ML20148C379

Amend 59 to License DPR-45,revising Tech Specs to Reflect Exemption from 10CFR50.54(o) & 10CFR50,App J Requirements to Perform Type a Containment Bldg Integrated Leak Rate Tests Per 10CFR50.12(a)(ii)

ML20148C379
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/15/1988
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148C351	List: ML20148C347 ML20148C379 ML20148C394 ML20148C441
References
NUDOCS 8803220370
Download: ML20148C379 (6)

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DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR (LACBWR)

AMENDMENT TO PROVISIONAL LICENSE Amendment No. 59 License No. DPR-45

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

A. The application for amendment filed by Dairyland Power Cooperative (the licensee) dated August 21, 1987 as revised August 28, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the 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 Commission's regulations set forth in 10 CFR Chapter I; D. The issidnce 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.

8803020370 880315 DR ADOCK 050 9

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosures to this license amendnent, and Paragraph 2.C.(2) of Provisional License No. DPP.-45 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendrent No. 59, are hereby incorporated ir, the license. The licensee shall maintain the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h h. 8- A" Lester S. Rubenstein, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Changes to the Technical Specifications Date of Issuance: March 15, 1988 l

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ENCLOSURE TO LICENSE AMENDMENT NO. 59 PROVISIONAL LICENSE NO. DPR-45 DOCKET NO. 50-409 Replace the following pages and figures of the Appendix A Technical Specifications as 1,1dicated below. The revised pages and figures are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Pages INSERT Pages 5-2 5-2 5-3 5-3 5-4 5-4 l

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5.1.5 Components which have been repaired, replaced, or otherwise subjected to temporary or permanent modification shall be tested in accordance with procedures which are appropriate in view of the nature of the repair, replacement or modification, and in view of the condition of the system.

5.1.6 All annual tests requiring the reactor to be shut down may be performed at the nearest scheduled shutdown, provided that the interval between tests does not exceed 16 months. The interval between semi-annual tests shall not exceed 8 months.

5.1.7 Definitions applicable to Section 5.2.15 are as follows:

Channel Check: A qualitative determination of acceptable operability by observation of channel behavior during operation. This determination shall include, where possible, comparison of the channel with other independent channels measuring the same variable.

Channel Test: Injection of a simulated signal into the channel to verify its proper response including, where applicable, alarm and/or trip initiating action.

Channel Calibration: Adjustment of channel output such that it responds, with acceptable range and accuracy, to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip.

5.2 TESTING 5.2.1 Containment Testing 5.2.1.1 - Deleted -

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+i PC4-20a 5-2 Amendment No. 59

. i 5.2.1.2 Individual Leak-Detection Test (Type B and C Tests):

Type B and C tests shall be performed as follows:

(a) Type B Tests: Leak-detection tests shall be perfonned at a pressure of at least 52 psig by using the soap-bubble technique (or other methods of equivalent sensitivity) or by detennining the rate of pressure loss of pneumatically pressurized test chambers on the following containment components:

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5-3 Amendment No. 59 PC4-20a

the electrical penetrations, the reactor building spray valve shaft penetration, the freight door, the main steam line penetration, the feedwater line penetration, the heating steam line and condensate return penetration, the containment building airlocks, and the flanges of the ventilation system inlet and exhaust ducts.

Component Leak Surveillance System: A leak surveillance system (i.e.,

continuous pressurization of individual containment cor,ponents) that maintains a pressure not less than 52 psig at individual test chambers of containment penetrations and seals during normal reactor operation shall be acceptable in lieu of Type B tests for the components under such leak surveillance.

(b) Type C Tests: Containment isolation valve leak detection testing shall be conducted at a pressure of 52 psig.

(c) Acceptance Criteria: The combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 60%

of the design leak rate at 0.1 percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(d) Corrective Actions: Leaks which cause the acceptance criteria of (c) to be exceeded shall be repaired and retested until the criteria is met.

Repairs of lesser leaks are optional.

(e) Test Frequency: Type B tests (except for air locks and electrical penetrations) shall be performed at intervals no greater than two years. Air locks shall be tested at 4-month intervals. The freight door shall be tested following each closure prior to plant startup. Electrical penetrations shall be tested at intervals no greater than one year. Type C tests shall be

- performed during each reactor shutdown for refueling, but in no case at intervals greater than two years.

5.2.1.3 - Deleted - .

5.2.1.4 - Deleted - l 5.2.1.5 Report of Test Results: The leakage rate results of Type B and C l

' tests that meet the acceptance criteria shall be reported in the appliceSle LACBWR operating report. Leakage test results of Type B and C tests that l fail to meet the acceptance criteria shall be reported in a separate summary that includes an analysis and interpretation of the test data, the least 23 squares fit analysis of the test data, the instrumentation error analysis, i and the structural conditions of the containment or components, if any, which contributed to the failure in meeting the acceptance criteria.

5-4 Amendment No. 59 PC4-20a

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