ML20205M897
| ML20205M897 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/28/1988 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20205M892 | List: |
| References | |
| NUDOCS 8811030343 | |
| Download: ML20205M897 (9) | |
Text
p RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES IAhlt 2192 4.1-2 HINIMUM EQU7aHENT TEST FRtQUENCY 4-8 4.1-3 HINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY HITHDRAHAL SCHEDULE AT EAVIS-BESSE 1 4-12b 4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-34j 4.6-2 ADDITIONAL RELIABILITY ACTIONS 4-34k 4.6-3 NUCLEAR SERVICE BATTERY SURVEILLANCE REQUIREMENTS 4-34n l
4.14-1 SNUBBERS ACCESSIBLE DURING P0HER OPERATIONS 4-47d e 4.17-1 HINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-28 STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDRATER HEATER SURVEILLANCE 4-S7b.c 4.19-1 RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS 4.21-1 RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAH 4-70 4.21-2 RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-72b 4.22-1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUM VALUES FOR THE LOHER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS HIXTURE INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4 98 4.34-1 METEOROLOGICAL HONITORING INSTRUMENTATION 4-94 6.2-1 HINIMUM SHIFT CREW COMPOSITION
(.2 Proposed Amendment No. 28, f6, 76, 28, 9A, 96, 97, 96, 169 x
!!P988M 8u886 P
PNV
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.6.4 Eusitar Service B dtary_0pirability Apolicability HEATUP-C00LDE, through POWER OPERATION Specifica11.on Each 125 volt DC Nuclear Service battery and battery charger shall be demonstrated OPER/BLE:
a.
At least weekly by verifying that:
1.
The Category A parameters listed in Table 4.6-3 meet their Limits, i
and 2.
The total battery terminal voltage is greater than or equal to 125 volt DC when on float charge.
b.
At least quarterly and within 7 days after a battery discharge with battery terminal voltage below 105 volts, or battery overcharge with battery terminal voltage ab w e 145 volts, by verifying that:
1.
The Category B parameters listed in Table 4.6-3 meet their Limits, ard 2.
The electrolyte temperatures of a representative sample of cells, consisting of at least every sixth cell, are within 5'F of each other.
c.
At least every refueling interval by verifying that:
1.
The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.
2.
The cell-to-cell and terminal connections are clean and coated with an anti-corrosion material, 3.
The total resistance of each cell-to-cell and terminal connections is less than or equal to 20% above an established base-line or benchmark value, and 4.
The battery charger will supply at least the established current output necessary to re-charge the battery in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less following an emergency discharge.
Proposed Amendment No. 46, 94, 97, 169 4-34h
RANCHO SECO UNIT 1 TECHNICAL SPECIFICAT!ONS Surveillance Standards 4.6.4 gutisar service Battsry_00srability (Continued) l d.
At least once per refue,ing interval, during COLD SHUTDOHN, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for the design duty cycle or load profile when the battery is subjected to a battery service test.
e.
At least once per 60 months, during COLD SHUTDOWN, by verifying that the battery is at least 80% of the manufacturer's rating when subjected to a performance discharge test.
This performance discharge test may be performed in lieu of the battery service test required by Specification 4.6.4.d.
l f.
Nuclear Service inverters $1A2, S182, SIC 2, and S102 and static switches H8TA3, H8TB3, H8TC3, and H8TD3 for 120 volt AC vital bus power, and each vital 125 volt DC bus SOA, SOB, 50C, 500. SOA2, SOB 2, SOC 2, and S002 shall be determir.ed OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability with an overall voltage of greater than or equal to 120 volts AC and 125 volts DC, respectively.
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Proposed Amenveent No. 37, 169 4,34g
RANCHO SECO UNIT 1 1ECHNICAL SPECIFICATIONS Surveillance Standard TABLE 4.6-3 NUCLEAR SERVICE BATTERY SURVEILLANCE REQUIREMENTS II)
CATEGORY B(2)
CATEGORY A Limits for Each Limits for Each Allowable Value for(3)
Parameter Designated Pilot Cell Connected Cell Each Connected Cell Electrolyte Level
> minimuin level
> minimum level
%cve top of separator indication mark, and indication mark, plate, and rot i 1/4" above maximum and 1 1/4" above overflowing level indication mark maximum level indication mark Float Voltage 1 2.13 volts 1 2.13 volts
> 2,07 volts Specific Gravity (4) 1 1.200 1 1.195(5)
Not more than 0.020 15) below the average of all connected cells l
Average of all
/verage of all l
connected cells 1 1.195(5) cells connected 1 1.200 1
(1) For any Category A parameter outside its Limit, the battery may be considered operable provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the Category B measurements are taken and found to be within their Allowable Values, and the Category A & B parameters are restored to within their Limits within the next 6 days.
