ML19350A539
| ML19350A539 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/13/1981 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML19350A538 | List: |
| References | |
| NUDOCS 8103160454 | |
| Download: ML19350A539 (12) | |
Text
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O ATTACW ENT A TO PROPOSED CHANGE NO. 29 SUPPLEMENT #2 Ventilation and Filter Systems Limiting Conditions for Operation (Specification 3.22) and Surveillance Requirements (Specification 4.11).
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3.22 INSTALLED VENTILATION AND FILTER SYSTEMS Acolicability: Acplies to the operating statuc.f the plant installed ventilation and filter systems.
(bjective:
To define the operating status of the installed ventilation and filter systems required for plant operation.
Specification:
A.
The containment hydrogen purge system shall be operable wnenever the reactor is critical. With the containment hydrogea purge system inoperable, restore the hydrogen system to operable status within 30 days or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B.
One train of control room ventilation shall be operable wnenever minimum safeguards are required.
Two trains of centrol recm ventilation shall be operaale whenever the reactor is critical.
With one control room ventilation system incperable, restore the system to operable status within 14 days or be in Hot Stancby.
C.
Spent Fuel Pool Ventilation Requirements 1.
When irradiated fuel which has decayed less than 60 days is in the spent fuel pool, the spent fwl ventilation system shall be operating and discharging tnrough an FE?A and charcoal adsorcer l
filter train during either:
l a.
Fuel movement within the spent fuel pool, or I
b.
Crane operation with loads over the spent fuel pool.
2.
With C.1 above not satisfied, suspend all cperations involving movement of fuel within the spent fuel pool or crane operation with loads over the spent fuel pool.
Basis:
The operability of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be l
available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
l Each control room ventilation system censists of one recirculation system at 3300 cfm and one breathing air supply system at 40 cfm.
The operability of the control room ventilation system ensures that the control room will remain habitable for operations personnel during and following all credible accident conditions.
The operability of this I
system in conjunction with control room design provisions is based on j
limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criteria 19 of l
Appendix "A", 10 CFR 50.
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The limitations en the storage pool ventilation s stem ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEFA filters and charcoal adsorcer prior to discharge to the atmosphere.
The cperability of this system and the resulting iodine removal capacity are consistent with the assumptiens of l
the accident analyses.
4.11 VENTILATION FILTER SYSTEM SLRVEILLANCE TESTING Apolicability:
Apolies to the containment hydrogen purge system, the control rocm ventilation system, and the spent fuel pool ventilt. ion system.
Objective:
To specify the surveillance requirements necessary to demonstrate the operability of the above ventilation and filter systems.
Specification:
A.
Containment Hydrogen Purge System 1.
The hydrogen purge system shall be demonstrated operable at least once per month by initiating system flow through the HEPA filter and enarcoal adsorber train for at least 15 minutes and verifying that the purge system operates by observing flow indication on the system flowmeter.
Note:
The above evolution requires a deviation from containment integrity.
To compensate for this, an operator will be in close proximity to the isolation valve during this testing.
B.
Control Room Ventilation System 1.
Each train of the centrol room ventilation system shall be demonstrated operable at least once per month by initiating flow through the HEPA filter and charcoal adsorber train for at least 15 minutes verifying train operability.
2.
At least each refueling interval and following painting, fire or chemical release in any ventilation zone communicating with the system, while the system is operating, that could contaminate and impair the fonction of the HEPA filters or charcoal adsorbers, the filter system shall be demonstrated operable by verifying that:
a.
The results of the in-place cold DOP and halogenated hydrocarbon tests at design flows on HEPA and charcoal filter banks shall show 2: 99% DOP removal and 2: 99%
halogenated hydrocarbon removal.
b.
Within 31 days after removal that the results of laboratory carbon sample analysis shall show 2: 95%
radioactive nethyl iodide removal.
(250C, 70% R.H.)
