ML20043H489

Proposed Tech Specs 3.16 Through 4.7.2

ML20043H489
Person / Time
Site:	Three Mile Island
Issue date:	06/18/1990
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20043H486	List: ML20043H485 ML20043H487 ML20043H489
References
NUDOCS 9006260012
Download: ML20043H489 (4)

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l TABLE OF CONTENTS l 1

+ Section _P_ ate 3.16 ~ ' SHOCK SUPPRESSORS CSNUBBERS) 3-63 t 3.17 REACTOR BUILDING A"R TEMPERATURE 3-80 3.18' FIRE PROTECTION (DELETED) 3-86 3.19 CONTAINMENT SYSTEMS 3-95 3.20: . DELETED 3-95a 3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION 3-96 3.21.1 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-96 3.21.2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT 3-100 MONITORING INSTRUMENTATION 3.22 RADIOACTIVE EFFLUENTS 3-106 3.22.1- LIQUID EFFLUENTS 3-106 '

3.22.2 GASEOUS EFFLUENTS 3-111 3.22.3 SOLID RADIOACTIVE WASTE 3-118 3.22.4 TOTAL DOSE 3-119 3'23

. RADIOLOGICAL ENVIRONMENTAL MONITORING 3-120 3.23.1 MONITORING PROGRAM 3-120 3.23.2 LAND USE CENSUS 3-125 3.23.3 INTERLABORATORY COMPARISON PROGRAM '3-127 3.24 REACTOR COOLANT INVENTORY TRENDING SYSTEM 3-128 4 SURVEILLANCE STANDARDS 4-1 Y

4.1 OPERATIONAL SAFETY REVIEW 4-1 4.2 REACTOR COOLANT SYSTEM INSERVICE INSPECTION- 4-11 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4-2B

=4.4 REACTOR BUILDING 4-23

. 4.4.1 CONTAINMENT LEAKAGE TESTS 4-29 t L -4.4.2 STRUCTURAL INTEGRITY 4-35

, 3 4.4.3 DELETED 4-37 p 1 4.4.4 HYDROGEN RECOMBINER SYSTEM 4-38 l 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, 4-39' EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING

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-c 4.5.1 EMERGENCY LOADING SEQUENCE R 4.5.2 EMERGENCY CORE COOLING SYSTEM 4-41 h 4.5.3 REACTOR BUILDING COOLING AND ISOLATION SYSTEM 4-43 4.5.4 DECAY' HEAT REMOVAL SYSTEM LEAKAGE 4-45 L/: 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS. 4-46 A 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4-48 4.7.1 CONTROL ROD DRIVE SYSTEM FUNCTIONAL TESTS 4-48 h,, 4.7.? CONTROL ROD PROGRAM VERIFICATION 4-50 3;

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-iii-Amendment 72, 81, 108, 129, 137, 139, 146, 147 9006260012 900618 9 DR ADOCK 0500 h

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T i LIST OF FIGURES Figure  : Title l 3.5-2K'

-thru DELETED 3.5-2L-- ,

3.5-2M LOCA Limited Maximum Allowable Linear Heat Rate 3.5-1 Incore Instrumentation Specification Axial Imbalance Indicatiren, TMI-1 3.5-2 Incore li;strumentation Specification Radial Flux Tilt 1 Indica. tion, TMI-1 3.5-3 Ir. core Instrumentation Specification j 3.11-1 Transfer Path to and from Cask Loading Pit 4.17-1 Snubber Functional Test - Sample Plan 2 t

5-1 Extended Plot Plan TMI 5-2' Site Topography 5 Mile Radius 5-3 Locations of Gaseous Effluent Release Points and i Liquid Effluent Outfalls C

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viii  !

Amendment Nos. 72, 77, 126, 139, 142, 149, 150 l

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4.4.2.1.6 Reports l

a. Within 3 months after the completion of each. tendon surveillance a special-report shall'be submitted to '

+ the NRC Region-1 Administrator. This Report will.

include a section dealing with trends for the rate of "s prestress loss as compared to the. predicted rate for ,

the duration of the plant. life (after an adequate '

number of curveillances have beentcompleted).-

b. Reports. submitted in accordance with.10 CFR 50.73 shall in:1ude a description'of the. tendon condition, .

the conditionHof the concrete (especially at tendon ~  !

anchorages), the inspection procedures, the tolerances

3. on cracking, and'any corrective actions'taken.. '

'4.4.3 DELETED t

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4-37 Amendment No. 108, 129 e

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.e at'* ? . - 4i4.4 -Hydrogen Recombiner System'

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Applicability Applies to the testing of the hydrogen recambiner and associated controls.

Ob.iective

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To verify that the hydrogen recombiner and associated 3

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controls are operable. t 4.4.4.1 Specification

a. At least once per 6 months, perform a hydrogen e recombiner system functional test to demonstrate that

& the minimum reaction chamber gas temperature is maintained >'600*F for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

b. At least once per refueling interval, perform the following surveillances:

1. A channel calibration of all recombiner.

instrumentation and control circuits. 1

2. Verify through a visual examination that there is no evidence of abnormal conditions (i.e., loose wiring or structural connecticns,-deposits of foreign 4 materials, etc.)

3. Verify during a recombiner system functional test that the reaction chamber gas temperature is

, maintained 21200 F for at.least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

, 4. ' Verify'the integrity of the heater electrical circuits by performing a continuity and resistance to ground test. The resistance te ground for any heater phase shall be 210,000 ohms.

>t- Bases The surveillance program described ab'ove provides high assurance-

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that the hydrogen recombiner system will'be available to perform its post-LOCA function of maintaining the containment hydrogen concentration to below 4.1 volume percent. This system is not credited to mitigate any accident analyzed in Chapter 14 of .the TM?-1 FSAR. -The frequency of the surveillance of the hydrogen re:ombiner system is based on the safety significance of the system. TMI-1 FSAR Section 6.5.3.1 indicates that the hydrogen rt combiner system is not required until 9.8 days following a L]CA. This is adequate time to place a hydrogen recombiner in tervice.

4-38 ,

(Page 4-38a deleted)

Amendment No. 87 l

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