ML20215E864

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Amend 122 to License DPR-50,incorporating Tech Specs for Newly Installed Fuel Handling Bldg (Fhb) ESF Air Treatment Sys & Modifying Existing Specs Re Auxiliary & Fhb Air Treatment Sys
ML20215E864
Person / Time
Site: Crane Constellation icon.png
Issue date: 12/12/1986
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp
Shared Package
ML20215E867 List:
References
DPR-50-A-122 NUDOCS 8612230150
Download: ML20215E864 (23)


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UNITED STATES E

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20556

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t METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.122 License No. DPR-50 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by GPU Nuclear Corporation, et al.

(the licensees) dated August 25, 1986, as revised October 1, 1986, 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;

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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 (1) 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.

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8612230150 861212 PDR ADOCK 05000289 P

PDR

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPP-50 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.122, ere hereby incorporated in the license. GPU Nuclear Corporation 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 60 days or prior to fuel movement.

FOR THE NUCLEAR REGULATORY COMMISSION

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d Joh M Stolz, Directo Wy Project Directora e #6 0 vision of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: December 12, 1986 l

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s ATTACHMENT TO LICENSE AMENDMENT NO.122 FACILITY OPEPATING LICENSE NO. DPR-50 00CKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

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-f y iv 3-62c 3-62c 3-62d 3-62d 3-6?e 3-62f 3-104 3-104 3-105 3-105 3-105a 3-105a 4-55d 4-55d 4-55e 4-55e 4-b5f 4-55g 4-94 4-94 4-95 4-95 4-106 4-106 4-107 4-107 4-109 4-109 5-10 5-10 Figure 5-3 Figure 5-3

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O Section TABLE OF CONTENTS Page 2

SAFETY LIMITS AND LIMITING SAFETY SYSTEM 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 2-5 Instrumentation 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 Caolant System Vents 3-18f 3.2 Makeup and Purification and Chemical Addition Systems 3-19 3.3 Emergency Core Cooling, Reactor Building Emergency 3-21 Cooling and Reactor Building Spray Systems 3.4 Decay Heat Removal Caprbility 3-25 3.4.1 Reactor Coolant System Temperature Greater 3-25 Than 250'F 3.4.2 Reactor Coolant System Temperature 250*F or Less 3-26 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 3-37 Setpoints 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 Refuel'nq 3-44 3.9 Radioactive Materials 3-46 3.10 Miscellaneous Radioactive Materials Sources 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 Emergency Control Room Air Treatment System 3-61 3.15.2 Reactor Buildino Purge Air Treatrent System 3-62a 3.15.3 Auxiliary & Fuel Handling Building' Air Treatment System 3-62c 3.15.4 Fuel Handling Building ESF Air Treatment System 3-626 Amendment No. Se, }f, 7f, Sf, 9 AAN, 122 6

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Section TABLE OF CONTENTS 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 Decay Heat Removal Capability - Periodic Testing 4-52 4.9.1 Emergency Feedwater System - Periodic Testing 4-52 (Reactor Coolant Temperature Gr, eater Than 250*F) l 4.9.2 Decay Heat Removal Capability - Pariodic Testing 4-52a (Reactor Coolant Temperature 250*F or Less) 4.10 Reactivity Anomal'ies 4-53 4.11 Reactor Coolant System Vents 4-54 4.12

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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 & Fuel Handling Building Air Treatment System 4-55d n

4.12.4 Fuel Handling Building E5F Air Treatment System 4-55f l

4.13 Radioactive Materials Sources Surveillance 4-56 4.14 Reactor Bu11dino Purce Exnaust System 4-57 4.15 Main Steam System Inservice InspectEn 4-58 4.16 Reactor Internals Vent Valves Surve ffTance 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 & Inspection Methods 4-77 4.19.2 Steam Generator Tube Sample Selection & 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 Buildina Air Temperature 4-86 4.21.1 Radioactive Liquid Effluent Instrumentation 4-87 4.21.2 Radioactive Gaseous Process & Effluent Monitoring 4-90 Instrumentation 4.22.1.1 Liquid Effluents 4-97 i

4.22.1.2 Dose 4-102 4.22.1.3 Liquid Waste Treatment 4-103 l

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, Radiciodines, Radioactive Material in Particulate 4-111 l

Fonn & Radionuclides Other Than Noble Gases 4.02.2.4 Gaseous Radwaste Treatment 4-112 4.22.2.5 Explosive Gas Mixture 4-113 4.22.2.6 Gas Storage Tanks 4-114 l

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 4-121 4.23.3 Interlaboratory Comparison Program 4-122 Amendment No. g, %,W, ff, fT,%)(,g,g, f, Typ,122 IV

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h 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 Systen.

