ML20056C550

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Proposed Tech Specs Dividing Figure 5.1.1-1 Into Figure 5.1.1-1a,depicting Geographical Areas for Calculating Liquid Effluents & Figure 5.1.1-1b,depicting Exclusion of Area Around Reactor & Areas for Calculating Gaseus Effluents
ML20056C550
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 06/18/1993
From:
CENTERIOR ENERGY
To:
Shared Package
ML20056C548 List:
References
NUDOCS 9306250117
Download: ML20056C550 (14)
v • d • e


Text

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PY-CEI/NRR-1647 L f . ,

Attachment 2 Page 1 of 12 3/4.11 RADI0 ACTIVE EFFLUENTS

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(D 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive mate 1al rele sed in liquid effluents to UNRESTRICTED AREAS (see Figure 5. 1-li)sh 1 be limited to the concentrations specified in 10 CFR Part 20, e

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B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolvad or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcuries/ml total activity. ,

APPLICABILITY: At all times. 1 l . ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

(.), SURVEILLANCE REQUIREMENTS l

' 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accord-ance with Table 4.11.1.1.1-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at l the point of release is maintained within the limits of Specification 3.11.1.1. I I

4.11.1.1.2 Post-release analyses of samples composited from batch releases I shall be performed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assu're that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

4.11.1.1.3 Continuous releases of radioactive liquid effluents shall be sampled and analyzed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

kh PERRY - UNIT 1 3/4 11-1 9306250117 930618 [

PDR ADOCK 0500 0

1 PY-CEI/NRR- 164 7 L Attachm<at 2 RADIOACTIVE EFFLUENTS "8*

DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose *egmmitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid ef 1uents' released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1. -la)sh 11 be limited: ll

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and
b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems.to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated oose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 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 that have been taken to reduce the releases and the corrective actions to be

( taken to ensure that future releases will be in compliance with the above limits.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters of the ODCM at least once per 31 days.

PERRY - UNIT 1 3/4 11-5 Amendment No.30 i

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  • PY-CEI/NRR-1647 L i Attachment 2 i RAD?0 ACTIVE EFFLUENTS e LIQUID RADWASTE TREATMENT SYSTEM Q  !

LIMITING CONDITION FOR OPERATION 1

l 3.11.1.3 The LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce the release of radioactivity when the projected doses due to the liqu 6 ei h ent from each reactor unit to UHRESTRICTED AREAS (see Figure 5.1/1-1s)wo ld exceed 0.06 arem to the total body or 0.2 mrem to any organ, in a 31-da period.

APPLICABILITY: At all times.

ACTION:

a. ~

With radioactive liquid waste being discharged without treatment and in excess of the above limits, and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission, within 30 days pursuant to Specification 6.9.2, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-systems, and the reason for the inoperability, and p- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
3. Summary description of action (s) taken to prevent a recurrence.
b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with method-ology and parameters in the ODCH.

4.11.1.3.2 The installed LIQUID RADWASTE TREATHENT SYSTEM shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

PERRY - UNIT 1 3/4 11-6 Amendment tio. 30

  • PY-CEI /NRR- 164 7 L Attachment 2 Page 4 of 12 RADI0 ACTIVE EFFLUENTS (hh 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 f om't site to areas at and beyond the SITE BOUNDARY (see Figure 5.1. -lb)s all be limited to the following: t I
a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
b. For all iodine-131, iodine-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:

i 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 radionuclides in particulate form with half lives greater than 8 days in i gaseous effluents shall be determined to be within the above limits in accord-ance with the methodology and parameters of the ODCM by obtaining representa-tive samples and performing analyses in accordance with the sampling and anal-ysis program specified in Table 4.11.2.1.2-1.

