ML20115G028

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Proposed Tech Specs Re Compliance W/New Requirements of 10CFR20 to Reflect Implementation of Radiation Protection Program
ML20115G028
Person / Time
Site: Clinton Constellation icon.png
Issue date: 10/16/1992
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20115G027 List:
References
NUDOCS 9210230316
Download: ML20115G028 (13)
v • d • e


Text

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Attachment 2 to U-602052 .

, , LS-92-001

. Page 4 of 16 OEFINITIONS _

FRERuf9CY NOTATION 1.17 The FREQUENCY NOTATION specified for the performance of surveillance r2quirements shril corra.5 pond to the intervals defined in Table 1.1.

1.10 DELETED g

IDENTIFIED LEAKAGE.

i 1.19 IDENTIFIED LEAKAGE shall be: ~

a. Leakage int collection systems, such as pump seal or valve packing leaks, that is :. ptured cnd conducted to r sump or entlecting tank or h.' Leakarje into the drywell atmosphere from scurces that are both specifically located and known either not to intarfere with the operation of the leakage I detection systems or not to be PRFC%E BOUNDARY LEAKAGE.

MMITINGCONTROLR00 PATTERN 1.20 A LIMITING CONTROL R00 PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e. , operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE 1.21 ' LINEAR HEAT GENER*. TION RATE (LHGR) shall be ,the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

  • LOGIC SYSTEM FUNCTIONAL TEST 1.22 A LOGIC SYSTEM FUNCTIONAL 1EST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc., of a logic circuit from sensor throup and including the cctuated device to verify OPERABILITY, The LOGIC SYSTEM FUWJ.IONAL TEST nay be per-formed by any series cf sequential, . overlapping or total *ystem sttis such that the entire legic system is tested.

1 23 [ DELETED)

MEMBER (S)0FTHEPUBdC ,

lude-414-peesons-whcarc netw-upat4ena14y-1.24 MEMBER (S) 0F THE PUBLIC shall

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LS-9'-001 Page 5 of 16 ONS OfffN]I  :

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HlHlHUM CRITICAL POWER T RATl_0 1.25 The exists HINIMUM in the core. CRITICAL POWER RATIO (MCPR) shall be the smallest CP '

OFFSITEDOSE_CALCULATIONMANUAL(00C5)b 1.26 The OFF!,ITE DOSE CALCULATION MANUAL (0.0CH) shall contain the methodology

- and parameters used in the calculation of offsite doses resulting from radioactive gaseous and ifquid effluents, in the calculation of gaseous and itqu.d effluent monitorinn Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The OOCH shalt also contain 1

(1) the Radioactiw Cf fluent Controls and Radichgical Envirot. cntal .

Honitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environme tal Operating and Semianntd Specifications 6.9.1.6 andRadioactive 6.9.1.7. Effluent Release Reports required i;-

OPERABLE - OPERABILITY l.27 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and,when all necessary attendant instrumentation, cont.rols, electrical. power, cooling or seal dater, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support fu.stion(s).

OPERATIONAL CONDITION - CONDITION 1.28 An OPERATIONAL CONDITION, i.e. , CONDITION, shall be any one inclusive com-bination of mode switch position and avet age reactor coolant temperature as specified in Table 1.2.

PHYSICS TESTS 1.29 PilYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor :: ore and related instrumentation as 1) described in Chapter 14 of the FSAR, 2) as authorized under the provisions of 10 CFR 50.59, or 3) as otherwise approve i by the Commission.

PRESSURE BOUNDARY tEAKAGE 1.30 PRESSURE SOUNDARY LEAKAGE shall be leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall' .

CLIN")N - UNIT 1 1-5

,. Attachment 2

'. . to U*602052 DEFINITIONS LS-92-00)

Par,e 0 of 16 JURBINE DYPASS SYSTEM AESPONSE TIME (Continued) until initial movement of the turbine bypass valve. Either response time may be themeasured entire response by anytfac series of sequential, overlap,-Ing, or total steps such that is measured.

UNIOENTIFIED LEAKAGE 1.47 UNIDENTIFIED LEAKnGE shall be all leakage which is not IDENTIFIED LEAKAGE. -

UNRESTRICTEDARg ngg l[g*q,d W l.48 An UNRESTRICTED AREA shall be any area j et :r beyond-the >ME-BOUNDARY-access to which is-notr c1ntrolled by the licensee.fomeposs,-of-protecGon-of.

