ML20203L632

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Revising App a Re Fuel Handling Bldg ESF Air Treatment Sys
ML20203L632
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 08/25/1986
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20203L619 List:
References
NUDOCS 8608290023
Download: ML20203L632 (20)


Text

-

~

TABLE OF CONTENTS Section Page 2 SAFETY LIMITS AND LIMITING SAFETY SYSTP SETTINGS 2-1 2.1 Safety Limits, Reactor Core 2-1 2.2 Safety Limits, Reactor System Pressure 2-4 2.3 Limiting Safety System Settings, Protection Instrumentation 2-5 3 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 General Action Requirements _ 3-1 3.1 Reactor Coolant System 3-la 3.1.1 Operational Components 3-la 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality 3-6 3.1.4 Reactor Coolant Sy: tem Activity 3-8 3.1,5 Chemistry . 3-10 3.1.6 Leakage 3-12 3.1. 7 Moderator Temperature Coefficient of Reactivity 3-16 3.1.8 Single Loop Restrictions 3-17 3.1.9 Low Power Physics Testing Restrictions 3-18 3.1.10 Control Rod Operation 3-18a 3.1.11 Reactor Internal Vent Yalves 3-18b 3.1.12 Pressurizer Power Operated Relief Valve (PORV) 3-18c and Block Valv?

3.1.13 Reactor Coolant System Vents 3-18f 3.2 Makeup and Purification and Chemical Addition Systems 3-19 3.3 Emergency Core Cooling, Reactor Building Emergency Cooling, 3-21 and Reactor Building Spray Systems 3.4 Decay Heat Removal - Turbine Cycle

~

3-25 3.5 Instrumentation 5ystems 3-27 3.5.1 Operational Safety Instrumentation 3-27 3.5.2 Control Rod Group and Power Distribution Limits 3-33 3.5.3 Engineered Safeguards Protection System Actuation Setpoints 3-37 3.5.4 Incore Instrumentation 3-38 3.5.5 Accident Monitoring Instrumentation 3-40a 3.6 Reactor Building 3-41 3.7 Unit Electrical Power System 3-42 3.8 Fuel Loading and Refueling 3-44 l

3.9 Deleted 3-46 l 3.10 Miscellaneous Radioactive Materials Source 3-46 3.11 Handling of Irradiated Fuel 3-55 3.12 Reactor Building Polar Crane 3-57 3.13 Secondary system Activity 3-58 3.14 Flood 3-59 l 3.14.1 Periodic Inspection of the Dikes Around TMI 3-59 l 3.14.2 Flood Condition for Placing the Unit in Hot Standby 3-60 3.15 Air Treatment Systems 3-61 3.15.1 Emergency Control Room Air Treatment System 3-61 j 3.15.2 Reactor Building Purge Air Treatmant System 3-62a l 3.15.3 Auxiliary and Fuel Handling Building Air Treatment System 3-62c l 3.15.4 Fuel Handling Building ESF' Air Treatment System 3-62e 11 Amendment No. 59, 72, 78, 97, 98 8609290023 860825 i PDR ADOCK 05000289 p PDR

e TABLE OF CONTENTS l Section Page r 2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 1

