ML20035C670

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Amend 148 to License DPR-35,changing Low Pressure Isolation Signal from HPCI Steam Inlet Piping to Reactor Vessel as Sensed by Analog Trip Sys
ML20035C670
Person / Time
Site: Pilgrim
Issue date: 04/02/1993
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20035C672 List:
References
NUDOCS 9304080282
Download: ML20035C670 (7)
v • d • e


Text

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i" UNITED STATES

[.if 'k/2 1 j NUCLEAR REGULATORY COMMISSION 1

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BOSTON EDISON COMPANY DOCKET NO, 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.148 License No DPR-35 1.

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

A.

licensee) dated AugustThe application for amendment filed by the Bo 17, 1992, as supplemented January-February 1,1993, complies with the standards and requirements of the22, 199 Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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:

this amendment can be conducted without endangering the health 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 Par of the Commission's regulations been satisfied.

ad all applicable requirements have 2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No DPR-35 is hereby amended to read as follows:

9304080282 g h 93-PDR ADE PDR P

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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.148, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

t 3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION 2

u d t.-

Walter R. Butler, Director Project Directorate I-3 i

Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

April 2, 1993 i

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ATTACHMENT TO LICENSE AMENDMENT N0.148 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 i

i Replace the following pages of the Appendix A Technical Specifications with j

the attached pages.

The revised pages are identified by Amendment number and l

contain vertical lines indicating the area of change.

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been provided.*

Overleaf pages have Remove Insert 48 48 1

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52 52 8

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61 i

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PNPS TABLE 3.2-B (Cont'd)

INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum # of Operable Instrument Channels Per Trip System (1)

Trip Function Trip level Setting Remarks 2

liigh Drywell

$2.5 psig

1. Initiates Core Spray; LPCI; Pressure HPCI.
2. In conjunction with Low-low Reactor Water Level, 120 second time delay and LPCI or Core Spray pump running, initiates Auto Blowdown (ADS).
3. Initiates starting of Diesel Generators 4.

In conjunction with Reactor low Pressure initiates closure of HPCI vacuum breaker containment isolation valves.

1 Reactor Low Pressure 400 psig i 25 Permissive for Opening Core Spray and LPCI Admission valves.

1 Reactor low Pressure $110 psig In conjunction with PCIS signal permits closure of RHR (LPCI) injection valves.

1 Reactor low Pressure 400 psig i 25 In conjunction with Low-low Reactor Water Level initiates Core Spray and LPCI.

2 Reactor Low Pressure 900 psig i 25 Prevents actuation of LPCI break detection circuit.

2 Reactor low Pressure 100>P>50 psig Isolates HPCI and in l

conjunction with High Drywell Pressure initiates closure of HPCI vacuum breaker containment isolation valves.

Amendment No. 42;-113-148 48

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PNPS TABLE 3.2-B (Cont'd)

INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum # of Operable Instrument Channels Per Trio System (1)

Trio Function Trip level Setting Remarks 2

Condensate Storage Tank 218" above tank zero Provides interlock to HPCI Low Level pump suction valves 2

Suppression Chamber

.51'11" below torus Hign Level zero 1

RCIC Turbine Steam Line $300% of rates steam High Flow flow (2) 2 RCIC Turbine Compartment 5170 F (2)

Wall 0

2 Torus Cavity Exhaust sl50 F (2)

Duct 0

2 RCIC Valve Station Area $200 F (2)

Wall 4 (5)

RCIC Steam Line Lo-Press 100>P>50 psig (2) 1 HPCI Turbine Steam Line $300% of rated flow (3)

High Flow l

2 HPCI Turbine Compartment $170 F (3)

Exhaust Ducts 2

Torus Cavity Exhaust 190 - 200 F (3)

Duct j

U 2

HPCI/RHR Valve Station

$170 F (3)

Area Exhaust Duct j

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Amendment No.

143 52 l

NOTES FOR TABLE 3.2.8 1.

Whenever any CSCS subsystem is required by Section 3.5 to be operable, there shall be two (Note 5) operable trip systems.

If the first column cannot be met for one of the trip systems, that system shall be repaired or the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after this trip system is made or found to be inoperable.

2.

Close isolation valves in RCIC subsystem.

3.

Close isolation valves in HPCI subsystem.

4.

Instrument set point corresponds to 77.26 inches of active fuel.

5.

RCIC has only one trip system for these sensors.

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Amendment No.-108 148 53 l

PNPS TABLE 4.2.8 MINIMUM TEST AND CALIBRATION FRE0VENCY FOR CSCS Instrument Channel Instrument functional Test Calibration Freauency Instrument Check 1)

Reactor Water Level (1) (7)

(7)

Once/ day

2) Drywell Pressure (1) (7)

(7)

Once/ day

3) Reactor Pressure (1) (7)

(7)

Once/ day

4) Auto Sequencing Timers NA Once/ operating cycle None
5) ADS-LPCI or CS Pump Disch.

Pressure Interlock (1)

Once/3 months None 6)

St V.-up Transf. (4160V) a.

Loss of Voltage Relays Monthly once/ operating cycle None b.

Degraded Voltage Relays Monthly Once/ operating cycle None

7) Trip System Bus Power Monitors Once/ Operating cycle N/A Once/ day
8) Recirculation System d/p (1)

Once/3 months Once/ day

9) Core Spray Sparger d/p NA Once/ operating cycle Once/ day
10) Steam Line High Flow (HPCI&RCIC)

(1)

Once/3 months None

11) Steam Line High Temp. (HPCI&RCIC) (1)

Once/3 months None

12) Safeguards Area High Temp.

(1)

Once/3 months None

13) RCIC Steam Line Low Pressure (1)

Once/3 months None

14) HPCI Suction Tank Levels (1)

Once/3 months None 15 Emergency 4160V Buses A5 & A6 Monthly once/ operating cycle None loss of Voltage Relays Amendment No. 42;-61, 148 61

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