ML20148J465
| ML20148J465 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/20/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148J469 | List: |
| References | |
| NUDOCS 8801270431 | |
| Download: ML20148J465 (11) | |
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- tog'o UNITED STATES
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VERMONT YANKEE NUCLEAR P01/ER CORPORATTON DOCKET NO 50-271 VERMONT YANKEE NUCLEAR PONER STATION AMENDMENT TO FACILITY OPEP.ATING LICENSE Amendment No. 103 Licensa No. DPR-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated January 24, 1986 as supplemented May 13, 1986, Ju*ne 9, 1986, January 16, 1987, and February 2, 1987 ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) ard the Commission's rules and regulations set forth in 10 CFR Chapter I; l
B.
The facility will ocerate in conformity with.the apolication, the provisiens of the Act, and the rules and regulations of the Commission
- C.
There is reasonable assurance (i) that the activities authorized by this amendmant can be conducted without endangerina the health and j
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 inimicel to the cmmon i
defense and security or to the health and safety of the public; and l
E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Conmission's reculations and all applicable requirements hava been satisfied.
2.
Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. OPR-28 is hereby amended to read as follows:
8801270431 880120 PDR ADOCK 05000271 P
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-t-(D)
Technical Soecifications The Technical Specifications, contained in Accendix A, as revised j
thrauch Amendment No. 103, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION bY Richard H. Wessnan, Actina Director Pro.iect Directorate I-?
Division of Reactor Pro.iects I/II
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
January 20,1988
F.
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ATTACHMENT TO LICEf!SE A?!ENDi1 eft NO. 103 FACIl.ITY OPERATING LICEflSE fl0. DPR-23 DOCKET NO. 50-271 Replace the followine peces of the Accendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendnent nunber and contain vertical lines indicatina the areas of chance.
Tha corresponding overleaf paces are provided to maintain docurent completeness.
Renove Paaes Insert Paaes 4a 4a 66 66 166 166 167 167 168 168 169 169 172C 17?C 718 218 1
i l
VYNI'S UB.
Souree Check - The qualitative assessment of CG.
Deleted channel response when the channel sensor is exposed to a, radioactive source.
CC.
Dose Equivalent 1-131 - The dose equivalent 1-131 till.
Deleted shalI be that concentration of 1-131 (mi c rocu rie/ r,r mn ) which alone would produce the same thyroid dec:e as the quantity and fsotopic mixture of 1 151, 1-132, 1-133, 1-134 and I. 13',
actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in NRC Hegulatory Guide 1.109, Revision 1, October 1977.
DD.
Solidificati-Solidification shall be the conversion of mt wastes into a form that meets shipping and burial ground requirements. Suitable forms include dewatered resins and filter sludges.
EE.
Memberls) of the public - Members of the public shall include all persons who are not occupationally associated with the plant.
This category does not include employees of the II.
Off-Site Dose Calculation Manual (ODCM1 - A manual
- utility, its contractors or vendors. Also containing the current methodology and parameters excluded f rom this category are casual visitors t o used in the calculation of off-site doses due to the plant and persoas who enter the site to radioactive gaseous and liquid effluents, in the service equipment or to make deliveries.
calculation of gaseous'and liquid effluent monitoring alarm / trip setpoints, and in the FF.
Site Boundary - The site boundary is shown in conduction of the environmental radio?ogical Figure 2.2-5 in the FSAR.
monitoring program.
4a Amendment No. F/,103
~
VYNpS 3.2 (Continued) standby gas ' treatment system operation so t hat none of the activity released during the refueling accident leave the reactor 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 ventil,ation isolation and standby gas treatment system operation at a radiation. level equivalent to the maximum site boundary dose rate of 500 mrem / year as given in Specification 3.8.E.1.n.
The monitoring system in f
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.
4.2 PROTECTIVE INSTRUMENTATION The protective instrumentation systems covered by this Specification are listed in Table 4.2.
Most of these protective systems are composed of two or more independent and redur. dant subsystems which are combined in a dual-channel arrangement.