f 2.1 Safety Limits, Reactor Core 2-1 2.2 Safety Limits, Reactor System Pressure 2-4 2.3 Limiting Safety System Settings, Protection Instrumentation 2-5 3 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 General Action Requirements 3-1 3.1 Reactor Coolant System 3-la 3.1.1 Operational Components 3-la 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality 3-6 3.1.4 Reactor Coolant System Activity 3-8 3.1.5 Chemistry 3-10 3.1.6 Leakage 3-12 3.1.7 Moderator Temperature Coefficient of Reactivity 3-16 3.1.8 Single Loop Restrictions 3-17 3.1.9 Low Power Physics Testing Restrictions 3-18 3.1.10 Control Rod Operation 3-18a 3.1.11 Reactor Internal Vent Valves 3-18b 3.1.12 Pressurizer Power Operated Relief Valve (PORV) 3-18c and Block Valve 3.1.13 Reactor Coolant System Vents 3-18f 3.2 Makeup and Purification and Chemical Addition Systems 3-19 3.3 Emergency Core Cooling, Reactor Building Emergency Cooling, 3-21 and Reactor Building Spray Systems 3.4 Decay Heat Removal - Turbine Cycle 3-25 3.5 Instrumentation Systems 3-27 3.5.1 Operational Safety Instrumentation 3-27 3.5.2 Control Rod Group and Power Distribution Limits 3-33 3.5.3 Engineered Safeguards Protection System Actuation Setpoints 3-37 3.5.4 Incore Instrumentation 3-38 3.5.5 Accident Monitoring Instrumentation 3-40a 3.6 Reactor Building 3-41 3.7 Unit Electrical Power System 3-42 3.8 Fuel Loading and Refueling 3-44 3.9 Deleted 3-46 l 3.10 Miscellaneous Radioactive Materials Source 3-46 3.11 Handling of Irradiated Fuel 3-55 3.12 Reactor Building Polar Crane 3-57 3.13 Secondary System Activity 3-58 3.14 Flood 3-59 3.14.1 Periodic Inspection of the Dikes Around TMI 3-59 3.14.2 Flood Condition for Placing the Unit in Hot Standby 3-60 3.15 Air Treatment Systems 3-61 3.15.1 Emargency Control Room Air Treatment System 3-61 3.15.2 Reactor Building Purge Air Treatment System 3-62a 3.15.3 Auxiliary and Fuel Handling Building Air Treatment System 3-62c 3.15.4 Fuel Handling Building ESF Air Treatment System 3-62e if Amendment No. 59, 72, 78, 97, 98 8608290023 860825 PDR ADOCK 05000289 p PDR

[

s TABLE OF CONTENTS Section Page 4.7 Reactor Control Rod System Tests 4-48 4.7.1 Control Rod Drive System Functional Tests 4-48 4.7.2 Control Rod Program Verification 4-50 4.8 Main Steam Isolation Valves 4-51 4.9 Emergency Feedwater System Periodic Testing 4-52 4.9.1 Test 4-52 4.9.2 Acceptance Criteria 4-52a 4.10 Reactivity Anomalies 4-53 4.11 Reactor Coolant System Vents 4-54 4.12 Air Treatment Systems 4-55 4.12.1 Emergency Control Room Air Treatment System 4-55 4.12.2 Reactor Building Purge Air Treatment System .

4-55b 4.12.3 Auxiliary and Fuel Handling Building Air Treatment System 4-55d 4.12.4 Fuel Handling Building ESF Air Treatment System 4-55f 4.13 Radioactive Materials Sources Surveillance 4-56 a.14 Reactor Building Purge Exhaust System 4-57 4.15 fiain Steam System Inservice Inspection 4-58 4.16 Reactor Internals Vent Valves Surveillance 4-59 4.17 Shock Suppressors (Snubbers) 4-60 4.18 Fire Protection Systems 4-72 4.18.1 Fire Protection Instruments 4-72 4.18.2 Fire Suppression Water System 4-73 4.18.3 Deluge / Sprinkler System 4-74 4.18.4 CO2 System 4-74 4.18.5 Halon Systems 4-75' 4.18.6 Hose Stations 4-76 4.19 OTSG Tube Inservice Inspection 4-77 4.19.1 Steam Generator Sample Selection and Inspection Methods 4-77 4.19.2 Steam Generator Tube Sample Selection and Inspection 4-77 4.19.3 Inspection Frequencies 4-79 4.19.4 Acceptance Criteria 4-80 4.19.5 Reports 4-81 ,

