ML20211B678

Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance

ML20211B678
Person / Time
Site:	Vermont Yankee
Issue date:	08/18/1999
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20211B670	List: BVY-99-106, TS Proposed Change 225 to License DPR-28,revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20211B678
References
NUDOCS 9908250058
Download: ML20211B678 (6)

Text

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VERMONT YANKEE NUCLEAR POWER CORPORATION Docket No. 50-271 BVY 99-106 t

Attachment 3 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 225 i

l Missed Technical Specification Surveillance Marked-up Version of the Current Technical Specifications l

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o 9908250058 990818 PDR ADOCK 05000271 P- PDR 1 I

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- VYNPS 1.0 DEFINITIcNS f~ 2. The standby gas treatment -'

3. All reactor buildj*

are operable or Shutdown - The If it 13 discovered that a surveillance was not performed V.

ss. ch is in within its specified frequency, declaring applicable being perfo* Limiting Conditions for Operation (LCOs) not met may position a be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is remou or up to the limit of the specified frequency, whichever de-energ' 18 less. This delay period is permitted to allow performance of the surveillance. '

1. Hot .

• **l if the surveillance is not performed within the delay Period, applicable LCOs must immediately be declared ,

2* col not met, and applicable LCOs must be entered.

Shutd, When the surveillance is performed within the delay multip. Period and the surveillance is not met (i.e., acceptance criteria are not satisfied), applicabie LCOs must

w. Simulated Auts immediately be declared not met, and applicable LCOs applying a simu. must be entered.

question.

-X. Transition Boiling - L between nucleate and film . -

Ame in which both nucleate and film bv.. .. ch neither type being completely stable.

Y. Surveillancs 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.

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, l component, or system prior to being required to be operable. l AA. Deleted BB. Source Check - The qualitative assessment of channel response when the channel sensor is exposed to a radioactive source, i CC. Dose Equivalent I-131 - The dose equivalent I-131 shall be that l concentration of I-131 (microcurie / gram) which alone we' d produce the j j

same thyroid dose as the quantity and isotopic mixture e. 1-131, I-132,  !

I-133, I-134 and I-135 actually present. The thyroid dose conversion Amendment No. M, N, M, M, M, MG, M4, MG, 168 4 i

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. VERMONT YANKEE NUCLEAR POWER CORPORATION Docket No. 50-271

. . BVY 99-106 Attachment 4 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 225 Missed Technical Specification Surveillance Retyped Technical Specification Pages l-

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h VYNPS 1.0 DEFINITIONS

, , 2. The standby gas treatment system is operable.

3. All reactor building automatic ventilation system isolation valves are operable or are secured in the isolated position.

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-V. Shutdown - The reactor'is in a shutdown condition when the reactor mode switch ie 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 iniciated, 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. Sbutdown means conditions as above such that the effective multiplication factor (K.rr) 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 rhat 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 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 {

1ess. This delay period is permitted to allow performance of the surveillance.

If the surveillence is not performed within the delay period, applicable LCOs must immediately be declared not met, and applicable l LCOs must be entered.

When the surveillance is performed within the delay period and the J surveillance is not met (i.e., acceptance criteria are not satisfied), l applicable LCOs must immediately be declared not met, and applicable

.LCOs must be entered, i

Amendment No. M, M4, MG 4

VYNPS 1.0 DEFINITIONS 1

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Z. Surveillance Interval - The surveillance interval is the calendar time l 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, 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.

C;. Dose Equivalent I-131 - The dose equivclent 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 ;;esins and filter sludges.

i EE. Deleted l i

FF. Site Boundary - The site boundary is shown in Figure 2.2-5 in the FSAR.

GG. Deleted I

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 setpcints, 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 delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. ,

Amendment No. M, M, 44, M, M, Ma, M1, 168 4a

VYNPS 1.0 DEFINITIONS LL. Ventilation Exhaust Treatment ~ System - The Radwaste Building and AOG Building ventilation HEPA filters are ventilation exhaust treatment 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 radioactive particulates from the gaseous exhaust stream prior to release to the environment. Engineered safety feature atmospheric cleanup systems,.such as the Standby Gas Treatment (SBGT) System, are not considered to be ventilation exhaust treatment system components.

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

. 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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1 Amendment No. 44Gr 448, 171 5

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