ML20091K844
| ML20091K844 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/21/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20091K824 | List: |
| References | |
| NUDOCS 9508280170 | |
| Download: ML20091K844 (11) | |
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i DEVIATION 2 i
' VARIABLE (3) l i
Containment Hydrogen Concentration DEVIATION FROM RC 1.97 CUIDANCE The range recommended in RG 1.97., Revision 2 is 0 to 30 percent, whereas SQN has provided instrumentation for.this variable with a range.of 0 to 10 percent.
JUSTIFICATION SQN has perfortned an analysis that shows the worst-case hydrogen concentration will be less than 8 percent with the S ow plugs (hydrogen igniters) l operating. Thus, the instrumentation will be on scale at any particular time.
The hydrogen igniters' operat o i h __the cNvJnth and larms.
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nge pTtwrded of 0 o 10 percent is a equa e.
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Reference:
NRC letter to S. A. White dated May 11, 1987, " Emergency Response Capability - Conformance to Regulatory Guide 1.97, Rev. 2 [ TAC 51133/51134)")
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DEVIATION 22
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VARIABI.E (111)
Postaccident Sampling 5
. DEVIATION FROM RG 1.97 CUIDANCE The RG 1.97, Revision 2 (refer to Table 2, Type E variables), recommends that Primary coolant grab sample capability exists for hydrogen analysis.
JUSTIFICATION E0M*: pu tsuid=t sc p11.; f ain ty '.".^.SF) =r =n tly ::: inline escure ent
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af pr' ery ::1:nt hydr:g:r by ; : ch:: tegrepF;.
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Prere-tly, s part of the correcuFe acuon to aQM02, SQN Nuclear Engineer 1 g s conducted a design study to define the scope and d '
schedule for modifying SQN's PASF to provide hydrogen grab sampling capabilities with a range of 10 to 2,000 cc standard temperature and Pressure / kilogram (STP/kg). TVA considers this range to.be sufficient for estimating pos: accident core g dation and_co
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rimary_c ege t: th:t "I previl: at: n r :ppr: cal of SQN s v
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DEVIATION 28 VARI ABLE (111) '
Postaccident Sampling I
DEVIATION FROM RG 1.97 GUIDANCE i
RG 1.97 Revision 2, recommends that the analysis range for boron content in
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the primary coolant and sump be between 0 to. 6,000 parts per million (ppm).
TVA. recommends that the range be between 50 to 6,000 ppm.-
JUSTIFICATION-For boron concentrations ~below-500 ppm, the tolerance for SQN's instrumentation would be limited to plus or minus 50 ppm.
This tolerance band
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is considered'by.TVA to.be acceptable for ensuring that postaccident shutdown margin is maintained-TVA's position is that the current range, capability for boron analysis-(50 to 6,000 ppm) is sufficient.
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Air flow is from areas of lower radioactivity potential to areas of greater radioactivity potential. All exhaust air is monitored for excessive radicactivity levels.
Fire dampers 'are used to prevent the spread of fire between the CDWEB and the waste package area of the Auxiliary Building.
9.4.9.2 Svstem Description The CDWEB ECS is shown on Figures 9.4.2-1 and 9.4.9-1.
Air induced by the CDWEB supply fan from the waste package area supply duct is used for building ventilation.
The ventilation air is supplied to Areas of low radioactivity potential and migrates by naturally induced flow paths to progressively higher areas of contamination.
The CDWEB ventilation exhaust fan exhausts air from the area with highest contamination potential and directs it to the Fuel Handling Area Exhaust System where it is passed through a radiation monitoring station prior to its release to the atmosphere.
The COWEB utilizes one speed ventilation fans. The fans are manually controlled and operate continuously.
Additionally, separate air-conditioning recirculation systems serve the potentially contaminated areas and the moderately contaminated areas.
9.4.9.3 Safety Evaluation No nuclear safety-related systems or components are located in the 2
Condensate Demineralizer Waste Evaporator Building.