4.20 Reactor Building Air Temperature 4-86

4. 21 .1 Radioactive Liquid Effluent Instrumentation 4-87 4.21.2 Radioactive Gaseous Process and Effluent Monitoring 4-90 Instrumentation 4.22.1.1 Liquid Effluents 4-97 4.22.1.2 Dose 4-102 4.22.1.3 Liquid Waste Treatment 4-103 4.22.1.4 Liquid Holdup Tanks 4-104 4.22.2.1 Dose Rate 4-105 4.22.2.2 Dose, Noble Gas 4-110 4.22.2.3 Dose, Radioiodines, Radioactive Material in Particulate 4-111 Form and Radionuclides Other Than Noble Gases 4.22.2.4 Gaseous Radwaste Treatment 4-112 4.22.2.5 Explosive Gas Mixture 4-113 4.22.2.6 Gas Storage Tanks 4-114 4.22.3.1 Solid Radioactive Waste 4-115 4.22.4 ' Total Dose 4-116 4.23.1 Monitoring Program 4-117 4.23.2 Land Use Census 4 -1 21 4-23.3 Interlaboratory Compariscn Program 4-122 iv Amendment No. 11, 28, 30, 41, 47, 55, 72, 78, 95, 97

3.15.3 AUXILIARY AND FUEL HANDLING BUILDING AIR TREATMENT SYSTEM Applicability Applies to the Auxiliary and Fuel Handling Building Air Treatment System.

Objective To specify the minimum availability and efficiency for the Auxiliary and Fuel Handling Building Air Treatment System.

Specification 3.15.3.1 The Auxiliary and Fuel Handling Building Air Treatment System

!neluding at least one pair of exhaust fans and 4 banks of exhaust filters (AH-F2A, B, C, and D) shall be operabic at all times during power operation.

3.15.3.2 The Auxiliary and Fuel Handling Building Air Treatment System is operable when its surveillance requirements are met and:

a. The results' of the in-place DOP and halogenated hydrocarbon  ;

tests at design flows on HEPA filters and charcoal adsorber ,

banks shall show <0.05% DOP penetration and <0.05% halogenated I hydrocarbon penetration, except that the DOP test will be l conducted with prefilters installed.  ;

i

b. The results of laboratory carbon sample analysis shall show .

>90% radioactive methyl iodide decontamination efficiency when '

Tested at 30*C, 95% R.H.  ;

c. Each set of fans AH-E-14 A & C and AH-E-14 8 & D shall each be shown to operate within 11,881 CFM of dasign flow (118,810 CFM).

3.15.3.3 a. From the date that the Auxiliary and Fuel Handling Building Air Treatment System becomes inoperable for any reason during power operation, the system must be restored to operable condition within 7 days. If the system is not restored to operable within 7 days, prepare and submit a speciai .'eport to the NRC within the next 30 days outlining the actions take,n to restore operability and the plans and schedules for restoring the system to operable status.

{ 3-62c Amendment No. 55, 76

~

Bases The Auxiliary and Fuel Handling Building Air Treatment System is considered to be the 4 banks of exhaust filters (AH-F2A, B, C, and D) and the two sets of redundant exhaust fans (AH-E-14A and C or AH-E14B and D) which take the exhaust air from both the Auxiliary Building and the Fuel Handling Building and discharge it to the Auxiliary and Fuel Handling building exhaust stack.

Exhaust air passes through all of the exhaust filters (AH-F2A, B, C, and D) prior to being discharged to the stack whenever either set of AH-E14 exhaust fans is in operation.

High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers for all emergency air treatment systems. The charcoal adsorbers are installed to reduce the potential release of radiofodine to the environment.

If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10 CFR 100 guidelines for the accidents analyzed in Chapter 14 of the FSAR, which assumes 90%

efficiency. Mitigation of Fuel Handling Accidents is provided by the Fuel Handling Building ESF Air Treatment System and does not depend on the operation of the Auxiliary and Fuel Handling Building Air Treatment System.

This system is isolated by automatic damper actuation in the event of increasing activity in the Fuel Handling Building as sensed by radiation moni tors.

References (1) FSAR Section 9.8 (2) FSAR Figure 9.8-4 (3) FSAR Section 14.2.2.5 (4) FSAR Section 14.2.2.6 3-62d Amendment No. 55

3.15.4 Fuel Handling Building ESF Air Treatment System Applicability Applies to the Fuel Handling Building (FHB) ESF Air Treatment System and its associated filters.

Objective To specify minimum availability and efficiency for the FHB ESF Air Treatment System and its associated filters for irradiated fuel handling operations.

