ML20045D988

Amend 49 to License NPF-58,changing Submittal Frequency for Radioactive Effluent Release Rept from Semiannual to Annual

ML20045D988
Person / Time
Site:	Perry
Issue date:	06/23/1993
From:	Robert Stransky Office of Nuclear Reactor Regulation
To:
Shared Package
ML20045D989	List: ML20045D988 ML20045D990
References
NUDOCS 9306300293
Download: ML20045D988 (27)

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{{#Wiki_filter:I [g,PEIG 'o UNITED STATES ~, ?" 3 7 g NUCLEAR REGULATORY COMMISSION { WASHINGTON. D. C. 20555 \\... / THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL. DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-58 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company,. Pennsylvania Power Company, and Toledo Edison Company.(the licensees) dated January 19, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter'I; B. The facility will operate in conformity with.the application, the provisions of the. Act, and the rules and' regulations of'the Commission; C. There is reasonable assurance (i) that the -activities authorized by this amendment can be conducted without. endangering the health and 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 inimical to the common defense and security or to the health'and ' safety of the public; and E. 'The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to' the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows: 9306300293 930623 PDR ADOCK 05000440 P ppg

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Technical Specifications The Technical Specifications contained inl Appendix;A and the.'_ Environmental Protection Plan contained in Appendix; B, as revised. through Amendment No. 49 are hrreby incorporated into this license. The. Cleveland-Electric Illumincting Company shall operate the facility in accordance with.the TechnicalL.Specifi-cations and the Environmental Protection Plan. 3. This license. amendment is effective as of its date'of issuance. F0JJN AR LATORY COMMISSION // fI / / . w--.- ft J. Stransky Project. Manager. M y oject Directorate III-3 Division of. Reactor Projects ~III/IV/V 10ffice' of' Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of~ issuance: June 23, 1.'93 1 i

l l I 1 ATTACHMENT 10 LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 1 Replace the following pages of the' Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lires indicating the' area of change. Overleaf pages are provided to maintain document completeness. Remove Insert l xxvi xxvi l 3/4 3-84 3/4 3-84 3/4 3-89 3/4 3-89 3/4-11-4 3/4 11-4 3/4 11-7 3/4 11 3/4 11-11 3/4 11-11 3/4 12-1 3/4 12-1 3/4 12-7 3/4 12-7~ 3/4 12-13 3/4 12-13 6-19 6-19 6-20 6-20 6-21 6-21 6-24 6-24 6-25 .6-25

i 1 i f ADMINISTRATIVE CONTROLS i. MCTION k g j 6.5.2 NUCLEAR SAFETY REVIEW COWi!TTEE (NSRC) 5 k ? l Function.............................................. 5-10 1 Composition...........................'................ 5-11 1 j. Alternates............................................. 6. j Consultants............................................ 6 ; Meeting Frequency...................................... 6-11' Quorum................................................. 5-11 i-i j ROVi9W................................................. 6*12 m e L i Audits................................................. 4-12. Records................................................ '6-13 p 6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES................ 6-14 6.6 REPORTA8LE' EVENT ACT!0N..................................... 6-15 e t 6.7 SAFETY LIMIT V10LATION...................................... 5-15. 6.8 PROCEDURES.-INSTROCTIONS AND P E *f"S....................... 15 } 6.9 REPORTING REQUIREMENTS X h j '6.9.1: t ROUTINE REPORT5........................................ 6-17 Startup Report......................................... 6-17' ,j' Annual Reports.................................. 6-18 [ Annual Radiological Environmental Operating Report..... '6-18 i i ' Annual Ra dioa cti ve' Ef fluent Release Report.............. 6-19 [ Monthly Operating Reports..............~................- 6-21. -Core Operating Limits Report........................... 6 p 1 6.9.2 SPECIAL REP 0RTS......................................... 6-21 g 6.10 RECORD RETENTION..'................................-....'..... 6-21a v 6.11 RADIATION PROTECTION PR0 GRAM............................... 6 t: i-PERRY:- UNIT:1' xxvi Amendment No. '!! A3' 49 l 4 i 1.. ...a..

e ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY............................................... 6-1 6.2 ORGANIZATION................................................. 6 6.2.1 Corporate...............................................- 6-1 l 6.2.2 Unit Staff.............................................. 6-1 Table 6.2.2-1 Minimus Shift Crew Composition......................... 6 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP Function.............................................. 6-7 Composition............................................ 6-7. Responsibilities....................................... 6 Records................................................ 6-7 6.2.4 SHIFT TECHNICAL ADVIS0R................................- 6 - 6.3 UNIT STAFF QUALIFICATIONS.................................... 6-7 6.4 TRAINING...................................................._ 6-8 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE-(PORC) \\ Function............................................... 6-8 t Composition........................................... 6-8' l Alternates............................................. 6-8 l Meeting Frequency................'..................... 6-8 Quorum................................................. 6-9 Responsibilities...................................... 6 l Records................................................ 6-10 l l ' PERRY - UNIT.1 xxv3 Amendment No' 42

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM l LIMITING CONDITION FOR OPERATION 3.3.7.8 The loose part detection system shall be OPERABLE. l APPLICABILITY: OPERATIONAL CONDITIONS I and 2. i ACTION: l l a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Com-mission pursuant to Specification 6.9.2 within the next 10 days i outlining the cause of the malfunction and the plans for restoring l the channel (s) to OPERABLE status. ( b. The provisions of Specification 3.0.3 are not applicable. l l SURVEILLANCE REQUIREMENTS 4.3.7.8 Each channel of the loose part detection system shall be demonstrated l OPERABLE by performance of a: a. CHANNEL CHECK at least once per 24 hours, b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and c. CHANNEL CALIBRATION at least once per 18 months. PERRY - UNIT'1' -3/4 3-83 Amendment flo. 30

1 ,.I t INSTRUMENTATION + RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION f 1 3.3.7.9 The radioactive liquid' effluent. monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alare/ 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 DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: At all times. ACTION: a With a radioactive liquid eff.luent monitoring instrumentationichannel a. alarm / trip setpoint less conservative than required by the above specification,1immediately suspend the release of;. radioactive 311guid: effluents monitored byLthe affected channel'or: declare 1the channel, -inoperable, or. change the setpoint-so Lit)is acceptably conservative. 1 ' b. With less.than:the minimum number of' radioactive liquid effluent; i monitoring instrumentation channels OPERABLE,.take thel ACTION shown j in Table 3.3.7.9-1. LRestore,theLinoperablefinstrumentation to l OPERABLE status wit'hin 30 days and,:iffunsuccessful,; explain.why i ' this inoperability was, not. corrected inL-a: timely manner.in the next-Annual Radioactive EffluentfRelease ReDort; [ 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~'. l 1 i PERRY . UNIT T 3/4 3-84 1 Anendment No. 20,149 - ,,_,,.g%-i.-

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INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION 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 'et exceeded. -The alarm / trip setpoints of applicable channels shall be determinio 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 conservative 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 shown in Table 3.3.7.10-1. LRestore 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 Annual Radioactive Effluent Release Report. c. The provisions of Specification 3.0'.3 are-not applicable. SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive gaseous. effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of-the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST 1 operations at the frequencies shown'in Table 4.3.7.10-1.

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

R PERRY - UNIT.1 3/4 3-89 Amendment No. 30,49[ l

l l^ l TABLE 3.-3.7.10-1. Al

g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

.'e MINIMUM CHANNELS k INSTRUMENT-OPERABLE APPLICABILITY ACTION 1. 0FFGAS VENT. RADIATION MONITOR a. INoble Gas Activity Monitor : II 121-b. Iodine Sampler 'l -' 122 c. Particulate Sampler 1 122 d.' -Effluent System Flow Rate Monitor-1 123 -j-e. Sampler Flow Rate Monitor -1 123 Y 2. UNIT l'YENT RADIATION MONITOR. a. -Noble Gas. Activity. Monitor 1. 1, 2, 3 - 125 4, 5 121 b. ' Iodine Sampler 1: 122 c. . Particulate: Sampler-

1 122 d.

Effluent' System Flow Rate-Monitot 1 123-' -Sar ler Flow Rate Monitor - 1 e. s 123 7 c e ? .~ ~.

