ML20248M088
| ML20248M088 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/11/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248M089 | List: |
| References | |
| NUDOCS 9806120368 | |
| Download: ML20248M088 (31) | |
Text
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f UNITED STATES e
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NUCLEAR REGULATORY COMMISSION k
WASHINGTON, D.C. 3000640M
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VIRGINIA El FCTRIC AND POWER COMPANY DOCKET NO. 50-280 l
SURRY POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 213 License No. DPR-32 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 18,1997, 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 J
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 l
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.
I l
l 9906120369 990611 l
PDR ADOCK 05000290 i
P PDR
I s 2.
Accordingly, the license is ame'nded by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 213, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
Pa -Tsin Kuo, Acting Director Pr 'ect Directorate ll-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: June 11,1998 i
l 1
1
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- t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION t
t WASHINGTON, D.C. 20066-0001 l
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l i
VIRGINIA ELECTRIC AND POWER COMP 6bD' DOCKET NO. 50-281 l
SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 213 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 18,1997, 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 tacility will operate in conformity with the application, the provisions of the j
Act, and the rules and regulations of the Commission; I
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 applicable requirements have been satisfied.
I i
l l
1 l
s 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Soecificeuons The Technical Specifications contained in Appendix A, as revised through Amendment No. 213, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULA TORY COMMISSION
.c P o-Tsin Kuo, Acting Director P oject Directorate ll-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date oflasuance: June 11,1998 l
D
0 8
4 ATTACHMENTTO LICENSE AMENDMENT AMENDMENT NO. 213 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 213 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCXET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paoes insert Paoes TS 4.1-1 TS 4.1-1 TS 4.1-3 TS 4.1-3 TS 4.1-5 TS 4.1-5 TS 4.1-8c TS 4.1-8c TS 4.1-9a TS 4.1-9a TS 4.1-9b TS 4.1-9b TS 4.1-9c TS 4.1-9c TS 4.1-9d TS 4.1-9d TS 4.2-3 TS 4.2-3 TS 4.2-4 TS 4.2-4 TS 4.5-2 TS 4.5-2 TS 4.5-3 TS 4.5-3 TS 4.6-2 TS 4.6-2 TS 4.6-3 TS 4.6-3 TS 4.6-4 TS 4.6-4 TS 4.11-3 TS 4.11-3 TS 4.12-1 TS 4.12-1 TS 4.12-2 TS 4.12-2 TS 4.12-3 TS 4.12-3 TS 4.12-4 TS 4.12-4 l
TS 4.17-3 TS 4.17-3 TS 4.17-6 TS 4.17-6
)
TS 4.17-8 TS 4.17-8 I
TS 4.20-1 TS 4.20-1 I
TS 4.20-2 TS 4.20-2 TS 4.20-3 TS 4.20-3 TS 4.204 TS 4.20-4
d a
1 TS 4.1-1 a
e 4.1 OPERATIONAL SAFETY REVIEW I
Applicability l
Applies to items directly related to safety limits and limiting conditions for operation.
Obiective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
}
I Specification A. Calibration, testing, and checking ofinstrumentation channels and interlocks shall be performed as detailed in Tables 4.1-1,4.1-1 A, and 4.1-2.
B. Equipment tests shall be performed as detailed in Table 4.1-2A and as detailed below.
- 1. In addition to the requirements of 4.0.5, each Pressurizer PORV and block valve shall be demonstrated OPERABLE by:
Performing a complete cycle of each PORV with the reactor coolant average a.
temperature >350'F once per 18 months.
l b.
Performing a complete cycle of the solenoid air control valve and check valves on the air accumulators in the PORV control system once per 18 months.
l c.
Operating each block valve through one complete cycle of travel at least once per 92 days. This surveillance is not required if the block valve is closed in accordance with 3.1.6.a b, or c.
Amendment Nos. 213 and 213
TS 4.1-3 4
Other channels are subject only to the " drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibration. Process systems instrumentation errors resulting from drift within the l
individual instruments are normally negligible.
During the interval between periodic channel tests and d tily check of each channel, a comparison between redundant channels will reveal any abnormal condition resulting from a calibration shift, due to instrument drift of a single channel.
During the periodic channel test, if it is deemed necessary, the channel may be tuned to compen, ate for the calibration shift. However, it is not expected that this will be required at any fixed or frequent interval.
Thus, minimum calibration frequencies of once-per-day for the nuclear flux (power level) channels, and once per 18 months for the process system channels are considered acceptable.
