ML20043E997
| ML20043E997 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/04/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043E998 | List: |
| References | |
| NUDOCS 9006140078 | |
| Download: ML20043E997 (5) | |
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iE W ASHINGTON, D. C,20565 VERMONT. YANKEE NUCLEAR POWER CORPORATION D0CKET.NO. 50-271 VERMONT-YANKEE NUCLEAR POWER STATION AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No.122.
License No. DPR-28 1.
The Nuclear Regulatory Comission (the Comission or NRC) has found thst:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated March 9,1990 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: (1) that the activities authorized by this amendment cai 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 set forth in 10 CFR Chapter I; 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 Comission's regulations and all applicable requirements have 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 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through-Amendment No. 122, are hereby incorporated in the license. The licensee shall operate.the facility in accordance with the Technical Specifications.
0006140078 900604 PDR ADOCK 05000271 P
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This' license amendment is effective at the time of shutdown for the 1990 scheduled refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION TW sun Richard H..Wessman, Director J
Project Directorate 1-3 Division of Reactor Projects I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance:
June'4, 1990 i
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ATTACMENT TO LICENSE AMENDMENT NO.122 FACILITY OPERATING LICENSE'NO. DDR-28 DOCKET NO. 50-271 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 C
135 136 136
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-i TABLE 4.7.2.a
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l PRIMARY CONTAffGEDff ISOLATION VALVES VALVES SUBJECT TO TYPE C mArAN TESTS
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Number of Power Maximum
' Action on
._Ooerated Valves Operating -
Normal Initiating Grono (1)
Valve Identification Inboard Dutboard Tb (sec) Position Si===1-
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J Isolation l
4 4
5(Note 2)
Open GC' 1
Main Steam Line' Isolation (2-80A, D & 2-86A, D) 1 2
35 Closed SC 1
Main Steam Line Drain (2-74, 2-77) 1 Recirculation Loop Sample Line (2-39, 2-40) 1 1
5 Closed SC 2
25
- Closed, SG 2
RHR Discharge To Radwaste (10-57, 10-66) 2 20 Open GC 2
Drywell Floor Drain (20-82, 20-83) 2 20 Open GC-Drywell Equipment Drain (20-94, 20-95) 2 1
10 Closed SC 3
Drywell Air Purge Inlet (16-19-9) 1 10 Open GC 3
Drywell Air Purge Inlet (16-19-8) 1 10 Closed
- SC 3
Drywell Purge & Vent Outlet (16-19-7A) 1 10 Closed SC 3
Drywell Purge & Vent Outlet Bypass (16-19-6A) 3 Drywell & Suppression Chamber Main Exhaust (16-19-7) 1 10 Closed
- SC 1
10 Closed SC 3
Suppression Chamber Purge Supply (16-19-10) 1 10 Closed SC Suppression Chambcr Purge & Vent Outlet (16-19-7B) 1 10 Open GC 3
Suppression Chamber Purge & Vent Outlet Bypass (16-19-6B) 3 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) 3 NA Closed SC 3
Containment Purge Makeup (16-20-20, 16-20-22A, 16-20-22B) 1 1
25 Open GC 5
Reactor Cleanup System (12-15,12-18) 1 1
55 Open GC I
6 HPCI (23-15, 23-16) 1 1
20 OpenJ GC 6
RCIC (13-15, 13-16) 2 NA Closed SC Primary / Secondary Vacuum Relief (16-19-11A, 16-19-11B) 2 NA Closed Process Primary / Secondary Vacuum Relief (16-19-12A, 16-19-12B) 4 5
Open GC 3
Containment Air Sampling (VG 23, VG 26, 109-76A&B) l NA Open Process Feedwater Check Valves (V2-27A, -96A, -28A, - 28B)
- Valves 16-19-7 and 16-19-7A shall have stops installed to limit valve opening to 500 or less.
135 Amendment No. 58, 67, 7#, H, 122 0012V J
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.n VYNPS TABLE 4.7.2.b-PRIMARY CONTAI!# TENT ISOLATION VALVES VALVES NOT SUBJECT TO TYPE C TRAKAGE TESTS Number of Power Maximum
- Action on Isolation Onerated Valves Operating
-Normal Initiating Grnt o '(Note 1)
_ Valve Identification Inboard Outboard Time (sec) Pnsition Sienal 2
RHR Return to Suppression Pool (10-39A,B)
'2
'70
- Closed -
SC..
1 RHR Return to Suppression Pool (10-34A,B) 2 120 Closed SC' 2
' RER Drywell Spray (10-26A, B & 10-31A,B) 4 70 Closed
. SC 2
RER Suppression Chamber Spray (10-38A,B) 2 45 Closed SC 3
Containment Air Compressor Suetion (72-38A,B) 2~
20 Open~
- GC 4
RHR Shutdown Cooling Supply (10-18, 10-17) 1 1
28 Closed SC g
Standby Liquid' Control Check Valves (11-16, 11-17) 1 1
NA Closed Proc.
Hydrogen Monitoring (109-75 A, 1-4;'109-75. B-D, 1-2) 10 NA-NA NA Sampling Valves - Inlet Hydrogen Monitoring (VG-24, 25, 33, 34) 4 NA NA
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These valves are remote manual sampling valves which do not receive an isolation signal. Only one valve in each l
line is required to be operable.
l Amendment No. 58, 6I, II5,122
-136 l
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