ML20079N870

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Amend 165 to License NPF-03 Revising TS 3/4.4.10 & Section 4.4.10.1.b Surveillance Requirements by Changing Surveillance Intervals for Insp & Operability Testing of Reactor Vessel Internals Vent Valves
ML20079N870
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 10/24/1991
From: Hopkins J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20079N871 List:
References
NUDOCS 9111120059
Download: ML20079N870 (5)


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UNITED STATES

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TOLEDO EDISON COMPANY CENTER 10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO,1 AMENDMENTTOFACILITYOPERATINGLICiNlE trendment No. 165 License No. NPF-3 1.

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

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland E7ectric Illuminating Company (the itcensees) dated August 1,1989, as supplemented February 1,1990, 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 Comission; C.

There is reasonable assurance (1) 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 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 Part 51 of the Commission's.cgulations and all applicable requirements have-been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3-is hereby amended to read as follows:

9111120059 911024 PDR ADOCK 05000346 P

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(a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 165, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implenented not later than 45 days af tsr issuance.

FOR TI.E NUCLEAR REGULATORY COMMISSION

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9 on B. Hopkins,Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

October 24, 1991 1

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ATTACHMENT TO 1.! CENSE AMENDHENT NO,165 FACILITY OPERATING LICENSE NO. NFF-3 00(KET NO. 50-346 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by anendment number and 1

contains vertical lines indicating the area of change.

The corresponding overleaf page it also provided to maintain document completeness.

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REACTOR COOLANT SYSTDtS SURVEILLANCE PEQVIRJE_AENTS _(Continued)

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b.

Each internals vent valve shall be demonstrated OPERABLE at least once per 24 inonths during shutdown by:

1.

Verifying through visual inspection that the valve body and valve disc exhibit no abnormal degradation, f

2.

Verifying the valve is not stuck in an open position, and 3.

Verifying through manual actuation that the valve is fully open when a force of 1 400 lbs. is applied vertically upward.

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DAVIS-BESSE. UNIT 1 3/4 4-31 Amendment No. 23.95,165

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REACTOR COOLANT SYSTEM liEACTOR D t,LANT SYS M VENTS

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CIMITING CONDITION FOR OPERATION 3.4.11 The following reactor coolant system vent paths shall be operable a.

Reactor Coolant System Loop 1 vith vent path through valves RC 4608A and RC 46088.

b.

Peactor Coolant System Loop 2 vith vent path through valves RC 4610A and RC 4610B.

c.

Pressutizer; with vent path through EITHER valves RCll and RC 2A (PORV) l OR valves RC 239A and RC 200.

APPLICABILITY:

Modes 1, 2 and 3 ACTION:

Vith one of the above vent paths inoperable, restore the inoperable a.

vent path to OPERABLE status within 30 days, or, be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in ROT SHUTDOVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

Vith two of the above vent paths inoperable, restore at least one of the inoperable vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOVN vithin the following 30 nours.

c.

With three of the above vent paths inoperable, restore at least two of the inoperable vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOVN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d.

The provisions of specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREHENTS 4.4 11 Each reactor coolant system vent path shall be demonstrated O'

.DLE at least once per 18 months Sys 1.

Verifying all manual isolation valves in each vent path are locked in the open position, and 2.

Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOVN or REFUELING, and j

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Verifying flow through the reactor coolant vent system vent paths during COLD SHUTD0VN or REFUELING.

DAVIS-BESSE, UNIT 1 3/4 4-32 Amendment No. /g1,135

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