Testina The minimum testing frequency for those instrument channels connected to the 4
safety system is based on an average unsafe failure rate of 2/5 x 10 failure /hr per channel. This is based on operating experience at conventional and nuclear units.
An unsafe failure is defined as one which negates channel operability and which, due to its nature, is revealed only when the channel is tested or when it attempts to respond to a proper signal.
e i
Amendment Nos. 213 and 213'
TS 4.1-5 The refueling water storage tank is sampled weekly for Cl and/or F" contaminations. Weekly sampling is adequate to detect any inleakage of contaminated water.
The control room ventilation system is required to establish a positive differential pressure in the control room for one hour following a design basis loss-of-coolant accident using a bottled air supply as the source of air. The ability of the system to meet this requirement is tested by pressurizing the control room using the ventilation system fans and comparing the volume of air required to that stored.
The test is conducted once per 18 months normally" coinciding with the refueling l
outage of either Unit 1 or Unit 2.
Amendment Nos. 213 and 213
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4 TS 4.5-2
- 2. By verifying that each motor-operated valve in the recirculation spray flow paths performs satisfactorily when tested in accordance with Specification 4.0.5.
- 3. At least once per 10 years, coincident with the closest refueling outage, by 1
performing an air or smoke flow test and verifying each spray nozzle is l
unobstmeted.
I l
C. Each weight-loaded check valve in the containment spray and outside containment recirculation spray subsystems shall be demonstrated OPERAELE once per 18 months by cycling the valve one complete cycle of full travel and verifying that each valve opens when the discharge line of the pump is pmssurized with air and seats when j
a vacuum is applied.
D. A visual inspection of the containment sump and the inside containment recirculation spray pump wells and the engineered safeguards suction inlets shall be performed once per 18 months and/or after major maintenance activities in the containment. The inspection should verify that the containment sump and pump wells are free of debris that could degrade system operation and that the sump components (i.e., trash racks,
{
screens) are properly installed and show no sign of structural distress or excessive l
l Corrosion.
1 i
/
Amendment Nos. 213 and 213 1
TS 4.5-3 0
Basis The flow testing of each containment spray pump is performed by opening the normally closed valve in the containment spray pump recirculation line returning water to the refueling water storage tank. The containment spray pump is operated and a quantity of water recirculated to the refueling water storage tank. The discharge to the tank is divided into two fractions; one for the major portion of the recirculation flow and the other to pass a small quantity of water through test nozzles which are identical with those used in the containment spray headers.
The purpose of the recirculation through the test nozzles is to assure that there are no particulate material in the refueling water storage tank small enough to pass through pump suction strainers and large enough to clog spray nozzles.
Due to the physical arrangement of the recirculation spray pumps inside the containment,it is impractical to flow-test them other than during a unit outage. Flow testing of these pumps requires l
the physical modification of the pump discharge piping and the erection of a temporary dike to contain recirculated water. The length of time required to setup for the test, perform the test, and then reconfigure the system for normal operation is prohibitive to performing the flow-test on even the cold shutdown frequency. Therefore, the flow-test of the inside containment recirculation spray pumps will be performed once per 18 months during a unit outage.
l The inside containment recirculation spray pumps are capable of being operated dry for approximately 60 seconds without significantly overheating and/or degrading the pump bearings.
During this dry pump check, it can be determined that the pump shafts are turning by rotation sensors which indicate in the Main Control Room. In addition, motor current will be compared with an established reference value to ascertain that no degradation of pump c,peration has occurred.
~
Amendment Nos.213 and 213
TS 4.6-2 b.
Automatic start of each diesel generator, load shedding, and restoration to operation of particular vital equipment, initiated by a simulated loss of off-site power together with a simulated safety injection signal. Testing will I
demonstrate load shedding and load sequencing initiated by a simulated loss of off-site power following a simulated engineered safety features signal. Testing will also demonstrate that the loss of voltage and degraded voltage protection is defeated whenever the emergency diesel is the sole source of power to an emergency bus and that this protection is automatically reinstated when the diesel output breaker is opened. This test will be conducted during reactor shutdown for refueling to assure that the diesel generator will start within 10 sec and assume load in less than 30 sec after the engine starting signal.
Availability of the fuel oil transfer system shall be verified by operating the c.
system in conjunction with the monthly test.
d.
Each diesel generator shall be given a thorough inspection once per 18 months l
utilizing the manufacturer's recommendations for this class of stand-by service.
2.