Specifications 3.15.4.1 One train shall be operable and operating continuously whenever TMI-l irradiated fuel handling operations in the FHB are in progress.

a. With one train inoperable, irradiated fuel handling operations in the Fuel Handling , Building may proceed provided the redundant train is operating.
b. With both trains inoperable, handling of irradiated fuel in the Fuel Handling Building shall be suspended until such time that at least one train is operable and operating. Any fuel assembly movement in progress may be completed.

3.15.4.2 A FHB ESF Air Treatment System train is operable when its surveillance requirements are met and:

i

a. The results of the in-place DOP and halogenated hydrocarbon tests at design flows on HEPA filters and carbon adsorber banks shall show <0.05% D0P penetration and <0.05% halogenated hydrocarbon penetration.
b. The results of laboratory carbon sample analysis shall show '

>90% radioactive mrthyl iodide decontamination efficiency when tested at 30*C, 95% R.H.

c. The fans AH-E-137A and B shall each be shown to operate wi thin 10% of design flow (6,000 SCFM).

Bases Compliance with these specifications satisfies the condition of operation imposed by the Licensing Board as described in NRC's letter dated October 2, 1985, item 1.c.

The FHB ESF Air Treatment System contains, controls, mitigates, monito~rs and records radiation release resulting from a TMI-1 postulated spent fuel accident in the Fuel Handling Building as described in the FSAR. Offsite doses will be less than the 10 CFR 100 guidelines for accidents analyzed in Chapter 14.

3-62e

Bases (Cont'd.)

Normal operation of the FHB ESF Air, Treatment System will be during TMI-l irradiated fuel mvements in the Fuel Handling Building. The system includes air filtration and exhaust capacity to ensure that any radioactive release to atmosphere will be filtered and monitored. Effluent radiation monitoring and sampling capability are provided.

References (1) Updated FSAR, Section 14.2.2.1 3-62f

'I

,-.-,,,4- .--, , - , . - w, --. - - - - - - - , - - . - - - - - - - - - , - -- ~

g

E a

k TABLE 3.21-2 (Continued) 5 2 RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION

. MINIMlM

- CHANNELS S INSTRtNENT OPERABLE APPLICABILITY ACTION

5. Auxiliary and Fuel Handling Building Air Treatment System
a. Noble Gas Activity 1
  • 27 Monitor (RM-A8) or (RM-A4 and RM-A6)
b. Iodine Sampler (RM-A8) or 1
  • 31 (RM-A4 and RM-A6)
c. Particulate Sampler 1
  • 31 (RM-A8) or (RM-A4 and RM-A6)

. d. Effluent System Flow 1

  • 26 E e. Sampler Flow Rate Monitor
  • 1 26
6. Fuel Handling Building ESF Air Treatment System
a. Noble Gas Activity Monitor (RM-A14) 1 **** 27
b. Effluent System Flow (UR-1104A/B) 1 **** 26
c. Sampler Flow Rate lionitor 1 **** 26 i

TABLE 3.21-2 (Continued)

TABLE NOTATION

  • At all times
    • During waste gas holdup system operation.
      • 0perability is not required when discharges are positively controlled through the closure of WDG-V47, and RM-A8 and FT-151 are operable.
        • During Fuel Handling Building ESF Air Treatment System Operation.

ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment for up to 14 days provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, and
2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve if neup.
3. The Operations and Maintenance Director, Unit 1 shall approve each release.

Otherwise, suspend release of radioactive effleunt via this pathway.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (See also Specification 3.5.1 Table 3.5-1, Item 3.f).

ACTION 30 1. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel (s) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both channels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channal(s).

(a) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations.

4 (b) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations (e.g. Feed and Bleed).

l 3-105 Amendment Nos. 72, 78, 104

TABLE 3.21-2 (Continued)

TABLE NOTATION I

ACTION 30 2. If the inoperable gas channel (s) is not restored to (CONTINUED) service within 14 days, a special report shall be submitted to the Regional Administrator of the NRC Region I Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel (s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, and (c) action to be taker, to prevent recurrence.

ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided that within four hours af ter the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment.

ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is placed in service within one hour. Af ter 28 days, or if one OPERABLE channel does not remain in service or is not placed in service within one hour, the provisions of 3.0.1 apply.

i l

l 3

3-105a l

l Amendment Nos. //2, NJ,104

4.12.3 AUXILIARY AND FUEL HANDLING BUILDING AIP TREATMENT SYSTEM Applicability Applies to the Auxiliary and Fuel Handling Building Air Treatment System and associated components.

Objective To verify that this system and associated components will be able to perform its design function.

Specification 4.12.3.1 At least once per refueling interval:

a. The pressure drop across the combined HEPA filter and adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow rate ( 10%).
b. The tests and sample analysis required by Specification 3.15.3.2 shall be performed.

4.12.3.2 Testing necessary to demonstrate operability shall be performed as follows:

a. The tests and sample analysis required by Specification 3.15.3.2 shall be performed following significant painting, steam, fire, or chemical release in any ventilation zone communicating with the system that could contaminate the HEPA filters or charcoal adsorbers.

, b. DP0 testing shall be performed after each complete or partial replacement of a HEPA filter bank or af ter any structural maintenance on the system housing that could affect the HEPA filter bank bypass leakage.

c. Halogenated hydrocarbon testing shall be performed af ter each complete or partial replacement of a charcoal adsorber bank or af ter any structural maintenance on the AH-F2A, B, C, or D housing that could affect charcoal adsorber bank bypass leakage.

4.12.3.3 An air distribution test shall be performed on the HEPA filter bank after any maintenance or testing that could affect the air distribution within the system. The air distribution across the HEPA filter bank shall be uniform within 20%. The test shall be performed at 118,810 cfm ( 10% flow rate).

Bases Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.

Pressure drop should be determined at least once every refueling interval to show system performance capability.

4-55d Amendment Nos. 55, 76

Tests and sample analysis assure that the HEPA filters and charcoal adsorbers can perform as evaluated. The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples.

Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. The in-place test criteria and laboratory test criteria for activated charcoal will meet the guidelines of ANSI-N510-1980.

If test results are unacceptable, all adsorbent in the system should be replaced with an adsorbent qualified according to Regulatory Guide 1.52, March 1978 or ANSI-N509-1980. Any HEPA filters found defective should be replaced with filters qualified according to Regulatory Guide 1.52, March 1978 or ANSI-N509-1980.

If significant painting, steam, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational use. The determination of what is significant shall be made by the TMI-1 Operations & Maintenance Director.

4-55e Amendment No. 55

4.12.4 FUEL HANDLING BUILDING ESF AIR TREATMENT SYSTEM Applicability Applies to Fuel Handling Building (FHB) ESF Air Treatment System and associated corrponents.

Objective To verify that this sytem and associated components will be able to perform its design functions.

Specification:

4.12.4.1 Each refueling interval prior to movement of irradiated fuel:

a. The pressure drop across the entire filtration unit shall be demonstrated to be less than 7.0 inches of water at 6,000 cfm flow rate ( 10%).
b. The tests and sample analysis required by Specification 3.15.4.2 shall be performed.

4.12.4.2 Testing necessary to demoastrate operability shall be performed as follows:

i

a. The tests and sample ana'Ysis required by Specification 3.15.4.2 shall be performed following significant painting, steam, fire, or chemical reiease in any ventilation zone communicating with the system that could contaminate the HEPA filters or charcoal adsorbers. ,
b. DOP testing shall be performed after each complete or partial  !

replacement of a HEPA filter bank, and af ter any structural l maintenance on the system housing that could affect the HEPA filter bank bypass leakage. j t

c. Halogenated hydrocarbon testing shall be performed af ter each j complete or partial replacement of a charcoal adsorber bank,  ;

and af ter any structural maintenance on the system housing i that could affect charcoa? adsorber bank bypass leakage.