(2) For any Category B parameter outside its Limit, the battery may be considered operable provided that each Category B parameter is witnin its Allowable Value and is restored to within its Limit within 7 days.
(3) Hith a Category B parameter not within its Allowable Value, declare the battery inoperable.
(4) Corrected for electrolyte temperature and level.
(5) Or battery charging current is less than 2 amps when the cattery is on float charge.
Proposed Amendment No. 169 4-34n
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Balti The operability of the offsite circuits, the nuclear service 4160V buses, and the nuclear service 480V buses are demonstrated by verifying correct breaker alignments and indicated power availability.
Surveillance 4.6.1.B i
can only be performed during a refueling shutdown when both diesel generator i
trains are operable or the core is flooded to 37 feet to ensure the required decay heat removal capability is available.
The tests specified are designed to demonstrate that the diesel generators will provide power for operation of safety features equipment.
They also assure that the emergency generator control system and the control systems for the safety featutes equipment will function automatically in the event of a loss of all normal a-c station service power, and upon receipt of a safety features actuation signal.
The testing frequency specified is intended to identify before it can result in a system failure.
The fuel oil supply, starting circuits and controls are continuously monitored arid any faults are alarmd and indicated. An abnormal condition in there systems would be signaled without having to place the diesel generators on test.
I The limiting of the maximum load on the TOI diesel generators A2 and 82 to less than the qualified load of 3300 kw provides acsurance that the crankshafts will stay within the proven limits for high-cycle fatigue cracks.
Diesel generators A2 and M will be loaded during surveillance testing I
between 3000 and 3300 KH which provides assurance that the qualified load of 3300 KH will not be exceeded.
At least once per refueling outage a diesel generator test will be W rformed simulating a loss of off-site power in conjunction with a simulated SFAS and loading of actual loads to the maximum extent possible without damaging plant systems (i.e., ese of recirculation flow or manual valving out a 1
1 system to protect plant components).
I Precipitous failure of a Nuclear Service battery is extremely unlikely.
The surveillance requirements demenstrate th< operability of the batteries and are in accordance with the Standard Technical Specifications (NUREG-0103 and NUREG-0452).
The surveillance will provide indication of a cell becoming unserviceable before it falls.
~
REFERENCES i
(1)
IEEE 308 (2)
IEEE 450 t
i Proposed Amendment No. 31, (8, 74, 87, 94, 169 4-35
ATTACHMENT II Safety Analysis and No Significant Hazards Consideration for Proposed Am.idment No.169
Proposed Amendment No. 169 Log Mc. 1079 Safety Analysis Report Page 1 of 3 Delctlp11ofLDf_Ch4D90 The 125 volt DC Nuclear Service battery surveillance requirements are modified in accordance with the requirements stated in the Standard Technical l
Specifications, NUREG-0103 and NUREG-0452.
The format and content of the Standard Technical Specifications are ariopted for application to the 125 volt DC Nuclear Service battery surveillance, Specification 4.6.4.
A comprehensive table is added which describes the and actions required if a Limit or Allowable Value is vioin:
'rability limits surveillance requirements for the batteries and defines the The basis for the Nuclear Service battery surveillance rJqtb v is modified to reflect the c5anges proposed in this proposed ai e to the Technical Specifications. Also, the inder to the lechnical Spechications is modified to reflect the addition of the battery surveillan:e requirement table.
Eurpost. oLChangt The prcposed changes to the 125 volt DC Nuclear Service battery strvelliance are sou;nt to make the battery surveillance Specification consistl'It with the requirements of the Standard Technical Specifications The StanJacd Technical Specifications provide operational flexibility when a battery surveillance parameter is outside its Limit.
Safaty_Euntilons of Affacted_SyitensICosconents The system affected by the proposed changes is the vital 125 volt DC syttem.
The components affected are the 125 volt DC Nuclear Service batteries.
The vital 125 volt DC system provides a r211able source of power for DC l
motors, instrumentation, and controls.
The system is arranged such that a single failure or fault will not prevent the safety related equipment powered by the vital 125 volt DC system from performing its safety function.
The 125 volt Nuclear Service batteries are safety related.