4ndividuals from-exposure-towadiation-and-radioastrive--mateelois-or-ony-area.

d tH n-the-S I TE-DOUNDARY-used--fo n-re s iden tri a l-<tua rt ees-o e-foe-i ndus t e4 aly

-commercial i -institutionalv-and70erecreat4onal-purposee 1.49 DELETED VENTING 1.50 VENTING is the contro11e'd process of discharging air or gar from a con-finement to maintain temperature, pressure, humidity, concentration or other operating condition. In such a manner that replacement air or gas is not pro-vided or required during VENTING.

VENTING process. Vent, used in system names, does not imply a S

l CLINTON UNIT 1 1-9 i

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Attachm(nt 2 l to U-602052

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Y 1.5 92-001 1

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ADMIN 15drfIVL CON 1kOLS PROGRAMS 6.8.4 The is11owing pro' grams shall be estabitsbed, impleented, and maintained:

a. Primary Coolant tources outside Containment .

A program to reduce lestaga'from those portions of systems outside containment that* could contain highly redioactive fluids duriig a serious transient or acci-dent to as low as practical levels. The systems include the LPCS, hPCS, RHR, RCIC, Suppression Pool Makeup. Combustible Gas Control, Containment Honituring and Post-Accident Sampling. The program sha)) include the fol'owing:

1. Preventive maintenance and periodic visual inspection requirements, and
2. Integrated leak test requirements for each system at refueling cycle intervals or less. .
b. In-Plant Radiation Honitorin,j A program which will ensure the capability to accurately determine the airborne lodine concentration in vital areas under accident conditions.

This program shall include the following:

1. Training of personnel.
2. Procedures for monitot ing, and
3. Provisions for nalntenance of samplin'g and analysis equipment.

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4 c. Postaccident Sampling .

A pr'ogram which will ensure the capability to ottain and aniilyze reactor

.it coolant, radioactive iodines and particulates in plant gaseous ef fluents, -

ano containment atmosphere samples under accident conditions. The program shall include the following:

1. Training of personnel.

"'.- Procedures for sample and analysis, and J. Provisions for maintenance of samp1(pg and analysis equipment,

d. Ultimatr Heat Sink Erosion. Sediment Honitoring and Oredging Program ,

A program to provide maintenance on the ultimate heat sink (UHS.) in the event inspections of the UHS du.s its abutments or the UH5 shoreline indicates crusion or local instability. This program shall ensure that the UHS is maintained in such a way to achieve the following objectives:

(1) During normal operation, there will be a volume of water in the UPS below elevation 6~/5 sufficient to receive the sediment load from a once in 25 year flood event, and (2) Still be adequate to maintain the plant in a safe-shutdown condition for 30 days under :aeteorological conditions of the severity suggested by Regulatory Guide 1.27.

e. Fire Protection Program A program to implement and maintain in effect all provis ons of the approved fire protection program as described in the final Safety Analysis Report as amended, and as approved in the Saf ety Evalt.ation Report (NUREG-0853) dated february 1982 as supplemented. tioncompliance with the above Fire Protection Systems described in plant procedure CPS Ho, 1893.01 shall be reported as a REPOPTADLC EVENT in accordance with Section 6.6.1 of these 3 Technical Specifications.

CLINTON - UNIT 1 6-16

- _ _ _ . - - . . - - . - . . . - _ . - . - - . - . - _ - - - - - .-:.__~-_.-.

4 Attachment,2 to U-602057 13-97-001 i Page 8 of 16 ADMI R51HATIVE CONTROIS

, PROGRAH5

f. Radioactive fffluent Controls Program A program shall bn provided conforming with 10 CfR 50.36a for the contrni of radioactive efiluents and for maintaining the doses to HEMBERS OF Tile PUBLIC from radioactive effluents as low as reascnably achievable. The program (1) shall be, contained in the OOCH, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits ard exceeded. The program shall include the following elements:
1. Limitations on the operability of radioactive Ifquid and gaseout monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the 00CH:
2. Limitations or, the concentrations of radioactive material released Appendix 6, Table 4g, Column 2;inliquideffluentstoUNRES
3. Honitoring, sampling, and analysis of rc.dioactise liquid and gaseous effluents in accordance with 10 CFR 20.406-and with the methodology and parameters in the OOCH; (
4. Limitations on the annual and quarterly doses or dose commitment to a HEH8ER OF V'E PUBLIC from radioactive materials in Ifquid ef fluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 30 CFR Part 50;
5. Determination of cumulative and pro #cted dose contributions from radioactive ef fluents for the current calendar quarter and current

