ML20217G198
| ML20217G198 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/13/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217G201 | List: |
| References | |
| NUDOCS 9910210224 | |
| Download: ML20217G198 (6) | |
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1 UNITED STATES 4
j NUCLEAR REGULATORY COMMISSION E
' E' WASHINGTON. D.C. 205sH001 i
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.....,o VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.179 License No. DPR-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated August 18,199J, 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 Commission; 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 accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9910210224 991013 PDR ADOCK 05000271 p
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! 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:
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(B)
Teghnical Soecifications
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1 The Technical Specifications contained in Appendix A, as revised through-Amendment No.179, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, f
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 oays.
FOR THE NUCLEAR REGULATORY COMMISSION Af.
J es W. Clifford, hief, Section 2 Project Directorate i Division of Licensing Project Management Otl ice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
' Date of Issuance: October 13,1999 i
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ATTACHMENT TO LICENSE AMENDMENT NO.179
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FACILITY OPERATING OCENSE NO.' DPR-28 i
DOCKET NO. 50-271
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- Replace the following pages of the Appendix A Technical Specifications with the attached h
revised pages. The revised p' ages are identified by amendment number and contain marginal l
lines indicating the areas of change.
. Remove Insert
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- 1.0 DEFINITIONS 2.
The standby gas treatment system is operable, l
3.
All reactor building automatic ventilation system isolation valves are operable or are secured in the isolated position.
I V.
Shutdown - The reactor is in a shutdown. condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed. When the mode switch is placed in the shutdown position a reactor scram is initiated, power to the control rod drives is removed, and the reactor protection-system trip systems are de-energized.
1.
Hot Shutdown means conditions as above with reactor coolant temperature greater that 212*F.
2.
Cold Shutdown means conditions as above with reactor coolant temperature equal to or less than 212*F.
3.
Shutdown means conditions as above such that the effective multiplication factor (Krt) of the core shall be less than 0.99.
W.
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate circuit in question.
X.
Transition Boiling - Transition boiling means the boiling regime between nucleate and film boiling.
Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.
Y.
Surveillance Frequency - Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be. performed within the specified surveillance intervals.
These intervals.may be adjusted plus 25%.
The operating cycle interval is considered to be 18 months and the tolerance stated above is applicable.
If it is discovered that a surveillance was not performed within its specified frequency, declaring applicable Limiting Conditions for Operation (LCOs) not met may be delayed, from the time of discovery, up I
to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is
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less.
Tnis delay period is permitted to allow performance of the 1
surveillance.
I If the surveillance is not performed within the delay period, j
applicable LCOs must immediately be declared not met, and applicable l
LCOs must be entered.
I When the surveillance is performed within the delay period and the surveillance is not met (i.e.,
acceptance criteria are not satisfied),
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, applicable LCOs must immediately be declared not met, and applicable LCOs must be entered.
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[ - Amendment No. M, M4, M6. 463, @
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1.0 DEFINITIONS Z.
Surveillance Interval - The surveillance interval is the calendar time between surveillance tests, checks, calibrations, and examinations to be performed upon an instrument or component when it is required to be operable.
These tests unless otherwise stated in these specifications may be waived when the instrument, component, or system is not required to be operable, but these tests shall be performed on the instrument,
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. component, or system prior to being required to be operable.
AA. Deleted BB. Source Check - The qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
CC. Dose Equivalent I-131 - The dose equivalent I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in NRC Regulatory Guide 1.109, Revision 1, October 1977.
DD. Solidification - Solidification shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
Suitable forms include dewatered resins and filter sludges.
EE Deleted FF. Site Boundary - The site boundary-is shown in Figure 2.2-5 in the FSAR.
GG.
Deleted HH.
Deleted II. Off-Site Dose Calculation Manual (ODCM) - A manual containing the current methodology and parameters used in the calculation of off-site doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduction of the environmental radiological monitoring program.
JJ. Process Control Program (PCP) - A process control program shall contain the sampling, analysis, tests, and determinations by which wet radioactive waste from liquid systems is assured to be converted to a form suitable for off-site disposal.
KK Gaseous Radwaste Treatment System - The Augmented Off-Gas System (AOG) is the gaseous radwaste treatment system which has been designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and providing for j
delay or holdup for the purpose of reducing the total radioactivity i
prior to release to the environment.
l Amendment No, M, G4, 44, M, 44, Ma, 4M, M9, U9 4a
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1.0 DEFINITIONS LL. Ventilation Exhaust Treatment System - The Radwaste Building and AOG Building ventilation HEPA filters are ventilation exhaust treatment l
. systems which have been designed and installed to reduce radioactive material in particulate form in gaseous effluents by passing ventilation air through HEPA filters _for the purpose of removing racioactive particulates from the gaseous exhaust stream prior to release to the environment.
Engineered safety feature atmospheric i
cleanup systems, such as the Standby Gas Treatment (SBGT) System, are considered to be ventilation exhaust treatment system components.
not MM. Vent / Purging - Vent / Purging is the controlled process of discharging air or gas from the primary containment to control temperature, pressure, humidity, concentration or other operating conditions.
NN. Core Operating Limits Report - The Core Operating Limits Report is the I
unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.6.C.
Plant operation within these operating limits is addressed in individual specifications.
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{ Amendment No. M4r 14e, e 179 5