? TA8LE 4.11.1.1.1-1 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAN i TABLE NDTATION The LLD. is the smallest concentration of. radioactive material in a sample a. that will. yield a net count (above system background) that will be detected with 955 probability with only 55 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement. system (which may include radiochemical-separation): '4.66 s LLD = y E V 2.22 x 105 exp(-Aat) I Y where LLD is'the "a priori"~1ower limit of detection as defined above (as pCi per unit mass or. volume). b is the standard deviation of the background counting rate or of-l s the counting rate of'a blank sample as appropriate (as counts per minute) E is the counting efficiency (as~ counts per disintegration) V is the sample size (in units of mass ~or volume) 2.22 x 108 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide (sec.1) At is the elasped time between sample collection (or end of the sample collection period) and time of counting (sec) l Typical values of E, V, Y and At should be used in the calculation. j 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 t L not as a posteriori (after the fact) limit for a particular measurement, t e 4 . PERRY UNIT 1 -3/4 11. aa.

TABLE 4.11.1.1.1-1 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYS!$ PROGRAM ~ TA8LE NOTATION-(Continued) b. Acompositesample.isoneinwhichthequantity;ofINuid:sampledis 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.' ~ 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. eyci.:sively 'are the following radionuclidesi:.Mn-54, Fe-59,'.Co-58,.Co-60,, Zn-65, Mo-99,-Cs-134; Cs-137 and Ce-141. Ce-144 shall.also'be-measured, but with ar. LLD of 5x10 5 This list does not.mean-that'only.these. nuclides are to be detected and reported. 10ther peaks which are measurable and identifiable,:tooether~with the abovelnuclides, shall..also bezidentified and reported in the innnal Radina'r.tiva F.ffluant Rolaase-Rannrt nurpiant< .[ to Specification 6.9.1.7.in the format outlined in' Regulatory Guide;1.21 Appendix B, Revision 1, June 1974. A continuous. release-is the discharge of liquid wastes of!a nondiscrete e.- volume, e.g;, from a volume of.- a system that has: an inputL flow during the continuous release.. Sampling / Analysis.of.RHR-Heat Exchanger isLonly-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 hours when the samples indicate-levels greater than LLD. u f 1 PER'RY' UNIT 1-3/4 11 4 . Amendment No. 9-1

a 4 RADI0 ACTIVE EFFLUENTS l LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION-i 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 i i less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. 4 ] APPLICABILITY: At all times. 4 ACTION: 1 / 4 1 With the quantity'of radioactive material in any offthe above .) a. ~ specified tanks exceeding the above limit, immediately suspend all. additions of' radioactive material to the tanks and within 48 hours-reduce the' tank' contents to within the limit, and describe the i events. leading to the condition-in_ the next ' Annual Radioactive .l Effluent Release Report. pursuant t'o Specification 6.9.1.8. b. .The provisions 1of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS i 4.11.1 The quantity of radioactive material. contained.in each of the above I specis

• 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. i. 4 ~ I PERRY' ' UNIT 1-3/4 11-7 ~ Amendment No.M, 49 ? w

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous-effluents from the site to' areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following: a. For noble gases: Less than or equal to 500 arems/yr to.the total body and less than or equal to 3000 arems/yr to the skin, and b. For all iodine-131, fodine-133, tritium and all radionuclides in particulate form with half' lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately decrease the release rate (s) to within the above limit (s). SUREVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM. 4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium and to l radionuclides in particulate form with half lives greater than 8 days in l gaseous effluents shall be determined to be within the above limits-in accord-l ance with the methodology and parameters of the ODCM by obtaining'representa-tive samples and performing analyses.in eccordance with the sampling and anal-ysis program specified in Table 4.11.2.1.2-1. 1 PERRY - UNIT 1 3/4 11-8