Acceptance Criteria The above tests will be considered satisfactory if all applicable equipment operates i
as designed.
i l
l B.
Fuel Oil Storage Tanks for Diesel Generators l
1.
A minimum fuel oil storage of 35,000 gal shall be maintained on site to assure full power operation of one diesel generator for seven days.
l l
Amendment Nos. 213 and 213
TS 4.6-3 C.
Station Battenes 1.
Tests and Frequencies The specific gravity, electrolytic temperature, cell voltage of the pilot cell in a.
each battery, and the D.C. bus voltage of each battery shall be measured and recorded weekly, b.
Each month the voltage of each battery cell in each battery shall be measured to the nearest 0.01 volts and recorded.
Every 3 months the specific gravity of each battery cell, the temperature c.
reading of every fifth cell, the height of electrolyte of each cell, and the amount of water added to any cell shall be measured and recorded.
d.
Twice a year, during normal operation, the battery charger shall be turned off for approximately 5 min and the battery voltage and current shall be recorded at the beginning and end of the test.
During the normal refueling shutdown each battery shall be subjected to a e.
simulated load test without battery charger. The battery voltage and current as a function of time shall be monitored.
f.
Once per 18 months connections shall be checked for tightness and l
anti-corrosion coating shall be applied to the interconnections.
2.
Acceptance Criteria Each test shall be considered satisfactory if the new data when compared to the a.
old data indicate no signs of abuse or deterioration.
Amendment Nos. 213 and 213
TS 4.6-4 b.
The load test in (d) and (e) above shall be considered satisfactory if the batteries perform within acceptable limits as established i:y the manufacturers discharge characteristic curves.
D.
EMERGENCY DIESEL GENERATOR DATTERIES 1.
Tests and Frequencies The specific gravity, electrolytic temperature, cell voltage of the pilot cell in a.
each battery and the D.C. bus voltage of each battery shall be measured and recorded weekly.
b.
Each month the voltage of each battery cell in each battery shall be measured to the nearest 0.01 volts and recorded.
Every 3 months the specific gravity of each battery cell, the temperature reading c.
of every fifth cell, the height of electrolyte of each cell, and the amount of water added to any cell shall be measured and recorded.
d.
Once per 18 months, each battery shall be subjected to a normal load or l
simulated load test without battery charger. The battery voltage and current as a function of time shall be monitored.
Once per 18 months, connections shall be checked for tightness and l
e.
anti-corrosion coating shall be applied to interconnections.
2.
Acceptance Criteria Each test shall be considered satisfactory if the new data when compared to the a.
old data indicate no signs of abuse or deterioration.
b.
The load test in (d) above shall be considered satisfactory if the batteries perform within acceptable limits as established by the manufacturers discharge i
characteristic curves.
I l
l I
Amendment Nos. 213 and 213
..-.s b
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TS 4.11-3 Power may be restored to any valve or breaker referenced in Specifications c.
4.11.C.4.a and 4.11.C.4.b for the purpose of testing or maintenance provided that not more than one valve has power restored at one time, and the testing and maintenance is completed and power removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
Once per 18 months by:
l Verifying that each automatic valve capable of receiving a safety injection a.
signal, actuates to its correct position upon receipt of a safety injection test signal. The charging and low head safety injection pumps may be immobilized for this test.
b.
Verifying that each charging pump and safety injection pump circuit breaker i
actuates to its correct position upon receipt of a safety injection test signal. The charging and low head safety injection pumps may be immobilized for this test.
Verifying, by visual inspection, that each low head safety injection pump c.
suction inlet from the containment sump is free of debris that could degrade system operation. Perform each refueling outage and/or after major maintenance activities in the containment.
Basis Co:nplete system tests cannot be performed when the reactor is operating because a safety injection signal causes containment isolation. The method of assuring operability of these systems is therefore to combine system tests to be performed during unit outages, with l
more frequent component tests, which can be performed during reactor operation.
Amendment Nos. 213 and 213 9
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TS 4.12-1 a
4.12 AUXILIARY VENTILATION EXHAUST FILTER TRAINS Applicability Applies to the testing of safety-related air filtration systems.
Objective To verify that leakage efficiency and iodine removal efficiency are within acceptable limits.
Specifications A. Tests and Freauency
- 1. Each redundant filter train circuit shall be operated every month ifit has not already been in operation.
- 2. Once per 18 months, the operability of the entire safety-related portion of the l
auxiliary ventilation system shall be demonstrated.
