ML20195D393

Amend 89 to License DPR-36,adding Addl Manual Containment Isolation Valves & Blowdown & Body Vent Valves on Instrument Lines to List of Manual Containment Isolation Valves That May Be Repositioned

ML20195D393
Person / Time
Site:	Maine Yankee
Issue date:	05/27/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195D390	List: ML20195D386 ML20195D393 ML20195D398
References
NUDOCS 8606040175
Download: ML20195D393 (5)

Text

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET N0. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-36

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

A. The application for amendment by Maine Yankee Atomic Power Company (the licensee), dated April 23, 1985 as supplemented October 7, 1985, 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 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; 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 accordan:e with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8606040175 860527 PDR ADOCK 05000309 P PDR

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operating License No. OPR-36 is hereby amended to read as follows:

(b) Technical Specifications

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The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE N CLEAR REGULATORY COMMISSION f

A QLAn~'

Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: May 27, 1986

ATTACHMENT TO LICENSE AMENDMENT N0. 89 FACILITY OPEPATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:

Remove Pages Insert Paaes 3.11-2 3.11-2 3.11-5 3.11-5

Exception:

1. fianual containment isolation valves may be repositioned under administrative controls provided prior compensatory measures are taken to isolate the penetration. Compensatory measures which may be taken include closing other valves or installing blind flanges to isolate a penetration. Compensatory measures which are in effect for longer than seventy-two hours must meet the same design criteria as the original containment isolation valve.

2. The following manual containment isolation valves may be reposi-tioned under administrative control without compensatory measures to isolate the penetration:

RH-4, 6, 7, 26 fiS-48, 50, 68, 70, 88, 90, 239, 241, 243 PAP-1, 4, 23, 24, 25 HPD-4, 5, 9, 10, 14, 15  !

IA-212, 213, 218, 219, 220 l

3. Blowdown and body vent valves associated with instrumentation lines may be repositioned under administrative control without compensa-tory measures to isolate the penetration.

Remedial Action:

With one or more automatic, remotely operated, or manual containment isolation valves inoperable, maintain at least one automatic, remotely operated, or manual isolation valve operable in each affected penetra-tion that is open, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

1. Restore the inoperable valve to operable status, or

2. Isolate the affected penetration by use of at least one manual, remotely operated or deactivated automatic isolation valve secured (tagged) in the closed position or by use of a blind flange.

Compensatory measures which are in effect for longer than seventy- ,

two hours must meet the same design criteria as the original contain-ment integrity valve.

, C. The reactor shall not be critical if the containment internal pressure exceeds 3 psig.

D. On-line containment porne.

On-Line purging of containment is not allowed under the conditions of Specification 3.11.8 above, unless the following conditions are satisfied:

1. Prior to the depressurization of the containment for on-line purge, the two purge supply, two exhaust valves and one exhaust bypass valve will be cycled to test the automatic closure feature using both the Containment Gaseous Activity and Primar/ Vent Stack Gaseous Activity closure signals.

The operation of the inner and outer supply and exhaust 3.I1-2 Amendment No. O ,77,W,39

Basis (continued)

Manual containment integrity valves may be repositioned provided that actions are taken to isolate the penetration by alternate means. As soon as practicable, but within seventy-two hours, the alternate means utilized, including associated pip-ing, will be verified to meet the same design criteria as the original isolation.

Certain valves are allowed to be repositioned under administrative controls (e.g.,

written procedures) to effect required periodic tests and to allow certain required evolutions during startup and shutdown, including main steam line warmup, steam trap blowdown, and Residual Heat Removal (RHR) system operation. Examples of uses of these valves are provided below. These examples are not all inclusive.

The calorimeter isolation valves, MS-239, 241 and 243, are opened in order to perform planned calorimetrics.

The steam line vents, MS-48, 68 and 88, are open for several hours during heatup between reactor coolant temperatures of approximately 210 F and 300 F.

The steam trap drains, HPD-5,10 and 15, are cycled open briefly during steam line warmup to blow down the steam trap.

The isolation valves to the blowdown tank, HPD-4, 9 and 14, are open during heatup and are closed prior to entering power operation.

The steam generator non-return valve bypasses, MS 50, 70 and 90, are opened during steam line warmup.

The Residual Heat Removal System valves, RH-4, 6, 7 and 26, are utilized when the Residual Heat Removal System is in service or when low temperature overpressure protection is in service.

PAP 1 and 4 are opened monthly to perform periodic surveillance of the hydrogen purge system in accordance with Technical Specifications (TS 4.11).

The inner door 0-ring test valves, IA-218, 219 and 220, are opened to allow testing of the inner containment door 0-ring.

Hydrogen analyzer inlet valves, PAP-23 and 24, return valves, IA-212 and 213, and stop valve PAP-25 are opened briefly during flow testing and during operation of the post accident hydrogen purge and analysis system.

During the time that the steam line or steam trap isolation valves are open, the reactor is either subcritical or at low power conditions. A membrane barrier separates the main steam system from the containment atmosphere and the reactor coolant system at all times.

The RHR system containment isolation valves are opened only with the primary coolant temperature (TS 3.4) equal to or less than minimum pressurization temperature. There is a membrane barrier between the containment atmosphere and the RHR system.

Blowdown and body vent valves on instrumentation lines are allowed to be reposi-tioned under administrative controls (e.g. , written procedures) to effect required calibration and maintenance. These administrative controls ensure containment boundary conditions are maintained following calibration and maintenance.

3.11-5 Amend nen t No. M , 89