Each battery 's sized with sufficient capacity to carry its respective loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The Nuclear Service batteries are diesel backed through the 480 volt Nuclear i
Service Motor Control Centers which supply power to the Nuclear Service l
battery chargers.
AnalytiLof_LiitttLofLSafetylunctions The prcposed modification to the Nuclear Service battery Specification incorporates the surveillance requirements specified in the Standard Technical Specifications. Modifying the surveillance requirements so they are consistent with the content and format of the Standard Technical I
i Specifications will not reduce the ability of the Nuclear Service batteries to perform their safety function.
The proposed surveillance requirements will ensure the Nuclear Service batteries are properly maintained, and that the appropriate operability restrictions are imposed when a survelliance parameter Limit or Allowable Value is not met. Adherence to the proposed surveillance requirements will give assurance that a battery which is considered operable will be able to perform its safety function.
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Proposed Amendment No. 169 Log N@. 1079 i
Safety Analysis Report Page 2 of 3
)
'l Analy11s of-Efhc_ts_ofLSdttyluncilons (Continued)
A surveillance requirement, which periodics11y verifles that the spacing l
between each Nuclear Service battery cell and between each end cell and the t
battery rack are within seismic design tolerances, is removed.
Neither the l
Standard Technical Specifications (NUREG-0103 and NUPEG-0472), the vtidor i
manual for the batteries, or IEEE Standard 450-1987 contain a requiremant or i
recommendation to survell the cell spacing of plant batteries. Cell spacing is a design and installation requirement, iach cell is installed per vendor l
drawings and instructions.
These drawings and instructions contain the i
battery cell spacing specifications required tc6 meet the seismic goalific1 tion cequirements for Nuclear Service batterics.
Spacing requirements are terified t
Lpon installation of the batteries.
Based on the abov2, it is unnecessary to require a cell spacing surveillance for e a Nuclear Service batteries.
The proposed surveillance requirements are in accordance with NUREG-0103 and
(
NUREG-0452 and are consistent with IFEE Standard 450-1987 and the batt1rv vendor manual recommendations. The proposed requirement! provide a mechanism t
by which early detection of a failing cell is possible.
The procosed requirements allow sufficient time for corrective acticn to be taken before a battery must be declared ir. operable.
Sussnary l
l Modification of the Nuclear Service tattery st.rveillance Specifica', ton in j
accordance with the Standard Technical Specifications (NUREGs 0103 and 0452)
{
is proposed. The proposed change
- will provite operational flexibility if a i
battery surveillance parameter v autside its 1.imit. Tne proposed t
surveillance requirements and associated 'imits and actions will ensure the Nuclect Service batteries are proper 1) maintained, appropriate operability
[
restrictions are imposed, and sufficient time is allowed for corrective action
)
if a failing cell is detected.
[
The USAR was reviewed (Section 8 Electrical Systems) and a determination made that the proposed changes are within the Licensing Design Basis of the plar.t
[
and that no change to tht USAR is required.
[
Based on the above analysis, the proposed change to the Nuclear u rvice battery surveillance requirements will not increase the probability of occurrence or consequences of an accident previously evaluated in the SAR, or I
create the possibility of occurrsnce of an accident of a different type than previously evaluated in the SAR.
The margin of safety as Jefined in the basis for any Tecnnical Specification is not reduced; therefore, an Unreviewed Safety Question is not involved, f
i i
s Proposed Amendment No. 169 Log N2. 1079 Safety Analysis Report Page 3 of 3 NO SIGNIFICANT HAZARDS CONSIDERATION The District has reviewed the proposed Technical Specification changes against each of the criterion of 10 CFR 50.92 and concluded that the changes discussed in the above safety analysis would not:
a.
Involve a significant increase in the probability or consequences of an accident previously evaluated in the SAR because the proposed surveillance requirements will ensure the Nuclear Service batteries are properly maintained and appropriate operability restrictions are imposed.
The change will not affect the ability of the Nuclear Service batteries to perform their safety function.
b.
Create the possibility of a new or different type of accident than previously evaluated in the SAR because the proposed changes are in accordance with the Standard Technical Specifications (NUREG-0103 and NUREG-0452).
The changes do not create any new failure modes which could cause a new or different accident than previously evaluated.
c.
Involve a significant reduction in a margin of safety because the changes will not create any new failure modes or compromise the ability of the Nuclear Service batteries to perform their safety function.
The proposed Nuclear Service Battery Surveillance will provide indication of a cell becoming unserviceable before it fails.
On the basis of the above, the District concludes that the proposed changes do I
not constitute a significant hazard to the public and in no way endanger the public's health and safety.
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