Text

Recovery Operations Plan
	ML20154Q677
Person / Time
Site:	Three Mile Island
Issue date:	05/27/1988
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20154Q663	List: ML20154Q659; ML20154Q677;
References
	PROC-880527, NUDOCS 8806070093
	Download: ML20154Q677 (42)
	v • d • e

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RECOVERY OPERATIONS PLAN THI-2 6

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8806070093 880527 PDR P ADOCK 05000320 PDR

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. INDEX SURVEILLANCE REQUIREMENTS ___

SECTION Page 4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 4.1.1 B O RA T I O N C O N T R 0 L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.1.1.1 Borated Cooling Water Injection................................ 4.1-2 4.1.1.2 Boron Concentration Reactor Coolant System and Refueling Canal. 4.1-2 4.1.1.3 Boron Concentration Fuel Transfer Canal (Deep End).......... .. 4.1-2 4.1.1. 4 Boron Concentration Spent Fuel Pool 'A'........................ 4.1-2 4.1.3 CONTROL ASSEMBLIES...................... ...................... 4.1-2 l

4.3 INSTRUMENTATION 4.3.1 NEUTRON MONITURING INSTRUMENTATION............................. 4 . 3 -

4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..... 4.3-1 4.3.3 MONITORING INSTRUMENTATION..................................... 4.3-1 4.3.3.1 Radiation Monitoring Instrumentation........................... 4.3-1 l 4.3.3.4 Meteorological Instrumentation................................. 4.3-8 4.3.3.5 Essential Parameters Monitoring Instrumentation................ 4.3-8 4.3.3.7 Chlorine Detection Systems..................................... 4.3-8 4.3.3.8 Fire Detection................................................. 4.3-13 ,

4.4 REACTOR COOLANT SYSTEM 4.4.1 R E ACTO R COO LANT L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.4-1 4.4.2 REACTOR VESSEL WATER LEVEL MONITORING.......................... 4.4-1 l 4.4.3 PRESSURE / TEMPERATURE LIMITS.................................... 4.4-1 l

4.5 COMMUNICATIONS...................................................... 4.5-1 !

i i 4.6 CONTAINMENT SYSTEMS................................................. 4.0-1 l 4.6.1 PRIMARY CONTAINMENT l 4.6.1.1 Containment Integrity.......................................... 4.6-1 !

4.6.1.2 Containment Isolation.......................................... 4.6-1 4.6.1.3 Containment Air Locks (Mode I)................................. 4.6-1 l

1 THREE MILE ISLAND - UNIT 2 i Change No. 39 i

1 INDEX SURVE!LLANCE REQUIREMENTS SECTION Page 4.6.1.4 Internal Pressure.............................................. 4.6-2

4. 6.1. 5 A i r T e mp e ra t u re . . . . . . . . . . . . .) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.6-2 4.6.1.6 Containment Air Locks (Modes 2 and 3).......................... 4.6-2 l 4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM............................... R.6 I

,4. 7 PLANT SYSTEMS I

4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM............................. 4.7-1 4.7.6 FLOOD PROTECTION............................................... 4.7-1 4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM...................... 4.7-1 -

4.7.9 SEALED SOURCES................................................. 4.7-4 4.7.10 FIRE SUPPRESSION SYSTEMS 4.7.10.1 Fire Suppression Water System.................................. 4.7-5 l 4.7.10.2 Deluge / Sprinkler Systems....................................... 4.7-7 4.7.10.3 Halon System................................................... 4.7-7 l 4.7.10.4 Fire Hose Stations............................................. 4.7-8 4.7.11 PENETRATION FIRE BARRIERS...................................... 4.7-8 4.8 ELECTRICAL POWER SYSTE_M_S i

4.8.1 A.C. SOURCES................................................... 4.8-1 4.8.2 ON5ITE POWER DISTRIBUTION SYSTEMS i 4.8.2.1 A.C. Distribution.............................................. 4.8-2 4.8.2.2 D.C. Distribution.............................................. 4.8-2 l )

4.9 LIQUID RADIOACTIVE WASTE STORAGE '

4.9.1 I

SPEKT FUEL STORAGE POOL WAT,ER "A" LEVEL MONITORING............. 4.9 1 4.9.2 SPENT FUEL STORAGE POOL WATER " A" LEVEL. . . . . . . . . . . . . . . . . . . . . . . . 4.9-1 !

l 4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVELING MONITORING....... 4.9-1 4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL. . . . . . . . . . . . . . . . . . . . . 4.9-1 1

4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP dYSTEMS.. 4.9-1 l

1 THREE MILF ISLAND - UNIT 2 ii Change No. 39

c SURVEILLANCE REQUIREMENTS 4.0.1 Surveil

Requirements of the REC 0VERY OPERATIONS PLAN shall be applicable du he FACILITY MODE or other conditions specified for l individual L' nditions for Operation unless otherwise stated in an individual i Requirement. The Surveillance Requirements shall be 1erformed t. a compliance with the OPERABILITY requirements of the Limiting Cona. Operation and in accordance with the RECOVERY OPERA-TIONS PLAN; ho .he RECOVERY OPERATIONS PLAN shall not be considered a part of these te ..n cal specifications. Changes to the REC 0VERY OPERATIONS PLAN shal' be approved by the NRC prior to implementation.

4.0.2 Each Surveillance Requirement of the RECOVERY OPERATIONS PLAN shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance -

interval, and I

b. A total maximum combined interval time for any 4 consecutive tests not to exceed 3.25 times the specified surveillance interval.