= p .j b a e;- } TABLE 4.11 2.'I.2-1.(Continued) a 1.- l j RADIDACTIVE GASEOUS WASTE SAMPLING AND~ ANALYSIS PROGRAM i TABLE NOTATION (Continued) [ 1 l b. Analyses shall also'be performed following startup s shutdown.: or - i a THERMAL POWER change exceeding:15 percent of.the RATED THERMAL POWER ) within:a.one. hour period. 'This requirement,doesinot' apply.if;(1)! analysis shows that the DOSE EQUIVALENT 1-131 concentration lin.the primary ] coolant has.not increased more than a factor' of'3;.'and (2) the noble j gas monitor shows that effluent-activity has not' increased more than: 0 a factor-of 3. 1 l-I c. Samples shall be changed at lesst'once per 7 days-and analyses;shalllbe~ j-completed within 48 hours after changing'or_after removal from sampler. J' Sampling and' analyses lshal1[also be performed at' least' once per 24 hours. j j for at _least 7 days following each shutdown, startup or THERMAL ihfER - ~ i change exceeding' 15. percent of _ RATED THERMAL; POWER in' one hou. : When. j samples' collected for 24 hours are analyzed,.the corresponding.LLD!s'may. si j be increased by a factor of.10.. This requirement; does not apply if. T (1)' analysis shows that the DOSE EQUIVALENT.I-131 concentration intthe j z j , primary coolant hasEnot increased more.;than'a factor of: 3;'and (2) the J noble gas' monitor shows that effluent' activity.has'not.' increased more 1 than a factor'of 3. i [ d. The ratio of-the sample flow rate?to the sampled stream flo'w ratelshall i~ be known for'the time.. period covered by.each dose or dose rate 1 calculation [ made.in'.accordance with Specifications' 3.11.2.1,'3.11.2.2.and 3.11.2.3; 5-e. The principal gamma emitters for which the' LLD-~ specification applies [ exclusively'are the.following radionuclides: > Kr-87,' Kr-88,1 Xe-133, i. Xe-133m, Xe-135, and Xe-138 for gaseous emissions and.Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo;99, I-131, Cs-134, Cs-137, ice-141 and 'Ce-144 for - particulate emissions. This 1_ist does.not mean~that only'these.nuclides-are' to be detected and repo_rted. - Other peaks _ which are' measurable and. I identifiable, together with_the above<nuclides,;shall:also be identified. 9.1YinthefoNtout1In*eNn'e'g*uiak'o j__

Appendix B,-Revision 1, June 197_4.

uiTeT.Y1, L S cation i-O f. Sampling and analysis'of gaseous release points shallibe performed;initiallyj i whenever a high' alarm setpoint.is exceeded or whenever:two or more of the.- ~ " alert _setpoints are exceeded. ;If the high alare setpoint or two'or.more. i of the: alert setpoints continue (to be exceeded, verify atLleast once per i 4' hours via~the radiation monitors:that plant releases!are below the-i

Specification 3.11.2.1 dose rate limits and sampling and.analys.is shall=

c be, performed;at least once per 12 hours. l' p 7

PERRhiJUNIT 11

,'3/4 11-11 Amendme't No.- 49' n y,

RADI0 ACTIVE EFFLUENTS ~ DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at.and beyond the: SITE BOUNDARY (see' Figure 5.1.1-1) shall be limited to the following: a. During any calendar quarter: Less than or equal to 5 mrads for gamma. radiation _and less than or equal to 10 mrads for beta radiation, and b. During any calendar year: Less:than or equal to 10 mrads for gamma radiation and less than'or equal to 20 mrads for beta radiation. APPLICABILITY: At all times. ACTION: With.the calculated air dose from the radioactive noble gases in a. gaseous effluents exceedina any of the above limits, prepare-and submit to the Commission wishin 30 days, pursuant to Specifica-- tion 6.9.2, a Special Report'which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be. tsken to ensure that future releases will:be in compliance with Specification 3.11.2.2. b. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREHENTS 4.11.2.2 Dose Calculations. Cumulative dose contr'ibutions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the methodology >and parameters in the'0DCM at least once per -31 days. 3 i . i - 1 L PERRY - UNIT 1 3/4 11-12 Amendment No.-30 l n v v e n w w g-