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PERRY - UNIT 1 3/4 11-8

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PY-CEI/NRR-1647 L Attachment 2 Page 5 of 12 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The '

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. -16)sh 11 be limited to the following: l

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 caiendar 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:

a. With the calculated air dose from the radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 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-(g taken to ensure that future releases will be in compliance with Specification 3.11.2.2.
b. The provisions of Spet..fication 3.0.3 are not applicable. ,

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

PERRY - UNIT 1 3/4 11-12 Amendment No. 30

PY-CEI /NRR- 164 7 1 Attachment 2 Page fi o f 12 RADI0 ACTIVE EFFLUENTS

DOSE - 10 DINE-131,10 DINE-133, TRITIUM AND RADIONUCLIDES IN PARTICUt TE FORM LIMITING-CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half , lives greater than 8 days in gaseous effluents released, from each reactor' uni from the site to areas the at and beyond the SITE BOUNDARY (see Figure 5.1{1-lb)s all be limited to following
l
a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
b. During any calendar year: Less than or equal to ~15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131, iodine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant

@.. to Specification 6.9.2, a Special Report which identifies the cause(s) i for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Specification 3.11.2.3. ~

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

$n0 PEARY - UNIT 1 3/4 11-13 Amendment No. 30

PY-CEI/NRR-1647 L Attachment 2 Page 7 of 12 RADI0 ACTIVE EFFLUENTS 68 nw VENTILATION EXHAUST TREATMENT SYSTEMS LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of r -

activity when the projected dose due to gaseous effluent releases froe fa:h reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.I-lb)in a 31 day period would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for the inoperability,
2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
3. Summary description of action (s) taken to prevent a recurrence.
b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEMS shall be demonstrated OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.3.

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PERRY - UNIT 'l 3/4 11-15 Amendment No. 30 l

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PY-CEI/NRR-1647 L Attachment 2 Ppge 8 of 12 S.0 DESIGN FEATURES

&y 5.1 SITE 5.1.1 EXCLUSION AREA, UNRESTRICTED AREA FOR LIQUID EFFLUENTS, AND SITE BOUNDARY FOR GASEOUS EFFLUENTS higure5.1.1-1showsthePNPPsitearea,includingtheneteorological we r.

The DTInrion.Jtea boundary is 2900 feet from the center ljine -tti ctor.

All land within tiiirex ion area is jointly own jedy-thr CAPC0 Group Companies. CEI controls the xc4usion ar -

ntrols include mineral rights for oil, gas, and salt. In addi , e7&loas over the Lake Erie por ~ the exclusion area %. t Guard provides 14raad controlthe spur serves plant, headi n east-north easterly direction from the Mroad-company ri way to the plant site. CEI owns the tracks and only railroad cars consigned to the PNPP are brought onto the site over this spur.

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g (Fig"ures,5.1.1-1xWo thowy the 3iquid and gaseous effluent discharge locations is weil ls lbs'pla6C$ITE' BOUNDARY for gaseous ~ releases and the UNRESTRICTED AREA for liquid effluent releases. The dose rate and doses due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited pursuant to Specification 3.11.2.1, 3.11.2.2, and 3.11.2.3. All gaseous effluent releases at PNPP are considered to be ground-level releases.

The concentrations of radioactive materials released in liquid effluents to UNRESTRICTED. AREAS shall be limited pursuant to_Specifjcation 3.11.1,Ir. -s -e A

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l 5.1. 2 The low population zone shall be as shown in Figure 5.1.2-1.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The primary containment is a steel structure composed of a vertical right cylinder and an ellipsoidal dome. Inside and at the bottom of the primary con-tainment is a reinforced concrete drywell composed of a vertical right cylinder and a steel head which contains an approximately 18'3" deep water filled sup-pression pool connected to the drywell through a series of horizontal vents.

The primary containment has a minimum net free air volume of 1,160,000 cubic feet. The drywell has a minimum net free air volume of 276,500 cubic feet.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The containment and drywell are designed and shall be maintained for:

, a. Maximum internal pressure:

q.t,'

1. Drywell 30 psig. j
2. Containment 15 psig. l I

PERRY - UNIT 1 5-1 l

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gj FIGURE 5.1.1-1 PERRY - UNIT 1 5-2 1

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. Attachumt 2 -i Page 12 of 12-t DESIGN FEATURES PAGE SECTION 5.1 SITE Exclusion Area, Unrestricted Area for Liquid Effluents and Site Boundary for Gaseous Effluents...................... 5-1 P i Figure 5.1.1-Icigxchsten fr:T;> Unrestricted Area for uid _Ef_fluentjg/and Site Geunderj for C::sous

......... 5-2 f44uents.................................... < F; pre,5,s.//6 l Zone............................ .............