4.0.3 Perfarmance of a Surveillance Requirement within the specified time interval snali constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

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l THREE MILE ISLAND - UNIT 2 4.0-1 Change No. 39

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SURVEILLANCE REQUIREMENTS 4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS

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4.1.1 BORATION CONTROL BORATED COOLING WATER INJECTION 1

4.1.1.1 The systems capable of injecting borated cooling water into the l

Reactor Coolant System shall be demonstrated OPERABLE:

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a. At least once per 31 days by verifying that each accessible (per occupa-tional exposure considerations) valve in each flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position, j

b. At least once per 7 days by:

1. Verifying the boron concentration in the BWST is between 4350 and 6000 ppm.

2. Verifying the contained borated water volume in the BWST is at least __

390,000 gallons:

c. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the BWST temperature is at least 50 degrees Farenheit when the outside temperature is less than 50 degrees Farenheit.

d. At least once per 6 months by verifying the pumps associated with the Reactor Building Sump Recirculation System produce sufficient head and flow to meet makeup requirements.

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THREE MILE ISLAND - UNIT 2 4.1-1 Change No. 39 ;

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l SURVE8LLANCE REQUIREMENTS I

i BORON CONCENTRATION l l

4.1.1.2 The boron concentration of all filled portions of the Reactor Coolant l System and the Refueling Canal shall be determined to be within the specified limits by:

a. Determining the boron concentration of the coolant in the filled 4 portions to be between 4350 and 6000 ppm by: !

1. A mass balance calculation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. A chemical analysis at least once per 7 days.

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b. Verifying the temperature of the coolant in the filled portions of l the Reactor Coolant System to be greater than 50*F at least once per 1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , i 4.1.1. 3 The boron concentration of the water in the filled portions of the Fuel Transfer Canal (deep end) shall be determined to be within the specified -

limits by: -~

a. Determining the boron concentration of the water in the filled portions of the Fuel Transfer Canal (deep end) to be between 4350 and 6000 ppm by a chemical analysis at least once per 7 days.

4.1.1.4 The boron concentration of the water in the filled portions of spent fuel pool 'A' shall be determined to be within the specified limits by:

a. Determining the boron concentration of the water in the filled ;

portions of Spent Fuel Pool 'A' to be between 4350 and 6000 ppm by a chemical analysis at least once per 7 days. l 4.1.3 CONTROL ASSEMBLIES I l

4.1.3.1 Deleted. I l

THREE MILE ISLAND - UNIT 2 4.1-2 Change No. 39 c

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SURVEILLANCE REQUIREMENTS 4.3 INSTRUMENTATION 4.3.1 NEUTRON MONITORING INSTRUMENTATION 4.3.1.1 Each intermediate and source range neutron monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequency shown in Table 4.3-1.

4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Deleted 4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated-OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-3.

THREE MILE ISLAND - UNIT 2 4.3-1 Change No. 39

o 5$ TABLE 4.3-1 '

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NEUTRON MONITORING INSTRUMENTATION 3

m 0; CHANNEL MINIMUM 5 CHANNEL CHANNEL FUNCTIONAL TOTAL NO. CHANNELS CHANNELS READ OUT Ei FUNCTIONAL UNIT CHECK CALIBRATION TEST OF CHANNELS TO TRIP OPERABLE LOCATIONS i 1. Intermediate Range, Neutron D/M(4) R II) M 2 0 1 Cab 217(2&3) .

50 Flux and Rate Control Room

2. Source Range, Neutron Flux D/M(4) R(1) M 2 0 2 Cab 217(2&3) .

and Rate Control Hoom NOTES

!* (1) - Neutron detectors and all channel components located inside containment may be excluded from i' CHANNEL CALIBRATION.

to (2) - Only one readout required at Cabinet 217.

(3) - Intermediate and source range rate is not required at cabinet 217.

(4) - Monthly channel check applies only to cabinet 217.

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TABLE 4.3-2 ,

m ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION :

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(( RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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m U CHANNEL MINIMUM 52 CHANNEL CHANNEL FUNCTIONAL CHANNELS l is FUNCTIONAL UNIT CHECK CALIBRATION TEST OPERABLE APPLICABILITY ACTION cg 1. CONTAINMENT

-l a. Deleted

b. Reactor Building Equipment Doors (AMS-3) D SA W 1 Note 10 Note 7

c. Deleted

d. CACE Vent Monitor D SA W 1 Note 8 Note 9

2. FUEL HANDLING BUILDING EXHAUST MONITORS (HPR-221A or HPR-221B)

a. Gaseous Activity D R M 1 Note S Note 6 f

b. Particulate Activity D R M 1 Note 5 Note 6

) 3. SDS MONITORS

a. Process Monitor (IX04) D R M 1 Note 1 Note 4

. jf b. Area Monitor (IX03) D SA M 1 Note 1 Note 2

o 1 I 4. Deleted z

. (See following pages for notes) i l

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---e si TABLE 4.3-3 (Cont'd) .

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ag RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

m U CHANNEL MINIMUM Eh CHANNEL CHANNEL FUNCTIONAL CHANNELS c'

FUNCTIONAL UNIT CHECK CALIBRATION TEST OPERABLE APPLICABILITY ACTION

si 5. FUEL TRANSFER CANAL M

n, a. Criticality Monitor D R M 1 Note 11 Note 12 l

6. FUEL POOL "A"

, a. Criticality Monitor D R M 1 Note 11 Note 12 l f' 7. FUEL HANDLING BUILDING i> TRUCK BAY u,

a. Criticality Monitor D R M 1 Note 11 Note 12 l

8. WASTE HANDLING AND PACKAGING FACILITY

a. Exhaust Monitor D SA W l Note 1 Note 13 i 9. REACTOR BUILDING

a. End Fitting Storage D R M 1 Note 14 Note 15

! Area Criticality Monitor e,

j[ (See following pages for Notes.)

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_4 55 TABLE 4.3-3 (Con't) 2 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS P

"' NOTES:

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u 5; (1) During operation of the monitored system.

85 (2) If monitor becomes inoperable, repair or replace by equivalent equipment within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If not completed

, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months terminate operation of the monitored system and restore the inoperable monitor (s) to operable c: staLus.

25 (3) Deleted.