Note: Should the laboratory results not be available within 31 days after remcval, written notification to the Commission shall be provided within 7 days.
c.
Recirculation filter system flow rate is 2:3300 cfm during system operation.
4.11-1
d.
Breathing air supply system flow rate is 240 cfm during system cperation.
e.
The pressure drop acrcss the comoined pre-filter and E PA filter bank is 5. 4" H O while operating at the system 2
ficws specified above.
3.
Following maintenance or replacement activities, only those components which may have been adversely affected by the activity need be tested.
Specifically:
a.
Cold DCP testing shall be performed after eacn complete or partial replacement of the EEPA filter bank.
b.
Halogenated hydrocarcon testing shall be performed after each complete or partial replacement of the charcoal filter bank.
c.
00P and halogenated hydrecc; con test shall be performed following any significant modification to the filter hcusing that could nave an adverse effect en the filter efficiency.
d.
An air distribution test demonstrating uniformity within
+20% across the WPA filters and charcoal adsorters shall be performed if the filter hcusing is modified such that air distribution could be adversely affected.
4.
The sample analysis of Specification 4.11.B.2.b shall be performed after every 720 hrs, of system cperation.
C.
Spent Fuel Pool Ventilation System 1.
When irradiated fuel which has decayed less than 60 days is in the spent fuel pool, the spent fuel pool ventilation system shall be verified to be operating witnin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the
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initiatien of and at least once per shift during either fuel l
movement -
tin the spent fuel pool or crane operation with j
loads ~ c the spent fuel pool.
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Note: Operating shall be defined as: At least ene purge l
fan operating, and system aligned to provide flow l
thrcugh the filter train from the spent fuel building.
2.
At least each refueling interval and following painting, fire or cnemical release in any ventilation zone communicating with the system, while the system is operating, that cculd centaminate l
and impair the function of the EPA filters or charcoal adsorbers, the filter system shall be demonstrated operable by j
verifying that:
a.
The results of the in-place cold 00P and halogenated hydrocarbon tests at dasign ficws en MPA and charcoal i
filter banks shall show 2 99% OCP removal and 2: 99%
halogenated hyd:ccarben removal.
4.11-2
b.
Within 31 days after removal that the results of laboratory Eem*o?alsamib5088hh5.ghgw 2:99% radicactive methyl iodine Note: Should the laboratory results not be available within 31 days after removal, written notification to the Commission shall be provided within 7 days.
c.
The exhaust flow rate from the Spent Fuel Building is 2 9600 cfm during system operation.
d.
The pressure drop across the combined pre-filter and ffPA filter bank is.4 4" H O at 23,000 cfm.
2 NOTE:
The exhaust flow from the Spent Fuel Building is routed througn a deep bed filter wnich has a capacity of 23,000 cfm.
3.
Following maintenance or replacement activities, only those components which may have been adversely affected by the activity need be tested.
Specifically:
a.
Cold 00P testing shall be performed after each complete er partial replacement of the EEPA filter bank.
b.
Halogenated hydrocarbon testing th311 be performed after each complete or partial replacement of the charcoal filter bank.
c.
DOP and halogenated hydrocarbcn test shall be performed following any significant modification to the filter housing nat could have an adverse effect on the filter efficiency.
d.
An air distribution test demonstrating uniformity within
+20% across the HEPA filters and charcoal adsorbers shall be performed if the filter housing is modified such that air distribution could be adversely affected.
4.
The sample analysis of Scecification 4.ll.C.2.b shall be performed after every 1500 hrs. of system operation.
Basis:
To ensure that the H2 purge, control room and spent fuel pool filter systems will be effective in removing radioactive contaminates from their respective air streams, these systems will be tested periodically to mest the intent of ANSI N510-1975.
The hydrogen purge system discharges via the ssfety related fuel building deep bed charcoal filter bank, and as such surveillance testing of these filters is acccmplished via section C.2 of this specification.
