ML20212N487
| ML20212N487 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 08/26/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212N482 | List: |
| References | |
| NUDOCS 8608280250 | |
| Download: ML20212N487 (7) | |
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8 '% UNITED STATES
[ p, NUCLEAR REGULATORY COMMISSION 5 9j WASHINGTON, D. C. 20555
%.....j PACIFIC GAS AND ELECTRIC COMPANY HUMBOLDT BAY POWER PLANT, UNIT NO. 3 DOCKET N0. 50-133 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. DPR-7
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment by the Pacific Gas and Electric Company (the licensee), dated May 16, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 l 51 of the Comission's regulations and all applicable I requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph C.(2). of Facility Operating Licensing No.
t DPR-7 is hereby amended to read as follows:
(2) Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No.21, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.
8608280250 860826 PDR ADOCK 05000133 P PDR
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- 3. This license amendment is effective as of the date of its issuance with the exception that the revised stack gas monitoring requirements will become effective when the new monitoring system is installed, but in no case more than 60 days from the date of issuance of this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION H rbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Attachment:
Changes to the. Technical ^
Specifications ~
Date of Issuance: August 26, 1986 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 21 TO FACILITY OPERATING LICENSE NO. DPR-7 DOCKET NO. 50-133 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert IV-4 IV-4 VII-1 VII-1 VII-3 VII-3A '
- VII-3B s
from ATSH A-106 Grade B carbon steel. The line shall be designed for j 1250 psig and 575'F under the ASME Boiler and Pressure Vessel Code and the ASA Code for Pressure Piping. This line shall leave the dry well
- through two motor operated gate type isolation valves (one a-c and one d-c powered).
- b. Turbine Generator Unit - The turbine generator unit, including its controls and auxiliaries, shall be designed for operation on saturated steam. The turbine shall be a 3600 rpm, tandem compound, double flow, condensing unit direct connected to a hydrogen cooled generator. The i expected capability rating of the turbine shall be 70,000 kw at 1,120 psig, saturated, and 1.5 inches of mercury absolute exhaust pressure.
! The generator shall be rated at 76,800 kva with a 0.85 power factor and 30 psig hydrogen pressure. The turbine speed and load control system shall consist of a load limit, a speed governor, and an initial pressure regulator. The initial pressure regulator shall be a narrow band i proportional control device which is capable of maintaining approximately constant reactor pressure by. varying the steam flow to the turbine.
i c. Main Condenser - Steam exhauste'd from the turbine-generator unit shall be condensed in the main condenser. The main condenser shall be capable of handling turbine exhaust flow plus heater and miscellaneous drains when the turbine-generator is operating at 70 Mw electrical. The condenser shall be capable of handling up to 870,000 pounds of steam per hour i ~
through the bypass valve system when the turbine stop valve is closed.
j Low condenser vacuum, in addition to scramming the reactor as described in Section VI, shall trip the turbine stop valve and bypass valves closed. The main condsnser shall have a 6,500 gallon betwell designed to hold up the. condensate for a minimum of three minutes for decay of short-lived activity.
- d. Turbine Steam Dvoass System - Two turbine steam bypass valves with a combined design capacity of 750,000 poundt per hour at 1,075 psig shall l be provided for the purpose of increasing the reliability of the Unit.
These valves shall automatically open on turbine-generator load rejection or if reactor pressure increases to the set poir.t of the bypass valve control system. Normally the set point shall be 10 psi above normal full )
load reactor pressure. The bypass valves shall discharge reactor steam directly to the main condenser.
- e. Condensate and Feedwater System - Two 900 gpm half-capacity condensate pumps of conventional design shall be provided to pump the condensate from the main condenser hotwell through the condensate system. The
- condensate system shall be designed for 210 psig and 300*F.
The removal of turbine plant system corrosion products from the condensate shall be accomplished by two half-capacity mixed-bed l i
demineralizers and their associated resin regeneration equipment. The demineralizers shall be capable of removing an average of 75% of the ionic constituents in the influent at flow rates of 375 pgm to 785 gpm.
Condensate leaving the demineralizers shall pass through two NOTE: Remainder of paragraph is on origir.al TS page IV-5 AMENOMENT NO. 21 CB205/0044K 1
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l 3- VII-1 MONT0 RING SYSTEMS A. DESIGN FEATURES i
- 1. Air Eiector Off-Gas Monitorina System - The gases from the air ejector discharge shall be monitored by two separate gamma monitoring systems using ion chamber detectors which shall be designed to detect the noble gas fission products indicative of fuel cladding failures.
One of these monitoring systems shall be an operating spare. The sampling system shall be designed to hold up the gas sample to allow time for the decay of nitrogen-16 and other short lived activities.