-4 (4) If ion exchange effluent monitor is inoperable, sample on 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months frequency for gross beta. If inoperable longer than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months then terminate operation of ion exchange system and restore the inoperable monitor to I operable status.

(S) Modes 1 and 2 with radioactive waste in the fuel handling buildirg.

i (6) With the required instrumentation inoperable, suspend all operations involving movement of radioactive wastes l in the fuel handling building; restore the inoperable equipment to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

, (7) With the AMS-3 inoperable, close at least one of the Reactor Building Equipment Doors and restore the

,, inoperable equipment to operable status prior to the reopening of both Equipment Doors.

y, (8) Mode 1, during operation of the monitored system. l (9) Two filter trains and associatea monitors are normally available. If one monitor becomes inoperable, dis- '

continue operation through the effected filter train and transfer operations to the operable filter train. l If both monitors become inoparable, repair or replace by equivalent equipment within twelve (12) hours or conduct air sampling using alternate methods on a four (4) hour frequency. If repair or replacement is not completed within seven (7) days, terminate operation of the system until at least one monitor is returned to operable status.

(10) With both reactor building equipment hatch airlock doors open simultaneously.

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I"i r RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS P

NOTES:

G g 11. During either of the following operations:

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. a. Handling of canisters containing core material."

b. Handling of any heavy load over canisters containing core materials.

" 12. With less than one channel operable, terminate the following operations:

a. Handling of canisters containing core raaterial.*

b. Handling of any heavy load over canisters containing core material.

(4 13. With the required monitor inoperable, secure the ventilation system and suspend all operations involving movement of radioactive materials or generation airborne contamination until the inoperable monitor is-restored to operable status.

14. During periods when personnel are in the containment and end fittings are being transferred to or stored in their designated location outside the Reactor Vessel.

15. With less than one channel operable, terminate the following operations:

a. Handling of end fitting storage containers outside the Reactor Vessel.**

I b. Handling of any heavy load over the end fitting storage container area.

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! *This shall not prohibit placing a canister in transit in a safe storage location.

e **This shall not prohibit placing an end fitting storage container in transit in a safe storage location.

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l SURVEILLANCE REQUIREMENTS l l

l METEOROLOGICAL INSTRUMENTATION ;

4.3.3.4 Each of the meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance oi the CHANNEL CHECK and CHANNEL i CALIBRATION operations at the frequencies shown in Table 4.3-5.

I ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION 4.3.3.5 Each of the Essential Parameters Monitoring Instrumentation channels ;

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL '

CALIBRATION operations at the frequencies shown in Table 4.3-7.

CHLORINE DETECTION SYSTEMS 4.3.3.7 Each chlorine detection system shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and a CHANNEL FUNCTIONAL TEST at least once per 31 days. At least once per 18 months, the l ,

l following inspections and maintenance shall be performed:

a. Check constant head bottle level and refill as necessary,

b. Clean the sensing cells,

c. Check flow meter operation and clean or replace filters and air l lines as necessary,

d. Cneck air pump for proper operation, and

e. Verify that the detector responds to HCL.

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l THREE MILE ISLAND - UNIT 2 4.3-8 Change No. 39 L

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< -l TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMEN]

MINIMUM CHANNEL CHANNEL INSTRUMENT OPERABLE CHECK CALIBRATION

1. WIND SPEED

a. Nominal Elev. 100 ft 1 D SA

2. WIND DIRECTION

a. Nominal Elev. 100 ft. 1 D SA

3. AIR TEMPERATURE - DELTA T

a. Nominal ,

Elev. 33 ft. 1 0 SA -.

b. Nominal Elev. 150 ft. 1 0 SA l

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I THREE MILE ISLAND - UNIT 2 4.3-9 Change No, 39

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!! TABLE 4.3-7 '

3g ESSENTIAL PARAMETERS MONITORING INSTRllMENTATION SURVEILLANCE REQUIRLMENTS k

U MINIMUM hh CHANNEL CHANNEL (1) READOUT OPERABLE c) IMSTRUMENT CHECK CALIBRATION LOCATION (S) CHANNELS g 1. Transferred to Specification 4.6.1.4.a Z

n, 2. Transferred to Table 4.3-8

3. Incore Thermocouples/RCS 9 R Control Room or ?(2)

Temperature Detectors Cab!e Room

<3. Reactor Buildirig Water Level NA SA Control Bldg. 1

,, Area West or

,, Hot Instru-

4 ment Shop o

5. Borated Water Starage Tank Level D R Control Room 1 l

$ 6. Steam Generator Level NA NA NA 1/ Generator

7. Transferred to Table 4.3-8

8. Transferred to Table 4.3-8

. (See following page for notes) i

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--4 yi TABLE 4.3-7 (Cont'd) ,

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Notes:

M 5; (1) Nuclear detectors and all channel components located inside containment may be excluded from CHANNEL is CALIBRATON.

c: (2) Any combination of incore thermocouples, or RC-TI-106 points A, B, or C that results in a minimum

{c of two operable temperature detectors, satisfy this requirement.

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s ll TABLE 4.3-8 ,

ni WATER LEVEL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

- MINIMUM CHANNLL(1) READGUT OPERABLE (f CHANNELS g INSTRUMENT CHECK CALIBRATION LOCATION (S) 2(1)

[ 1. Reactor Vessel Water Level D/W(1) SA Control Room (1)

2. Spent Fuel Storage Pool D/W(1) SA Control Room (I) 2(I) m "A" Water Level or Fuel Handling Bldg.

3. Fuel Transfer Canal D/W(1) SA Control Room (I) 2(1)

(deep end) Water Level or Reactor Bldg.

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1. One channel may consist of a visual indication such as a level stand pipe. Seven day surveillance E applies to visual indication only. Visual indication readout may be in the Reactor Building, or Fuel

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Handling Building, or by remote television.