4.12.4.3 Each filter train shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.

4.12.4.4 An air flow distribution test shall be perfortred on the HEPA filter bank initially and af ter any maintenance or testing that could affect the air flow distribution within the system. The distribution across the HEPA filter bank shall be uniform within 20%. The test shall be performed at 6,000 cfm 10% flow rate.

4-55f I

I

Bases The FHB ESF Air Treatment System is a system which .is normally kept in a

" standby" operati ng status. Tests and sample analysis assure that the HEPA

. filters and charcoal adsorbers can perform as evaluated. The charcoal adsorber efficiency test procedure should allow for the removal of a sample from one adsorber test cannister. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. The in-place test cfiteria and laboratory test criteria for activated charcoal will meet the guidelines of ANSI-N510-1980. If test results are unacceptable, all adsorbent in the system shall be replaced with an adsorbent qualified in accordance with ANSI-N509-1980. Any HEPA filters found defective will be replaced with filters qualified in accordance with ANSI-N509-1980.

Pressure drop across the entire filtration unit of less than 7.0 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.

Operation of the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month will demonstrate operability of the filters and adsorber system and remove excessive moisture buildup on the adsorbers and HEPA filters.

If significant painting, steam, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational movement of irradiated fuel . The determination of what is significant shall be made by the TMI-l Operations &

Maintenance Director.

4-55g

Ei ~

8

[ TABLE 4.21-2 (continued)

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8F R$ CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

5. Auxiliary and Fuel Handling Building Air Treatment System
a. Noble Gas Activity Monitor D M R(3) Q(1) *

(RM-A8) or (RM-A4 and RM-A6)

b. Iodine Sampler (RM-A8) or

( R4-A4 a nd RM-A6 ) W N/A N/A N/A *

c. Particulate Sampler (RM-A8) W '

N/A N/A N/A

  • or (RM-A4 and RM-A6) j
d. System Effluent Flow Rate D N/A R Q
  • Measurement Devices T

$ e. Sampler Flow Rate D N/A R Q *

6. Fuel Handling Building ESF Air Treatment System
a. Noble Gas Activity Monitor (RM-A14) D M R(3) Q(2) ****
b. System Effluent Flow Rate (UR-1104 A/B) D N/A R Q ****
c. Sampler Flow Rate Measurement Device D N/A R Q ****

TABLE 4.21-2 (Continued)

TABLE NOTATION

  • At all times.
    • During waste gas holdup system operation.

Operability is not required when discharges are positively controlled through the closure of WDG-V47, and RM-A8 and FT-151 are operable.

        • During Fuel Handling Building ESF Air Treatment System Operation.

l (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary and ' Fuel Handling Building Air Treatment System, the supply ventilation is isolated and control room alarm annunciation occurs if the following condition exists:

1. Instrument indicates measured levels above the high alarm / trip setpoint. (Includes circuit failure)
2. Instrument indicates a down scale failure. (Alarm function only)

(Includes circuit failure)

3. Instrument controls moved from the operate mode. (Alarm function only)

(2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm setpoint.

(includes circuit failure)

2. Instrument indicates a down scale failure (Includes circuit failure)
3. Instrument controls moved from the operate mode.

(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation

shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with i

NBS. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, i

sources that have been related to the initial calibration should be used.

, (Operating plants may substitute previously established calibration procedures for this requirement. )

l (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen, and
2. Four volume percent hydrogen, balance nitrogen.

4-95 Amendment No. 72 l

Er k TABLE 4.22-2 R

R RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM -

.E

-a I i

" l I I Sampling I tiinimum i I Lower Limit Gaseous Release Type l Frequency l Analysis l Type of Activity I of Detection l l Frequency l Analysis I (LLD) 1 l l l (uCi/ml)a l I I I I I I I l P l P l l A. Waste Gas Each Tank l Principal Gamma Storage Tank l

Grab l Each Tank l 1 x 10-4 l l l Emitters 9 l l Sample l l l l l l 1 I I I I B. Containment l P l P l H-3 l 1 x 10-6 l Purge Each Purge b Each Purge b l