The off-gas monitoring channels shall be calibrated so that their indicated and recorded output can be evaluated in terms of microcuries of noble gas and gaseous activation products per unit volume of off-gas. Off-gas flow shall be monitored by a flow indicator in the control room. The information from the radiation recorders and the flow indicator shall permit evaluation of noble gas and gaseous activation products release rates in the range of 10-4 to 10 curies per second.
- 2. Stack Gas Monitorina System - A system shall be provided to determine routine releases of particulate radioactivity and to provide monitoring and annunciation of nonroutine releases of radioactive noble gases. The stack gas monitoring system shall consist of a particulate filter holder, a beta sensitive detector system, and a sample pump to produce a sample flow controlled at approximately 2
- cfm. The particulate filters are removed for laboratory counting.
The detector system shall have two detectors (one is an operating spare) which respond to radioactive (beta emitting) gases that pass throughthe-sysggm. The detector system shall be designed to be sensitive to Kr 3 in to approximately2x10ghestackgasfromapproximately5x10-7 microcuries/cc.
- 3. Emeraency Condenser Vent Monitors - The normally non-radioactive ;
steam which is discharged directly to the environs when the emergency l condenser is activated shall be monitored by means of two gamma sensitive channels employing halogen quenched GM tubes as sensing
. elements. These channels shall have a range of 0.01 to 100 mr/hr.
One of the channels shall be a part of the area monitoring system which is described below. The other. channel shall provide local indication. Both channels shall be provided with an alarm to warn the operator of the release of radioactivity in the event a gross leak should occur in the emergency condenser coils. Also, the emergency condenser shall be provided with a temperature alarm to warn the operator of a coil leak during the periods of normal operation when the emergency condenser is not in service.
- 4. Liould Haste System Vent Monitor - A fixed gamma monitor errploying a halogen quenched GM tube as the sensor shall be installed on a vent header which collects all vents from the radwaste facility. The monitor shall have a range of 0.01 to 100 mr/hr and its output shall be recorded in the control room. It shall be provided with an alarm which shall be annunciated in the control room.
AMENDMENT NO. 21 0820S/0044K I
. VII-3A also provide gamma monitoring of the fuel storage areas. A high radiation level signal from either of these channels shall sound the evacuation horns in the refueling building.
In addition to the area monitorirg system, suitable portable alpha and beta-gamma detection instruments and beta-gamma and neutron dose rate instruments shall be provided for use of perscnnel entering the unit's radiation areas and radioactive materials areas.
- 8. Off-site Environmental Monitorina Stations - At least thirty off-site environmental monitoring stations shall be provided for determining the integrated gamma dose rate in the environs. Each monitoring station shall be equipped with two 10 mr stray radiation chambers and with a film pack.
B. OPERATING LIMITS AND REOUIREMENTS !
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- 1. Air Eiector Off-Gas Monitor's - At least one of the two air ejector ;
off-gas monitoring systems shall be operable and capable of initiating closure of the off-gas isolation valve whenever there is off-gas flow during power operation. The monitors shall be se alarm if the off-gas activity reaches a level that would corre,tspond to to a stack release rate of 0.05 curies per second and to initiate closure of the off-gas isolation valve if the activity reaches a l
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level that would correspond to a stack release rate of 0.5 curies per second and remain at this value (or higher) for 10 minutes. The i calibration of these monitors shall be checked at least once each .
month during power operation. The automatic functions of these monitors shall be checked at least once each quarter during power operation.
- 2. Stack Gas Monitorina System - The stack gas monitoring system shall be operable and capable of initiating the stack gas high radiation level alarm whenever the ventilation system is in operation. It may be taken out of service for calibration or maintenance, but shall be returned to service as soon as practicable. The monitors shall be set to alarm at or below the level where the noble gas release rate would result in instantaneous offsite concentration of airborne radioactive material equal to the appropriate value given in 10 CFR 20, Appendix B Table II, column 1.
The calibration of these monitors shall be checked at least cnce each year. Alarm functions shall be checked weekly for operability.
The stack particulate filter will normally be removed for laboratory !
counting on a weekly schedule (sample intervals shall not exceed 200 l hours). l
- 3. Emeroency Condenser Vent Monitors - At least one of the emergency condenser vent monitors shall be operable and in service during power operation. The monitors shall be set to alarm at 10 mr/hr above background. The calibration of these monitors shall be checked at least once each quartir and the monitors shall be source checked at least once each week during power operation.
4 AMENDHENT NO. 21 0820S/0044K j
VII-3B
- 4. Liauid Haste System Ve'nt Monitor - The liquid waste system vent monitor shall normally be in service and shall be set to ala'rm at 10
.. mr/hr above background. It may be taken out of service for maintenance purposes but shall be returned to service as soon as practicable. The liquid waste system vent shall be monitored routinely using portable instruments when the vent monitor is out of service. The calibration of the vent monitor shall be checked at least once each quarter and the monitor shall be source checked at least once each week.
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AMENCHENT NO. 21 OS205/0044K s
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