ML20083K174

Revised Pages to Proposed Radiological Effluent Tech Specs, Change 7 Re Automatic Containment Isolation Valves

ML20083K174
Person / Time
Site:	Cooper
Issue date:	04/10/1984
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20083K154	List: ML20083K151 ML20083K174
References
TAC-08140, TAC-8140, NUDOCS 8404160089
Download: ML20083K174 (4)

Text

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3. All automatic containment isolation valves are operable or de-activated in the isolated position .

4. All blind flanges and manways are closed.

P.A Purge - Purging - Purge or Purging is the controlled process of discharging air or gas from a confinement to establish temperature, pressure, humidity, concentra-tion or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

P.B Process Control Program - The Process Control Program outlines the solidification of radioactive waste from liquid systems. It does not substitute for station operating procedures, but provides a general description of equipment, controls, and practices to be considered during waste solidification to assure solid wastes. ,

Q. Rated Power - Rated power refers to operation at a reactor power of 2381 megawatts thermal. This is also termed 100% power and is the maximum power

' level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power. Design power, the power to which the safety analysis applies, is 104.4% of rated power (105% of rated steam flow), which corresponds to 2486 megawatts thermal.

R. Reactor Power Operation - Reactor power operation is any operation with the mode switch in- the "Startup/ Hot Standby" or "Run" position with the reactor critical and above 1% rated pcwer.

S. Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steam space detectors.

T. Refueling Outage - Refueling outage is the period of time be. tween the shutdown of the unit prior to a refueling and the startup of the plant after that refueling.

IU. Safety Limits _The safety limits are limits within which the reasonable maintenance of the fuel. cladding integrity and-the reactor coolant system

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integrity are assured. Violation of such a limit is,cause for unit shut- ,

down and_ review-by the' Nuclear Regulatory Commission before resumption of unit operation. Operation beyond such a limit may not in itself result in serious consequences but it indicates an' operational deficiency subject to regulatory, review.

.V. . ' Secondary Containment Integrity - Secondary containment' integrity means

_ that the reactor building is intact and - the following conditions are met:;

[ 1. At'least one door'in each access opening is closed.

2.. .The. standby gas treatmant system is operable.

A11' automatic ventilation system' isolation-valves are. operable or

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3.

secured in:the isolated position.

W., Shutdown - The reactor is'in a shutdown condition when the mode switch-is .in the " Shutdown ~ or " Refuel" ~ position.-

' 1. . ' Hot Shutdown means conditions as above with reactor coolant' Jtemperature greater than 212*F.

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2.- ' Cold Shutdown means~ionditions as'above'with' reactor coolant

. temperature' equal to or less'than.212*F and the reactor vessel vented.1

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TABL'E 3.21.F.1 (CONTINUED)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Exposure Pathway . Number of Sampling and Type and Frequency and/or Sample Sample Stations ' Collection Frequency of Analysis

4. Ingestion' ,

'a. Milk At least'one location At least once ger 15 days during Peak Gamma isotopic and I-131 (Nearest Pasture Period ; at least once per analysis of each sample.

Producer)' 31 days at other times,

b. Milk- At least 2 locations At least once per 92 days.- Gamma-isotopic and I-131 (Other analysis of each sample.

Producers) b

c. Fish .At least 2 locations Two cimes per year (once in the Gamma isotopic analysis on summer and once in the fall). edible portions.

s Attempt to include the following:

1. Bottcm feeding species Q '

.g- 2. Middle-Top feeding species b

d.' Food. Samples of.three dif- Monthly when available. Gamma isotopic and I-131 1 Products .ferent kinds of broad analysis.

leaf vegetation grown-nearest each of.two

.different offsite locations of. highest predicted annual

. average ground-level D/Q if milk sampling is not performed.