In specification 4.ll.C.1 the reference to a 60-day decay pericd is appropriate because calculations have shown that after a 60-day decay the off-site doses from a fuel drop accident with no filtration are significantly less than those from the design basis accident with filtration.
4.11-3
In specification 4.11.C.2.b, the 2t99% radioactive methyl iodide removal requirement is necessary because 95% removal credit was taken for the H2 purge contribution to the LOCA case.
In specification.4.11.C.4, the increase in the testing interval from 720 hrs to 1500 hrs. is appropriate because of the incorporation of both a 4-inch bed of activated impregnated charcoal bed and a 1" guard ted of activated charcoal.
Laboratory sample analyses of charcoal adsorbers from the control room or spent fuel pool building ventilation system shall be performed at flow rates wnich are representative of the system flow rates.
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4.11-4 l
ATTACtNENT B TO PROPOSED CHANGE NO 29 SUPPLEMENT #2 4
Revised page 3.13-2, 3.13-3 and 4.2-4 to the Maine Yankee Technical Specifications, and revised Table of Contents, pages 1 and 2.
Note:
The revision to page 4.2-4 deletes exicting page 4.2-5.
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6.
Direct communication between personnel in the control room and at the refueling station shall be operab?.e whenever changes in core gecmetry are taking place.
B.
If any of the conditions in Specification A. are not met, all refueling operations shall cease immediately; work shall be initiated to satisfy the required conditions; and no operations that may increase the rer,civity of the core shall be made.
C.
Prior to initial core loading and prior to each refueling, a complete check out, including a load test, shall be conducted on fuel handling cranes that will be used to handle spent fuel assemblies.
D.
A minimum of 23 feet of water above the top of the core shall be maintained whenever spent fuel is being handled.
E.
Irradiated fuel shall not be handled for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reactor shutdown.
F.
Spent fuel storage racks may be moved only in accordance with written procedures which ensure that no rack modules are moved over fuel assemoli s
Basis:
The equipment and general procedures to be utilized during refueling are discussed in the FSAR. Detailed instructions, the above specifications and the design of the fuel handling equipment incorporating built-in interlocks and safeguards systems provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety. Whenever changes are not being made in core gecmetry, cne flux monitor is sufficient.
This permits maintenance of the instrumentation.
Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition.
The residual heat removal flow is used to remove core decay heat and maintain a uniform baron concentration.
The shutdown margin as indicated will keep the core substantially subcritical, even if the highest worth CCA's were inadvertently withdrawn from the core without compensating boron addition.
Periodic checks of rufueling water baron conce7tration insure the proper snutdown margin. Communicatior requirements allow the control room operator to inform the refueling station operator of any impending unsafe condition detected from the main control board indicators during fuel movement.
In addition to the above engineered safeguards systems, interlocks are utilized during refueling to insure safe handling.
An excess weight interlock is provided to prevent excess loading of a fuel assembly, should it inadvertently become stuck.
In the analysis of the refueling accident conducted by the Staff, 23 feet of water and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of decay time were used to limit exposures to 10% of 10 CFR 100.
3.13-2
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Procedures are required for movement of spent fuel racks to avoid i
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unnecessary risk of spent fuel damage caused by dropping spent fuel racks.
Heferences:
(1) FSAR, Section 14.16 (2)
FSAR, Section 5.2 (3) FSAR, Section 9.10 i
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3.13-3
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Table 4.2-2 Minimum Frecuencies for Ecuiccent Tests Test Frecuency 1.
Control Element Assemolies Drop Times of all full-Each refueling interval.
Control Element Assemolies Partial Movement of all Every two weeks when the CEA's (minimum of 6")
reactor is critical.
3.
Pressurizer Safety Valves Set Point One valve each refueling interval.
4.
Main Steam Safety Valves Set Point 2 valves per steam generator, each refueling interval.
5.
Refueling System Interlocks Functioning Prior to refueling operations.
6.
Primary System Leakage Evaluate Daily
- Diesel Fuel Supply Fuel Inventory Weekly 8.
