each failure the criteria will be reviewed for reentry into once per weekly testing.
The surveillance requirements for demonstrating the OPERADILITY of the u*it batteries are in accordance with the recommendations of Regulatory Guide 1.129 " Maintenance Testing and Replacement of Large Lead StoraDe Batteries for Nuclear Power Plants", February 1978, and IEEE Std 450-1975, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."
Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, and connec-tion resistance values, and performing battery service and discharge tests, ensures the effectiveness of the charging system and the ability to handle high discharge rates, and compares the battery capacity at that time with the rated capacity.
Table 4,8.2.1-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity.
The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and.015 below the manuf acturer's nominal full charge specific gravity, or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity.
The normal limits for each connected cell for float voltage and specific gravity, Creater than 2.13 volts and not more than.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than
.010 below the manufacturer's full charge specific gravity, ensures the OPER-ABILITY and capability of the battery.-
RIVER BEND - UNIT 1 B 3/4 8-2 Amendment No. 62
4 ELECTRICAL POWER SYSTEM,5 BASES A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8.2.1-1 is permitted for up to 7 days.
During this 7 day period:
(1) the allowable values for electrolyte level ensures no physical damage to_the plates so that they retain an adequate electron transfer capability; (2) the allowable value for the average specific i
gravity of all the cells, not moro.than.020 below the manufacturer's recom-mended full charge specific gravity, ensures that the decrease in rating will-be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity ensures that an individual cell's spe-cific gravity will not be more than.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be main-tained within an acceptable limit; and (4) the allowable value for an indi-vidual cell's float voltage, greater than-2.07 volts, ensures the battery's capability to perform its design function.
3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations, penetration conductors, main control room lighting, and RPS alternate source of power are protected by either.
de-energizing circuits not required during reactor operation or demonstrating the OPERABILITY of the overcurrent protection circuit breakers and/or motor starters by periodic surveillance.
The surveillance requirements applicable to lower voltage circuit breakers and/or motor starters provide assurance of breaker and starter reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker and/or starte,
Each manufacturer's molded case and metal case circuit breakers and/or more starters are grouped into representative samples which are tested on a rotating basis to ensure that all breakers and/or star-ters are tested.
If a wide variety exists within any manufacturer's brand of cricuit' breakers and/or motor starters, it.is necessary to divide that manufac-turer's breakers and/or starters into groups and treat each group as a separate type of breaker or starter for surveillance' purposes.
Specific surveillance tests on the bypass circ' lts of motor-operated valves' u
thermal overload protection is not: required at. River Bend because the circuits are integral with the starting circuits of_the motor operated valves and are therefore tested during functional tests of_the' valves.
For the motor operated valve thermal overloads not bypassed. the thermal overloads are tested under Specification 4.8.4.1.a.3._ These surveillance requirements are in accordance with RG 1.106,'" Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.
The reactor protection system (RPS) electric power _~menitoring assemblies provide redundant protection to the RPS, and-to other systems-tnt to.dve power from the RPS buses, by acting to disconnect the RPS-from the po<er source c M-cuits in the presence of an electrical fault'.in the' power-Supp'y.
RIVER BEND _- UN P 1!
B 3/4 8-3 Amendment No. 62-i
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