- 3. Auxiliary ventilation system exhaust fan flow rate through each filter train in the LOCA mode of operation shall be determined initially, after any structural maintenance on the HEPA filter or charcoal adsorber housings, once per 18 months, or after panial or complete replacement of the HEPA filters or charcoal adsorbers.
The procedure for determining the air flow rate shall be in accordance with Section 9 of the ACGIH Industrial Ventilation document and Section 8 of ANSI N510-1975.
- 4. A visualinspection of the filter train and associated components shall be conducted before each in-place air flow distribution test, DOP test, or activated charcoal adsorber leak test in accordance with the intent of Section 5 of ANSI N510-1975.
Amendment Nos. 213 and 213
TS 4.12-2
- 5. An air distribution test accross the prefilter bank shall be performed initially and after any major modification, major repair, or maintenance of the air cleaning system affecting the filter bank flow distribution. The air distribution test shall be performed with an anemometer located at the downstream side and at the center of
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each carbon filter.
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- a. Initially;
- b. Once per 18 months;
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- c. Following painting, fire, or chemical release in any ventilation zone communicating with the system;
- d. After each complete or partial replacement of the HEPA filter cells; and
- e. After any structural maintenance on the filter housing.
The procedure for in-place cold DOP tests shall be in accordance with ANSI N510-1975, Section 10.5 or 11.4. The flow rate during the in-place cold DOP tests l
shall be 36,000 CFM i10 percent. The flow rate shall be determined by recording the flow meter reading in the control room.
- 7. In-place halogenated hydrocarbon leakage tests for the charcoal adsorber bank shallbe performed:
- a. Initially;
- b. Once per 18 months; l
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Amendment Nos. 213 and 213
TS 4.12-3
- c. Following painting, fire, or chemical release in any ventilation zone l
communicating with the system;
- d. After each complete or panial replacement of charcoal adsorber trays; and
- e. After any structural maintenance of the filter housing.
The procedure for in-place halogenated hydrocarbon leakage tests shall be in accordance with ANSI N510-1975, Section 12.5. The flow rate during the in-place halogenated hydrocarbon leakage tests shall be 36,000 CFM i10 percent. The flow rate shall be determined by recording the flow meter reading in the control room.
- 8. Laboratory analysis on in-place charcoal samples shall be performed:
- a. Initially, whenever a new batch of charcoal is used to fill adsorbers trays;
- b. Once per 18 months; l
- c. After 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; and
- d. Following painting, fire, or chemical release in any ventilation zone communicating with the system or after any structural maintenance on the HEPA filter or charcoal adsorber housings.
The procedure for iodine removal efficiency tests shall follow ASTM D3803.
The test conditions shall be in accordance with those listed in Specification 4.12.B.7.
Amendment Nos. 213 and 213
TS 4.12-4
- 9. The pressure drop across the HEPA filter and adsorber banks shall be checked:
- a. Initially; l
- b. Once per 18 months thereafter for systems maintained in a standby status and l
after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; and I
- c. After each complete or panial replacement of filters or adsorbers.
B. Acceptance Criteria
- 1. The minimum period of air flow through the filters shall be 15 minutes per month.
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- 2. The system operability test of Specification 4.12.A.2 shall demonstrate automatic start-up, shutdown and flow path alignment.
- 3. The air flow rate determined in Specification 4.12.A.3 shall be:
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- a. 36,000 cfm i10 percent with system in the LOCA mode of operation.
- b. The ventilation system shall be adjusted until the above limit is met.
- 4. Air distribution test across the prefilter-bank shall show uniformity of air velocity within 20 percent of average velocity. The ventilation system shall be adjusted until the limit is met.
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i Amendment Nos. 213 and 213 j
TS 4.17-3 a.
- 4. A review and evaluation shall be performed and documented tojustify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the action requirements of Specification 3.20 shall be met.
C. FunctionalTests
- 1. Once per 18 months, a representative sample of 10% of the total of each type l
snubber used in the plant shall be functionally tested using either an in-place test machine or a bench test.
- 2. The representative sample selected for functional testing shall include the various configurations, operating enviroi ments and the range of size and capacity of snubbers. This representative san.ple shall not, to the extent practicable, include those snubbers tested in a previous representative sample.
- 3. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:
- a. the first snubber away from each reactor vessel nozzle,
- b. snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc),
and
- c. snubbers within 10 feet of the discharge from a safety relief valve.
4e Amendment Nos. 213 and 213
TS 4.17-6
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- c. Snubber release rate, where required, is within the specified range in compression and tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be veri 5ed.
