ML20081L889

Amend 162 to License DPR-35,reducing Reactor Pressure Setpoint at Which Shutdown Cooling Sys Automatically Isolates

ML20081L889
Person / Time
Site:	Pilgrim
Issue date:	03/27/1995
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20081L890	List: ML20081L889 ML20081L894
References
NUDOCS 9503310069
Download: ML20081L889 (6)

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7 UNITED STATES i

YS NUCLEAR REGULATORY COMMISSION T

'" j WASHINGTON, D.C. 20555-0001 R.....]

BOSTON EDIS0N COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. DPR-35 1.

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

A.

The application for amendment filed by.the Boston Edison Company (the licensee) dated September 6, 1994, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),

anc the Comission's rules and regulations; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon i

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 Part 51 of the Comission's regulations and all applicable requirements have i

been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifica-l tions as indicated in the attachment to this license amendment.

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3.

This-license amendment becomes effective as of its date of issuance and shall be implemented within 30 days following restart from refueling outage #10.

FOR THE NUCLEAR REGULATORY COMISSION

'7 Ledyard B. Marsh, Director Project Directorate I-I I

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

Attachment:

Changes to the Technical Specifications Date of Issuance: March 27, 1995 i

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P ATTACHMENT-TO LICENSE AMENDMENT NO.162 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The. revised pages are identified.by Amendment number and contain vertical lines: indicating the area of' change.

Remove Insert 3/4.2-7 3/4.2-7 3/4.2-21 3/4.2-11 B 3/4.2-1 B 3/4.2-1 i

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,.c PNFS TABLE 3.2.A INSTRUNENTATION THAT INITIATES PRIMARY CONTAINNENT ISOIATION Operable Instrument Channels Per Trip System (1)

Minimum Available Instrument Trio Level Setting Action (2)-

2(7) 2 Reactor' Low War.er Level 211.7* indicated level (3)

A and D 1

1 Reactor High Pressure

$76 psig D.

- l 2

2 Reactor Low-Low Water Level at or above - 46.3 in.

A indicated level (4) 2 2

Reactor High Water Level

$45.3" indicated level (5)

B 2(7) 2 High Drywell Pressure

$2.22 psig A

2 2

Low Pressure Main Steam Line 2810 psig (8)

B 2(6) 2 High Flow Main Steam Line

$136% of rated steam flow

.B' 2

2 Main Steam Line Tunnel Exhaust Duct High Temperature

$170 F B.

2 2

Turbine Basement Exhaust Duct High Temperature

$150 F

'B 1

1 Reactor Cleanup System High Flow

$300% of rated flow C

2 2

Reactor Cleanup System High Temperature

$150*F'

.C 34 -42;-86,-147 -150 -151,-154, 162' 3/4.2 Amendment No.

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PNPS-TABIK 3.2.5 (Cont)

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

Trio Function Trio Level Settinz Remarks 2

High Drywell Pressure

$2.22 psig

1. 'nitiates C' ore Spray; LPCI; HPCI.

2. In conjunction with Low-Low Reactor- ~

. Water Level, 94.4-115.6 second. time

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delay and LPCI or Core Spray pump running, initiates Auto Blowdown (ADS) 3.-Initiates starting'of-Diesel Cenerators...

. 4. In conjunction'with Reactor Low

-Pressure initiates closure of HPCI' vacuum breaker containment isolation valves.

i Reactor Low Pressure

. 400 psig i 5 Permissive for opening Core Spray and LPCI

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Admission valves.

1 Reactor Low Pressure 576 psig-In conjunction with PCIS signal permits -

l-closure. of RHR (12CI) ir,jection valves.

1

. Reactor Low. Pressure 400 psig i 5 In conjunction with [Iow-law Reactor-Water-j Level initiates Core Spray'and LPCI.

2 Reactor; Low Pressure:

. 900 psig i 5 Prevents actuation of LPCI. break. detection circuit.

2 Reactor Low-Pressure

. 80 psig i 5

-Isolates HPCI and in conjunction with High -

Drywell Pressure initiates closure of HPCI

. vacuum breaker containment isolation valves.

Amendment No. 42r-ll3r-148 -151,162 3/4.2-11 1

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BASES:

4 3.2

• PROTECTIVE INSTRUMENTATION-

-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 errors 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 t reatment systems.

The objectives of the Specifications are (i) to assure the effectiveness of the protective instrumentation when required by preserving its capability to tolerate a ringle 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 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.

Reactor pressure instrumentation is used for closure of Group isolation valves and is set to trip at 576 psig. This prevents overpressurization of the RHR shutdown cooling piping.

The isolation setpoint is chosen: (1) at a pressure below where the RHR piping could be overpressurized, (2) so that the isolation valves can close in the required time, and (3) at the point where the maximum differential pressure associated with the isolation valves is not exceeded.

The low low reactor water level instrumentation closes the Main Steam Line Isolation Valves, Main Steam Drain Valves, Recire Sample Valves (Group 1) activates the CSCS subsystems, starts the emergency diesel generators and trips the recirculation pumps. This trip setting level was chosen to be high enough to prevent spurious actuation but low enough to initiate CSCS operation and primary system isolation so that no fuel damage will occur and so that post accident cooling can be accomplished and the guidelines of 10CFR100 will not be violated.

For large breaks 195 -113 -151, 162 B3/4.2-1 Amendment No.

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