PY-CEI-NRR-1571, Proposed Tech Specs,Revising Frequency Re Semiannual Radioactive Effluent Release Rept

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Proposed Tech Specs,Revising Frequency Re Semiannual Radioactive Effluent Release Rept
ML20127L270
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 01/19/1993
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CENTERIOR ENERGY
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ML20127L264 List:
References
PY-CEI-NRR-1571, NUDOCS 9301270069
Download: ML20127L270 (14)
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Py-c er/n RR.- 15 7) L -

mamen+ A Py e I of It 1

A,0HINISTRATIVE C0KTROLS

.G-SECTION PAGE 6.5.2 NUCLEAR SAFETY REVIEV Co>t(ITTEE (NSRC)

Function .............................................. 6-10 C omp o s i t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-n Alternates............................................. 6-u Consu1t4nts............................................ 6-u Neeting Frequency...................................... 6-1 Quorua........................................... ..... 6-11 Review................................................. 6-12 Audits................................................. 6-12 Records................................................ 6-13 6.5.3

( TE CHNICAL REVIEV AND CONTROL ACTIVITIES. . . . . . . . . . . . . .6-14 ..

6. 6 REPORTABLE EVENT ACTI0N..................................... 6-15 6.7 SAFETY LIMIT i

VIOLATION...................................... 6-15 L 6.8 PROCEDURES , INSTRUCTIONS AND P R0 GRAMS. . . . . . . . . . . . . . . . . . . . . . . 6-15

6. 9 REPORTING REQUIREMENTS 6.9.1 RO U T IN E R E P0 RTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-17 ............

S t a r t u p Re po r t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-17 Annual Reports......................................... 6-18 Annual Radiological Environmental Operating Report..... 6-18 nnual Radioactive Effluent Release Report. ........ 6-19 Mo n t h l y Op e ra t i ng R epo rts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 Co re Opera ti ng L imi ts Report. . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 6.9.2 l SFECIAL REP 0RTS........................................ 6-21 6.10 RECORD RETENT10N........................................... 6-21a l 6.11 RA 0 !AT ION PRO TECT ION P ROGRA.'4. . . . . . . . . . . . . . .6. 23 ...............

PERRY - UNIT I xxvi Amendment No. 22,33 h

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7 PY-CEIh4RR -jf 71 L A%&mn+-2 INSTRUdENTATION fq e. A ef it .

RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alarr/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alare/ trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE 005E CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspead the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or changa the setpoint so it is acceptably conservative,
b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.9-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why I this inoperability was not corrected in a timely manner in the next

/hnual Radioactive Effluent Release Report.

ll

c. The provisions of Specification 3.0.3 are not applicable. .

SURVEILLANCE REQUIREMENTS 4.3.7.9 Each radioactive liquid effluent monitoring instrumentation' channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.9-1.

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?ERRY - UNIT l' 3/4 3-84 Amendment No.30

. P1-CEZ/NRR-lCll L Ahdmmt1 f INSTRUMENTATION .

RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION LIMITING CONDIT!ON FOR OPERATION 3.3.7.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limit of Specification 3.11.2.1* are not exceeded. The alarm / trip setpoints of applicable channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.10-1 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less ennservative than required by the above specification, declare the channel inoperable, or change the setpoint so it is acceptably conservative,
b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION snown
g. in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next M/hnual Radioactive Effluent Release Report. ll
c. The provisions of Specification 3.0.3 are not applicable.  ;

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive gaseous effluent monitoring instrumentatIion char.nel shall be demonstrated OPERABLE by performance of the CHANNEL CHECX, 00VRCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

"See Specification 3.11.2.6 for the Main Condenser Offgas Hydrogen Honitor (IN64-N012A/B) limit.