= 1 9 3/4.12 RADIOLOGICAL ENVIROPMENTAL MONITORING - 4 3/4.12.1 MONITORING PROGRAM i LIMITING CONDITION FOR OPERATION-2 3.12.1 The radiological environmental monitoring program shall be conducted as specified in~ Table 3.12.1-1. APPLICABILITY: At all times. ACTION: With:the radiological environmental. monitoring' program not being con-a. 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. 3 ] i b. With the level.of radioactivity. as the result of plant effluents in - i an environmental. sampling medium at a.specified location exceeding the reporting levels of Table 3.12.1-2 when av'eraged over,any calendar o 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 dose to ~a MEMBER OF. THE.PUBLIC is less than the calendar year' limits taken to reduce radioactive offluents_so'that the potential annual 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 submittedfif: ' concentration (1) reporting level (1)

• concentration (2)-

41.0 reporting level (2) When radionuclides other than-those.in Table 3.12.la2 are detected-and are the-result of plant effluents, this report shall be submitted if the potential annual dose

• to a MEMBER OF THE PUBLIC is equal to o'r 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 ofiradioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in i the Annual Radiological Environmental Operating Report required by 1 Specification 6.9.1.6. 3 i With milk or broad' leaf vegetation samples unavailable from one or. c. more of the-sample locations required by Table 3.12.1-1,- identify specific locations for obtaining replacement samples;and add them-a within 30 days to the Radiological Environmental Monitoring Program l given in the ODCM. The; specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant. to Specification 6.14, submit-in the next" Annual. Radioactive. Effluent Release. Report documentation for a change in the 00CM includ- ' '[ .-ing a' revised figure (s).and table.for the ODCM reflecting the new location (s) with supporting information identifying the;cause of1the-i unavailability of samples andjustifying the selection"of:the new location (s) for obtaining samples. - d. .Th'e provisions of Specification-3.0.3-are not applicable.

• The methodology and parameters used to estimate the potential annual dose to a i-

' MEMBER OF THE PUBLIC shall-befindicated.in thist report. l . PERRY.- UNIT'l 3/4.12-1 AmendmentNo.W,49t l

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RADIOLOGICAL ENVIRONMENTAL MDNITORING SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples'shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and. figures in the 00CM and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1. I l PERRY., : UNIT l' 3/4 12-2 = .___-_-_______L- ......A

) TO LE 3.12.1-1 (Ccntinued). RADIOLOGICAL ENVIR0000 ENTAL IGNITORING PROGRAM TABLE NOTATIONS Sample locations are given on 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 cifications for Nuclear Power Plants," October 1978, and to Radiol ical Assessment Branch Technical. Position, Revision 1, November 1979. viations 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 samples 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 substitutions made within 30 days in the Radiological Environ-mental Monitoring Procram civen in the 00CM. Pursuant to Specification 6.14, submit in the next Annual Radioactive-Effluent Release Report documen-l tation for a change in the 00CM, including a revised figure (s) and table for the DDCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathwa justifying the selection of the new location (s) for obtaining samples.y and (2) One or more instruments, such as a pressurized ion chamber, for seasuring and recording dose rate continuously may be used in place of or in-addition to, integrating dosimeters. ForthepurposesofthIstable,a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two 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. (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 inforination with minimal fading.) (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after stapling to allow for redon and thoron daughter decay. -If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control-samples, gamma isotopic analysis shall be performed on the individual samples. l PERRY - UNIT 1 3/4 12-7 Amendment No. 49 V ...,L _ _

1. I i 3 TABLE 3.12.1-1 (Continued) i TABLE NOTATI0fts (Continued) (4) Gamma isotopic analysis means the identification and quantification of' l gamma-amitting radionuclides that' any be attributable to the affluents-from the facility.- (5) A composite sample is one in which the ' quantity (aliquet) of liquid sampled 1s. proportional to the quantity of flowing liquid and in which the: method 4 of sampling employed results in a ' specimen that'is-representative of the i liquid flow.' .In this program composite sample aliquets shall he collected i at time intervals that are very short (e.g..' hourly) relative to the. compositing period.(e.g., monthly) in order to assure obtaining a representative sample. j' (6) The dose shall be calculated for the. maximum organ and age group, using 1-the methodology and parameters in the 00CM. ~ i ) F ) PERRY.- UNIT 1 '3/4 12-8 .) 1 'l

RADIOLOGICAL ENVIRONMENTAL MONITORING 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 of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden

• of greater than 50 m2 2

(500 ft ) 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 Specification 4.11.2.3, identify the new location (s)* in the next - Annual Radioactive Effluent Release l Report, pursuant to Specification 6.9.1.7. b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (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 and/or broad leaf vegetation samples are' identified in 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 location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring. program af ter October 31 of the year in which this land use ~ census was conducted.* Identify the new location (s) in the next Annual 4 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). 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 agriculture' 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.

