ML20085M726
| ML20085M726 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/24/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085M728 | List: |
| References | |
| NUDOCS 9111120124 | |
| Download: ML20085M726 (8) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION c
wasmNG TON. D. C. 00555
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VERMONT YAtlKEE NUCLEAR P0}!EP, CORP 0PAIJ0!!
DOCKET f10. 50-271
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VERMCtT YAtlKEE f;UCLEAR POWER STATION
.AIjgEp,T,,TO,,F,A,CILITY OPERATit!G LICENSE Amendment tio. 132 License No. DPR-28 1.
The fluclear Regulatory Corraission (the Commission or the NRC) has found that:
A.
The application fur amendment filed by the Vermont Yankee t!uclear Power Corporation (the licensee) dated January 15, May 16 and July 12, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as ar. ended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The f acility 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 authorizec 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 15suance 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 arendment is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Cperating License tio. OPR-28 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment tio.132, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
9111120124 911024 PDR ADOCK 0500 1
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This license amendrr.ent is effective as of its date of issuance, FOR THE NUCLEAR REGULATORY COMMISSION g
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Walter R. Butler, Director Project Directorate 1-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Attachrrent:
Changes to the Technical Specifications Date of Issuance:
October 24, 1991
l ATTACPPENT T0_ L1,C,E,NS,E,,Ajt ENDMENT NO._,132 FACILITY OPERATING LICENSE NO. DPR-28 DOCKETNO.}0-271 e
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 34a 24a 49c A9c 60b 60b 66 66 220 220
i VYNPd 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS 3.2 Protective Instrument Systems Specification 4.2 PROTECTIVE INSTRUMENT SYSTEMS (cont'd)
Specification (cont'd) 1.
Recirculation Pump Trip Instrumentation I.
Recirculation Pump Trip Instrumentation During reactor power operation, the The Recirculation Pump Trip Instrumentation Recirculation Pump Trip Instrumentation shall shall be functionally tested and calibrated.
be operative in accordance with Table 3.2.1.
in accordance with Table 4.2.1.
I J.
Deleted J.
Deleted i
K.
Degraded Grid Protective System K.
Degraded Grid Protective System During reactor power operation, the emergency The en.ergency bus undervoltage bus undervoltage instrumentation shall be instrumentation shall be functionally tested operative in accordance with Table 3.2.8.
and calibrated in accordance with Table 4.2.8g L.
Reactor Core Isolation Cooling System L.
Reactor Core Isolation Cooling System l
Actuation Actuation
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When the Reactor Core Isolation Cooling Instrumentation and Logic Systems shall be System is required in accordance with functionally tested and calibraten as Specification 3.5.G, the instrumentation indicated in Table 4.2.9.
which initiates actuation of this system shall be operable in accordance with Table 3.2.9.
t Amendment No. Jg, pg, 93, f(f, 132 33,
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VYNPS 3.2 (re.tinued) system operation so that none of the activity released during the refueling accident leave stan 1y gas treatment the eactor Building via the normal ventilation stack but that all activity is processed by the standby gas treatment system. Trip settings for the monitors in the ventilation duct are based upon initiation of the normal ventilation irolation and standby gas treatment system operation at a radiation level equivalent to the maximum site boundary dose rate of 500 mrem / year as given la Specification 3.8.E.1.a.
The monitoring system in the plant stack represents a backup to this system to limit gross radioactivity releases to the environs.
The purpose of isolating the mechanical vacuum pump line is to limit release of radioactivity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam line to the main condenser. The fission product radioactivity would be sensed by the main steam line radiation monitors which initiate isolation.
Post-accident instrumentation parameters for Containment Pressure, Torus Water Level, Containment flydrogen/ Oxygen Monitor, and Containment liigh-Range Radiation Monitor, are redundant, environmentally and seismically qualified instruments provided to enhance the operators' ability tc, follow the course of an event.
The purpose of each of these instruments is to provide detection and neasureiaent capabity during and following an accident as required by NUHEG-0737 by ensuring continuous on-scale inoication of t following:
containment pressure in the 0 to 275 psia range; torus water level in the O to 25 foot range (i.e., the bottom to 5 feet above the normal water level of the torus pool); containment hydrogen / oxygen concentrations (0 to 30% hydrogen l
and 0 to 25% oxygen); and containment radiation in the 1 n/hr to 107 R/hr gamma.
The Degraded Grid Protective System has been installed to assure that safety-related electrical equipment will not be subjected to sustained degraded voltage. This system incorporates voltage relays on 4160 Volt Emergency Ituses 3 and 4 which are set to actuate at the minimum voltage required to prevent damage of safety-related equipment.
If Degraded Grid conditions exist for 10 seconds, either relay will actuate an alarm to alert operators of this condition. Based upon an assessment of these conditions the operator may choose to manually disconnect the off-site power.
In addition, if an ESF signal is initiated in conjunction with low voltage below the relay setpoint f or 10 seconds, the off-site power will be automatically disconnected.
Amendment No. pg, pg,1g3, yfg 132 66
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VYHPS 7.
An estinaate of the exposure to plant operating ;.ersonor' -
a result of the change; and 8.
Documentation of the fact that the change was rtv ww
. V faand acceptable by PORC.
B Shall beconie effective upon review and acceptance by PORC and approval by the Plant Manager.
6.15 8til K _CH_t_0.R.i.f1E R.A.l.l. _S_ilI_P_ME__N.T.S.
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Every three / cars, starting in October 1994, the licensee shall submit to the NFC, for reciew, the annual frequcncy of railroad shipments of bulk calorine within five miles of the plant sita in order to verify that the probobility of loss of controi room habitability meets the accepta criteria of Section 2.2.3, " Evaluation of Potential Accidents" of the NRC Standard Review Plar, (NL9EG - 0800 July 1981).
The rep.-t will also consider any changes in the quantity of chlorine in each snipment. The report shall reference License Amendment t!c.13 1aud Oct ober 24, 1991-I
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