ML20198H439

Proposed Radiological Effluent Tech Specs,Permitting Incineration of Contaminated Oil in Equipment,Revising Table 3.9.2, Gaseous Effluent Monitoring Instrumentation & Adding Limits in Tech Spec 3.8.G.1.a

ML20198H439
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/24/1986
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20198H428	List: ML20198H424 ML20198H439
References
NUDOCS 8601310027
Download: ML20198H439 (14)

Text

ATTACHMENT A Proposed Amended Technical Specification Pages 4a, 66, 152, 160a, 160c, 166, 168 and 169. (Page 167 provided for information only) 9601310027 060124 PDR ADOCK 05000271 P PDR

VYNPS BB. Source Check - The qualitative assessment of CG. Deleted channel response when the channel sensor is exposed to a radioactive source.

CC. Dose Equivalent I-131 - The dose equivalent 1-131 HH. Deleted 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, 1-132, 1-133, 1-134 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. Member (s) of the Public - Members of the public shall include all persons who are not I

occupationally associated with the plant. This category does not include employees of the II. Off-Site Dose Calculation Manual (ODCM) - A manual utility, its contractors or vendors. Also containing the current methodology and parameters excluded from this category are casual visitors to used in the calculation of off-site doses due to the plant and persons 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 radiological Figure 2.2-5 in the FSAR. monitoring program.

Amendment No. 83 4a

VYNPS 3.2 (Continued) standby gas treatment system operation so that 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 ventilation 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.a. The monitoring system in l

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 redundant 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), bistable 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 failure 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 circuits 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 operating properly.

It has been the practice in boiling water reactor plants to functionally test protective 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. However, 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. 83 66

VYMPS 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS G. Gaseous Effluents: Dose from Iodine-131. G. Gaseous Effluents: Dose from Iodine-131.

Iodine-133. Tritium, and Radionuclides in Iodine-133. Tritium, and Radionuclides in Particulate Form Particulate Form

1. The dose to a member of the public from 1. Cumulative dose contributions for the Iodine-131. Iodine-133, tritium, and total time period shall be determined in radionuclides in particulate form with accordance with the methods in the ODCM i half-lives greater than 8 days in at least once every month.

gaseous effluents released from the site to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter:

less than or equal to 7.5 arem to any organ, and

b. During any calendar year:

less than or equal to 15 mrem to any organ.

c. Less than 0.1% of the limits specified in 3.8.G.I.a and b as a result of burning contaminated oil.

H. Gaseous Radwaste Treatment H. Gaseous Radwaste Treatment

1. The Augmented Off-Gas System (AOG) shall 1. The readings of the relevant instrument be used in its designed mode of shall be checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the operation to reduce noble gases in main condenser SJAE is in use to ensure gaseous waste prior to their discharge that the AOG is functioning.

whenever the main condenser steam jet air ejector (SJAE) is in operation.

Amendment No. 83 152

VYMPS TABLE 4.8.2 (continued)

RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Mir.imum of Detection Sampling Analysis Type of Activity (LLD)

Gaseous Release Type Frequency Frequency Analysis (uci/ml)"

C. Continued Continuous e Once per Sr-89, Sr-90 1 x 10-11 quarter Composite Particulate Sample Continuous Noble Gas Noble Gases 1 x 10-5 Monitor Gross Beta or Gamma D. Incinerated Oil & Prior to each Prior to each Principal Canna 5 x 10-7 I

release release Emitters d (for particulate emissions only)

Grab sample h I-131 1 x 10-6 i

H-3 1 x 10-5 i

Amendment No. 83 160a

VYMPS TABLE 4.8.2 (continued)

TABLE NOTATION

f. The gascs * <aste sampling and analysis program does not explicitly require sampling and analysis at a specified LLD to a.d $ne the I-133 release. Estimates of I-133 releases shall be determined by counting the weekly charcoal *w le for I-133 (as well as I-131) and assume a constant release rate for the release period.

