ML20056F729
| ML20056F729 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/23/1993 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20056F726 | List: |
| References | |
| NUDOCS 9308300314 | |
| Download: ML20056F729 (19) | |
Text
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ATI'ACHMENT B ANNOTATED PAGES j
OF THE PROPOSED CHANGE TO APPENDIX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES DPR-39 AND DPR-48 l
LICENSING AMENDMENT REQUEST NO. 93-08 PAGES MODIFIED i
310b j
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312 6a 319 229a 321 242a 322 309a 325 310a i
t PAGES DELETEll l
None I
PAGES ADDED None l
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93083003121 930823 PDR ADOCK 05000295 P
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TABLE OF CONTENTS 1.0 DEFINITIONS 1.26 Offsite Dose Calculation Manual Page 1 1.1 Actlon 1.27 Operable - Operabt11ty 1.2 Actuation Device 1.3 Actuated Equipment 1.4 Actuation Logic Test Page 5 1.28 Operating 1.29 Operating Cycle 1.5 Axtal Flux 01fference 1.30 Operational Mode - Mode 1.6 DELETED 1.31 Physics Tests l
Channel Calibration, Instrument 1.7 1.32 Pressure Boundary leakage 1.8 Channel Check 1.33 Process Control Program (PCP) 1.34 Protection Logic Channel Page 2 1.9 Channel Functional Test 1.35 Protection System l
1.10 DELETED 1.11 Containment Integrity Page 6 1.36 Purge - Purging l
1.12 DELETED 1.37 Quadrant Power Tilt Ratto 1.13 Controlled leakage 1.38 Rated Thermal Power 1.14 Core Alteration 1.39 Reactor Pressure Page 2a 1.14a Core Operating Limits Report 1.40 Refueling Outage 1.41 Reportable Event Page 3 1.15 Defined Terms 1.42 Shutdown Margin 1.16 Degree of Redundancy 1.43 Site Boundary l
1.17 Dose Equivalent I-131 1.44 DELETED 1.18 E - Average 01slutegration Energy l
1.19 DELETED 1.20 Identifled Leakage Page 6a 1.45 Source Check 1.46 Surveillance Frequency Notation 1.47 Thermal Power Page 4 1.21 Instrument Channel 1.48 Unidentlfted Leakage 1.22 Leakage 1.49 Unrestricted Area 1.23 Master Relay Test 1.50 DELETED g
1.24 Member (SP of the Pubile 1.51 Venting 1.25 Off-Site AC Power Sources LIMITING SAFETY SYSTEM SETPOINI SAFETY LIMITS 2.1 Protective Instrumentation Setpoints 1.1 Reactor Core 2.2 Protective Equipment Setpoints Bases 1.2 Reactor Coolant System Pressure Bases Amendment Mos.146 and 134 1
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1.0 DEFINITIONS 1.21 INSTRUMENT CHANNEL 1.25 Off-SLIE AC P0HER SOURCs3 An INSTRUMENT CHANNEL shall be the combination of The OFF-SITE A.C. P0HER SOURCES shall be the System sensor (s), signal processing elements, output devices Auxillary Transformer - 142 - (Unit 1); 242 - (Unit and other components and circuitry as required to 2).
The System Auxillary Transformer from the measure and evaluate a process variable for the opposite unit (242 - Unit 1; 142 - Unit 2).
purpose of observation, control and/or protection of the process system. A channel may produce both 1.26 0FFSITE DOSE CALCULATION MANUAL (00CM) analog signal outputs and discrete (signal or electromechanical component operation) outputs.
The The OFFSITE DOSE CALCULATION MANUAL shall contain the channel terminates and loses its identity where methodology and parameters used in the calculation of
' Individual channel outputs are combined.
offsite doses resulting from radioactive gaseous and i liquid effluents, in the calculation of gaseous i
1.22 LEAKM E 11guld effluent monitoring alarm / trip setpoints, and in the conduct of the Environmental Radiological Refer to the following specific paragraphs.