, calendar year in accordance with the methodology and parameters _in the OOCH at least every 31 days;

6. Limitations on the operability and use of the liquid and caseou:s effluent treatment systems to ensure that the appro riate 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 pidelines for the annual dose or dose commitment conforraing to i Appendix I to 10 CFR Part 50-l 7. Limitations on the dose r.te resulting from radioactive material released in gaseous ef fisents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table. -1+, Column 1; w@

CLINTON - UN11 1 6-16a l

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Attachment 2 y to U-602052 ,

LS-92-001 I a"'""- l

{do tba.v\.3e.<> . Pmaa & can Wnua enty. '

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A_0MINISTRATIVE CONTROLS

~

PROGRAHs ,

Padioactive Effluent Controls Program (Continued)  !

8. Limitations on the annual and quarterly air doses resulting from

. noble gases released in gaseous effluents-from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50;

9. Limitations on the annual and quarterly doses to a HEMBER OF THE PUBLIC from 16 dine-131, Iodine .* 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released 'irom the unit to areas beyond the SITE BOUM0ARY conforming to Appendix I to 10 CFR Part.50; and
10. I, imitations on the annual dose or dose commitment to any HEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
g. Radiological Environmental Monitoring Program -

A program shall be provided to monitor the radiati'on a.1d radionuclides in the environs of the plant. The 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 ODCH, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methedology and parameters in the OOCH;

! 2. A Land Use Census to ensure that. changes in the use of areas at and I beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by.the results of this census; and l 3. Participation in an Interlaboratory Comparison Program to ensure that

( independent checks on the precision and accuracy of the measurements l

of radioactive materials in environmental sample matrices are-I performed as part of the quality assurance program for environmental monitoring.

9 l

CLINTON - UNIT 1 6-16b t

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4 At tachraen t 2, to U 602052

1.92-001

, Paga 10 of 16 i l

ADHINISTRA1!VE C0!41ROL5 L-l 6.9 REPORTING Rf00!RfMflH5 l ROUtlNE RfPORTS ,

6.9.1 in addition to the app 1! cable ' reporting requirements of Title 10. Code l of Federal Regulations, the following reports shall be submitted to the Regional i Administrator of the Regional Office of the NRC unless othervise not.d.

.'- STARTUp REPORT 4

6. 9.1.1 A summary report of plant startup and power etcalation testing shall 1 be submitted following (1) receipt of an Operating License, (2) amendment to .

the license involving a planned increase in power level, (3) installation of fuel that has a dif ferent design or has been manufactured by a dif ferent fuel supplier, and (4) modifications tha'. may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

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6.9.1.2 The startup report shall address each of the tests identified in the '

Final Safety Analysis Report and shall include a description of the measured d values of the operating conditions or characteristics obtained during the. test Q program and a comparison of these values with design predictions and specifica-6 tions. Any corrective actions that were required to obtain satisfactory opera-

. .) tion shall also be described. Any additional specific details required in .

license conditions based on other commitments shall N included in this report. '

' .' , , ' , 6.9.1.3 Startup reports shall be submitted within (1) 90 days following com-pletion of the startup test program, (2) 90 days (cllowing resumption nr com-

. mencement of commercial pover operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all j three events (i.e., ini,tf al criticality, completion of startup test program, and 3(y~ resumption or commencement of commercial operation) supplemntary reports shall

- be submitted at least every 3 months until all-three events have been completed.

ANNUAL *REPOR15 6.9.1.4 Annual reports ccvering the activities of the unit as described below for the pre <ious calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial crituality.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater-than' 100 mreta/yr and their associated man rem expose e according to work, and job f unctions" (e.g. , reactor operations and surveillance, inservice .in-spection' routine maintenance, special maintenance, waste processing, and +

refuelings). The dose assignments to various duty functions may be

%2o6  :

"This tabulation supplements the requiiuents of $20. 7-of 10 CFR Part 20.

CLINTON - UNIT 1 6-17 c

l

Attachment 2 Chn evje9 . r'rNihec) .fev Cordirius Ort h , to U-602052 i

/ 1.S-92-001 {

A _f Pnee 11 of 16 AfDjilHISTRATIVE CONTROL $

MONTHLY _0PERATING Rf}0RTS 6.9.1.8 Routine reports of operatt.jg statistics and shutdown experience,  ;

including documentation of all challenges to the uain steam system safety / ,

relief valves, shall be submitted on a (nonthly basis to the Document Control '

Desk, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Ith a copy to the Regional Administrator of the Regional Office of the NRC, no later than  !

the 15th of each month following the calendar month covered by the report.