Specifica-tions for broad leaf. vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples. PERRY - UNIT 1 3/4 12-13 Amendment nom, '49

4 d n i i d N -RADIOLOGICAL ENVIRO M ENTAL' MONITORING 1: 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM; l LIMITING' CONDITION FOR'0PERATION' 3.12.3 Analyses shall be performed on radioactive materials that:correspondJ i to samples required by Table:3.12.1-1. These'satorials'are supplied ~as part of an Interlaboratory Comparison Program which. has been; approved by'the Commission. APPLICABILITY: At'all times. ' ACTION: a. With analyses not'being performed as1 required above,l report the-corrective ~ actions taken to preventia. recurrence to'the Commission-: in the Annual'Radiologica1' Environmental Operating Report' pursuant to Specification 6.9.1.6. ~ ' b. The provisions'of Specification ~ 3.0.3 are?notfapplicable. I SURVEILLANCE REQUIREMENTS- ~ - 4.12.3 A summary of the results obtained as part'of the.abovef required'. Interlaboratory Comparison Program shall befincluded Lin1the" Annual: Radiological: - Environmental Operating Report pursuant:to Specification'6.'9.1.6. ) 4 V ' PERRY UNIT 1_ ~ 3/4:12-14 . Amendmant No.-30. 1

ADMINISTRATIVE CONTROLS i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) prior to May 1 of each year. The initial report shall be submitted prior to May 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 radiological environmental surveillance activities for the report period, including.a com-parison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports 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. In 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 results. The missing data. shall be submitted as soon as possible in a 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 1

the specified program is not being 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 sampling schedule of Table 3.12.1-1; discussion of environmental sample measure- 'i ments that exceed the reporting levels of Table 3.12.1-2 but are not the result of plant effluents, pursuant to ACTION b of Specification 3.12.1; and discus-sion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 Routine radioactive release reports covering the operation of the unit during the previous calendar year shall be submitted annually. The report must be submitted as specified in 10 CFR 50.4, and the time between submission of reports must be no longer than 12 months. "One map shall cover stations near the SITE BOUNDARY; a second shall. include the more distant ~ stations. PERRY - UNIT 1 6-19 Amendment No. 49

ADMINISTRATIVE CONTADLS 4 j AdNUAL RADIDACTIVE EFFLUENT. RELEASE REPORT (Continued)- f i l The.. Annual Radioactive Effluent Release Reoort shallLinclude. a sum-- mary of the quantities of radioactive. liquid and gaseous effluents and solid 4 j waste released from the unit as outlined in Regulatory: Guide 1.21, "fleasuring,- i Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-l active Naterials in Liquid and Gaseous Effluents from Light-Water-Cooled Nu-4 I clear Power Plants, Revision 1, June 1974, with data suimmerized-on a guarterly - basis following the format of Appendix 8 thereof. For solid westes, the: format for Table 3 in Appendix 8 shall-be supplemented with.three additional categories: j class of solid wastes (as defined by 10 CFR Part 61),' type of^ container-(e.g.', i LSA, Type A, Type B, Large Quantity) and SOLIDIFICATION. agent or absorthent l (e.g., cement, urea fonnal.dehyde). o l l The Annual Radioactive Effluent Release Report: submitted each year shall j include a summary of hourly meteorological data collected over the previous ] calendar 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 i distributions of wind speed, wind direction, and atmospheric stability.* :This-l r i report shall include'an assessment of the radiation doses due to the ] radioactive liquid and gaseous effluents released from the unit or. station ~ i during the. previous calendar year. 'This; report shall also include an l-j assessment of the radiation doses from radioactive liquid and gaseous t effluents to MEMBERS OF'THE PUBLIC~due to their activities inside the SITE'. j BOUNDARY'(Figure 5.1.1.1-1) during the report; period. All? assumptions'used in' making these assessments, i.e., specific activity, exposure time,-and 3 j location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous' a effluents, as determined by sampling frequency and measurement, shall be used j for determining the gaseous pathway doses. The assessment of radiation doses l shall be performed in' accordance with the methodology and parameters in the } OFFSITE DOSE CALCULATION' MANUAL (ODCM). 2;- The Annual Radioactive Effluent Release Report submitted-each year-- shall d i also include an assessment'of radiation doses to the likely most exposed l MEMBER OF THE PUBLIC from 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 contribution from liquid and' gaseous effluents are given in Regulatory Guide.1.109, Rev.1, October 1977. [ The Annual Radioactive Effluent Release Report.'shall include a list' l and description of unplanned releases from the site to UNRESTRICTED' AREAS of-radioactive materials in' gaseous and liquid effluents made during the reporting l period. Y s b