Monitoring Program. The OOCH shall also contain (1) 1.13 CONTROLLED LEAKAGE the Radioactive Effluent Controls and Radioiogical 1.20 IDENTIFIED LEAKAGE Environmental Honitoring Programs required by Section 1.32 PRF.SSURE BOUNDRY LEAKAGE 6.2.6 and (2) descriptions of the Information that 1.48 UNIDENTIFIED LEAKAGE should be included in the Annual Radiological Environmental Operating and Radioactive Effluent 1.23 HASTER RELAY TEST Release Reports required by Specifications 6.6.1.C and 6.6.1.D.
A HASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each 1.27 DEEMBLE - OPERABILITY relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of 1.24 tiEliaER(Sdf THE PUBLLC performing its specified function (s), and when all necessary attendant instrumentation, controls, i
HEMBER(SV0F THE PUBLIC shall include-all-persons,-who-electrical power, cooling or seal water, lubrication are-not-occupationally-associated-with-the-plant, or other auxillary equipment that are required for This-category-doet,-not-include-employees-of the-the system, subsystem, train, component, or device to u t t i t ty;-i t s - con t rac tor s-or-I t s-vendor-s,---Al so-perform its function (s) are also capable of peforming e x c l uded-f rom-th i s-c a tegory-a r e-pe r son s-who-e n t e r-t he-their related support function (s),
site-to service equipment-or-to make deliverlesr This-category does-Include--persons-who-use-portions-The OPERABILITY requirement for both normal and of-the-site-for-recreationalroccupa tional-or-other-emergency AC power supplies does not apply to AC purposes-not-assocJated-with the-plant -
instrument busses and associated instruments.
[ be w 'o$. Ael h o. conb otid - mGstectrb RS A.
pcH.A 6 A;<.A &<_.h e.;ek 3z oc' ~1M Th&uc. Ae,+Mn -
l ha kd'sA&ml Is net nctt8n a
ruom m ecceb
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4 dose.
Amen % nts 146 and 134
i 1.0 DEFINITIONS 1.50 DELETED l
l 1.45 SDURCLCHECK A SOURCE CHECK shall be the qualitative assessment of 1.51 VENTING channel response when the Channel sensor is exposed VENTING is the controlled process of discharging air to a radioactive source.
or gas from a confinement to maintain temperature, 1.46 SURVEILLANCE FREQUENCY NOTATION pressure, humidity, concentration or other operating condition, in such a manner that replapement air or The SURVEILLANCE FREQUENCY NOTATION specified for the gas is not provided or required during venting.
performance of Surveillance Requirements shall-Vent, used in system names, does not imply a venting correspond to the intervals defined in Table 1.2. and process.
General Surveillance Requirement 4.0.2.
1.47 THERNAL PONER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
1.48 UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
1.49 UNRESTRICTED AREA An UNRESTRICTED AREA shall be an rea at-or-beyond the-SI T E-9OUNDARY-to-wh i c h - a c c e s s-I s-n,o t-con t rol l ed
-by-t he-t-I c en s e eJor-pu r po s e s-of-p ro t e c t i on-of-Individuals-fron-exposure-to-radiation-and-radioactive.materlais-or-any-area wlthin-the.-site.
bounda ry-u sed -for-re s i den t I a l-qua r t e r 5-or-for-Industriaircommerclabinstitutional-and/or-g,ce,3, ge, gg;c,g,,3
+ecreat4enal-purposes, no t.ke.-
(a mi f ed.
o, con b-e NJ by b
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6a
' Amendment Nos. 146 and 134
Bases:
3.11.1 001000R L10010 TANKS Restricting the quantity of radioactive material contained in those outdoor tanks spe:lfied, that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have 4.11.1 tank overflows and surrounding area drains connected to the liquid radwaste treatment system, provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table If, Column 2, at the nearestpotablewatersupplyandthenearestsurfacewatersupplyinanshrestrictedjarey7 j
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Amendment Nos. 146 and 134 229a
Bases:
etwle f
Restricting the quantity of radioactivity contained in each gas decay tankf 3.12 & 4.12 individual-at-the-nearest-unrestr4eted-erea-boundary will not exceed 0.5 rem.
FinMBER or w G Fu6 tac-Amendment Hos. 146 and 134 242a
+b 6.2.2 Radiation Protection Proarao 6.2.2.A Radiation control procedures shall be prepared, implemented, and maintained.
