ML20082B810

Amend 144 to License DPR-28,re Changes to TS to Extend Radioactive Effluent Release Rept Submittal Frequency

ML20082B810
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	04/03/1995
From:	Mckee P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082B813	List: ML20082B810 ML20082B821
References
NUDOCS 9504060046
Download: ML20082B810 (11)

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UNITED STATES ye 4

NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 2c4864m R.....,$

VERMONT YANKEE NUCLEAR POWER CORPORATION DQCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE j

Amendment No.144 License No. DPR-28

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1.

The Nuclear Regulatory Comission (the Comission) has found that-A.

The application for amendment by the Vermont Yankee Nuclear Power Corporation (the licensee), dated August 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 authprized 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 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 3.8 of Facility Operating License No. OPR-28 is hereby amended to read as follows:

9504060046 950403 PDR ADOCK 05000271 p

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_2-Technical Soecifications The Technical Specifications contained in Appendix A, as revised through knendment No.144, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license' amendment is effective as of its date of issuance, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Phillip F. McKee, Director-Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 3, 1995

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1 ATTACHMENT TO LICENSE AMENDMENT N0.144 FACILITY OPERATING LICENSE NO. DPR-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 1.ines indicating the areas of change.

Remove Insert 182 182 184 184 201 201 270 270 271 271 272 272 277 277 278 278 f

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4 VYNPS TABLE 4.8.1 NOTATION: -(Cont'd) c.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

Prior to analyses, all samples.taken,for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release, d.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Hn-54, Fe-59, Co-58, co-60, Zn-65, Ho-99, Cs-134, Cs-137, co-141, and Co-144.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level, but as "not detected". When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the l

Annual Radioactive Effluent Release Report.

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l Amendment No. 64, 144 182

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. TABLE 4.8.2' NOTATION:

a.

See footnote a. of Table 4.8.1.

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b.

Samples shall be changed at least once per 7 days and analyses shall-be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from' samplers.. Sampling shall also be performed at least once per.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days i,

following each shutdown, startup or thermal power change exceeding'25% of rated thermal power in one hour, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing the samples. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of.10.

This requirement to sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for -7 days applies only its (1) analysis shows that.the dose equivalent I-131 concentration in the primary coolant has increased more t a factor of 3 and the resultant concentration is at least 1 x 10'p i/mir and (2) the noble pc gas monitor shows that eftluent activity has increased more than a factor:

of 3.

c.

sampling and analyses shall also be performed following shutdown, startup, or a thermal power _ change exceeding 25% of rated thermal power per hour unless (a) analysis.shows that the dose equivalent I-131 i

concentration in the primary coolant has not increased more than a factor j

of 3 and the resultant concentration is at least 1 x 10-1 pci/ml; and.

(2).the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

d.

The principal gansna emitters for whi:h the LLD specification will apply ~

are exclusively the followig radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions, and Mn-54, Fe-59, co-58, co-60, 2n-6s, Mo-99, Cs-134, Cs-137, Co-141 and Co-144 for particulate emissions. This list does not mean that only these.nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below LLD for the analyses shomld not be reported as being present at the LLD level for that nuclide, but as

• not detected'. When unusual circumstances result in LLDs higher than l

required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

e.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate:

calculation made in accordance with Specifications 3.8.E.1, 3.8.F.1 and l

3.8.G.1.

f.

The gaseous waste sampling and analysis program does not explicitly require sampling and analysis at a specified LLD to determine the I-133

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release.

Estimates of I-133 releases shall be determined by counting the weekly charcoal sample for I-133-(as well as I-131) and assume a constant release rate for the release period.

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2 Amendment No. 84,144 184

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. y VYNPS TABLE 3.9,3 NOTATION specific parameters of distance and direction sector from the centerline of the reactor and additional descriptions where pertinent, shall be-provided for each and every sample location in Table 3.9.3 in a table and figure (s) in the ODCM. Deviations are permitted from the requi, red-sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

If specimens are unobtainable due to sampling equipment malfunction, every reasonable effort shall be-made to complete corrective action prior to the end of the next sampling period.

Alla, deviations from the sampling schedule shall be documented in the annual-Radiological Environmental Surveillance Report pursuant to specification 6.7.c.3.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances, suitable alternative nedia and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.- In lieu of a.

Licensee Event Report and pursuant to Specification 6.7.C.1, identify the cause of the unavailability of samples for that pathway and identify,the l

new location (s) for obtaining replacement samples.in the next Annual Radioactive. Effluent Release Report and also include in the report _a revised figure (s) and table for the ODCM reflecting the new location (s).

b one or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in o

addition to, integrating dosimeters For.the purposes of this table, a Thermoluminescent Dosimeter (TLD) is considered to be one phosphors two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stations is not an absolute number. The frequency of e

analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optipum dose information with minimal fading.

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more.after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is greater than ten times the yearly-mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

d Gamma isotopic analysis means the identification and'quantification of gamma-emitting' radionuclides that may be attributable to the effluents from the facility.

