ML20045F728

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Amends 176 & 179 to Licenses DPR-44 & DPR-56,respectively, Revising TS Table 3.15 & Associated Bases Re Seismic Monitoring Instrumentation
ML20045F728
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 06/21/1993
From: Chris Miller
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20045F729 List:
References
NUDOCS 9307080310
Download: ML20045F728 (10)


Text

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NUCLEAR REGULATORY COMMISSION.

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.y WASHINGTON, D. C. 20555

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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No.176 License No. DPR-44 i

1.

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

l A.

The application for amendment by Philadelphia Electric Company, et.

al. (the licensee) dated March 5,1993, as supplemented by letter dated May 13, 1993, complies with the standards and reouirements of the Atomic Energy Act of 1954, as amended (the Act), and the.

j Commission's rules and regulations set forth in 10 CFR Chapter I.

l 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 (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 Commission's regulations-D.

The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of.the public;. and i

E.

The issuance of this amendment.is in accordance with 10 CFR Part 51 of.-

l the Commission's regulations.and all applicable requirements have' been satisfied.

l 2.

Accordingly, the license is amended by changes to the Technical-q Specifications as indicated in the attachment to this license; amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

9307080310 930621 PDR ADOCK 05000277 P

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(2) Igchnical Specifications The ' Technical Specifications contained in Appendices A and B, as revised through Amendment No.176, are hereby incorporated in the license.

PECO shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective upon installation of the new solid-i state seismic instrumentation.

f FOR THE NUCLEAR REGULATORY COMMISSION

(.) A W D1 N Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical Specifications Date of Issuance: June 21, 1993 i

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ATTACHMENT TO LICENSE AMENDMENT NO.176 l

l FACILITY OPERATING LICENSE NO. DPR-44 l

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DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

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Unit 2

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PBAPS TABLE 3.15**

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SEISMIC MONITORING INSTRUMENTATION i

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Minimum

-l Measurement Instruments i

Jnstruments-and Sensor Locations #

Rance Operable l

1.

Triaxial Time-History Accelerometers

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a.

Containment Foundation j

(torus cornpartment)

-1 to lg 1

b.

Refueling Floor

-1 to lg 1

i c.

RCIC Pump (Rm #7)

-1 to lg.

1

'l d.

"C" Diesel Generator

-1 to lg 1

2.

Triaxial Peak Accelerographs f

a.

Reactor Piping (Drywell) 0.01 to 2g 1

b.

Refueling Floor 0.01 to 2g 1

l c.

"C" Diesel Generator 0.01 to 2g 1-l 3.

Central Recording and Analysis-

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System s

-1 to lg 1*

a.

Cable Spreading Ra

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Vith reactor control room annunciation

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Effective upon completion of installation Seismic instrumentation located in Unit 2 i

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. Amendment No. 73, 85,;

j 176 l

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Unit 2 FBAPS r

3.15/4.14 BASES The operability of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magni-tude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the plant.

~

The time-history data from the Triaxial Time-History Accelerometers is recorded in the cable spreading room using a solid-state central recording system.

Following a seismic event, the data is downloaded into t

a computer so that the results and data can be analyzed.

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Anendment No. 75. E5, 176

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UNITED STATES _

NUCLEAR REGULATORY COMMISSION

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p, WASHINGTON, D. C. 20555 p

PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPAl(1

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-l DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY i

DOCKET NO. 50-278 i

f PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.179

.l License No. DPR-56 1.

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

A.

The application for amendment by Philadelphia Electric Company, et.

al. (the licensee) dated March 5,1993, as supplemented by letter dated May 13, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended-(the Act), and the Comission'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 i

Comission;

[

C.

There is reasonable assurance (1) that the activities authorized by -

this amendment can be conducted without endangering the health and

l safety of the public, and (ii) that such. activities will be conducted 1

in compliance with the Comission's regulations; D.

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

defense and security or-to the health or safety of the public; and

.l E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of-the Comission's regulations and all applicable requirements have_ been _

j satisfied.

q 2.

Accordingly, the license is amended by changes to the Technical i

Specifications as indicated in the attachment to this' license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is'hereby-amended to read as follows.

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.179, are hereby incorporated in the license.

PECO shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective upon installation of the new solid-state seismic instrumentation.

t FOR THE NUCLEAR REGULATORY COMMISSION

&b f (Nd.AA-)

Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

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Attachment:

Changes to the Technical Specifications Date of Issuance: June 21, 1993

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F ATTACHMENT TO LICENSE AMENDMENT NO.179 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Insert 240u 240u 240w 240w l

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I Unit 3 i

PBAPS l.

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TABLE 3.15**

SEISMIC MONITORING INSTRUMENTATION Minimum

' Measurement Instruments Instruments and Sensor Locations #

Ranae Ooerable 1.

Triaxial Time-History Accelerometers i

a.

Containment Foundation (torus compartment)

-1 to.lg 1

b.

Refueling ~ Floor

-1 to lg 1.

-?.'

c.

RCIC Pump (Rm #7)-

-1 to Ig 1

d.

"C" Diesel Generator

-1 to lg 1

i 2.

Triaxial Peak Accelerographs I

a.

Reactor Piping (Drywell) 0.01 to 2g i

b.

Refueling Floor 0.01 to 2g 1

c.

"C" Diesel Generator 0.01 to 2g 1

.c 3.

Central Recording and Analysis System

{

-1 to Ig.

1*

a.

Cable Spreading Rm

'I With reactor control' room annunciation Effective upon completion cf installation l

Seismic instrumentation located in Unit 2 i

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1

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- 240u -

Amendment No. '74. 84.179 f

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3.

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Unit 3 PBAPS

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3.15/4.14 BASES The operability 'of the seismic monitoring instrumentation ensures' l

that sufficient capability. is available to promptly determine the magni- -

l tude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the plant.

The. time-history data from the Triaxial Time-History Accelerometers l

1s recorded in the. cable spreading room using a solid-state central

-l recording system.

Following a seismic event, the data is downloaded into

-l' a computer so that the results and data can be analyzed.

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F e

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- 240w -

Amendment No. 74, H, 179-i

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