PERRY - UNIT 1 3/4 3-89 Amendment No. 30

1

. PY -CE.E/NRR-lS71 L A Adment ,2 TABLE 4.11.1.1.1-1 (Continued)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste dischcrged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
c. A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn"54, Fe-59, Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5x10 8 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, ether with the above nuclides, she,11 also be identified and reported in nual Radioactive Effluent Release Report pursuant ll to Specification 6.9.1. in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
c. A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g. , from a volume of a system that has an input flow during the continuous release. Sampling / Analysis of RHR Heat Exchanger is only applicable when there is ESW flow thru the RHR Heat Exchanger.
f. Sampling and analysis is required of the RHR heat exchanger ESW outlet every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the samples indicate levels greater than LLD.

PERRY - UNIT 1 3/4 11-4

Py- cer/NRR-If 7l L RADIOACTIVE EFFLUENTS A Nas. h Pte.n t 2

/

LIQUID HOLDUP TANKS I'jt E of lY LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside tempo-rary tank, not including liners for shipping radwaste, shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above specified tanks exceeding tne above limit, immediately suspend all additions of radioactive material tG the tanks and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the liqit. and describe the events leading to the condition in the neft9ee4/hnual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8. ll
b. The provisions of Specification 3.0.3 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above .

specified tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

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' PERRY-UNITi 3/4 11-7 Amendment No.3D

a' Py-cer/NRR-1571 L.

. A %.k msnf L TABLE 4.1122.1.2-1 (Continued) Qt G ef it

[ RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM =

TABLE NOTATION (Continued)-

b. Analyses shall also be performed following startup, shutdown, or. l a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. This requirement does not apply if (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 monitor shows that effluent activity has not increased more than a factor of 3.

c. 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 /> af ter changing or after removal from sampler.

Sampling and analyses 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 following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour. When sampics 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:LLD's may be increased by-a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the i primary coolant has not increased more'than a factor of 3; and (2)-the noble gas monitor shows that effluent activity has' not increased more -

than a factor of 3. r

d. The ratio of the sample flow rate to the sampled stream ficw rate shall be known for the time period covered by each dose or. dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
e. The principal gamma eroitters for which the LLD specification applies exclusively are the following radionuclides: - Kr-87, Kr-88, _ Xe-133, Xe-133m, Xe-135, and'Xe-138 for ganous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-13), Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are seasurable and.

identifiable, tog ith the above nuclides, shall also be identified and reported in.t nual Radiological- Effluent Release Report pursuant y to Specification 6.9. . in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1,-June 1974.

f. Sampling and analysis of gaseous release points .shall be performed initially whenever a high alarm setpoint is exceeded or_ whenever two or more of-'the L alert setpoints are exceeded. If the high alarm setpoint or two or more
of the alert setpoints continue' to-be exceeded, veri _fy at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> via the radiation monitors that plant releases are below the

$pecificaticn 3. n.2.1_ dose rate limits and sampling and analysis-shall L be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

L PERRY-- UNIT 1 3/4 11-11

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Py-c.er/AIRR-1571 L

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p.h+ A 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING Pap 7 of lY .

(^ 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be ennducted as specified in Table 3.12.1-1. 1 APPLICABILITY: At all times.

ACTION:

a.

With the radiological environmental monitoring program not being cor-ducted as specified in Table 3.12.1-1, prepare and submit to the Com-mission, in the Annual Radiological Environmental Operating Report per Specification 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of lable 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a i4 EMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

When more than one' of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

(

concentration (1) reporting level (1)

  • concentration (2) reporting level (2) + .. Q 1.0 When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shell be submitted if the potential annual dose" to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; howeter, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report r'equired by Specification 6.9.1.6.
c. With milk or broad leaf vegetation samples unavailable from one or more of the sample locaticos required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and edd them within 30 days to the Radiological Environmental Monitoring Frogram given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the, monitoring program. Pursuant to Specificatien 6.14, submit in the nex nual Radioactive j Effluent Release Report documentation for a e ange in the ODCM includ-ing a revised figure (s) and table for the 00CM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.
d. The provisions o' Specification 3.0.3 are not applicable. l "The methodology and parameters used to estimate the potential annual dose to a .