Grab l l Principal Gamma l 1 x 10-4 1 l l Emitters 9 l u l Sample l l l

.' I I I I 8 I I I I C. Auxiliary and I l l H-3 l 1 x 10-6 Fuel Handling l Mc,e l M l Principal Gamma l 1 x 10-4 Building Air I Grab l l Emitters 9 l Treatment System l Sample l I l l l l 1 I I I I D. Fuel Handling Building 1 M (during l l H-3 1 1 x 10-6 ESF Air Treatment System I system opera- l M (during l Principal Gamma I 1 x 10-4 l tion) I system i Emitters 9 l l Grab Sample I operation) l I I I I I I I I I E. Condenser Yacuum Mb ,h l H-3 Pumps Exhaust h l l Mb ,h l 1 x 10-6 l Grab Sample I l Principal Gamma i 1 x 10-4 I l l Emitters 9 l l l l 1

! 1 1 I

E .

TABLE 4.22-2 (Continued)

RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

.E

" l

~ I I I l Sampling l Minimum l l Lower Limit Gaseous Release Type Frequency Analysis Type of Activity I of Detection Frequency Analysis I (LLD) l I I I (uCf/ml) a I i l l I I I I F. All Release Types as l I Wd l I-1 31 l 1 x 10-12 Listed Above in A, B, C I Continuous f I Charcoal l I-133 l 1 x 10-10 ,

I and D (during System l I Sample i I Operation) l I l l l l l l l l l l l l l l

' I Continuous f I Wd i Principle Gamma l 1 x 10-11 l l Particulate l Emitters 9 l

, I l l (I-131, Others) l l I I I 5 I I I I l l 6 l l Continuous f i o I Q l Gross Alpha l 1 x 10-11 l l l Composite l l l l Particulate I l l I Sample l l l l l l l l l l l Continuous f i I Q l Sr-89, Sr-90 l 1 x 10-11 l l Composite l l l l l Particulate l l l l Sample l I I I I I

TABLE 4.22-2 (Continued)

d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing (or af ter removal from sampler),
e. Tritium grab samples shall be taken weekly from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.
f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.22.2.1, 3.22.2.2, and 3.22.2.3.
g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emmissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and rep'arted. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.
h. Applicable only when condenser vacuum is established. Sampling and analyses shall be perfonned within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following each shutdown, startup or thermal power level change exceeding 15% of Rated Thermal Power in one hour,
f. Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

i I

i-i t

l 4-109 Amendment No. 72

ELEVATIONS FOR GASEOUS EFFLUENT RELEASE POINTS Unit 1 Stack 483' 7" Unit 1 Turbine Building 425' 4" Unit 2 Stack 483' 0" Epicor II 359 ' 6" Unit 1 Fuel Handling Building 348' ESF Vent Stack B a

i l

l l

l 5-10 Amendment No. 72

~

an g

- - . a --

\k_

%s ? - -

puustwa stacu

- ' -. x _g:Li A ~:d'E w[_=.'U 3 = I1:~ :::::h#pc

m::n: - ~~

. T ~

1/

I

" [" ]Z ' r m..

~- M ' i ...

-__.;:1-- .

~

Y l%

\ T =a .

)

m, e - f ,f ~.; ~-- -- .

- y, (1 _ ._

& s . ,c 9 ir:mS ./ l+.[2s

- . 7 i

. Q.g

' l!p q L n p QhQ-},4 ,

  • 5

,1 Ls l .'. .~. _

- ~ ~

s . %;. -

= .

$V -

-- )kLE>=.

c I v fr.=- .u=

[q l .L=--=

?=. j ,r l

_ ,4 -- -

.n_ g sw iw =-J - I r w 3 8J p i e m3= .-

g __go

.-'-- s gy - ~ -i yl,  % ._

E N _ _;,. -~

s .

E. f  ;

g M %*)r' ,

uns7*s staca da' ' - lW

,,M'fys1 .. ._,. d ) ,

.r . i . . .-

~"d ^7 ~~b ~ 1 -- '

~ ' -

UNIT #1 FUEL HANDLING BLDC. '-

ESF VENT STACK - --~

w Site Boundary for Gaseous Effluents

. Figure S-3 a