Specification

'3.15.3.1 The Auxiliary and Fuel Handling Building Air Treatment System including both pairs of exhaust f ans (AH-E14A, B, IL and D) and 4 banks of exhaust filters (AH-F2A, B, C, and D) shall be operable at all times during power opera. tion, except as provided in 3.15.3.3 l

and spe,cified in 3.22.2.4.

3.15.3.2 The Aux'iliary and Fuel Handling. Building Air Treatment System is operable when its surveillance requiremnts are met and:

a.

The results of the in-place 00P and halogenated hydrocarbon tests at design flows on HEPA filters and charcea.1 adsorber i

banks shall show <0.05% DOP penetration and <0.05% halogenated hydrocarbon penetration, except that the 00P test will be conducted with prefilters installed, b.

The results of laboratory carbon sample analysis shall show

>90% radioactive methyl iodide decontamination ef ficiency when Tested at 30*C, 95% R.H.

l 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 design flow t

(118,810 CFM).

3.15.3.3 a.

With one pair of Auxiliary and Fuel Handling Building Air Treatment System exhaust f ans ( AH-E14A and C or AH-E148 and D) inoperable, verify that the redundant pair of exhaust fans is in operation and discharging through its HEPA filters and charcoal adsorbers within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, except as provided in 3.15.3.3.b.

b.

From the date that the Aux,iliary and Fuel Handling Building Air Treatment System becomes inoperable for any reason during power operation, the system (at least one pair of exhaust fans discharging through i.ts HEPA filters and charcoal adsorbers) must be restored to operable condition within 7 days.

If the system is not restored to operable within 7 days, prepare and submit a special report to the NRC within the next 30 days outlining the actions taken to restore operability and the plans and schedules for restoring the system to operable s ta tu s.

3-62c Amende nt No. 66, 16,122

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 frma 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 cmergency air treatment systems. The charcoal adsorbers are installed to reduce the potential release of radioiodine 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.

The Auxiliary and Fuel Handling Building Air Treatment System is isolated by automatic damper actuation in the event of increasing activity in the Fuel Handling Building as sensed by radiation monitors.

References i

(1) FSAR Section 9.8 l

(2) FSAR Figure 9.8-4 (3) FSAR Section 14.2.2.5 l

(4) FSAR Section 14.2.2.6 l

f 3-62d Amendment No. /!i5,122

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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 Prior to fuel movement each refueling outage, two trains shall be operable.

One train shall be operating continuously whenever THI-1 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 continue provided the redundant, train is operating.

With both trains inoperable, handling of irradiated fuel in b.

the Fuel Handling Building shall be suspended until such time that at least one train is operable and operating. Any fuel assembly mnvement in progress may be completed.

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

The results of the in-place D0P and halogenated hydrocarbon a.

tests at design flows on HEPA filters and carbon adsorber banks shall show <0.05% DOP penetration and <0.05% halogenated i

hydrocarbon penetration.

b.

The results of laboratory carbon sample analysis shall show

>90% radioacti/e methyl 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 within 110% of disign 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, monitors and l

records radiation release resulting from a TMI-1 postulated spent fuel

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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.

Amendment No.122 3-62e i

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Bases (Cont'd.)

Normal operation of the FHB ESF Air Treatment System will be during TMI-l irradiated fuel movements 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 Amendment No. 122 3-62f

f TABLE 3.21-2 (Continued)

RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION k

MINIMUM g

CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION k

5.

Auxiliary and Fuel Handling Building Air Treatment System a.