One sample of each of Monthly when available. Gamma isotopic and I-131 the similar broad leaf analysis.

vegetation grown 15-30

.km distant in the least prevalent wind. direction

.if milk sampling is not

. performed.-

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NOTES FOR TABLE 3.21.F.1

a. DELETED

b. Ge(L1) gamma isotopic analysis refers to high resolution Ge(Li) gamma spectrum analysis as follows: the sample is scanned for gamma-ray activity. If no activity is found for a selected nuclide, the detection sens.itivity for that nuclide will be calculated using the counting time, detector efficiency, gamma energy, geometry, and detector background appropriate to the particular sample in question. The following nineteen (19) nuclides shall be analyzed for routinely:

Be-7 Ru-103 Ce-144 K-40 Ru-106 Ra-226 Mn-54

• I-131 Th-228 Fe-59 Cs-134 Co-58 Cs-137 Co-60 BaLa-140 Zn-65 Ce-141 Zr-95 Nb-95 Any radionuclide detected, i.e., ha"',3 a measured concentration greater than the LLD, whether or not it is one of the 19 nuclid o listed above, shall be regarded as present in the sample.

c. Thermoluminescant Dosimeters (TLD) is a single phosphore. Two or more phosphores in one package are considered to be two or more dosimeters.-

d. Peak Fasture Period is June 1 through September 30 of each year.

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. u 6.6 Environmental Qualification A. By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:

Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 " Interim Staf f Position on Environmental Qualification of Safety-Related Electrical Equipment", December 1979.

Copies of these documents are attached to Order for Modification of License DPR-46 dated October 24, 1980.

B. By no later than December 1, 1980, complete and auditible records must be available and maintained at a central location which describe the

, environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.7 Systems Integrity Monitoring Program A program shall be established to reduce leakage from systems outside the primary containment that would or could contain highly radioactive fluids during a serious accident to as low as pracrical levels. This program shall include provisions establishing preventive maintenance and periodic visual inspection requirements, and leak testing requirements for each system at a frequency not to exceed refueling cycle intervals.

6.8 Iodine Monitoring Program

-A' program shall be established to ensure that capability to. accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include training of personnel, procedures for monitoring and provisions for maintenance of sampling and analysis equipment.

' 6. 9. Process Control Program (PCP) 6.9.1 The PCP shall be a manual detailing the program of sampling, analysis-and formulation determination by which SOLIDIFICATION of. radioactive waste.from liquid systems is assured consistent

.vith Specification 3.21.E and-the surveillance requirements of.

these Technical Specifications.

6.9.2 District Initiated Changes .

. A. 'Shall be submitted to the Commission by inclusion in the

' Semiannual Radioactive Material Release Report for the period in which the' change (s) was made effective and shall contain:

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1. Sufficiently detailed information to totally support.the' rationale for the changeJwithoutibenefit of additicnal or supplementa1'information; I: j2. . A~ determination that-the change did not-reduce'the overall conformance.of the solidified waste product'to' existing

. . criteria for' solid wastes; Land 3., Documentation,of the fact that thel

! change has been reviewed' and found acceptable by;the SORC.

B. 1Shall become effective upon, review and a'cceptance by the SORC.

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ATTACHMENT 2 PROCESS CONTROL PROGRAM FOR Cooper Nuclear Station June 7, 1982 O

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PROCESS CONTROL PROGRAM INTRODUCTION This Process Control Program outlines the solidification of radioactive waste from liquid systems at Cooper Nuclear Station. It is not intended to be a substitute for station operating procedures, but to provide a general description of equipment, controls, and practices to be considered during waste solidification. Station operating procedures will provide detailed instructions as to the actual operation during the solidification process.

CLASSIFICATION OF TERMS This Process Control Program Document describes the process used to solidify wet wastes. Wet wastes are those wastes produced from the liquid radwaste treatmsnt system. These vastes may be typically described as spent resins (bead and powdex), filter material, waste sludges, and evaporator concentrates. The solidification of these wastes as defined is the conversion of radioactive wastes from liquid systems to a solid, which is as uniformly distributed as reasonably achievable, with definite volume and shape, bounded by a stable surface of distinct outline on all sides. The solidification of the wastes mentioned above is achieved with equipment installed at CNS and this equipment operated in accordance with CNS operating procedures. Those wastes which progress through the process system, fill, mix, and capping stations will normally meet the solidification criteria. Those wastes that deviate from the normal operation, needing special technique, such as hand-mixing, material injection by manipulator or hand, etc., will be as uniformly distributed as reasonably achievable. Keeping exposures ALARA and physical makeup of the material to be solidified will be the governing considerations in determining what is reasonably achievable.