g. Incinerated oil may be discharged via points other than the plant vent Stack (e.g., auxiliary boilers),

h. The grab sample taken praor to release shall be of the oil in liquid form, and be repre.2entative of the contaminated oil to be incinerated.

i Amendment No. 83 160c

VYWPS TABLE 3.9.2 CAST 00S EFFLUENT MONITORING INSTRUtWNTATION Instrument Minimum Channels Operable Notes

1. Steam Jet Air Ejector (SJAE)

a. Noble Gas Activity Monitor 1 7, 8, 9

2. Augmented Off-Cas System

a. Moble Gas Activity Monitor Between the Charcoal Bed 1 2, 5, 6, 7 System and the Plant Stack (Providing Alarm and Automatic Termination of Release)

b. Flow Rate Monitor 1 1,5,6

c. Hydrogen Monitor 1 3, 5, 6

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

d. Sampler Flow Integrator 1 1, 5

e. Stack Flow Rate Monitor 1 1, 5 Amendment No. 83 166

.~.

I 1 VYNPS l

TABLE 3.9.2 l

(continued)

TABLE NOTATION 1

I NOTE 1 -

With the nu- e of channels operable less than required by the minimum channels operable requirement, effluent rel.2ses via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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 least one of the stack monitoring systems is operable and off-gas system temperature and pressure are measured continuously.

NOTE 3 -

With the number of channels operable less than required by the minimum channels operable requirement, operation of the AOG System may continue provided gas samples are collected at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or an orderly transfer of the off-gas ef fluents from the 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, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment.

NOTE S -

With the number of channels operable less than required by the minimum channels operable requirement, exert reasonable efforts 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 shall 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 instrumentation 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.1 are met, immediately take actions to suspend the release of radioactive gaseous ef fluents monitored by the af fected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

Amendment No. 83 167

1 VYNPS TABLE 3.9.2 (continued) ,

TABLE NOTATION NOTE 8 -

Minimum channels operable 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, gases from the SJAE may be released to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided:

1. The AOG System is not bypassed; and

2. The A0G System noble gas activity monitor is operable.

NOTE 10 - With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 I

l l

Awndx nt No. 83 168 l

l l

i _ _ _

- - _ - - .. -, . _ _ - .~ . - . . - . - . - _ . .- ._. - . - . - _ . _ - _

O O e

I YYMPS TABLE 3.9.3 j RADI_O*EICAL ENVIROOMENTAL MONITORING PROGRAM i

j F -r E w rc PathwaF a Type and Frequency l _ and/or 54 Q1e Number of Salele Lac 2tions_ Sampling and Collection Frequency of Analysis j I. AIR 906tNE I

j q a. R diciodine and Sa:nples from 5 locatic,ns: continuous operation of sampler Radiolodine i

Partientates with sample collection semimonthly canister: Analyze

I sasple from up valley. or more frequently as required by each sample for (major wind direction) dust loading or plant effluent 1-131.

j releasesh. Particulate sampler:

j 1 surple from down valley. Cross beta j (major wind direction) radioactivity j 4 analysis on each

1 sample each from the vicinity sample following i of two nearby conmunitics. filter change c,

Composite (by I 1 sample from a control location) for gamma I

) location. isotopled at least l once per quarter.

1 I

l i

1 l

j A m *sent No. 83 169 4

j I

1 i,

, ,-,__.,_,.---,,._-.,---w - - - - - - - . -er--- --*-

1 ATTACHMENT B Revision 1 Pages 4-1, 4-1A and 4-1B to the Vermont Yankee Offsite Dose Calculation Manual (ODCM)

l ~

4.0 ENVIRONMENTAt. MONITORING PROGRAM The radiological environmental monitoring stations are listed in Table

! 4.1. The locations of the stations with respect to the Vermont Yankee plant are shown on the maps in Figures 4-1 to 4-6.

l 4.1 Intercomparison Prooram All routine radiological analyses for environmental samples are l performed at the Yankee Environmental Laboratory. The Laboratory participates l in the U.S. Environmental Protection Agency's Environmental Radioactivity l Laboratory Intercomparison Studies Program for all the species and matrices routinely analyzed.