5-1 g i Low Population Figure 5.1.2-1 Low Popul ati on Zone. . . . . . . . . . . . . . . . . . . . .

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ETTlaats M 5.2 CONTAINMENT he.tos;on lien-  ;

5-1 Configuration................................................ %da f r 5-1 Design Temperature and Pressure..............................

5-4 Secondary Contai nment. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5.3 REACTOR CORE 5-4 Fuel Assemblies..............................................

5-4 Control Rod Assemblies.......................................

5.4 REACTOR COOLANT SYSTEM 5-4 Design Pressure and Temperature. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5-5 Volume.......................................................

i 5.5 METEOROLOGICAL TOWER LOCATION t

Figure 5.1.1-Ib%cksica f ree. Unrestricted ^re: fe[

LL4cuid-U m ni.s_endfSite Boundary for Gaseous '.

5-5 Ef fluents.ord .E.s cinico. Atw. Lee.w)/. . . . . . . . . . . . . . .

5.6 FUEL STORAGE 5-5 Criticality..................................................

5-5 0rainage.....................................................

...... 5-5 Capacity...............................................

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT..........................

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Table 5.7.1-1 Component Cyclic or Transient Limits..... 5-6 PERRY - UNIT 1 xxiv.

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PY-CEI/NRR-1647 L I

' Attachment 3

- Page 1 of 2 .

Significant Hazards Consideration The' standards used to arrive at a determination.that a reque.st for amendment  !

involves no significant hazards considerations are included in the Commission's Regulations, 10CFR50.92, which state that the operation of the '

facility In accordance with the proposed amendment vould not (1) involve a significant increase in the probability or consequences of_an a'ecident previously evaluated, (2) create the possibility of a new or different kind of accident'from any previously evaluated, or (3) involve a significant reduction in a margin of safety.

The proposed amendment has been reviewed with respect to these-three factors '

and it has been determined that the proposed changes do not involve a significant hazard because:

1. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed separation of Technical Specification Figure 5.1.1-1, into .

Figure 5.1.1-la and 5.1.1-lb, and the revision of the appropriate-sections of the Technical Specifications which refer to these_ figures,  ;

are clarifications to the geographical areas utilized.vhen computing dose ,

calculations resulting from liquid and gaseous effluents. This change is- i requested to resolve the inconsistency between the Technical Specification and the licensing basis in the Updated Safety Analysis _  ;

Report (USAR) along with the guidance given by the NRC in NUREG-0133 .i

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants". This change does not affect any plant systems,-

nor could it affect possible: initiating events for accidents previously evaluated, or any system functional requirements. . Additionally,'the l proposed changes have no effect on accident-conditions-or assumptions. .)

Based upon the above, the proposed change could not increase the probability or consequences of'any accident previously evaluated.-

2. The proposed changes do not create the possibility of a new or different kind of-accident from any accident previously evaluated.

As stated above, the proposed change is a clarification, which does not increase the possibility of any new or different kind of accident since -

it'does not affect the reactor coolant pressure boundary _or other plant.

systems or structures which could initiate a new or different kind of accident. This. clarification vill also not impact any. system functional requirements nor plant maintenance'or, operability requirements'in such a- ,

manner that could initiate a new or different kind of accident.  !

Consequently, no new failure modes are introduced as.a result of the proposed changes.

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PY-CEI/NRR-1647 L Attachment 3

. Page 2 of 2

3. The proposed changes do not involve a significant reduction in a margin of safety.

The change does not involve a significant reduction in the margin of safety because it is a clarification to resolve the inconsistency between the Technical Specifications and the licensing basis in the USAR Figures 2.1-3 and 2.1-4, along with the NRC's guidance in NUREG-0133.

Therefore, the proposed change does not reduce the margin of safety as defined in the basis for any Technical Specification. ]

l Based upon the above considerations, it has been concluded that the proposed change does not involve significant hazards considerations.

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