Noble Gas Activity Monitor 1

27 (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 rN-A6) d.

Effluent System Flow 1

26 e.

Sair.pler Flow Rate Monitor 1

26 t

w 6.

Fuel Handling Building ESF Air Treatment System a.

Noble Gas Activity Monitor 1(2) 27, 33 (RM-A14 or Suitable Equivalent) b.

Iodine Cartridge N/A(3) 31, 33 c.

Particulate Filter N/A(3) 31, 33 d.

Effluent System Flow (UR-1104A/B) 1 26, 33 e.

Sampler Flow Rate Monitor 1

26, 33 NOTE 2: Until the beginning of the 7R refueling outage, a suitable equivalent OPERABLE channel may be defined for item 6.a of this specification and specification 4.21.2 (Table 4.21-2, item 6.a) as a system capable of alerting the Control Room by alarm or voice communication and capable of measuring the full range of normal and calculated accident releases for existing plant conditions.

NOTE 3: No instrumentation channel is provided. However, for determining operability, the equipment named must be installed and functional or the ACTION applies.

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 Rfi-A8 and FT-151 are operable.

' ****During Fuel Handling Building ESF Air Treatment System Operation.

l ACTION 25 With the number of channels OPERABLE less than required by the tiinimum 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

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2.

At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.

3.

The Operations and liaintenance Director, Unit 1 shall approve each release.

Otherwise, suspend release of radioactive effluent 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 />.

(For RM-A9 j

only, see also Specification 3.5.1, Table 3.5-1, Item C.3.f).

ACTION 30 1.

With the number of char.nels 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 channel (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.

(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).

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3-105 Amendment Nos. 72, 78, W,122

l 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 char.nel(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 taken 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 after 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 requirement, 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.

ACTION 33 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 dtys, or prepare l-and submit a special report within 30 days outlining the i

action (s) taken, the cause of the inoperability, and plans and j

schedule for restoring the system to OPERABLE status.

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I 3-105a Amendment Nos. ?f, ljd, N4,122

4.12.3 AUXtLIARY AND FL'EL HANDLING BUILDING AIR 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 fi~lter 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 he 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.

D0P testing shall be performed af ter 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 charccal 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, d.

The fan combination AH-E 14A and C and AH-E 148 and D 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.

4.12.3.3 An air distribution test shall be performed on the HEPA filter bank af ter any maintenance or testing that could af fect the air distribution within the system.

The air distribution across the HEPA filter bank shall be uniform within 120%.

The test shall be performed at 118,810 c f m ( 210t f l ow ra te ).

4-SSd Ame ndme n t No s. H, 7tf, 122 I

Bases P' essure drop across the combined HEPA filters and charcoal adsorbers of less r

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.

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 f rom 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 ir. the system should be replaced with an adsorbent qualified according to Regulatory Guide 1.52, fiarch 1978 or ANSI-N509-1980. Any HEPA filters found defective should be replaced with filthrs 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 analys shall be performed as required for operational use. The determination of what is significant shall be made by the TMI-l Cperations & Maintenance Director.

Operation of the Auxiliary and Fuel Handling Building Exhaust Fans each month for at least ten (10) hours will demonstrate operability of the fans.

4-55e Amendment No. 7/,122

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

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

1 Specification i

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 demonstrate operability shall be performed as follows:

a.

The tests and sample analysis required by Specification 3.15.4.2 shall be performed following significant painting, steam, fire, or chemical release in any ventilation zone comunicating 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 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, and after any structural maintenance on the system housing that could affect charcoal 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 performed on the HEPA filter bank initially and af ter any r.1aintenar.:e or testing that could affect the air flow distribution within the system. The distribution across the HEPA filter bank shall be uniform within t

20%. The test shall be performed at 6,000 cfm 10% flow rate.

Amendment No.122 4-55f

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Bases The FHB ESF Air Treatment System is a system which is normally kept 1.n a

" standby" operating status. Tests and sample analysis assure that the HEPA filters and charcoal adsorbers can perform as evaluated. Tlq 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 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 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 adsoroer 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 funes, 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-1 Operations &

Maintenance Director.