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SURVEILLANCE REQUIREMENTS FIRE DETECTION 4.3.3.8.1 Each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

4.3.3.8.2 The NFPA Code 71 supervised circuits supervision associated with the detector alarms of each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.8.3 The nonsupervised circuits between the local panels in Surveillance Requirementt 4.3.3.8.2 and the control room shall be demonstrated OPERABLE at least once per 31 days.

4.3.3.8.4 In lieu of Specification 4.3.3.8.2, fire detection instrument for the Southeast Storage Facility shall have circuitry per site-approved procedures. l THREF MILE ISLAND - UNIT 2 4.3-13 Changc No. 39

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, TABLE 4.3-11 FIRE DETECTION INSTRUMENTS Required Instruments Alternate Operable Instrument Instrument Location Heat Flame Smoke Heat Flame Smoke

1. Auxiliary Building NA NA 2 NA NA 2

2. Control Building 351' Elevation NA NA 1 NA NA 3 331' Elevation (Control Room) NA NA 1 NA NA 1 305', 293', 280 Elevations NA NA 1 NA NA 7

3. Control Building Area NA NA 1 NA NA 3

4. Diesel Generator Building A Diesel NA 1 1 NA NA 1 -

B Diesel NA 1 1 NA NA 1

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5. Fuel Handling Building NA NA 3 NA NA 1

6. Reactor Building NA NA 1 NA NA 1 RC-P-1A/2A NA NA 1 NA NA 2 RC-P-1B/2B NA NA 1 NA NA 2

7. River Wtter Pump House NA 1 1 NA NA 2

8. Service Building NA NA 3 NA NA 3

9. Deleted

10. Southeast Areas Storage Facility NA NA 2 NA NA 2 THREE MILE ISLAND - UNIT 2 4.3-14 Change No. 39

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SURVEILLANCE REQUIREMENTS 4.4 REACTOR COOLANT SYSTEM

-REACTOR COOLANT LOOPS 4.4.1 Deleted.

4.4.2 REACTOR VESSEL WATER LEVEL MONITORING 4.4.2 The Reactor Vessel Water Level Monitoring Instrumentation shall be demonstrated OPERABLE as required by Table 4.3-8.

4.4.9 PRESSURE / TEMPERATURE LIMITS 4.4.9.1 REACTOR COOLANT SYSTEM 4.4.9.1.1 The pH of the reactor coolant shall be determined to be greater than or equal to 7.5 and less than 8.4 at least once per 7 days. I 1

4.4.9.1.2 The chloride concentration in the reactor coolant shall be deter- l mined to be less than or equal to 5 ppm at least once per 7 days.

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I THREE MILE ISLAND - UNIT 2 4.4-1 Ctange No. 39

, SURVEILLANCE REQUIREMENTS 4.5 COMMUNICATIONS 4.5.1 Verify that communications channels are OPERABLE between the Control Room or the Command Center and personnel in the Reactor Building once each day prior to the initiation of any activities involving CORE ALTERATIONS. Also .

verify that the additional S0L or SOL limited to fuel handling has OPERABLE I communication channels once each day prior to the initiation of any activities involving core alterations.

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i THREE MILE ISLAND - UNIT 2 4.5-1 Change No. 39

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SURVEILLANCE REQUIREMENTS :

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4.6 CONTAINMENT SYSTEMS l

4.6.1 PRIMARY CONTAINMENT l CONTAINMENT INTEGRITY 4.6.1.1.a Primary CONTAINMENT INTEGRITY shall be demonstrated at least once per 31 days. l 4.6.1.1.b Modifications to containment penetrations shall be checked daily by verifying that the penetration is closed by a valve, blind flange, or deactivated automatic valve secured in its position.

CONTAINMENT ISOLATION 4.6.1.2 Primary CONTAINMENT ISOLATION shall be verified quarterly.

Penetrt ns which are closed by bolted or welded blind flanges are not )

required to be surveilled.

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CONTAINMENT AIR LOCKS _(MODE 1) 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE: l

a. After ecen opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying less than or equal to 0.01 L seal leakage when the volume between the door seals is stabilized to a pressure of 6.5 psig.

b. At least once per three months by performing a mechanical operability check of each airlock, including a visual inspection of the components and lubrication if necessary.

l 4.6.1.3.1 When both equipment hatch personnel airlock doors are opened !

simultaneously, verify the following conditions: '

a. The capability exists to expeditiously clos 6 at least one airlock door.

b. The airlock doors and containment purge are configured to restrict the outflow of air. During periods when both airlock doors are open, the following activities will be prohibited:

1. Core Alterations.

2. Heavy load lifts in the Reactor Building.*

3. Activities which could result in a fire in the Reactor Building (e.g., welding, burning), ,

c. The airlock doors are cycled to ensure mechanical operability within seven days prior to opening both doors.

- This does not preclude completion of those activities necessary to place the plant in a safe configuration.

THREE MILE ISLAND - tINIT 2 4.6-1 Change No. 39

, - -, ,--_-.._.-,_,,.-,_,--.m, ~ - , _ ,_

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. l SURVEILLANCE REQUIREMENTS INTERNAL PRESSURE 1

4.6.1.4.a The primary containment internal pressure shall be determined to be I within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,except during periods when the containment building is open to the atmosphere. The instrumentation surveil-lance requirements are as follows:

1. Minimum operable Channels .................................... 2 I

2. Channel Check ................................................. D

3. Channel Calibration ........................................... R

4. Readout Location ................................... Control Room 4.6.1.4.b During periods when the containment building is open to the atmosphere, methods to ensure airflow into the containment building shall be implemented in accordance with site-approved procedures. The restrictions of l 4.6.1.3.1.b, "Containment Airlocks (Mode 1)," and 4.6.1.6.1.b, "Containment Airlocks (Modes 2 and 3)," shall also apply. l AIR TEMPERATURE -

4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

Location

a. RB nominal Elev. 350' (1 temperature indication)

b. RB nominal Elev. 330' (1 temperature indication)

c. RB nominal Elev. 305' (1 temperature indication) l CONTAINHENT AIRLOCKS (MODES 2 AND 3) l 1

4.6.1.6 Each Containment Airlock shall be demonstrated OPERABLE:

a. After each opening, if not performed within the last 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying less than or equal to 0.01 L seal leakage when the volume between the door sealsisstabilizedtoaprefsureof6.5psig.

b. At least once per three months by performing a mechanical operability check of each Airlock, including a visual inspection of the components and lubrication if necessary.