These procedures shall specify permissible radiation exposure limits and shall be consistent with the requirements of 10 CFR 20.
The radiation protection program shall meet the requirements of 10 CFR 20.
6.2.2.B High Radiation Area mos (a)
PursuanttoParagraph20)03(c,6Yof10CFRPart20,inlieu7 the " control device" or " alarm signal" 6.2.2.B.1 required by paragraph 20.203(
, each high radiation area, as t,c ened in 10 CFR Part 20, in which the dou. rate intensity-of-radiation is equal to or less than 1000 mrem /hr at 30 cm (12 In.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RHP).
Individuals quallfled in radiation protection procedures or personnel continuously escorted by such Individuals may be exempt from the RHP issuance requiremant during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of Individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously Indicates the radiation dose rate In the area; or a.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset Integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or An individual quallfled in radiation protection procedures with a radiation dose rate monitoring c.
device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the Radiation Work Permit.
309a Amendment Nos. 143 and 132 9
4 6.2 (Continued)
Drills of the emergency procedures described in Specification 6.2.1.0 shall be conducted at the frequency 5.
specified in the Generating Station Emergency Plan.
These drills will be planned so that during the course of the year, communication links are tested and outside agencies are contacted.
The following programs shall be established, implemented, and maintained:
6.
A.
Radioactive Effluent Co!LtLois_P_rcstas A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to HEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably The program (1) shall be contained in the ODCH, (2) shall be implemented by station achievable.
procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
Limitations on the operability of radioactive liquid and gaseous monitoring Instrumentation 1) including surveillance tests and setpoint determination in accordance with the methodology in the
- 00CH, Limitations on the concentrations of radioactive material released in liquid effluents to 2)
UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B. Table JI', Column 2, Honitoring, sampilng, and analysts of radioactive liquid and gaseous effluents in accordance -with.
- 3) GFR-20r106-and-with the methodology and parameters in the 00CH, Limitations on the annual and quarterly doses or-dose-commitment to a MEMBER OF THE PUBLIC from 4) radioactive materials in liquid effluents released from each unit to-UNRESTRIGTED-AREAE conforming to Appendix I to 10 CFR Part 50, Determination of cumulative and projected dose contributions from radioactive effluents for the 5) current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCH at least every 31 days, Limitations on the operability and use of the liquid and gaseous effluent treatment systems to 6) ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose er-dose-commLtment conforming to Appendix I to 10 CFR Part 50, 310a Amendment Nos. 146 and 134
6.2 (Continued)
I Limitations on the dose rate resulting from radioactive material released in gaseous effluents to 7) 2 A
din 6,
-areas beyond-the-SME BOUM0ARY-conforming-to-the-doses-associated-with-10-CFR-Part- 0r ppen MeMI5eR, o rag Nw c..
-Table-t-I r-Goluwt-i,
c c,
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous 8) effluents from each unit to-areas-beyond-the-SITE-BOUNDARY-conforming to Appendix ! to 10 CFR Part 50, Limitations on the annual and quarterly doses to a HEMBER OF THE PUBLIC from Iodine-13),
9)
Iodine-133, tritium, and all radionucildes in particulate form with half-Ilves greater than 8 days In gaseous effluents released from each unit-to-areas-beyond-the-SHE-800NDARY-conforming to Appendix I to 10 CFR Part 50, Limitations on the annual dose or-dose-commitment-to any HEMBER OF THE PUBLIC due to releases of 10) radioactivity and to radiation from urantum fuel cycle sources conforming to 40 CFR Part 190.
B.
Radioloalcal Environmental Monitorina Proaran The A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.
program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the OOCH, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
Monitoring, sangling, analysis, and reporting of radiation and radionuclides in the environment in 1) accordance with the methodology and parameters in the 00CH, A Land Use Census to ensure that changes in the use of areas -at and beyond-the-SITE-BOUNDARY are 2) identifled and that modifications to the monitoring program are made if required by the results of this census, and Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision 3) and accuracy of the measurements or radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.3 Action to be Taken in the Event of a Reportable Event in Plant Ooeration:
Any Reportable Event shall be promptly reported to the Vice President PHR Operations or his designated alternate.