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knendment No.122 4-55g

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i TABLE 4.21-2 (continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 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 (RM-A4 and 24-A6)

W N/A N/A N/A c.

Particulate Sampler (RM-A8)

W N/A N/A N/A or (M4-A4 and RM-A6) d.

System Effluent Flow Rate D

N/A R

Q Measurement Devices Sampler Flow Ra Measurement Devke D

N/A R

Q e.

ce 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 f

+

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 CMANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary and Fuel Handling Building Air Treatment System, I

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 o: using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources-that have been related to the initial calibration should be used.

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

(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. 74,122

i F

TABLE 4.22-2 l

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 8e EI I

I I

l l

Sampling i

Mi n'..asm l

l Lower Limit D

Gaseous Release Type l

Frequency l

Analysis l

Type of Activity l

of Detection l

l Frequency l

Analysis I

(LLD)

C l

l l

l (uCi/ml)a l

l l

1 I

I I

I l

P l

P l

l A.

Waste Gas l

Each Tank l

Each Tank l

Principal Gamma 1 x 10-4 Storage Tank l

Grab l

l Emitters 9 l

l Sample l

l l

1 I

I l

l l

l 1

B.

Containment l

P l

P I H-3 l 1 x 10-6 l

Purge l

Each Purge b l

Each Purge b l Principal Gamma l 1 x 10-4 i

Grab l

l Emitters 9 l

l Sample l

l l

1 l

1 I

f I

I I

I E

C.

Auxiliary and l

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 i

Sample l

l l

l l

1 l

l l

l I

D.

Fuel Handling Building l

M (during l

l H-3.

l 1 x 10-6 ESF Air Treatment System l system opera-l M (during l

Principal Gamma l 1 x 10-4 I

tion) l system l

Emitters 9 l

Grab Sample l

operation) i i

1 l

l l

l l

l l

b M,h l

l H-3 l 1 x 10-6 E.

Condenser Vacuum l

Pumps Exhaust h l

Grab Sample l

M,h l Principal Gamma l 1 x 10-4 b

l l

l Emitters 9 l

l l

l l

=

.i N

o.

g TABLE 4.22-2-(Continued) l RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l

5 I

.1-1 I

1 Sampling l

Minimum l

l Lower Limit y

Gaseous Release Type l

Frequency l

Analysis l

Type of Activity I

of Detection l

l Frequency 1.

Analysis I

(LLD) l l

l l

(uCi/ml) a l

l 1

1 I

I I

I F.

All Release Types as l

l Wd l

I-1 31 l

1 x 10-12 Listed Above in A, B, C l

Continuous f l

Charcoal l

I-133 l 1 x 10-10 and D (during System l

l Sample l

l Operation) l l

l l

1 I

I I

I I

I I

l l

1 l

l Continuous f l

Wd l

Principle Gamma l 1 x 10-11 l

l Particulate l

Emitters 9 l

l l

l (I-131, Others)

I

.l' l

l 1

l L

I I

I I

S I

I I

l l

Continuous fo i l

Q l

Gross Alpha i 1 x 10-11 l

l l

Composite l

l l

l Particulate l

l l

l Sample 1

l l

l l

l l

l l

l l

Continuous f.i l

Q l Sr-89, Sr-90 l 1 x 10-11 I

i l

Composite l

l I

l Particulate l

l l

l l

Sample l

l l

l l

1

... /.

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 amitters for which the LLD specification applies exclusively are the cIlowing 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, 2n-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 measurabl~e and' identifiable, together with the above nuclides, shall also be identified and reported. 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. Sanpling and analyses shall be performed 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.

i.

Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

4-109 Amendment No. 72',122

-s l.

~

. s.

..s'J.

1

, t '..

  • N-
ss A,

.i ELEVATIONS FOR GASEOUS EFFLUENT RELEASE POINTS

/

i x

Unit 1 Stack 483' 7" Unit 1 Turbine Building "425' 4" Unit 2 Stack 483' 0" Epicor II 3 59 ' 6" Unit 1 Fuel Handling Building I 348' ESF Vent Stack d

5-10 Amendment No. //,122

O

.o 6 S.

I T

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