4.6.1.6.1 When both Equipment Hatch Personnel Airlock doors are opened simul-taneously, verify the following conditions:

a. The capability exists to expeditiously close at least one Airlock door,

b. The Airlock doors and containment purge are configured to restrict the outflow of air in accordance with site-approved procedures,

c. The Airlock doors are cycled to ensure mechanical operability within seven days prior to opening both doors.

THREE MILE ISLAND - UNIT 2 4.6-2 Change No. 39

SURVEILLANCE REQUIREMENTS CONTAINMENT VENTILATION 4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM 4.6.3.1 The Containment Purge Exhaust System shall be demonstrated OPERABLE:

a. Prior to system operation if not performed within the previous 31 days and thereafter at least once per 31 days during operation by verifying that the Purge Exhaust System in the normal operating mode meets the following conditions:

1. Filter Pressure Orop: The d/p across the combined HEPA filters shall not exceed 6 inches water gauge while the system is operating.

b. Prior to system operation if not performed within the previous 18 months and thereafter at least once per 18 months by verifying that the ventila-tion system meets the following conditions: -

1. Visually inspect each filter train and associated components in accordance with Section 5 of ANSI N510-1980, as required by Regulatory Position C.5.a of Regulatory Guide 1.52, Revision 2, March 1978. The inspection should be performed prior to the 00P test of this section.

2. Flow Test: Exhaust flow rate shall be within 18,000 cfm to 27,000 cfm operating band for each filter train with one filter train and one exhaust fan operating. Testing shall be in accordance with ANSI N510-1980, Section 8.3.1, parag aphs 3 and 4.

3.

00P Test: Each filter train shall be tested in accordance with Section 10 of ANSI N510-1980, as required by Regulatory Position C.5.c of Regulatory Guide 1.52, Revision 2, March 1978.

NOTE: Installed system flow instrumentation is adequate for the test described in Section 4.6.3.1.b.3 above.

c. After structural maintenance of the HEPA filter or charcoal absorber housings, or following fire or chemical release in any ventilation zone communicatirig with the system by verifying that the ventilation system meets the following conditions:

1. Filter Pressure Drop: Reverify the filter pressure drop surveillance prescribed in Section 4.6.3.1.a.1 for the affected filter train (s).

2. DJP Test: Each affected filter train shall be retested in accordance with Section 4.6.3.1.b.3.

3. Visual inspection in accordance with ANSI N510-1980 Section 5.

THREE MILE ISL/.ND - UNIT 2 4.6-3 Change No. 39

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4 .- SURVEILLANCE REQUIREMENTS i

d. After each complete or partial replacement of a HEPA filter bank by verify.ing that the ventilation system meets the following condition:

1. 00P Test: Each affected filter train shall be retested in '

accordance with Section 4.6.3.1.b.3.

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i THREE MILE ISLAND - UNIT 2 4.6-4 Change No. 39

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l SURVEILLANCE REQUIREMENTS 4.7 PLANT SYSTEMS l

4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM 4.7.4.1 Deleted. l 4.7.6 FLOOD PROTECTION 4.7.6.1 The water level at the Unit 1 intake structure shall be determined to be within the limit by:

a. Measurement at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the water level is below elevation 301 feet Mean Sea Level USGS datum,

b. Measurement at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the water level is equal to or above elevation 301 feet Mean Sea Level datum.

4.7.6.2 The dike surrounding the island and the dike errosion protection _

shall be-

a. Inspected at least once per 6 months and within 31 days after every flood which exceeds 485,000 cfs at the Harrisburg gauge. This inspection shall include:

1. Dike slope and notation of any location where slope is steeper than 2:1.

2. Depressions and notation of their size and location.

3. Stone degradation and notation of any areas where splitting, spalling or weathering of stone appears excessive.

4. Vegetation and notation of location,~ quantity, and type.

5. Operability of inside and outside gates of the Southeast Drainage Culvert.

4.7.6.3 A Special Report shall be prepared and submitted to the Commission within 30 days if evidence of degradation is noted during an inspection. This report shall describe the extent and I;ature of the degradation and the plans and schedule for restoring the dike and errosion protection to a status equiva-lent to the original design provisions.

4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM 4.7.7.1 The Control Room Emergency Air Cleanup System shall be demonstrated OPERABLE:

a. At least once per 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months by verifying that the control room air ter;,erature is less then or equal to 80*F.

THREE MILE ISLAND - UNIT 2 4.7-1 Change No. 39

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SURVEILLANCE REQUIREMENTS CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM (Continued)

b. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes; and the pressure drop across the combined HEPA filters and charcoal adsorbers banks is less than six (6) inches water gauge while operating,

c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1. Verifying that the cleanup system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.5.c* and C.S.d* of Regulatory Guide 1.52, Revi-sion 2, March 1978, and the system flow rate is 14,350 cfm i 10%.

2. Verifying within 31 days after removal that a laboratory analysis _

of a representative carbon sample obtained in accordance with Regu- .

latory Guide 1.52, Revision 2, March 1978, when performing Methyl Iodide, 30*C, 95% RH testing per Table 5-1 of ANSI N509-1980 meets an acceptable criteria of 5% penetration maximum.

3. Verifying a system flow rate of 14,350 cfm + 10% during system operation when tested in accordance with AN3I N510-1980, Section 8.3.1 Paragraphs 3 and 4.

d. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, when performing Methyl Iodide, 30 C, 95% RH testing per Table 5-1 of ANSI N509-1980 n.eets an acceptance criteria of 5% penetration maximum,

e. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEPA filter and charcoal adsorber banks is less than 6 inches water gauge while operating the system at a flow rate of 14,350 cfm + 10%.