The incident shall be promptly reviewed pursuant to Specification 6.1.7.B.2.(k) and a separate report for each reportable event shall be prepared in accordance with the requirements of 10CFR 50.73.
310b Amendment Mos.146 anti 134
Startup reports sh'all be submitted within 6.6 REPORilNG REQUIREMENTS (a) 90 days following completion of the in addition to the applicable reporting startup test program, requirements of Title 10, Code of federal (b) 90 days following resumption of Regulations, the following identified reports shall commercial power operation, or be submitted to the Director, of the Regional (c) 9 months following initial criticality.
whichever is earliest.
Office of Inspection and Enforcement unless If the Startup Report does not cover all three otherwise noted.
events (i.e., initial criticality, completion of startup test program, and resumption of 1.
Routine Reports A.
Startup Report. A sumary report of comercial power operation), supplementary plant startup and power escalation reports shall be submitted at least every testing shall be submitted following three months until all three events have been (1) receipt of an operating license, completed.
(2) amendment to the license involving a planned increase in power level, B.
Annual Occupational Exposure Report. A (3) lestallation of fuel that has a tabulation covering the previous calendar year d1fferent design or has been should be submitted prior to March 1 of each manufactured by a different fuel year on the number of station, utility and supplier, and other personnel (including contractors) receiving exposures greater than 100 mrem / year (4) modifications that may have Segge,s
-- F "' S" yand their associated marf' rem exposureaccordingtoworkan significantly altered the nuclear, p aent thermal, or hydraullt performance of g gG a the plant.
W eocr'c.
reactor operations and surveillance, inservice
%d ") s inspection, routine maintenance, special The report shall address each of the tests identified in the FSAR and shall in general maintenance (describe-maintenante), waste include a description of the measured values processing,andrefueling) The dose assignments to various duty functions may_be of the operating conditions or characteristics estimates based on pocket dostmetersfTLD,4 r " g obtained during the test program and a comparison of these values with design
-flim badge measurements. Small exposures totaling less than 20% of the individual totel-predictions and specifications. Any dese,need not be_ accounted for.
In the corrective actions that were required to gg aggregate, alleasf~50% of the' total-whole-obtain satisfactory operation shall also be
,Imtant body. dose rece%ved-from-external-sourcesr shall l
described. Any additional specific details required in license conditions based on other be assignrd to specific major work functions, i
comitments shall be included in this report.
/,- T hi s - t a b'Ji a t i on -s uppl emen t 5-the-req u i t emen t s-of-20 ddi-of-10CFR-part-20:
Amendment Nos. 96 and 86 312 0615t/0bl6t 02bbA l
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6.6.2.A. 3.
f.ollowup Notification:
6.6.2.A.2.b (Continued) 4)
a)
Any airborne radioactive /
f release that exceeds 2 times
- With respect to the telephone the applicable concentrations g.,.
of-the-limits specified in,r ',
notifications made under paragraphs endix B. Table f of 10CFR20 6.6.2.A.1 and 6.6.2.A.2 in addition to App $restrictedarea],'when
- 4. b al making the required initial notification, in, averaged over a time period of each licensee, shall during the course of the event:
one hour.
w b)
Any11guldelfluen_tdelease a.
Imediately Report that exceeds T Times the g*
Ilmit4ng-comMned Maw 1 mom
- T!'
1)
Any further degradation in the level of safety of the plant or other (see-Mete-1 foncentration (MPC)uet Appendix B te**~T*Jal* Z. Cole n2 of worsening plant conditions, permiss4He sracNel m including those that require the 10CF3207'at the point of entry declaration of any of the Emergency w t d nio the receiving water (1.e.
Classes, if such a declaration has
/hrestrictedarel)forall radionuclides except tritium not been previously made, or and dissolved noble gases, when averaged over a time period of 2)
Any change from one Emergency Class to another, or one hour.
(lmediate notifications made under this paragraph also satisfy the 3)
A termination of the Emergency Class requirements of paragraphs (a)(2) and (b)(2) of 10CFR 4)
The results of ensuring evaluations or assessments of plant conditions.
20.403 )
tro 2.
5)
Any event requiring the transport of 5)
The effectiveness of response or a radioactively contaminated person protective measures taken to an offsite medical facility Ior 6)
Information related to plant trealment.
behavior that is not understood.