• In lieu of submission with the Annual R2dioactive' Effluent Releas~e Report the licensee has' the option of retaining this summary of required meteorological-3

. data on site !in a file that shall. be provided to the NRC upon request. ~ L ' PERRY UNIT 1 6-20 Amendment No. 49 L ~. ,~. w--,, .._nm,._,

4 ADMINISTRATIVE CONTROLS } ^ - ANNUAL RADI0 ACTIVE UTLutriT XtLLAbt KL'VUNT (Continued) The Samiannual Radioactive Effluent Release Report. OFFSITE DOSE CALCULATION MANUAL (ODCM), p i : Treatment Systems pursuant to Specification Li5.respectively, as we i by the Land Use Census pursuant to Specification 3.12.2.of The Annual Radioactive Effluent Release Report shall also include the-l following: 4 an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified i leading to liquid holdup tanks exceeding-the limits of Spe j 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, Office of Resource Management, U. S. Nuclear Regulatory Conrnission, Washington, D. C. 20S55, with a copy to the j

Regional Administrator of the Regional Office no later than the 15th of each j month following the calendar month covered by the report. l _ CORE OPERATING LIMITS REPORT 6.9.1.9 OPERATING LIMITS REPORT before each reload cycle or l reload cycle for the following: j I (1) The Average Planar Linear Heat Generation Rate (APLHGR) for' Technical Specification 3.2.1. (2) The Minimum Critical Power Ratio (MCPR) for Technical Spe:ification 3.2.2. (3) The Linear Heat Generation Rate (LHGR) for Technical Specification 3.2.3. (4) The Simulated Thermal-Power Time Constant for Technical ) Specification 3.3.1. i The analytical methods.used to detemine the core' operating limits shall be those previously reviewed and approved by NRC in NEDE-24011-P-A, General-Electric i Standard Application for Reactor Fuel. (The approved revision at the time' reload analyses are perfomed shall be identified in the COLR.) (e.g., fuel themal-mechanical limits, core themal-hydrauli limits, nuclear limits such as SHUTDOWN MARGIN, and transtent and ' accident analysis limits) of the safety analysis are met. The CORE OPERATING ~ LIMITS REPORT, including any mid-cycle revisions o 1 supplen..ats thereto, shall. be provided upon issuance, for each reload cycle, to the U.S. Nuclear Regulatory Comission Document Control Desk with copies to the Regional Administrator and Resident Inspector. ~ PERRY - UNIT l' 6-21 Amendment No.)i,43, 49 w m. m-r-- s ,e

a ADMINISTRATIVE CONTROLS SPECIAL REPORTS l 6.9.2 Special reports shall be submitted to the Regional Administrator of'the Regional Office within the time period specified for.each report. 6.9.3 Safety-relief valve failures will be reported to the Regional Administrator of the Regional Office of the NRC via the Licensee Event. Report system within 30 days. 6.9.4 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would~have. adversely affected the-ability to achieve and maintain safe shutdown in the' event of a fire shall-be reported to the Regional Administrator of the Regional Office of the'NRC'via the Licensee Event Report system within 30' days. 6.10 RECORD RETENTION 6.10.1 In addition to'the applicable record retention. requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.2 Thefollowingrecordsshallberetained:foratleast5l years: a. Records and logs of unit operation covering the~ interval at each power level, b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items.of equipment 'related to nuclear safety.~ d PERRY ' UNIT 1 6-21a' Amendment No. 33 L[

