ML20043H489

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 3.16 Through 4.7.2
ML20043H489
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/18/1990
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20043H486 List:
References
NUDOCS 9006260012
Download: ML20043H489 (4)


Text

..-

y,.

TABLE OF CONTENTS

+

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 4.4.3 DELETED 4-37 p

1 4.4.4 HYDROGEN RECOMBINER SYSTEM 4-38 l

3 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, 4-39' EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 EMERGENCY LOADING SEQUENCE 4-39

-c 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;

W

l

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

h 5 '

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

d 1

1 1

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

4.4.2.1.6 Reports Within 3 months after the completion of each. tendon a.

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

3.

'4.4.3 DELETED t

i l:

E L

b 4-37 Amendment No. 108, 129 e

.o j

.e at'* ?

- 4i4.4

-Hydrogen Recombiner System'

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

Ob.iective To verify that the hydrogen recombiner and associated 3

.g

~

controls are operable.

t 4.4.4.1 Specification a.

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

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-

~

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

_ _