The

• upstream sample

• shall be taken at a distance beyond significant influence of the discharge. The

• downstream

• sample shall be taken in an 4

area beyond but near the mixing zone.-

f Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g.,

monthly) in order to assure obtaining a representative sample.

9 Each meteorological sector shall have an established " inner" and an

• outer

• monitoring location based on ease of recovery (i.e., response time) and year-round accessibility.

h Sample collection will be performed weekly whenever the main plant stack effluent release rate of I-131, as determined by the sampling and 4

analysis program of Table 4.8.2, is equal to or greater than 1 x 10-1 uci/sec. Sample collection will revert back to semimonthly no 4

sooner than at least two weeks after the plant stack effluent release ratw of I-131 falls and remains below 1 x 10-1 uci/sec. 144 201 Amendment No. 64, w,

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WNPS Letter from L. A. Tremblay, Jr. (WNPC) to USNRC,

' Supplemental Information to WNPC April 19, 1990 Response Regarding FROSSTEY-2 Fuel Performance Code,

• BW 90-054, dated May 10, 1990 (Approved by NRC SER, dated September 24, 1992).

Letter,from L. A. Tremblay, Jr. (WNPC) to USNRC,** Responses to F.equest for Additional Information on FROSSTRY-2 Fuel.

Perfonnance Code,' BW 91-024, dated March 6, 1991 (Approved by NRC SER, dated September 24, 1992).

. Letter from L. A. Tremblay, Jr. (WNPC) to USNRC, "LOCA-

'Related Responses to Open Issues on FROSSTRY-2 Fuel Performance Code,

• BW 92-39, dated March 27, 1992 (Approved by NRC SER, dated September 24, 1992).

Letter from L. A. Tremblay, Jr. (WNRC) to USNRC, "FROSSTEY-'

2 Fuel Performance Code - Vermont Yankee Response to Remaining Concerns,

• BW 92-54, dated May 15, 1992 (Approved by NRC SER, dated September 24, 1992)'.

Report, " Loss-of-Coolant Accident Analysis for Vermont Yankee Nuclear Power Station,* NEDO-21697, August 1977, as amended (Approved by NRC SER, dated November 30, 1977).

Report, ' General Electric Standard Application for Reactor Fuel (CESTARII),

• NEDE-24011-P-A, GE Company Proprietary 4

(the latest NRC-approved version will be listed in the 4

COLR).

n The core operating limits shall be determined so that all I

applicable limits (e.g.,

fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident-analysis i

limits) of the safety analysis are met.

The COLR, including j

any mid-cycle revisions or supplements thereto, shall be i '

provided upon issuance, for each reload cycle, to the NRC t

j Document control Desk with copies to the Regional Admir.istrator and Resident Inspector, i

B.

Reportable Occurrences This section deleted.

C.

Uniaue Reportina Reauirements

-l 1.

Annual Radioactive Effluent Release Report l

a.

Within 90 days after January 1 of each year, a report shall be submitted covering the radioactive content of effluents released to unrestricted areas during the l

previous calendar year of operation.

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i Amendment No. M, H, M, H4, M6, 4M,144 270

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b._

The Annual Radioactive Effluent-Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, Revision 1,-June 1974, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gesedus Effluents from Light-Water-Cooled Nuclear Power Plants', with data sumanarized on a quarterly basis following the format of Appendix B thereof. For solid j

wastes the format for Table 3 in Appendix B of Regulatory Guide 1.21 shall be supplemented with three additional categories: class of solid wastes (as defined by 10CFR Part 61), type of container (e.g.,

LSA, Type A, Type B, Large Quantity), and solidification agent'or absorbent, if any.

In addition, the Annual Radioactive Effluent Release I

Report shall include an annual-susanary of hourly meteorological data collected over the previous year.

This annual susanary may be either in the form of an hour-by aour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report (or a supplement to it to be submitted within 180 days of January 1 each year) shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year. The Annual Radioactive Effluent Release Report (or supplemental dose report) shall also-include an assessment of the radiation-doses from radioactive effluents to member (s).pf the public due to any allowed recreational activities inside the site boundary during the previous calendar year. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports. For any batch or discrete gas volume' releases, the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determine? by sampling frequency and measurement) shall be usec. for determining the gaseous pathway-doses. For radioactive' materials released in concinuous effluent streams, quarterly average

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meteorological conditions concurrent with the J

quarterly release period shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the off-site Dose calculation Manual (oDcM).

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• In lieu of submission with the Annual Radioactive Effluent Release Report,-

the licensee has the options of retaining this sununary of required meteorological data in a file that sh:,11 be provided to the NRC upon request.

