ML20237A839

Revised Proposed Tech Spec Pages ii,68 & 225 Re Table of Contents,Reactor Protection Instrumentation & Integrated Leak Rate Test for Secondary Containment

ML20237A839
Person / Time
Site:	Pilgrim
Issue date:	12/08/1987
From:	BOSTON EDISON CO.
To:
Shared Package
ML20237A828	List: ML20237A826 ML20237A839
References
NUDOCS 8712150303
Download: ML20237A839 (4)

Text

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t ATTACHMENT Revised Pages 11, 68, and 225 i

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l ADO O DR 9

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a Surveillant Pace No.

3.7 CONTAINMENT SYSTEMS 4.7 152 A. Primary Containment A 152 B. Standby Gas Treatment System B 158 C. Secondary Containment C 159

! I 3.8 RADI0 ACTIVE EFFLUENTS 4.8 177 {

A. Liquid Effluents Concentration A 177 B. Radioactive Liquid Effluent B 177 Instrumentation C. Liquid Radwaste Treatment C 178 D. Gaseous Effluents Dose Rate D 179 E. Radioactive Gaseous Effluent E 180

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Instrumentation j F. Gaseous Effluent Treatment F 181 G. Main Condenser G 182 H. Mechanical Vacuum Pump H 183 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 194 A. Auxiliary Electrical Equipment A 194 B. Operation with Inoperable Equipment B 195 3.10 CORE ALTERATIONS 4.10 202 A. Refueling Interlocks A 202 B. Core Monitoring B 202 C. Spent Fuel Pool Hater Level C 203 3.11 REACTOR FUEL ASSEMBLY 4.11 205A A. Average Planar Linear Heat A 205A Generation Rate (APLHGR)

B. Linear Heat Generation Rate (LHGR) B 205A-1 C. Minimum Critical Power Ratio (MCPR) C 205B D. Power / Flow Relationship D 205B-1 3.12 FIRE PROTECTION 4.12 206 A. Fire Detection Instrumentation A 206 B. Fire Water Supply System B 206 C. Spray and/or Sprinkler Systems C 206c D. Halon System D 206d E. Fire Hose Stations E 206e F. Penetration Fire Barrier F 206e G. Dry Chemical Systems G 206e-1

( H. Yard Hydrants and Exterior Hose H 206e Houses Amendment No. ii l

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BASES:

3.2 In addition to reactor protection instrumentation which initiates a reactor scram, protective instrumentation has been provided which initiates action to mitigate the consequences of accidents which are beyond the operator's ability to control, or terminates operator errers before they result in serious consequences. This set of specifications provides the limiting conditions of operation for the primary system isolation function, initiation of the core cooling systems, control rod block and standby gas treatment systems. The objectives of the Specifications are (i) to assure the effectiveness of the protective i instrumentation when required by preserving its capability to tolerate a single failure of any component of such systems even during periods when portions of such systems are out of service for maintenance, and (ii) to prescribe the trip settings required to assure adequate performance.

When necessary, one channel may be made inoperable for brief intervals to conduct required functional tests and calibrations.

Some of the settings on the instrumentation that initiate or control core and containment cooling have tolerances explicitly stated where the high and low values are both critical and may have a substantial effect on safety. The set points of other instrumentation, where only the high or low end of the setting has a direct bearing on safety, are chosen at a level away from the normal operating range to prevent inadvertent actuation of the safety system involved and exposure to abnormal situations.

Actuation of primary containment valves is initiated by protective instrumentation shown in Table 3.2.A which senses the conditions for which isolation is required. Such instrumentation must be available whenever primary containment integrity is required.

The instrumentation which initiates primary system isolation is connected in a dual bus arrangement.

The low water level instrumentation set to trip at 128.26 inches above the top of the active fuel closes all isolation valves except those in Groups 1, 4 and 5. This trip setting is adequate to prevent core uncovery in the case of a break in the largest line assuming a 60 second valve closing time. Required closing times are less than this.

1 The low low reactor water level instrumentation is set to trip when reactor water level is 77.26 inches above the top of the active fuel

(-49" on the instrument). This trip closes Main Steam t.ine Isolation l

l Amendment No. 68 l

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i TABLE 6.9.1 J

area Reference Submittal Date

a. Secondary Containment 4.7.C.l.c Upon completion of l I Leak Rate Testing (1) each test (2) l

b. (Deleted)

c. (Deleted)

d. Gross Gaseous Release 4.8.B Ten days after the 0.05 Ci/sec for 48 release occurs Hours

e. Standby Liquid Control 3.4.C.3 Fourteen days after solution enrichment out receipt of a non-of specification complying enrichment report or lack of ,

receipt of such a l report within the required thirty days, if enrichment compliance cannot be achieved within seven days.

NOTES: 1. Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report shall include data en the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.

2. The report shall be submitted approximately 90 days after l ,

completion of each test. Test periods shall be based on the I commercial service date as the starting point.

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Amendment No. 225

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