6)
Any event or situation, related to the health and safety of the pubile b.
Maintain an open, continuous comunication channel with the NRC or onsite personnel or protection of Operations Center upon request by,the NRC.
the environment, for which a news release is planned or notification to other government agencias has been or will be made. Such an event may include an onsite fatality or inadvertent release of radioactively contaminated materials.
Amendment Nos. 96 and 86 319 0615t/0616t
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6.6.2.B.1.a (Continued)
(iv)
Any event or condition that
-(VII)
Any event where a single cause or condition caused at least one resulted in manual or automatic independent train or channel to actuation of any Engineered Safety become inoperable in multiple Feature (E5f), including the systems or two independent trains Reactor Protection System (RPS).
or channels to become inoperable flowever attuation of an E5F.
in a single system designed to:
including the RPS, that resulted from and was part of the preplanned sequence during testing A)
Shutdown the reactor and maintain it in a safe or reactor operation need not be shutdown condition; reported.
B)
Remove residual heat:
C)
Control the release of (V)
Any event or condition that alone radioactive material; or could have prevented the f ulfillment of the saf ety function 0)
Mitigate the consequences of an accident.
of structures or systems that are needed to:
(Vill)
A)
Any airborne radioactivity _
^0 release that exceeded,2' times A)
Shutdown the reactor and the applicable concentrations maintain it in a safe of-the-limits specified in shutdown condition;
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Table JG10CFR 2, Cokmn 13y-Appendix B,Mhristrjcted' B)
Remove residual heat:
Part 20 in C)
Control the release of
,i'rea;", when averaged over a radioattive material; or time period one hour.
D)
Mitigate the consequences of B)
Any 11guld effluent, release,,
an accident.
that exceeded 7~ tim _es the limi t ing -c ombined-Ma ximum-(VI)
Events covered in paragraph (V) b c"U '
Permissible,foncentration air above may include one or more procedural errors, equipment specici.A k (MPG) (see-Note-1 of Appendix failures, and/or discovery of nue 2 *h z.V @t V10CFR Part 20) at the point of entry into the design, analysis, fabrication, receiving water (i.e.
construction, and/cr procedural
,dhres_t.ricted_a_rea) f or all inadequacies, flowcver, individual radionutildes except tritium conponent f ailures need not be and dissolved noble gases, reported pursuant to this when averaged over a time paragraph if redundant equipment period of one hour.
in the same system was operable and available to perform the required safety function.
Amendment Nos. 96 and 86 321 Ob111/0610t 026bA
6.6.2.B.I.a (Continued)
(IX)
Reports. submitted to the Comission in accordance with paragraph (VIII) above also meet the effluent release reportl.9 requirements of 10CFR Part 20 paragraph 20.405(+He 12.o 5 (X)
Any event that posed an actual threat to the safety of the plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases.
6.6.3 Unlaue Recortino Reautrements A.
DELETED k
Amendment'Nos. 146 and 134 322-
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6.7 0FFStiE _ DOSE CALCULATION MANUAL (ODCH)
Changes to the 00CH:
a.
Shall be documented and records of b.
Shall become effective after review and acceptance by reviews performed shall be retained as the Onsite Review and Investigative Function, and the required by Specification 6.5.2.S.
The approval of the Station Hanager on the date specified documentation shall contain:
by the Onsite Review and Investigative Function.
1)
Sufficient Information to support c.
Shall be submitted to the Commission in the form of a the change together with appropriate complete, legible copy of the entire OOCH as a part analyses or evaluations justifying of, or concurrent with, the Radioactive Effluent the change (s); and Release Report for the period of the report in which any change to the ODCH was made effective. Each 2)
A determination that the change will change shall be Identifled by markings in the margin maintain the level of radioactive of the affected pages, clearly indicating the area of effluent control required by 10 CFR the page that was changed, and shall Indicate the 20,10fr, 40 CFR Part 190,10 CFR date (e.g., month / year) the change was implemented.
