ML20249A751

Amend 223 to License NPF-3,revising TS Section 3/4.6.1.3 & Associated Bases

ML20249A751
Person / Time
Site:	Davis Besse
Issue date:	06/11/1998
From:	Hansen A NRC (Affiliation Not Assigned)
To:
Shared Package
ML20249A752	List: ML20249A751 ML20249A755
References
NUDOCS 9806180187
Download: ML20249A751 (6)

Text

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t UNITED STATES j

NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. enmaa ms

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TOLEDO EDISON COMPANY CENTERIOR SERVICE COMPANY h.!!Q THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 223 License No. NPF-3 1.

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

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and The Cleveland Electric Illuminating Company (the licensees) dated August 26, 1997, complies with the standards and requirements of the 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 (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 enmpliance 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 Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

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

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby I

amended to read as follows:

9006180187 900611 PDR ADOCK 05C 3346 P

PDR

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-(2)

Technical Specifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 223, are hereby incorporated in the 1.icense.

'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 120 days after issuance.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: June 11, 1998

ATTACHMENT TO LICENSE AMENDMENT NO. 223 FACILITY OPERATING LICENSE N0. 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.

Remove Insert TS 3/4 6-6 TS 3/4 6-6 TS 3/4 6-6a TS 3/4 6-6a TS B 3/4 6-1 TS B 3/4 6-1

j CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS J

LIMITING CONDITION T9R OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for entry and exit, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of s 0.002 L, at P,, 38 psig.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

• a..

With one air lock door inoperable in one or more containment air locks, or with the containment air lock interlock mechanism inoperable in one or more containment air locks:

1.

Verify an OPERABLE door in each affected air lock is closed within one hour, and 2.

Lock an OPERABLE door closed in each affected air lock within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 3.

Operation may then continue provided that an OPERABLE door in each affected air lock is maintained closed and is verified to be locked' closed at least once per 31 days, and provided that the containment air lock passes each scheduled performance of SR 4.6.1.3b.

4.

Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• b.

With one or more containment air locks inoperable except as a result of an inoperable air lock door or air lock interlock mechanism:

1.

Verify at least one door in each affected air lock is closed within one hour, and 2.

Restore air lock (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the iallowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• Entry and exit through the OPERABLE door is permissible if necessary to perform repairs of the affected air lock components. After each entry and exit, the OPERABLE door must be closed without delay.

DAVIS-BESSE, UNIT 1 3/4 6-6 Amendment No. 4947 223

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS

. SURVEILLANCE REQUIREMENTS

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4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

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a. By verifying either no detectable seal leakage when the volume between the door seals is pressurized to 10 psig, or by verifying a seal leakage rate of s 0.0015 L when the volume between the door seals is l.

pressurized to P,,,38 psig, and the air lock door holddowns are installed:

1. #Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening, (in MODES 1, 2, 3 and 4) except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and

2.

• Prior to establishing CONTAINMENT INTEGRITY when maintenance has not been performed on the air lock that could af fect the air lock

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sealing capability. Reperformance of this '.est is not required j

prior to entering MODE 4 if the air lock has not been opened since the previous test.

b. By conducting an overall air lock leakage test at P,, 38 psig, and by verifying that the overall air lock leakage ra:e is within its limit:

1. #At least once per 6 months, and

2.

• Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability,

c. At least once per REFUELING INTERVAL by verifying that only one door in l

each air lock can be opened at a time.

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• txemption to Appendix "J" of 10 CFR 50.

1. The provisions of Specification 4.0.2 are not applicable.

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l-DAVIS-8 ESSE, UNIT 1 3/4 6-6a Amendment No. +9+r 223

3/4.6' CONTAINMENT SYSTEMS BASES

~3/4.6.l~ PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY

. ' Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths.and associated leak rates assumed in the safety analyses.

This restriction, in conjunction with the leakage rate limitation and air lock door requirements, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure of 38 psig, P conservatism, the measured ~overall as-left integrate 8. As an addedleakage rate is f!'r limited to s 0.75 L, during ' performance'of the periodic tests to account for possible degradatio,n of the containment leakage barriers between leakage tests.

The special' test for the containment purge and exhaust isolation valves is intended to detect gross degradation of seals on the valve seats. The special test is performed in addition to the Appendix J requirements.

USAR 6.2.4 identifies all penetrations that are secondary containment

~ bypass leakage paths.

3/4.6.1.3 CONTAINMENT AIR LOCKS

- The limitations on closure and leak rate for the containment air locks are required to meet the restrictions.on CONTAINMENT INTEGRITY and containment leak rate.: Surveillance testing of the air lock seals provide assurance that the overall air. lock leakage will not become excessive due to. seal damage during the intervals between air lock leakage tests.

'The air lock interlock allows only one air lock door of an air lock to be opened at a time. This provision ensures that a gross breach of containment

.does not exist when CONTAINMENT INTEGRITY is required.

Closure of a single door in each air lock is sufficient to provide a leak tight barrier following postulated events. Nevertheless, in MODES 1 through 4, both doors are kept closed when the air lock is not being used for entry and exit, i.e.,

containment entries / exits, air lock maintenance, or air lock testing.

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. DAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendment No. 00,145,150,100, 100,205, 223

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