MEMBER OF THE PUBLIC shall be indicated in this report.

PERRY - UNIT 1 3/4 12-1 Amendment No.30

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. . P Y-C.EI/N A R -l& 71 L A# shmen+ 2 TABLE 3.12.1-1 (Continued) Q e g of lt RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM TABLE NOTATIONS

  • Sample locations are given en the figure and the table in the 00CM.

(1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radio-logical Effluent Technical Specifications for Nuclear Power Plants,"

October 1973, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete correc-tive action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6. It is recognized that, at times, it may not be possible or practicable to continue to obtain 5tmples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and

( appropriate substituticas made within 30 days in the Radiological Environ-mental Monitoring,Procram given in the OOCH.

inual Radioactive Effluent Release Report documen-sebmit in theinneit @the ODCM, including a revised fig tation for a change for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples.

(2) One or more instruments, sud as a pressurized ion chamber, for measuring and recording dose rate cont nuous!y may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two l 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.

l (The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.)

l (3) 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 greatar than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

I PERRY - UNIT 1 3/4 12-7

. . P y- CE.t/N R R- 15 71 L h its a me.nt 1 RADIOLOGICAL- ENVIRONMENTAL MONITORING [A,3e.3of IY 3/4.12.2 LAND USE CENSUS ,

LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a dis--

tance of 8 km (5 miles) the location in each 9f the 16 meteorological- sectors of the nearest milk animal, the nearest residence and the nearest garu.n* of greater than 50 m 2 (500 f t 2) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in 5 tion 4.11.2.3, identify the new location (s)* in the n nual Radioactive Effluent Release Q Report, pursuant to Spec 1 cation 6.9.1.7.
b. With a land use census identifying a location (s) which yields a calculated dose er dose con:mitment (via the same exposure pathway) 20 percent greater than at a location from which milk and/or broad-leaf vegetation samples are currently being'obtained in accordance.

with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30' days. If no milk anGor

( broad leaf vegetation samples are identifiedin the new sector with the highest D/Q value, then the next sector with the highest D/Q value will be considered and so on until a sampling location can be -

established. The sampling location (s), excluding the control ~ station lucation, having the lowest calculated dose or dose commitment (s), s' via the same exposure pathway, may be deleted from this monitoring- .

program after October 31 of the year in which this land use census was conducted.*- Identify the new location (s) in the ne'xt]gfhnual _O Radioactive Effluent Release-Report and also include-in,the report a revised figure (s) and table (s) for the ODCM reflecting the new '

location (s). i

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the' best results, such as by a door-to-door survey, aerial survey, or by consulting '

local agrir.ulture authorities. The results of the land use-census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

  • Broad leaf- vegetation sampling of at least three different kinds of vegetation ,

may be performed at the site boundary in each of two different direction sec-tors with the highest predicted 0/Qs in lieu of the garden census. Specifita-tions for broad leaf vegetation sampling:in Table 3.12.1-1 shall be foliosed, including analysis of _ control samples.

PERRY - UNIT 1 3/4 12-13 Amendment No.30 -

Py-car /nRR-Ir71 L miono + 2 ADMINISTRATIVE CONTROLS C

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) prior to May 1 of each year. The initial report shall be submitted prior to day 1 of the year following initial criticality and shall include copies of -

reports of the preoperational Radiological Environmental Monitoring Program of the unit for at least two years prior to initial criticality in addition to the following.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radio 1cgical environmental surveillance activities for the report period, including a com-parison with preoperational studies, operational controls (as appropriatc),

and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report:

shall also include the results of land use censuses required by Specifica-tion 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all loca-tions specified in the table and figures in the Offsite Dose Calculation Manual, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. I. the event that some individual results are not available for inclusion with the report, the report shall be submitted

