ML20209F037

Proposed Tech Specs,Correcting Typos,Adding Figure & Revising Definitions Section

ML20209F037
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/02/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20209F021	List: B11594, Revised Application for Amend to License DPR-61,correcting Typos,Adding Figure & Revising Definitions Section of Tech Specs Submitted w/850529 Application ML20209F037
References
NUDOCS 8507120376
Download: ML20209F037 (10)

Text

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.s Attachment 1 Corrections to the Haddam Neck Proposed Radiological Technical Specifications I

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Change-Out Instructions REMOVE INSERT

1. Remove existing " Definition" Insert 3 correctly revised " Definition" section pages (3) included in pages 1-Sa, b and c.

the beginning of Attachment 5.

2. N/A After pages B3/411-1 of the Haddam Neck Plant RETS (Attachment 5),

insert Figure 5.1-1.

3. N/A After the Attachment 6 title page, insert the title page for the Haddam Neck Plant Radiological Effluent Monitoring Manual.

4. Remove existing page C-3 of Insert the corrected page C-3.

the Haddam Neck Radiological Effluent Monitoring Manual.

5. Remove existing page D-3 of Insert the corrected page D-3.

the Haddam Neck Radiological Effluent Monitoring Manual.

6. Remove existing page E-9 of Insert the corrected page E-9.

the Haddam Neck Radiological Effluent Monitoring Manual.

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1.0 DEFINITIONS -

The defined terms below appear in capitalized type and are applicable to l Sections 7 and 8 of these Technical Specifications.

ACTION 1.26 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.--

CHANNEL CALIBR ATION j 1.27 A CHANNEL CALIBRATION shall be the adjustment,.as necessary, of the channel

- such that it responds with the required range and accuracy to known values of x- = input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip runctions, and may be

, performed by any series of sequential, overlapping or total channel steps such that

. the entire channelis calibrated.

CHANNEL CHECK 1.28 A CHANNEL CHECK shall be the qualitative assessment of channel behavior -

during operation by observation. This determination shallinclude, where possible,-

comparison of the channelindication and/or status with other indications and/or _

. status derived from independent-instrument channels measuring the same . . _ -

parameter.

i CHANNEL FUNCTIONAL TEST i

1.29' A CHANNEL F NCTION AL TEST shall be:

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a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable.to verify OPERABILITY including alarm .

and/or trip functions.

b. Bistable chan els - the injection of a simulated signalinto the sensor to -

verify OPERABILITY. including alarm interlock and/or trip functions. . ... .

DOSE EQUIVALENT I-131.

1.30 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce.the same thyroid dose as the quantity and isotopic ~ r_.

mixture of I-131, I-132, I-133,J-134, and-I-135 actually present. The thyroid-dose- ~

conversion factors used for this calculation shall be those listed in Table E-7 of U. S. Regulatory Guide 1.109,'" Calculation of Ahnual Doses to Man from Routine - .

Releases of Reactor Effluent for the Purpose of Evaluating Compliance with-10CFR50, Appendix I," Revision 1, October 1977.

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MEMBER (S) OF THE PUBLIC 1.31 MEMBER (S) OF THE PUBLIC shallinclude all persons who are not occupationally associated with the plant. This category does'not include employees of the ~

utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or'to make deliveries. This category does include persons ~who use portions of the site for recreational,

- occupational or other purposes not associated withthe plant. -

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. OPERABLE - OPER ABILITY 1.32 A system, subsystem, train, component or device shall be OPER ABLE or

.have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary

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equipment that are requi. red for the system, subsystem, train, component

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or device to perform ~ifsTunction(s) are also capable of performing their related support function (s).

PURGE-PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RADIOACTIVE WASTE TREATMENT SYSTEMS

~ 1.34 RADIOACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over

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radioactive materialin order to meet the LCO's set forth in these specifications.

RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION M ANUAL 1.35 A RADIOLOGICAL EFFLUENT MONITORING MANUAL shallbe a manual containing the site and environmental s'afnpling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An OFFSITE DOSE CALCULATION MANUAL shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous end liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the REMODCM are provided in Specification 6.15.

SITE BOUNDARY 1.36 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.

Source Check '

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l.3 7 - A SOURCE CHECK shall be the qualitative assessment.'of channel response when the channel sensor is exposed to a source of radioactivity.

UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the site boundary' to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive ,

materials or any area within the site boundary used for residential quarters

- or for industrial, commercial, institutional, and/or recreational purposes.

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VENTING 1.39 VENTING is the controlled process of discharging air or gas from a " '

confinement to maintain temperature, pressure, humidity, concentration or .

other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names,' does.

not imply a VENTING process.

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Figure S M t Exclusion Area Boundary, Site Boundary for Liquid arul_ Gaseous Effluents -

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INTA UCTURE I

Section I Radiological Effluent Monitoring Manual For The Haddam Neck Plant Docket No. 50-213 r

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- TABLE C-1 (Continued)

TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may' include radiochemical separation):

LLD = 4.66 Sh i E V 2.72 . Y . exp ( ,\ar) '

I where -

LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb si the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume) i 2.22 is the number of transformations per minutes per picocurie l

Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide

.at is the elapsed time between midpoint of sample collection and l midpoint of counting time-It should be recognized that the LLD is defined as an a_ priori (before the fact) limit representing the capability of a measurement system and not as a_ posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and recorded on the analysis sheet for that particular sample.

b. 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.

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TABLE D-1 (Continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a. of Table C-1.

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 changing. Special sampling and analysis of -

iodine and particulate filters shall also be performed whenever reactor coolant I-131 samples taken 2-6 hours following a THERMAL POWER -

change exceeding 15 percent of RATED THERMAL POWER in one hour show an increase of greater than a factor of 5. These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until the reactor coolant I-131 levels are less than a -

factor of 5 greater than the original coolant levels or until seven days have passed, whichever is shorter. Sample 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 LLD's may be increased by a factor of 10 for these samples. .

c. Sampling and ana_ lysis shall also be performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not

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

d. 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.

e. _ The principal gamma emitters for which the LLD specification will apply are exclusively the following radionucaldes: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, i Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate  ;

emissions. The 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 be identified and reported.

Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.

f. When the refueling cavity is flooded, samples shall be taken at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the charging floor-(refueling floor) and analyzed for tritium. The results shall be used along with containment purge flow rates to determine tritium releases.

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.e TABLE E-3 (Continued)

TABLE NOTATION ~

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. a. - The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system'(which may include radiochemical separation): -

LLD = 4.66 56 l

- E

• V

• 2.22

• Y

• exp(-M) i where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counter per transformation)

V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide  !

l at is the elapsed time between sample collection'(or end of the i sample collection period) and time of counting '

It should be recognized that the LLD is defined as a_ priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample ~ sizes,' the presence of interfering nuclides, or other uncontrollable circumstances may render these ' a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report,

b. LLD for leafy vegetables.

c. Background and onsite well water will not contain the short-lived I-131 isotope. River water is not used as offsite potable water supply and need not be analyzed for I-131.

d. From end of sample period. E-9