Turbine Stop, Governor, Functioning Monthly when the turbine Reheater and Intercept is operating.
Valves 9.
L.P. Turbine Rotor Inspection Visual, Magnetic Particle One Rotor each 4 years or Liquid Penetrant
- 10. Post-accident containment vent system a)
Hydrogen detector Calibrate Upon installing and within one month of startup from each refueling shutdown.
l Whenever the reactor coolant system is at or above operating pressure.
4.2 4 7
TECHNICAL SPECIFICATION Table of Contents Definitions Page 1.1 Fuel storage 1.1-1 1.2 Site Description 1.2-1 1.3 Reactor 1.3-1 1.4 Containment 1.4-1 2.0 Safety Limits and Maximum Safety Settings 2.1 Limiting Safety Settings Reactor Protection System 2.1-1 2.2 Safety Limits - Reactor Core 2.2-1 2.3 Safety Limits - Reactor Coolant System Pressure 2.3-1 3.0 Limiting Conditions for Operation 3.1 Incore Instrumentation 3.1-1 3.2 Reactor Coolant System Activity 3.2-1 3.3 Reactor Coolant System Operational Components 3.3-1 3.4 Combined Heat-up, Cooldown and Press-Temp. Limits 3.4-1 3.5 Chemical and Volume Control System 3.5-1 3.6 Core Cooling and Containment Spray Systems 3.6-1
'7 Boren and Sodium Hydroxide Available for Containment Spray System 3.7-1 3
Reactor Core Energy Removal 3.8-1 3.9 Operational Safety Instrumentation and Control Systems 3.9-1 3.10 CEA Group and Power Distribution Limits 3.10-1 3.11 Containment 3.11-1 3.12 Station Service Power 3.12-1 3.13 Refueling Operation 3.13-1 3.14 Primary System Leakage 3.14-1 3.15 Reactivity Anomalies 3.15-1 3.16 Radioactive Liquid Waste Release 3.16-1 3.17 Radioactive Gaseous Waste Release 3.17-1 l
3.18 Chemistry 3.18-1 3.19 Safety Injection Valving 3.19-1 3.20 Shock Suppressors 3.20-1 3.21 Steam Generators 3.21-1 3.22 Installed Ventilation and Filter Systems 3.22-1 l
3.23 Fire Protection Systems 3.23-1 3.24 Secondary Coolant Activity 3.24-1 4.0 Surveillance Requirements 4.0-1 4.1 Instrumentation and Control 4.1-1 4.2 Equipment and Sampling Tests 4.2-1 i
4.3 Reactor Coolant System Leak Tests 4.3-1
- 4. 4 Containment Testing 4.4-1 4.5 Emergency Power System Periodic Testing 4.5-1
- 6 Periodic Testing 4.6-1
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Reactor Coolant System Surveillance Testing 4.7-1 4.8 Operational Environmental Monitoring 4.8-1 4.9 Shock Supressor (Snubber) Surveillance 4.9-1 4.10 Steam Generator Tube Surveillance 4.10-1 4.11 Ventilation Filter System Surveillance Testing 4.11-1 l
4.12 Fire _P_rotection S_y_s M a Su M illance Testig.1 4.12-1
TECMICAL SPECIFICATIONS Table of Centents
. Pace 5.0 Administrative Controls 5.1 Responsibility 5.1-1 5.2 Organization 5.2-1 5.3 Facility Staff Qualifications 5.3-1 5.A Training 5.A-1 5.5 Review and Audit 5.5-1 5.6 Reportable Occurrence Action 5.6-1 5.7 Safety Limit Violation 5.7-1 5.8 Procedures 5.8-1 5.9 Reporting Requirements 5.9-1 5.10 Record Retention 5.10 1 5.11 Radiation Protection Program
- 5. l'.-l 5.12 High Radiation Area 3.12-1 5.13 Environmental Qualification 5.13-1
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