ML20071A345

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Amend 74 to License DPR-28,changing Tech Specs to Permit one-time Use of Manual Valve to Accomplish Primary Containment Isolation,Not to Exceed 72 H
ML20071A345
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 02/14/1983
From: Vassallo D
Office of Nuclear Reactor Regulation
To:
Vermont Yankee
Shared Package
ML20071A347 List:
References
DPR-28-A-074 NUDOCS 8302240017
Download: ML20071A345 (4)


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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.74 5

License No. DPR-28 l

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

A.

The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated February 8,1983 complies with the standards and rcquir+ mats cf the Ato.aic Energy Act of 195", 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is ir. accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 74 are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

8302240017 830214 PDR ADOCK 05000271 P

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2-3.

Within 90 days after the effective date of this amendment, or such later time as the Commission may specify, the Licensee shall satisfy any applicable requirement of P.L.97-425 related to pursuing an agreement with the Secretary of Energy for the disposal of high-level radioactive waste and spent nuclear fuel.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION 4

Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Char.gts to the Technical Specificaties.s Date of Issuance:

February 14, 1983

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ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271_

Revise the Technical Specifications as follows:

REMOVE INSERT 135 135 E

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VYNPS TABLE 4.7.2.a

'. PRIMARY CONTAINMENT ISOLATION VALVES

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VALVES SUBJECT TO TYPE C LEAKAGE TESTS Number of Power Maximum Action on Isolation Operated Valves Operating-Normal Initiating Grcup (Note 1)

Valve Id ent.i f i ca t ion Inboard Outboard Time (sec) Position Signal 1

Main Steam Line Isolation (2-80A, D & 2-86A,.D) 4 4

5(notec2)

Open GC 1

Main Steam Line Drain (2-74, 2-77) 1 2

35 closed SC 1

Recirculation Loop Sample Line (2-39, 2-40) 1 1

5 Closed SC 2

RRR 01scharge To Radwaste (10-57, 10-66) 2 25 Closed SG 2

Dryeell Floor Drain (20-82, 20-83) 2 20 Open GC 2

Drywell Equipment Drain (20-94, 20-95) 2

.20 Open GC 3

Drywell Air Purge Inlet (16-19-9) 1 10 Closed SC 3

Drywell Air Purge Inlet (16-19-8) 1 10 Open.

GC 3

Drywell Purge & Vent Outlet (16-19-7A) 1 10 Closed SC 3

Drywell Purge & Vent Outlet Bypass.(16-19-6A) 1 10 Closed SC 3

Drywell & Suppression Chamber Main Exhaust (16-19-7) 1 10 Closed SC 3

Suppression Chamber Purge Supply (16-19-10) 1 10 Closed SC 3

Suppression Chamber Purge & Vent Outlet (16-19-78) 1 10 Closed SC 3

Suppression Chamber Purge & Vent Outlet Bypass (16-19-6B) 1 10 Open GC 3

Exhaust to Standby Gas Treatment System (16-19-6) 1 10 Open GC 3

Containment Purge Supply (16-19-23) 1 10 Open GC 3

Containment Purge Makeup (16-20-20, 16-20-22A, 16-20-22B)*

3 NA Closed SC 5

Reactor Cleanup System (12-15, 12-18) 1 1

25

'Open GC 5

. Reactor Cleanup System (12-68) 1 45 Open GC

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6 HPCI (23-15, 23-16) 1 1

55 Open GC 1

1 20 Open GC 6

RCIC (13-15, 13-16)

Primary / Secondary Vacuum Relief (16-19-11A, 16-19-11B) 2 NA Closed SC Primary / Secondary Vacuum Relief (16-19-12A, 16-19-12B) 2 NA Closed Process Control Rod Ilydraulic Return Check Valve (3-181)

NA Open Process 3

Containment Air Sampling (VG 23, VG 26, 109-76A&B) 4

'5 Open GC Ialve V

16-20-22D may be closed to ef f ect primary containment isolation during repairs to valves 16-20-20

  • Note:

- a nd 16-20-2 2 8.

Use of valve 16-20-22D in this manner is restricted to on'e time-for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Use of 16-20-22D in this manner is not allowed af ter March 5,1983.

Amendment No. 58, SJ 74 135

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