Therefore,'a single failure within the EC System will not affect nuclear safety.
l 9.4.9.4 Inscettien and Testing Recuirements The CDWEB ECS will be tested initially to assure that design criteria have been met. Continued satisfactory operation will demonstrate the system capability.
9.4.10 Postaccident Sampline ventilation System 9.4.10.1 Design Basis The postaccident sampling facility environmental control system (PASFECS) provides heating, cooling, and ventilation during normal plant operations and training activities. In addition, heating, ventilation, and control of airborne radiological contamination is provided during postaccident acquisition and testing of samples. This is accomplished through I
pressurization of the areas by the ventilation system which induces air
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from areas of lesser to areas of greater contamination potential. The system maintains temperatures within a range of 50*F to 104*F.
The l6 PASFECS has redundant isolation capability in all ductwork which interfaces with the Auxiliary Building Gas Treatment System (ABGTS) or g
penetrates the Auxiliary Building Secondary Containment Enclosure (ABSCE).
9.4-41 0083F/COC4
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9.4.10.3! System Description The PASFECS is shown on the following figures:
9 4.'30-1 (Flow Diagram 47W866-15),9.4.10-2 (Logic Diagram 47W611-31-9), and 9.4.10-3 Cratrol Diagram 47W610-31-9). The PASFECS consists of a ventilation subsystem (PASFVS), a heating and cooling subsystem (PASFHCS), and a radiological gas treatment subsystem (PASFGTS).
1 9.4.10.2.1 PASFVS i
l 11 Durinff normal plant operation, ventilation air is supplied to the facility via the Unit 2 Auxiliary Building general ventilation system and an auxiliary supply fan. Exhaust air is ducted directly to theI 11 '
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fuel handling area exhaust f ans.
During postaccident conditions or sampling operations, the normal supply and exhaust systems are isolated and ventilation air is taken directly from the outside at a point on the roof of the unit 1 7
additional equipment building. Both the unit 1 and unit 2 systems share this common intake. A supply fan provides air to the sampling side of the facility in response to a differential pressure controller. Air is drawn from both the sample and valve gallery areas and through a gas treatment system by an exhaust f an and routed to the exhaust duct downstream of the ABGTS air cleanup unit. The sarnpling area is maintained at a positive pressure ;>._ O.12 inch WG with respect to atmosphere while the valve gallery is kept at a negative pressure of < O.25 inch WG with respect to the sample side.
9.4.10.2.2 PASFHCS In the normal mode of operation, supply air taken from the unit 2 Auxiliary Building general j
f ventilation system has already been tempered and no additional heating or cooling is required.
6 in the postaccident mode, incoming air is preheated in response to a duct mounted temperature switch. No cooling is provided in this mode. However, the ventilation system will maintain the facility below 104'F with 97'F outside conditions.
9.4.10.2.3 PASFGTS The radiological gas treatment subsystem consists of one HEPA/ charcoal-type air cleanup unit located just upstream of the exhaust f an. Air supplied to the facility during postaccident conditions or sampling operations is processed through the air cleanup unit prior to being discharged to the atmosphere.
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9.4.10.3 Safety Evaluation The PASFECS is not a nuclear safety related system: however, the isolation valves and duct which interface with the ABGTS and ABSCE are f
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designed to Category 1 standards. These valves are also backed by Class 1E power. All remaining portions of the system are designed to Category 1(L) requirements.
9.4.10.4 Inspection and Testina Reauirements.
I 11 The ost Accident Sampling Facility Ventilation Subsystem will be periodically inspected and P
l 17 tested.
. Air cleanup units are designed and tested per the requirements of NRC Regulatory Guide 1.140.
Preoperational tests provided data for the initial balance of the system and verification of design flow rates.
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9.5.10 Postaccident Samplino Facility 9.5.10.1 Design Basis The posta nt ampling factitty (PASF) is designed to safely obtain, transfer taa!yze. nd dispose of, as necessary, samples of reactor coolant, to nt sump water, and the containment atmosphere samples.