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-Amendment No. 84, 94, I44 271

.:w-q; VYNPS With the limits of specification 3.8.M.1 being

. exceeded during the calendar year, the Annual-

. Radioactive. Effluent Release Report (or supplemental dose report) shall also include an assessment of radiation doses to the likely most exposed real member (s) of the. public from reactor releasy (including. doses from primary effluent pathways and direct radiation) for the previous calendar year to p

show conformance with 40CFR190, Environnantal

- Radiation Protection Standards for Nuclear Power Operation.

l The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to site boundary of radioactive materials in gaseous and liquid effluents made during

- the reporting period.

With the quantity of radioactive material in any

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outside tank exceeding the limit of Specification 3.8.D.1, describe the events leading to l

this condition in the next Annual Radioactive Effluent Release Report.

If inoperable radioactive liquid effluent monitoring.

instrumentation is not returned to operable status prior to the next release pursuant to Note 4 of 4

l Table 3.9.1, explain in the next Annual Radioactive Effluent Release Report the reason (s) for delay in correcting the inoperability.

If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9w2, l

explain in the next Annual Radioactive Effluent Release Report the reason (s) for delay in correcting the inoperability.

With milk samples no longer available from one or more of the sample locations required by Table 3.9.3, identify the cause(s) of the sample (s)~no longer being available, identify the new location (s) for obtaining available replacement samples, and include revised CDCM figure (s) and table (s) reflecting the new-l' location (s) in the next Annual Radioactive Effluent 4

Release Report.

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With a land use census identifying one or more locations which yield at least a 20 percent greater dose or dose cossaitment than the values currently being calculated in specification 4.8.0.1,l identify l

the new location (s) in the next Annual Radioactive Effluent Release Report.

l Changes made during the reporting period to the j

Process Control Program (PCP) and to the off-site Dose Calculation Manual (ODCM), shall be identified in the l

next Annual Radioactive Effluent Release Report.

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Amendment No. &&, 96, 144 272 i

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l 6.10 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT A program to reduce leakage from systems outside containment that j

would or could contain highly radioactive fluids during a serious j

transient.or accident to as low as practical levels will be

-1 implemented. This program shall include the following:,

A.

Provisions establishing preventive maintenance and periodic visual inspection requirements.

O B.

System leakage inspections, to the extent permitted by system t$esign and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals. The systems subject to this testing ares (1) Residual Heat

-Removal, (2) Core Spray, (3) Reactor Water Cleanup, (4) HPCI, (5) RCIC, and (6) sampling systems.

6.11 IODINE MONTTORING A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

• under accident conditions will be implemented. This program shall include the-following

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Training of personnel.

B.

Procedures for monitoring.

C.

Provisions for maintenance of sampling and analysis equipment.

6.12 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.

A.

Licensee initiated changesJco the PCP:

1.

Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made. This suksmittal shall contain:

4 a.

sufficiently detailed information to support the rationale for the change without benefit of additional or supplemental information.

i b.

A determination that the change'did not reduce the i :

overall conformance of the dewatered spent-resins / filter media waste product to existing criteria for solid waste shipments and disposal.

c.

Documentation of the fact that the change has been reviewed by PORC and approved by the Manager of Operations (Moo).

2.

shall become effective upon review by PORC and approval by the Manager of operations (Moo).

• Areas requiring personnel access for establishing hot shutdown conditions.

W 277 Amendment No. G, H, M,

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6.13 OFF-SITE DOSE CALCULATION MANUAL (CDCM)

An Off-Site Dose Calculation Manual shall contain the current methodology and parameters used in the calculation of off-site doses due to radioactive gaseous and liquid offluents, in the calculation of gaseous and liquid effluent monitoring al, arm / trip setpoints, and in the conduct of the environsnental radiological monitoring program.

A.

Licensee initiated changes to the ODCM 1.

Shall be sukuaitted to the comunission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This suksmittal shall contain:

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- Sufficiently detailed information to support the a.

-rationale for the change without benefit of

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additional or supplesmental information.

Information suksnitted should consist of a package of those pages of the ODCM which were changed with each page numbered and provided with the revision nusaber, together with appropriate analyses or evaluations justifying the change (s).

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or.

setpoint determinations.

A Documentation of the fact that tho' change has been c.

reviewed by PORC and approved by the Manager of Operations (M00).

2.

Shall become effective upon review by PORC and approved by the Manager of operations (M00).

6.14 MAJOR C)ANGES TO RADI0 ACTIVE LIQUID, GASEQUS, AND SOLID WASTE

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TREATHEDT SYSTEMS

• Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):

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A.

Shall be reported to the Coussission in the Annual' Radioactive Effluent Release Report for he period in which the evaluation was reviewed by the PORC. The discussion of etch change shall contains 1.

A sununary of the evaluation that led to the deternination that the change could be made in accordance with 10CFR Part 50.59; i

2.

Sufficient detailed information to support the reason for the change without benefit of additional or il supplemental information; 3.

A detailed description of-the equipment, components, and processes involved and the interfaces with other plant systems;

• Licensee may choose to mutanit the informatien called for in this Specification as part of the annual FSAR update.

Amendment No. 44, M, 4M 144 278 i

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