4.2 Airborne Pathway Monitorina The environmental air sampling program is designed around several major

, objectives, including sampling air in predominant up-valley and dcwn-valley 1

wind directions, and sampling air in nearby communities and at a proper control location, while maintaining continuity with two years of preoperational data and 13 years of operational data (as of 1985). The chosen air sampling locations are discussed below.

10 assure that an unnecessarily f requent relocation of samplers will l

not be required due to short-tenn or annual fluctuations in meteorology thus l incurring needless expense and destroying the continuity of the program, long term, site-specific ground level 0/05 (5-year averages - 1978 through 1982) were evaluated in comparison to the existing air monitoring locations to determine their adequacy in meeting the above-stated objectives of the program and the intent of the NRC general guidance. The long-term average meteorological data base precludes the need for an annual re-evaluation of air sampilng locations based on a single year's meteorological history.

1 1

Revision 1 Approved by:

4 -1 l

l

The Connecticut River valley in the vicinity of the Vermont Yankee plant has a pronounced up- and down-valley wind flow. Based on five years of meteorological data, wind blows into the 3 "up-valley" sectors (N, NNW, NW) 27 percent of the time, and the 4 "down-valley" sectors (S. SSE, SE, ESE) 49 percent of the time, for a total "in-valley" time of 76 percent. Station AP/CF-12 (NNW, 3.6 km) in North Hinsdale, NH, monitors the up-valley sectors.

It is located in the sector that ranks fourth overall in terms of wind f requency (i.e., in terms of how of ten the wind blows into that sector), and is approximately 0.5 miles from the location of the calculated maximum ground level D/Q (i.e., for any location in any sector, for the entire Vermont Yankee environs). This station provides a second function by its location in that it also monitors North Hinsdale, NH, the community with the second highest ground level D/Q for surrounding communities, and it has been in operation since the preoperational period.

The down-valley direction is monitored by two stations - at River Station Number 3.3 ( AP/CF-11. SSE,1.9 km) and at Northfield, MA ( AP/CF-14, SSE, 11.3 km). They both reside in the sector with the maximum wind f requency and they bound the down-valley point of calculated maximum ground level D/0 (the second highest overall ground level D/0 for any location in any sector).

Station AP/CF-il is approximately one mile f rom this point, between it and the plant. Station AP/CF-14 also serves as a community monitor for Northfield, MA. Both stations have been in operation since the preoperational period.

In addition to the up- and down-valley locations, two communities have been chosen for connunity sampling locations. The four nearest population groups with the highest long-term average D/0 values, in decreasing order, are Northfield, MA; North Hinsdale, NH; Brattleboro, VT; and Hinsdale, NH. The community sampler for Northfield is at Station AP/CF-14 (mentioned above).

North Hinsdale is already monitored by the up-valley station (AP/CF-12, NNW, 3.6 km), which also indirectly monitors the city of Brattleboro, located further out in the same sector. The second sampler specifie. ally designated for a community is 49 Hinsdalerjubstation ( AP/CF-13, E, 3.1 km) in Hinsdale.

i Revision 1 Approved by:

i 4-1A f I

The control air sampler was located at Spof ford Lake (AP/CF-21, NNE, 16.1 km) due to its distance from the plant and the low frequency for wind blowing in that direction based on the long-term (5 year) meteorological history. Sectors in the general west to southwest direction, which would otherwise have been preferable due to lower wind frequencies, were not chosen since they approached the region surrounding the Yankee Atomic plant in Rowe, MA.

An additional air sampler is maintained at the Tyler Hill site (AP/CF-15, WNW, 3.4 km), which is along the western side of the valley in general proximity of historical dairy operations. (This sixth location is not a specific Technical Specification requirement.)

/

Revision 1 Approved by:

4-1B

.