ADMINISTRATIVE CONTROLS i HIGH RADIATION AREA (Continued) 6.12.2 In addition to the requirements of Specification 6.12.1, areas access-4 l ible to personnel with radiation levels such that a major portion of the body I could receive in 1 hour a dose greater than 1000 ares

• shall be provided with j

uniquely keyed locked doors or continuously guarded to prevent unauthorized ~ entry, and the keys shall be maintained under the administrative control of the 4 Shift 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-l tion of the body could receive in 1 hour a dose.in excess of 1000 aren* that are located within large areas, such as the containment, where no enclosure exists j for purposes of locking, or that cannot be continuously guarded and no enclosure can be reasonably constructed around the individual areas, then that area shall j 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 arem*, entry shall require { i an approved RWP which will specify dose' rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. { In lieu of the stay time specification of the RWP,' continuous' surveillance, diru t ore remote, such as use of closed circuit TV cameras, may be madeLby personnel qual-1 ified in radiation protection procedures to provide positive exposure control over activities within the area. 6.13 PROCESS CONTROL PROGRAM (PCP) ) i 6.13.1 { The PCP shall be approved by the Commission prior to' implementation. i 6.13.2 Licensee initiated changes to the PCP: t 1. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for.the period in which the change (s) was made. This submittal shall contain: Sufficiently detailed information to totally support the rationale a. i for the change without benefit of additional or supplemental information; 3 b. A determination that the change did not reduce the overall 4 'conformance of the solidified waste product to existing criteria for solid wastes; and ] Documentation of the. fact that the change has been reviewed and c. found acceptable by the PORC. ] " Measurement made'at 18 inches from source of radioactivity. 3 PERRY - UNIT 1 6-24 Amendment No. 49

1 ADMINISTRATIVE CONTROLS 3 PROCESS CONTROL PROGRAM (PCP) (Continued) 2. Shall become effective upon review and acceptance by the PORC. l 6.14, 0FFSITE DOSE CALCULATION MANUAL (0DCM) i 6.14.1 The ODCM shall be approved by the Commission-prior to implementation. i i 6.14.2--Licensee initiated changes to the ODCM: i a 1. Shall be submitted to the' Commission in the Annual Radinactiva Effluent Release Report for the period in which the change (s) was j made. This submittal shall contain: Sufficiently detailed information to totally support the. 1 a. rationale for the change without benefit ~of additional ~or-supplemental information. Information submitted.should. consist- -of a package of those pages of.the:0DCM to be chenged with each. j page numbered and provided with an-approval end data box, together with appropriate analyses or evaluations, justifying the change (s); 3 1 1 b. A determination that the change will-not reduce the accuracy or reliability of dose calculations or-setpoint determinations; j and a j Documentation of the fact that'the change has'been reviewed and c. } found acceptable by the PORC. . 3 4 i 2. Shall become effective upon review and acceptance by the PORC. 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYME'1S* i. 6.15.1 Licensee initiated major changes to the.radioac'tive waste systems, j liquid, gaseous and solid: 1. Shall be reported to the Commission-in the Annual Radioactives l i Effluent Release Report for_the period in which the evaluation was-reviewed by the PORC. The discussion of each change shall containi A summary o'f the evaluation that led to the determination that 3 a. the change could be made in accordance wth 10 CFR 50.59; e i 4- } Sufficient detailed information to totally support.the reason b. for the change without benefit of additional or supplemental information; A detailed description of the equipment, components and c. processes involved and the interfaces with other plant systems; i " Licensee may choose to submit the information called for in this Specification as part of the annual FSAR update. PERRY - UNIT 1 6-25 Amet.dment No. 49 T -e-c e up-4--v f-r& >tr -r tW-Se'-4 4- wt'- .'-V-T'N^* W ='t--f-T if7}}