2. Verifying that on a control room air inlet radiation test signal or chlorine detection test signal, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

3. Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/10 inch water gauge relative to the outside atmosphere during system operation.

The prerequisites of Section 10.3 and 12.3 of ANSI-N510-1980 do not apply.

THREE MILE ISLAND - UNIT 2 4.7-2 Change No. 39

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a , SURVEfLLANCE REQUfREMENTS i

CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM (Continued)

f. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the 00P when they are tested in place in accordance with ANSI H510-1980* Section 10 while operating the system at a flow rate of 14,350 cfm + 10%.

g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980,* Section 12, while operating the system at a flow rate of 14,350 cfm i 10%.

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The prerequisites of Section 10.3 and 12.3 of ANSI-510-1980 do no apply.

THREE MILE ISLAND - UNIT 2 4.7-3 Change No. 39

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y SURVEILLANCE REQUIREMENTS 4.7.9 SEALE0 SOURCES 4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.9.2 Test Frequencies - Each category of sealed sources shall be tested at the frequency described below,

a. Source in use (excluding startup sources and fission detectors previously subjected to core flux) - At least once per six months for all sealed sources containing radioactive material- .

1. With a half-life greater than 30 days (excluding Hydrogen 3) and

2. In any form other than gas.

b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.9.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of >0.005 microcuries of removable contamination.

t THREE MILE ISLAND - UNIT 2 4.7-4 Change No. 39

_ SURVEILLANCE'RE0VIREMENTS 4.7.10 FIRE SUPPRESSION SYSTEMS ,

FIRE SUPPRESSION WATER SYSTEM 4.7.10.1.1 The FIRE SUPPRESSION WATER SYSTEM shall be demonstrated GPERABLE:

a. At least,once per-7 days by verifying that at least 90,000 gallons of water are in the Altitude Tank, equivalent level in Unit 1 circulating water flume and/or equivalent level in the river. !

b. At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it for at least 20 minutes on recirculation flow.

c. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.

d. At least once per 12 months by:

1. Running the full flow of one fire pump through all main header loops _..

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as a flush, and

2. Cycling each testable valve in the flow path through at least one complete cycle of full travel.

e. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system (i.e., pumps start at set pressure i 10 psig), and:

1. Verifying that each pump develpps at least 2500 gp.a at a total dynamic head no more than 10% below that indicated on manufactures curves.

2. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and

3. Verifying that each high pressure pump starts (sequentially) to main-tain the fire suppression water system pressure greater than or equal to 70 psig.

f. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, lith Edition, published by the National Fire Protection Association.

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THREE MILE ISLAND - UNIT 2 4.7-5 Change No. 39

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e SURVEILLANCE REQUIREMENTS FIRE SUPPRESSION WATER _ SYSTEM (Continued) 4.7.10.1.2 Each fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by ve 'fying;

1. Its associated fuel storage tank contains at least 250 gallons of fuel, and

2. The diesel sta.ts from ambient conditions and operates for at least )

20 minutes. '

b. At least once per 92 days by verifying that a sample of diesel fuel I from each fuebstorage tank, obtained in accordance with ASTM-D270-65', is !

within the acceptable limits specified in Table 1 of ASTM 0975-74 when checked for viscosity, water and sediment.

c. At least once per 18 months, by: l l

1. Subjecting each diesel to an inspection in accordance with procedures- l prepared in conjunction with its manufacturer's recommendations for l the class of service, and )

2. Verifying each diesel starts from ambient conditions on the auto-start l signal and operates for greater than or equal to 20 minutes while loaded with the fire pump. ;

l 4.7.10.1.3 Each fire pump diesel starting battery bank and charger shall be !

demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

1

1. The electrolyte level of each battery is above the plates, and !

2. The overall battery voltage is greater than or equal to 24 volta.

b. At 1sast once per 92 days by verifying that the specific grevity is l appropriate for continued service of the battery,

c. At least once per 18 months by verifying that:

1. The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and

2. The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

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THREE MILE ISLAND - UNIT 2 4.7-6 Change No. 30

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, SURVEXLLANCE REQUXREMENTS e

DELUGE / SPRINKLER SYSTEMS 4.7.10.2 Each of the required deluge and/or sprinkler systems shall be demonstrated OPERABLE:

a. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel,

b. At least once per 18 months:

1. By performing a system functional test which includes tripping detectors and verifying actuation of trip devices on associated deluge valves. Deluge / sprinkler valves shall be inspected internally to verify operability in all instances where header flooding during the test is not practical.

2. Cycling each valve in the ficu path that is not testable during plant operation through at least one complete cycle of full travel.

3. By visual inspection of the deluge headers to verify their integrity. -

4. By visual inspection of each nozzle to verify no blockage,

c. At least one per 3 years by performing an air or gas flow test through each deluge header and verifying each deluge nozzle is unobstructed.

HALON SYSTEM 4.7.10.3.1 The Cable Room and Transformer Room Halon system shall be demon-strated OPERABLE at least once per 6 months by verifying each Halon storage tank weight and pressure.

4.7.10.3.2 The Air Intake Tunnel Halon System shall be demonstrated OPERABLE:

a. At least once per 6 eonths by verifying pressure in each halon storage tank, and

b. At least once per 18 months by verifying storage tank weight.

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THREE MILE ISLAND - UNIT 2 4.7-7 Change No. 39

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.1 SURVEILLANCE REQUIREMENTS ti FIRE HOSE STATIONS 4.7.10.4 Each fire hose station listed in Table 4.7-1 shall be verified OPERABLE:

a. At least once per 31 days by visual inspection of the station to assure all required equipment is at the station,

b. At least once per 18 months by:

1. Removing the hose for inspection and re-racking, and

2. Replacement of all degraded gaskets in couplings.

c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

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2. Conducting a hose hydrostatic test at a pressure at least 50 psig __

greater than the maximum pressure available at that hose station.

