ML20207K096

Amend 120 to License NPF-3,revising Tech Specs 4.6.1.2 c.3 Involving Containment Sys Surveillance Requirements

ML20207K096
Person / Time
Site:	Davis Besse
Issue date:	09/19/1988
From:	Perkins K Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207K100	List: ML20207K096 ML20207K107
References
NUDOCS 8809280240
Download: ML20207K096 (5)

Text

UNITED STATES 8

NUCLEAR REGULATORY COMMISSION g

WASH WGTON. D. C. 20666

...../

TOLEDO EDIS0N COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 1

DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.120 License No. NPF-3 1.

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

A.

The application for amendment by the Toledo Edison Company)and The Cleveland Electric Illuminating Company (the licensees dated December 8, 1987 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 It 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 convron 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 requiresnents have I

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:

l ADO K 0 0 y

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(a) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment N0120, 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 implemented not later than November 3,1988 FOR THE NUCLEAR REGULATORY COMMISSION Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects - III, )?,

V, & Special Projects

Attachment:

Changes to the Technical Specifications Date of issuance: Seotemb1r 19, 1988 i

1 1

ATTACHMENT TO LICENSE AMENDMENT NO.120 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO 50-346 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. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 6-3 3/4 6-3 I

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREME?TTS (Continuedl b.

If any periodic Type A test fails to meet 0.75 L, the :est schedule for subsequent Type A tests shall be reviewed an8 approved by the Commission.

If two consecutive Type A tests fail to meet 0.75 t Type A test shall be performed at least every 18 months until tv8, a consecutive Type A tests meet 0.75 L, at which time the above est schedule may be resumed.

c.

The ac:uracy of each Type A test shall be verified by a supplemental test which:

1 1.

Confirms the accuracy of the Type A test by verifying that the l

difference between supplemental and Type A test data is within 0.25 L,.

2.

Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.

3.

Requires that the rate at which gas is injected into the containment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L,.

d.

Type B and C tests shall be conducted with gas at P, 36 psig, at intervals no greater than 24 mont.hs except for testI involving:

1.

Air locks.

2.

Penetrations using continuous leakage monitoring systems, and 3.

Valves pressurized with fluid from a seal system.

e.

The combined bypass leakage rate shall be determined to be < 0.015 L by applicable Type B and C tests at least once every 24 months except for penetratiens which are not individually testables penetrations not individually testable shal.1 be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P,, 38 psig, during each Type A test.

f.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

DAVIS-BESSE, UNIT 1 3/4 6-3 Amendment No. 90. 120

CONTAINMEF SYSTEMS

.iURVgILLANCR nEQUIREMENTS (Continued) 3

'eakagv from isolation valves that are sealed with fluit from a seal system say be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal System and valves are pressurized to at least 1.10 P 41.8 psig, end the seal system capacity is adequate to maintain syI, tem pressure for at least 30 days.

h.

Type B tests for penetrations employing a continuous leakage menitoring system shall be conducted at P,,

38 psig, at intervals no greater than once per 3 years.

1.

Each time the containment purge and exhaust isolation valves are opened, a special test shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after valve I

closure or prier to entering mode 4 from mode 5, whichever is later.

The special test is conducted by pressurizing the piping section including one valve inside and one valve outside the containment to a pressure greater or equal to 20 psig.

The leckage rate per penetration shall not exceed 0.15 L,.

j.

The special test as defined in Surveillance Requirement 4.6.1.2.1 shall be performed for the containment purge and isolation valves when the plant has been in any combination of modes 3, 4, 5 or 6 for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> provided that the tests required by Surveillance Requirements 4.6.1.2.1 or 4.6.1.2.d have not been performed in the previous 6 months.

k.

All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage reasurement system.

1.

The provisions of Specifiestion 4.0.2. are not applicable.

i DAVIS-BESSE, UNIT 1 3/4 6-4 Amendment No. 90 L

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