Each reactor unit has its own respective PASF that will obtain the necessary samples following a loss of coolant accident (LOCA).
9.5.10.2 Facilities The major components of the postaccident sampling system (PAS) are discussad in the following sections.
sw PuML 9.5.10.2.1 Reactor Coolant and Containment Sump Svstem Each unit has a reactor coolant sampling system equipped with a closed cooling water heat exchanger to cool the sample as it is acquired by the liquid sampling panel (LSP).
Samples are taken from the reactor coolant hot legs and from the containment sump, when the RHR system is in the 5
recirculation mode of operation.
4 9.5.10.2.2 Chemicel Anelysi s Systea.
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Tank which is drained into the tritiated drain collector tank or the containment sump.
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9.5.10.
/ Containment Air Sampi ystem Acquisition of the containment air samples is performed by the Radiological and Chemical Technology (RCT) particulate, iodine, and gas separation system and containment air sample panel (CASP), jointly.
These samples are subsequently transported to an onsite facility for.
Isotopic analysis.
Hydrogen levels in the containment atmosphere are determ n
nt hydrogen monitors.
SA M PLJ N g wn 9.5.10737 Analysi s c4 easiuvie s ON s M
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9.5.1 Design Evaluation i
The design life of all major components, equipment, and instrumentation I
is 40 years.
Items designed for postaccident service will be designed to remain 4 nctional in the expected postacci int environment.
9.5.1./ Tests and Inspections I
The equipment located in the PASF will be tested and inspected to verify equipment operability and availability.
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TABLE 9.5.10-1 SEQUOYAH NUCLEAR PLANT REVISED POSTACCIDENT SAMPLING PROGRAM k
Sample / Analysis.
Analysis Sampling / Analysis Sample / Analysis Samole Point Parameter En.its Ranoe + +
Accuracy Accuracy Resoonse Time Sample Tvoe RCS and/or Cont.
Boron PPM 50 to 6000 1 5 % (1000-6000)*
1 10 % (500-6000)*
8 Hours @,#
Grab Sample Sump **
1 50(50-1000)*
1 50 (50-500)*
RCS and/or Cont.
Gamma uCi/mL isotopic Factor of Two Factor of Two 24 Hours #
Sump' Spectrum Analysis RCS and/or Cont.
Gross uCi/mL 10 to 1E+7 Factor of Two Factor of Two 24 Hours #
Determine by Sump' Activity Totaling Gamma Isotopic Activities RCS and/or Cont.
Chloride PPM O.1 to 20 1 10% (0.5-20)*
1 10% (0.5-20)*
24 Hours (Sampling)# Provisions Are Sump
1 0.05(0.1-0.51' 1 0.05(0.1-0.5)*
96 Hours (Analysis)# Established for Off Site Analysis 1 0 % (50-2000)*
1 20 % (50-2000)*
24 Hours #
RCS Dissolved CC(STP) 10 to 2000 Hydrogen or Kg 1 5.0(10-50)*
15 (10-50)'
Total Gas Containment Gamma uCi/cc Isotopic Factor of Two Factor of Two 24 Hours #
Grab Sample Atmosphere Spectrum Analysis Containment Hydrogen Percent 0 to 10
+ 1.5
+ 1.5 Not Applicable Determine by Atmosphere Reading Containment Hydrogen Analyzers The Containment Sump is Sampled via the Residual Heat Removal System Following a Loss-Of-Coolant Accident.
+ + The Sampling / Analysis Ranges Have Been Approved as Part of the Sequoyah Nuclear Plant Regulatory Guide 1.97 Finalized Program.
Accuracies Are Expressed as 1 Standard Deviation (68% Confidence interval) Uncertainty Estimates.
O If Potential Core Damage is Not Indicated Following an Accident, the RCS Wdt Be Sampled and Boron Analyzed to Verify Shutdown Margin as Soon as Possible in Response to Emergency Procedures.
Following a Potential Core Damage Accident, Sampling / Analysis is Capable of Being Performed Within the Stated Response Times after the Accident.