(, noting and explaining the reasons for the missing re:ults. The missing data shall be submitted as soon as possible in e supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps

  • covering all sampling locations keyed to a table giving distances and direc-tions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not bring performed as required by Specification 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Specification 3.12.1, and discussion of all deviations from the sam;, ling schedule of Table 3.12.1-1; discussion of environmental sampid measure-ments that exceed the reporting levels of Table 3.12.1-2 but are not the result of plant effluents, pursuant te ACTION b of Specification 3.12.1; and discus-sion of all analyses in which the LLD required by Table 4.1" 1-1 was not achievable.

ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

.14 44, ye=0 6.9.1.7 Routine r joactive release reports covering the operation of__the unit durina the previou 'O ; nth: Of :perati Qshall be submittedhith" S0 d y: 'S 4f ter January 1-end July 1 Of ::d ye:r 9: pcrkd Of th: " r:t 7:p:rt ch llj jef 'ith th; d:t ef 'iti:1 crithclity[4nnaaHy. The rer.rt Nas t k sdW1fd as spe dUna in se cra sa.yj .. t 4 he t;m b. N ee n s&.;is ,n .f rer.ets me3f be n. -

1.y e r t kea n. m e.1k s.

  • 0ne map shall cover stations near the SITE BOUNDARY; a second shall include i the more distant stations.

PERRY - UNIT 1 6-19

f Y~ CEZ/NRR-151l L

. . A w ,& 2 ADMINISTRATIVE CONTROLS Y

ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continuee [

Th M /nnual P.adioactive Effluent Release Repor all include a sum- y mary of the quantities of radiractive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Heasuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Ef fiuents from Light-Water-Cooled Nu-clear Power Plants," Revision 1 June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories:

class of sclid wastes (as defined by 10 CFR Part 61), type of container (e.g.,

LSA, Type A, Type B, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g. , cement, urea formaldehyde). gg A p 9 o-The f4mMhnual Radioactive Effluent Relea e ReAort 4 JO%;,= "r/: :Oeach year shall inc ;de ? crr:D summary of hourly P ^ MsubmittedMt"rF meteorological data collected over the previous 9 year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distril utions l of wind speed, wind direction, and atmospheric stability.* This kame} report shall include an assessment of the ll radiation doses due to the radioactive liquid and gaseous effluents re eased from the unit or station during the previous calendar year. This report ll shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside

' the SITE BOUNDARY (Figure 5.1.1-1) during the report period. All assumptions used in making these assessments, i.e. , specific activity, exposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determin-ing the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the 0FFSITE DOSE CALCULATION MANUAL (00CM).

y The nnual Radioactive Effluent Release Report .,mitted E;i tWb TC e, . ter J:u:-"; 13each year shall also include an assament of radia-tion cases to the likely most exposed MEMBER OF THE PUBLIC froe reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose con-tribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

Th nual Radioactive Effluent Release Repor hall include a list ll and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

  • In lieu of submission with th nnual Radioactive Effluent Release Report, ll the licensee has the_ option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

PERRY - UNIT 1 6-20

P y-c.e r/nng-tr7; L M.d-t A e ADMINISTRATIVE CONTROLS Psy l A ef it W-J.

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' MAtmUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) i The [nnual Radioactive Effluent Release Report [ hall include any changes l made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (0DCM), pursuant to Specifications 6.13 and 6.~14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems pursuant to Specification 6.15. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Specification 3.12.2.

Th nnual Radioactive Effluent Release Repor hall also include tne following: an explanation as to why the inoperability of liquid or gaseous ll effluent monitoring instrumentation was not corrected within the time specified in Specification 3.3.7.9 or 3.3.7.10, respectively; and description of the even'.s leading to liquid holdup tanks exceeding the limits of Specification 3.11.1.4.