The radwaste solidification process will be operated on a batch basis. A batch will consist of all the resulting continuous drums processed from the contents of a single source. An example would be the sludge from a condensate phase separator solidified in a continuous drumming operation until the phase separator is empty or the batch is terminated.

Radioactive vastes from liquid systems processed on a batch basis for solidification will normally be, but not limited to, the condensate phase separators, reactor water cleanup phase separators, waste sludge tank, spent resin tank, or concentrated waste tank.

OPERATION Wastes to be solidified will normally be from the condensate or reactor water cleanup phase separators, vaste eludge tank, or spent resin tank. These wastes are routed through the centrifuge units. - Af ter dewatering in the centrifuge, vastes then enter a stcrage. hopper. ' Wastes at this step will vary from a fairly ' dry granular consistency to a wet putty-like consistency depending.upon the source material; filtered sludges, filter material, resins, etc. Department of Transportation 17H . specification 55-gallon' drums containing cement are - then transferred under the hopper and filled with vastes. The drum then progresses to the mixing section.

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l The in-drum mixer mixes the cement and waste materials. Water is then added to the mixture in quantities to ensure solidification. Because of the varying degree of wetness from one batch to the next, periodic visual inspection of the first few drums is necessary to determine ene correct amount of water needed. After the amount of water to achieve soJidification has been determined, it may be added automatically by the mixing program.

After mixing has been achieved, radiation levels of each drum is taken. The drum is then transferred to the drum storage lines.

The drumming operation will be continuous, centrifuging, and drumming until the source, phase separators, or tanks are emptied or the batch terminated. '

After at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the drums are taken from the storage line to the capping station. Here the drum is visually inspected for freestanding water.

If the material is solid and no freestanding water is present, the drum is capped. If it is not solidified or freestar. ding water is present, cement may have to be added or the drum is put back on the storage line to cure. After capping, the drum is washed to remove contamination. The capped drum is then taken to the storage line. Prior to shipment, the drums will be taken to the smear station and checked'for contamination levels.

The third or fourth drum of each batch will be sampled prior to the mixing station. This sample is considered representative of that batch. The sample is taken to the Radiochemistry Laboratory for analysis.

PARAMETERS AND TESTING Two cubic feet of cement will be added to each 55-gallon 17H specification d rum. It has been demonstrated that this volume of cement with the remaining drum volume being powdex resins, powdex filter material, sludges, etc., and water will achieve solidification.

After the material to be solidified has been added to the drum, a sample of this material, considered to be representative of that batch, will be taken.

This sample will be analyzed for pH. It has been demonstrated that, if the material to be solidified has a pH value within the range of 2 to 13, the solidification process will not be affected. This sample is also isotopically analyzed to determine isotope distribution. By comparing this isotopic distribution and radiation readings on each drum, the total concentration of the radionuclides present can be determined, also any carry-over from ~ the previous batch or changes in the amount of solidified material may be taken into account.

'Because of the variation in water content of the material af ter being centrifuged (dry to paste-like consistency), varying amounts of water will be added during the mixing stage. The first few drums will provide'a basis for determining the correct amount of water to be'added to each drum of the batch.

This will be done visually and with mixer torque indications. Once.the amount of water needed for solidification has been determined, this amount of water will be edded to each drum by the automatic mixing sequence controls.

At least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after mixing and prior to capping, each drum ~ is ' visually '

-inspected. ~ This provides assurance that no freestaading water is present and that the radwaste material has been solidified.

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REPORTS The volume = and curie content of wet wast'es solidified at Cooper Nuclear Station _ will be documented in the . Station Semiannual Reports. This information will be in the format outlined in Regulatory

• Cuide 1.21 Revision 1, Table 3.

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