Each of these subsystems contains an arrangement of electrical relays which operate to initiate the required system protective action.
The relays in a subsystem are actuated by a number of means, including manually-operated switches, process-operated switches (sensors), histable devices operated by analog sensor signals, timers, limit switches, and other relays.
In most cases, final subsystem relay actuation is obtained by satisfying the logic conditions established by a number of these relay contacts in a logic array. When a subsystem is actuated, the final subsystem relay (s) can operate protective equipment, such as valves and pumps, and can perform other protective actions, such as tripping the main turbine-generator unit.
With the dual-channel arrangement of these subsystems, the single f ailure of a ready circuit can be tolerated because the redundant subsystem or system (in the case of high pressure coolant injection) will then initiate the necessary protective action.
If a failure in one of these circ its occurs in such a way that an action is taken, the operator is immediately alerted to the failure.
If the failure occurs and causes no action, it could then remain undetected, causing a loss of the redundancy in the dual-channel arrangement.
Losses in redundancy of this nature are found by periodically testing the relay circuits in the subsystems to assure that they are operatinn properly.
It has been the practice in boiling water reactor plants to functionally test _ protect.ive instrumentation sensors and sensor relays.on.line on a monthly. frequency. Since logic circuit tests result in the actuation of plant equipment, testing of this nature was done while the plant. was. shut down for refueling.
In this way, the testing of equipment would not jeopardize plant operation. Ilowever, a refueling interval could be as long as eighteen months, which is too long a period to allow an undetected failure to exist.
Amendment No. Hy,103 g
VYNPS TABLE 3.9.2 CASEOtIS EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Cha_nnels Operable Notes 1.
Steam Jet Air Ejector (SJAE) a.
Noble Gas Activity Monitor 1
7,8,9 2.
Augmented Off-Gas System Noble Gas Activity Monitor Between the Charcoal Bed 1
2, 5, 6, 7
a.
System and the Plant Stack (Providing Alarm and Automatic Termination of Release)
I b.
Flow Rate Monitor 1
1,5,6 1
3,5,6 c.
Ilydrogen Monitor 3.
Plant Stack a.
Noble Gas Activity Monitor 1
5, 7, 10 b.
Iodine Sampler Cartridge 1
4, 5
c.
Particulate Sampler Filter 1
4, 5 1
1, 5 d.
Sampler Flow Integrator e.
Stack Flow Rate Monitor 1
1, 5 Amendment No. pp,103 166
e e
a VYNI'S TAllLE _342 (continued) l TAlli.E NOTATION NOTE 1 With te number of channels operable less than required by the minirmam channels operable requirement, effluent releases via this pathway may continue provided the flow rate is est imated at.. least once per 4 hours. NOTE 2 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue for a period of up to 7 days provided that at. laast one of the stack monitoring systems is operable and ofI-gas system temperature and pressure are measured continuous 1y. NOTE 3 With the number of channels operable less than required by the minimum channels operable requirement, operation of the AOC System may continue provided gas samples are collected at least once per 24 hours and analyzed within the following 4 hours, or an orderly transfer of the of f-gas ef fluents from t.he operating recombiner to the standby recombiner shall be made. NOTE 4 With the number of channels operable less than required by the minimum channels operable requirement, ef fluent releases via the af fected pathway may continue provided samples are cont.inuously collected with auxiliary sampling equipment.. NOTE 5 With the naur.bor of channels operable less than required by the minimum channels operable requirement, exert. reasonable ef forts to return the instrument (s) to operable status within 30 days. NOTE 6 During releases via this pathway. NOTE 7 The alarm / trip setpoints of these channels shalI be determined and adjusted in accordance with the methodology and parameters in the Of f-site Dose Calculation Manual (ODCM). With a gaseous process or effluent monitoring instrumentsition channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.8.E.1.a and 3.8.K.I'are met, immediately take actions to suspend the release of radioactive gaseous ef fluents monitored by the af f ected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative. Amendment No. /VS, 103 167 i