MONTHLY, OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, O'fice of Resource Management, U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar man? overed by the report, b CORE OPcRATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

(1) The Average Planar Linear Heat Generation Rate (APLHGR) for Technical Specification 3.2.1.

(2) The Minimum Critical Power Ratio (MCPR) for Technical Specification 3.2.2.

' (3) The Linear Heat Generation Rate (LHGR) for Technir.al Soecification 3.2.3.

The analytical methods used te determine the core coerating limits shall be those previously reviewed and approved by NRC in NEDE-240ll-P-A, General Electric Standard Application for _ Reactor Fuel. (The approved revision at the time reload analyses are performed shall be. identified in the COLR.)

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The core operating limits shall be detemined so that all aoplicable limits (e.g. , fuel themal-mechanical limits, core themal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.

l m The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or D supplements thereto, shall be provided upon issuance, for each reload cycle, to the U.S. Nuclear Regulatory Commission Document Cont ol Desk with copies to the Regior11 Administrator and Resident Inspector.

PERRY - UNIT 1 6-21 Amendaent No. 33 l

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- A b d m m + 2, Pa, y. l 3 * + l t ADMINISTRATIVE CONTROLS b

HIGH RADIATION AREA s':ontinued) 6.12.2 In addition to the requirements of Specification 6.12.1, areas access-ible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem

  • shall be provided with uniquely keyed locked doors or continuouMy guarded to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shif t Supervisor or the Plant Health Physicist. Doors shall remain locked ex-cept during periods of access by personnel under an approved RWP. For individ-ual areas accessible to personnel with radiation levels such that a major por-tion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrem
  • that are located within large areas, such as the containment, where no enclosure axists for purposes of locking, or that cannot be continuously guarded and no enclosure can be reasonably constrrted around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device.

6.12.3 In addition to the requirements of Specifications 6.12.1 and 6.12.2, for individual areas accessible to personnel such that a major portion of the body could receive in I hour a dose in excess of 3000 mrem *, entiy shall rcquire an approved RWP which will yecify dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. In lieu of a

the stay time specification of the RWP, continuous surveillance, direct or remote, such as use of closed circuit TV cameras, may be made by personnel qual-ified in radiation protection procedures to provide positive exposure control over activities within the area.

6.13 PROCES^, CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changu to the PCP:

1. Shall be submitted to the Commission in the " [nnualRadioactive y Effluent Release Report for the period in wh ch the change (s) was mede. This submittal shall contain:
a. Suf ficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;
b. A determination that the change did not reduce the overall confo mance of the solidified waste product to existing criteria for solid wastes; and
c. Documentation of the fact that the change has been reviewed and found acceptable by the PORC.
  • Measurement made t 18 inches from source of radioactivity.

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PERRY - UNIT 1 6-24 I

' PY-c.cI/NKR-/f 71 L l

Abdmut A ADMINISTRATIVE CONTROLS l%Ue. If e4 It PROCESS CONTROL PROGRAM (PCP) (Continued)

2. Shall become effective upon review and acceptancu by the PORC, 6.14 0FFSITE 00SE CALCULATION MANUAL (00CM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCH:

1. Shall be submitted to the Commission in th nnual Radioactive Effluent Release Report for the period in which the change (s) was ll mada. This submittal shall contain:
a. Sufficiently detailed .nformation to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and data box, 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; and
c. Documentation of the fact that the change has been reviewed and found acceptable by the PORC.
2. Shall become effective upon review and acceptance by the PORC.

6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATHENT SYSTEMS

  • 6.15.1 Licensee initiated major changes to the radioactive waste systems, liquid, gaseous and solid:
1. Shall be reported to the Commission in th [nnualRadioactive ll Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussioh of each change shall contain:
a. A summary of the evaluation that led to the determination that the change could be made in accordance wth 10 CFR 50.59;
b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
c. A detailed description of the equipment, components and processes involved ar.d the interfaces with other plant systems;

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

PERRY - UNIT 1 6-25

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