PENETRATION FIRE BARRIERS ,

4.7.11 The required (accessible per occupational exposure considerations) penetration fire barriers shall be verified to be functional:

a. At least once per 18 months by a visual inspection,

b. Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

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THREE MILE ISLAND - UNIT 2 4.7-8 Change No. 39

TABLE 4.7-1 FIRE HOSE STATIONS Auxiliary Buildina

1. Fire hose near stairway at South end of building near Decay Heat Closed Cooling Surge Tank, 328' elevation.

2. Fire hose neaa entrance to Chemical Addition area, 328' elevation.

3. Fire hose near Miscellanceous Waste Holdup Tank room, 305' elevation.

4. Fire hose near Intermediate Closed Coolers, 305' elevation.

5. Fire hose near Evaporator Condensate Test Tank Room, 280' elevation.

6. Fire hose near Reactor Building Emergency Cooling Booster Pumps, 280' elevation.

Control Buildina Area

1. Fire hose near 480 Volt Bus 2-34 282'6" elevation.

2. Fire hose near entrance to Service Building 282'6" elevation.

Reactor Buildina* _

1. Deleted.

2. Deleted.

3. Fire hose near West stairway, 305' elevation.

4. Fire hose near Southwest stairway, 305' elevation.

5. Fire hose on East 0-ring, 367' elevation.

6. Fire hose on West 0 ring, 367' elevation.

Control Building

1. Fire hose near doorway on North wall, 305' elevation.

Fuel Handlina Buildino

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1. Fire hose on East wall, 347'6" elevation.

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Fire hose stations in the Reactor Building shall be OPERABLE prior to initiating operations which generate combustible materials, and prior to initiating operations which involve the use of open flames, welding, burning, grinding, etc.

THREE MILE ISLAND - UNIT 2 4.7-9 Change No. 39

SURVEILLANCE REQUIREMENTS 4.8 ELECTRICAL POWER SYSTEMS t'

4.8.1 A.C. SOURCES

4. 8.1.1 Each of the required independent circuits between th, offsite trans- I mission network and the onsite Class 1E distribution system shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availablity.

4.8.1.2 Deleted.

4.8.1.3 Deleted.

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THREE MILE ISLAND - UNIT 2 4.8-1 Change No. 39

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, SURVEILLANCE REQUIREMENTS l

1 4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 4.8.2.1 A.C. DISTRIBUTION 4.8.2.1.1 The specified A.C. busses shall be determined OPERABLE with tie l breakers open between redundant busses at least once per 7 days by verifying !

correct breaker alignment and indicated power availability.

4160 volt Bus # 2-1E 4160 volt Bus # 2-2E 4160 volt Busses # 2-3 and 2-4 480 volt Busses #2-11E and 2-12E 480 volt Busses # 2-21E and 2-22E 480 volt Busses # 2-32, 2-35, 2-36, 2-42, 2-45, and 2-46 i 4.8.2.1.2 The specified A.C. busses shall be determined OPERABLE at least l once per 7 days by verifying correct breaker alignment and indicated power <

availability. _

- 1 120 volt A.C. Vital Bus # 2-1V 120 volt A.C. Vital Bus # 2-2V ,

120 volt A.C. Vital Bus # i'-3V 120 volt A.C. Vital Bus # 2 4V i

D.C. DISTRIBUTION 4.8.2.2.1 Each D.C. bus train shall be determined OPERABLE and energized with ;

tie breakers open at least once per 7 days by verifying correct breaker align- 1 ment and indicated power availability. I 4.8.2.2.2 Each 250/125-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

1. The elec*.rolyte level of each pilot cell is between the minimum and )

maximum level indication marks. j

2. The pilot cell specific gravity, corrected to 77*F and full electrolyte I level, is greater than or equal to 1.20.

3. The pilot cell voltage is greater than or equal to 2.13 volts.

4. The overall battery voltage is greater than or equal to 250/125 volts.

THREE MILE ISLAND - UNIT 2 4.8-2 Change No. 39

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, SURVEILLANCE REQUIREMENTS ;

D.C. DISTRIBUTION (Continued)

b. At least once per 92 days by verifying that: 1

1. The voltage of each connected cell is greater than or equal to 2.13 l volts under float charge and has not decreased more than 0.10 volts from the value observed during the original acceptance test.

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2. The specific gravity, correct to 77'F and full electrolyte level, of '

each connected cell is greater than or equal to 1.20 and has not decreased more than 0.01 from the value observed during the previous ;

test. '

3. The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

c. At least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual indication -

of physical damage or deterioration.

2. The cell-to-cell and terminal connections are clean, tight and coated with anti-corrosion material.

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THREE MILE ISLAND - UNIT 2 4.8-3 Change No. 39 1

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l j I~ SURVEILLANCE REQUIREMENTS 4.9 LIQUID RADWASTE STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING 4.9.1 The Spent Fuel Storage Pool "A" water level monitoring instrumentation !

shall be demonstrated OPERABLE as required by Table 4.3-8.

4.9.2 Verify by surveillance that the water level of Spent Fuel Storage Pool !

"A" is between elevations 326'10" and 328'01". i FUEL TRANSFER CANAL WATER LEVEL MONITORING 4.9.3 The Fuel Transfer Canal (deep end) water level monitoring instrumentation shall be demonstrated OPERABLE as required by Table 4.3-8. j t

4.9.4 Verify by surveillance that the water level of the Fuel Transfer Canal l (deep end) is between elevations 326'10" and 328'01".

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FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS -

4.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that the Air Cleanup Exhaust System l in the normal operating mode meets the following conditions:

1. Deleted.

2. Filter Pressure Drop: the d/p across the combined HEPA filters 1 and charcoal adsorbers shall not exceed 6 inches water gauge.