s e i VYNPS TABLE 3.9.2 (continued) TABLE NOTATION NOTE 8 fli n imupt channels -operabic required only during operation of the Steam Jet Air Ejector. NOTE 9 With the number of channels operable less than required by the minimum channels operable requirement, r,ases f rom the SJAE may be released to the environment for up to 12 hours provided: 1. The AOG System is not bypassed; and 2. The AOG System noble gas activity monitor is operable. NOTE 10 - With the number of channels operable less than required by the minimum channels operable requirement, offluent releases via this pathway may continue provided grab samples are-taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. i 4 4 6 4 Amendment No. y/,103 168 6
8 VYNPS TABLE 3.9.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway' a Type and Frequency and/or Sample Number of Sample Locations Sampling and Collection Frequency of Analysis 1. AIRBORNE a. Radioiodine and Samples from S locations: Continuous operation of sampler Radioiodine Particulates with sample collection semimonthly canister: Analyze 1 sample from up valley, or more frequently as required by each sample for within 4 miles of Site dust loading or plant effluent I-131. Boundary. releasesh. Particulate sampler: (major wind direction) Gross beta radioactivity 1 sample from down valley, analysis on each-within 4 miles of Site sample following Boundary. filter change. C (major wind direction) Composite (by location) for gamma 1 sample each from the vicinity isotopied at least of two nearby communities, once per quarter. within 10 miles of Site Boundary. 1 sample from a control location. Amendment No. 7,3, 103 169 ~ e A
VYNPS e TABI.E 3.9.4 a HEPORTIUC LEVELS FOR HADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAI. SAMPl.ES(a) Heporting Levels Water Airborne PacLiculate Fish Milk Vegetation Sediment Analysis (pCL/1) or Cases (pC1/m3) (pC1/Kg. wet) 1pC1/11 1pC1/KR. wet) {pci/Kn, dry) 2 x 10 (b) '4 11 - 3 Mn-S4 1 x 10 3 x 10 Fe-59 4 x 10 1 x 10 Co-58 1 x 10 3 x 10 Co-60 3 x 10 1 x 10 3 x 10 (c) 2 4 3 In-65 3 x 10 2 x 10 Zr-Nb-95 4 x 10 1-131 0.9 3 1 x 10 Cs-134 30 10 1 x 10 60 1 x 10 Cs-137 50 20 2 x 10 10 2 x 10 3 x 10 Ba-l.a-140 2 x 10 1 (a) Reporting levels may be averaged over a calendar quarter. When more than one of the radionuclides in Table 3.9.4 are detected in the sampling medium, the unique reporting requirements are not exercised if the following condition holds: concentration (1) concentration (2) + 4 1*O* ~~~ reporting level (1) reporting level (2) ~ When radionuclides other than those in Table 3.9.4 are detected and are the result of plant effluents, the potential annual dose to a member of the public must be less than or equal to the calendar year limits of Specifications 3.8.B. 3.8.E and 3.8.F. 4 Heporting level for drinking water pathways. For nondrinking water pathways, a value of 3 x 10 pCi/L may be (b) used. '( c ) Heporting level for individual grab samples taken at North Storm Drain Outfall only. ~ 172c Amendment No. 64, 103
VYNPS e 1. Shall be submitted to the Commission in the semiannual Effluent Release Report for the period in which the change (s) was made. This submittal shall contain: 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 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 (M00). 2. Shall become effective upon review by PORC and approval by the Manager of Operations (M00). 6.13 0FF-SITE DOSE CALCULATION MANUAL (ODCM) 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 effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radiological monitoring program. A. Licensee initiated changes to the ODCM: 1. Shall be submitted to the Commission in the semiannual Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: Sufficiently detailed information to support the rationale for the change without benefit a. of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM which were changed with each page numbered and provided with the revision number, 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. dmendm'nt No. et3, HA, 97,103 e 218 .~ 9 -a . - -}}