F. Snubber Service Life Monitorina
- 1. A record of the service life of each snubber, the date at which the designated service life commences, and the installation and maintenance records on which the designated service life is based shall be maintained as required by the Virginia Electric and Power Company Operational Quality Assurance Program Topical Report.
- 2. Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next sclieduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
Amendment Nos. 213 and 213
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TS 4.17-8 To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested once per 18 months. Functional testing is to be in accordance l
with the ASME Section XI Inservice Inspection program approved by the NRC. Observed failures l
of these sample snubbers shall require functional testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
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1 Amendment Nos. 213 and 213 4
TS 4.20-1 4.20 CONTROL ROOM AIR FILTRATION SYSTEM Applicability l
Applies to the testing of safety-related air filtration systems of the control room and relay room.
Obiective i
To verify that leakage efficiency and iodine removal efficiency are within acceptable i
i limits.
Specification.
A. Tests and Freauency 1
- 1. The control room air filtration system flow rate test shall be performed:
- a. Initially; I
- b. Once per 18 months;
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- c. Following painting, fire, or chemical release in any ventilation zone communicating with the system during system operation;
- d. After each complete or partial replacement of the HEPA filter or charcoal l
adsorbers; and
- e. After any structural maintenance the HEPA filter or charcoal adsorber housings; and l
- f. After any major modification or repair of the air cleaning system.
L Amendment Nos. 213 and 213
)
TS 4.20-2
- 2. The procedure for detennining the air flow rate shall be in accordance with Section 9 of the ACGIH Industrial Ventilation document and Section 8 of ANSI N510-1975. A visual inspection of the filter train and its associated components shall be conducted before each in-place airflow distribution test, DOP test, or activated charcoal adsorber leak test in accordance with the intent of Section 5 of ANSI N510-1975.
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- a. Initially;
- b. Once per 18 months; l
- c. Following painting, fire, or chemical release in any ventilation zone communicating with the system during system operation;
- d. After each complete or partial replacement of the HEPA filter cells; and
- e. After any structural maintenance of the filter housing.
- 4. The procedure for in-place cold DOP tests shall be in accordance with ANSI N510-1975, Section 10.5 or 11.4. The flow rate during this test shall be that value determined under Specification 4. 20. A. I and shall be within the range specified in Specification 4. 20. B.1.
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Amendment Nos. 213 and 213-
0 TS 4.20-3 o
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- 5. In place halogenated hydrocarbon leakage tests for the charcoal adsorber bank shall be performed:
- a. Initially;
- b. Once per eighteen months; l
- c. Following painting, fire, or chemical release in any ventilation zone communicating with the system during system operation;
- d. After each complete or partial replacement of charcoal adsorber trays; and
- e. After any structural maintenance on the filter housing.
- 6. The procedure for in-place halogenated hydrocarbon leakage tests shall be in accordance with ANSI N510-1975 Section 12.5. The flow rate during this test shall be that value determined under Specification 4.20.A.1 and shall be within the range specified in Specification 4.20.B.1.
- 7. Laboratory analysis on charcor! :vnples shall be performed:
Initially, whenever a new batch of charcoal is used to fill adsorber trays; a.
- b. Once per eighteen months; l
- c. After 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; and
- d. Following painting, fire, or chemical release in any ventilation zone communicating with the system during system operation.
l Amendment Nos. 213 and 213
o TS 4.20-4 e
4 fe
- 8. The procedure for iodine removal efficiency tests shall follow ASTM D3803. The test conditions shall be in accordance with those listed in Specification 4. 20. B. 4.
- 9. The pressure drop across the HEPA filter and adsorber banks shall be checked:
- a. Initially;
- b. Once per 18 months; and l
- c. After each complete or panial replacement of filters or adsorbers.
- 10. Each filter train circuit shall be operated every month. Filter Train Operation shall be initiated manually from the control room.
B. Acceptance Criteria
- 1. Fan flow tube test shall show a flow rate through any single filter train of 1000 t 10 percent efm.
- 2. In-place cold DOP ta.sts on HEPA filters shall show greater than or equal to 99.5 percent DOP removal. I. caking sources shall be identified, repaired and retested.
Any HEPA filter found defective shall be replaced.
- 3. In-place halogenated hydrocarbon leakage tests on charcoal adsorber banks shall show greater than or equal to 99 percent halogenated hydrocarbon removal.
Leakage sources shall be identified, repaired and retested.
1 8-Amendment Nos. 213 and 213
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