3. Fuel Handling Building Pressure: Demonstrate that the system is l capable of achieving a negative pressure within the building equal l to or greater (more negative) than 1/8 inch water gauge with respect i to atmospheric. It may be necessary to close doors and other build-ing openings to achieve the required value,

b. At least once per 18 months by verifying that the ventilation system meets the following conditions: j

1. Visually inspect each filter train and associated components in accordance with Section 5 of ANSI H510-1980, as required by Regulatory Position C.5.a of Regulatory Guide 1.52, Revision 2, March 1978. The inspection should be performed prior to the flow and DOP tests of this section.

2. Flow Test: Exhaust flow rate shall be within 18,000 cfm to 27,000 cfm operating band for each filter train with one filter train and one exhaust fan operating. Testing shall be in accordance with -

ANSI N510-1980, Section 8.3.1, Paragraphs 3 and 4.

THREE MILE ISLAND - UNIT 2 4.9-1 Change No. 39 1

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/EILLANCE REQUIREMENTS

3. 00P Test: Each filter train shall be tested in accordance with Section 10 of ANSI H510-1980, as required by Regulatory Position C.5.c of Regulatory Guide 1.52, Revision 2, March 1978. Flow through the filter train being tested shall be as prescribed for the flow test in Section 4.9.12.1.b.2 above.

The install 1d system flow instrumentation is adequate for the test described in 4.9.12.1.b.3 above.

4. Fuel Handling Building Pressure: Demonstrate that the system is capable of achieving a negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with respect to atmospheric. It may be necessary to close doors and other build-ing openings to achieve the required value. A test instrument, such as an inclined manometer or equivalent, shall be used in the perfor-mance of this test.

Mter structural maintenance of the HEPA filter or charcoal adsorber -l hous'ngs, or following fire or chemical release in any ventilation zone coraunicating with the system by verifying that the ventilation system reets the following conditions:

1. Flow Test: Reverify exhaust flow rate for the affected filter train (s) per Section 4.9.12.1.b.2.

2. Filter Pressure Drop: Reverify the filter pressure drop surveil-lance prescribed in Section 4.9.12.L a.2 for the affected filter train (s)

3. DOP Test:

Each affected filter train shall be retested in accordance eith Section 4.9.12.1.b.3.

' After each complete or partial replacement of a HEPA filter bank by verify- l ing that the ventilation system meets the following conditions:

1. 00P Test:

Each affected filter train shall be retested in accordance with Section 4.5.12.1.b.3.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by checking a d/p alarm or d/p indication. l 8

Supply fans may be operated as desired except that the number of opera-ting supply fans shall not exceed the number of operating exhaust fans.

.2 The Auxiliary Building Air Clea7up Exhaust System shall be demon-ed OPERABLE:

At least once per 31 days by verifying that the air cleanup exhaust system in the normal operating mode meets the following conditions:

1. Deleted.

1 MlLE ISLAND - UNIT 2 4.9-2 Change No. 39

SURVEILLANCE REQUIREMENTS

2. Filter Pressure Drop: The d/p across the combined HEPA filters and charcoal adsorbers shall not exceed 6 inches water gauge.

3. Auxiliary Building Pressure: Demonstrate that the system is capable of achieving negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with respect to atmospheric. It may be necessary to close doors and other building openings to achieve the required value,

b. At least once per 18 months by verifying that the ventilation system meets the following conditions:

1. Visually inspect each filter train and associated components in accordance with Section 5 of ANSI N510-1980, as required by Regulatory Position C.S.a of Regulatory Guide 1.52, Revision 2, March 1978. The inspection should be performed prior to the flow and 00P tests of this section.

2. Flow Test: Fxhaust flow rate shall be within 27,000 cfm to 40,000 -

cfm operato 1 band for each filter train with one filter train and one exb h ran operating. Testing shall be in accordance with ANSI H510-1980, Section 8.3.1, Paragraphs 3 and 4.

3. 00P Test: Each filter train shall be tested in accordance with Section 10 of ANSI N510-1980, as required by Regulatory Position C.S.c of Regulatory Guide 1.52, Revision 2. March 1978. Flow through the filter train being tested shall be as prescribed for the flow test in Section 4.9.12.2.b.2 above.

NOTE: Installed system flow instrumentation is adequate for the test described in 4.9.12.2.b.3 above.

4. Auxiliary Building Pressure: Demonstrate that the system is capable of achieving a negative pressure within the building equal to or ,

greater (more negative) than 1/8 inch water gauge with respect to I atmospheric. It may be necessary to close doors and otner building openings to achieve the required value. A test instrument, such as an inclined manometer or equivalent, shall be used in the performance of this test.

c. After structural maintenar.ce of the HEPA filter or charcoal adsorber housing, or following fire or chemical release in any ventilation zone {

communicating with the system by verifying that the ventilation system meets the following conditions: ;

1. Flow Test: Reverify exhaust flow rate for th affected filter train (s) per Section 4.9.12.2.b.2.

I THREE MILE ISLAND - UNIT 2 4.9-3 Change No. 39 l

e SURVEILLANCE REQUIREMENTS

2. Filter Pressure Drop: Reverify the filter pressure drop surveil-lance prescribed in Section 4.9.12.2.a.2 for the affected filter train (s).

3. 00P Test: Each affected filter train shall be ratested in accordance with Section 4.9.12.2.b.3.

d. After each complete or partial replacement of a HEPA filter bank by verifying that the ventilation system meets the following conditions:

1. DOP Test: Each affected filter train shall be retested in accordance with Section 4.9.12.2.b.3.

e. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by checking a d/p alarm or d/p indication.

NOTE: Supply fans may be operated as desired except that the number of operat-ing supply fans shall not exceed the number of operating exhaust fans, j i

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THREE MILE ISLAND - UNIT 2 4.9-4 Change Nc. 39

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ML20154Q677

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