56.36a and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
325 Amendment Nos. 146 and 134
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h ATTACHMENT C EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION FOR i
LICENSING Al\\ENDhENT REQUEST NO. 93-08 l
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i EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION FOR
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LICENSING AMENDMENT REQUEST NO. 93-08 i
Commonwealth Edison has evaluated this proposed amendment and determined j
that it involves no significant hazards considerations. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards if operation of the facility in accordance with the proposed amendment would not:
1.
Involve a significant increase in the probability or consequence of an accident previously evaluated; or 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.
Involve a significant reduction in a margin of safety.
The proposed amendment makes several changes to Zion's Technical Specifications which are necessary to implement the htest revision to 10 CFR Part 20,
" Standards for Protection Against Radiation". These changes includes: 1) revised I
definitions for " Member (s) of the Public" and Unrestricted Area',2) the correction of references made to 10 CFR Part 20,3) incorporation of the term " Deep Dose Equivalent" and 4) conforming administrative and editorial changes.
i The following evaluation is provided for the three categories of significant hazards consideration standards:
l 1.
Does the proposed change involve a significant increase in the probability or consequence of an accident previously evaluated?
The proposed change to the Technical Specifications does not affect any accident initiators or precursors and does not change or alter the design assumptions for the systems or components used to mitigate the consequence of an accident. The proposed change only involves administrative and editorial changes which are necessary to implement the latest version of the 10 CFR Part 20 standard. The purpose of the revision to 10 CFR Part 20 was to modify the NRC's radiation protection standards to reflect developments in the principles and scientific knowledge underlying radiation protection that have occurred since part 20 was originally issued more than 30 years ago. These developments not only include updated scientific information on radionuclide uptake and metebolism, but also reflect changes in basic philosophy of radiation protection. Incorporation of these changes will ensure that part 20 and Zion's Technical Specifications continue to provide adequate protection of public health and safety. As such, the proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
1 i
2.
Does the proposed change create the possibility of a new or different kind j
of accident from any previously analyzed?
The proposed change does not necessitate a physical alteration of the plant (no new or different type of equipment will be installed) or changes in the i
parameters governing normal plant operation. The proposed change is administrative and editorial in nature and is intended to provide l
consistency with the latest version of the 10 CFR Part 20 standard. Thus i
this change does not create the possibility of a new or different kind of
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accident from any accident previously evaluated.
l 3.
Does the proposed change involve a significant reduction in a margin of safety?
The margin of safety is not affected by this change. The initial conditions I
and methodologies utilized in the accident analysis remain unchanged.
Thus, accident analysis results are not impacted. The proposed change consist of administrative and editorial and therefore does not result in the increase in individual or cumulative occupational radiation exposure. The protection ofindividuals against radiation will be enhanced based on the revised requirements of the 10 CFR Part 20 standard which imposed l
additional restrictions relative to the exposure of radiation. The proposed change does not change the type or increase the amount of any radioactive effluent released from the station. The release of radioactive effluent from the station will continue to remain within the design objectives specified in
-t 10 CFR Part 50, Appendix I. Therefore, this change does not involve a significant reduction in a margin of safety.
Based on the above evaluation, Commonwealth Edison has concluded that these changes do not involve a significant hazards consideration.
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ATTACHAENT D ENVIRONhENTAL ASSESSAENT FOR l
LICENSING AhENDAENT REQUEST NO. 93-08 i
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ENVIRONMENTAL ASSESSMENT FOR LICENSING AMENDMENT NO. 93-08 Commonwealth Edison has evaluated the proposed amendment against the criteria for and identification oflicensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. It has been j
determined that the proposed change meets the criteria for a categorical exclusion t
as provided for under 10 CFR 51.22(c)(9). This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant i
to 10 CFR 50, it involves changes to surveillance requirements and the amendment meets the following specific criteria:
(i) the proposed change involves no significant hazards consideration as evaluated in Attachment C of this License Amendment Request; (ii) there is no significant change in the types or significant increases in the amounts of any efiluents that may be released from offsite;
- and, (iii) there is no significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criteria for categorical l
exclusion set forth in 10 CFR 51.22(c)(9). Based on the aforementioned and pursuant to 10 CFR 51.22(b), no environmental impact statement or enviromnental assessment needs to be prepared in connection with the issuance of this amendment to the license incorporating the proposed change.
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