CORE OPERATING L: HITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LlHITS REPORT before each reload cycle or any remaining part of c r reloa'd cycle. The analytical methods used to determine the core operating 'l limits shall be those previously reviewed and approved by the NRC in General i i Electric Standard Application for Reactor fuel (GESTAR), NE0E-240ll-P-A 8, as attended (latest approved version) and Maximum Extended Operating Domain and Feedwater Heater Out-of-service Analysis for Clinton Power Station.

NEDC-3154FP, August 1988. The core operating limits shall be determined so that all application limits (e.g., fuel thennal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as S!!UTOOWN MARGIN, and transtent and accident analysis limits) of the safety analysis are met.

THC CORE OPERATING LlHITS REPORT, it.cluding any mid-cycle revision or supplements theretu, for each reload cycle, shcIl be submitted upon issuance to the NRC Document Control Desk with copics to the Regional Administrator and Resident '

Inspector.

SFECIAL rep 0RTS 6.9.2 Special reports stall be submitted to the Regional _ Administrator of the Regional Office of the NRC within the time period specified for each report.

6.10 LECORD RETENTION 6.10.1 In addition to the applicable record retention requi ements of Title 10, Code of federal Regulations, the following records shall be retained for at least the minimum period indicated. '

6.10.2 The following records shall be retained for at least 5 years:

i

a. Records and logs of unit operation covering time interval at each power level.
b. Records and logs of principal maintenance activities, inspections, repair, and replccement of principal items of equipment related to nuclear safety.
c. All REPORTABLE EVENTS.
d. Records of surveillance activities, inspections, and calibrations requircJ 1- by these Technical Specifications and the F;re Protection Program.

CLILTON - UNIT 1 6-21 y n--ey., ,-, ,,n,-r -my ,,,,,,,,--,<,,.,w.wr,, , ,-_m- - . , . n e ..--...n . . . - - _ , , . ,,nwa ,m.< ,,,. a w.,_,, , . , - , - + . -

Attachment 2 to U-6020$2

. LS92-001 l'a g e 12 of 16 ACHINISTRATIVE CONTROLS RECOPD RETENTION (Continuedl

e. Records of changes made to the procedures required by Specification 6.0.1.

-f. . R e c o rds-o f-44dioact. W4-shipments,-.

f -43 Records of sealed source and fission detector leak tests and results.

s g .N Records of annual physical inventory of all sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the final Safet;' Analysis Report,
b. Records of new and irradiated fuel inventory, fuel transfer's, and '

assembly burnup histories.

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c. Records 4 d i a t4 o n-e x po s u re-fe e- eM--i n d i v i du a l s-e n t e e i ng--ea d ie tton-.

-<ontrol-areas, i d. Records of gaseous and liquid radioactive material released to the -

envirnns.

c. f',. ords of transient or operational ~ cycles for those unit components a identified in Table 5.7.1-1.
( Records of reactor tests and experiments.

l' f.

g. Records of training and qualification for current members of the unit staf f.
h. Records of inservica inspections performed pirsuant to these Technical j Specifications,
i. Records of' quality assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.2, which are classi-fled as permanent records by applicable regulations, codes, and standards.

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j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k. Record:, of meetings of the FRG and the NRAG.

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CLINTON 'JNIT 1 6-22

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Attachment 2 {

to 11-6020$2 l 1.S92-001 I

.O. Mecon.lu c# md.tootclth Os.preds .

, page 13 or 16 A

ADMINISTRATI\E CONTROLS ,

z kECORD RETENTION (Continued)

1. Records of the service lives of all snubbers including the date at which the service life connences and associated installatian and maintenance records. .

m.

Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at speciffeu times and QA records showing that these procedures were followed.

n .' Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

_6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consis- '

tent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation'exposur;.

6.12 IIIGli RADIATION AREA .

D - d2.1 In lieu of the " control device" or " alarm signal" requited by paragraph

' 207203(+}Q}-of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspricuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).* 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. A radiation monitoring device which continuously indicates the radiation dose rate in the area,
b. A r&diation monitoring device which conti,nuously 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,

c. A health physics qualified individual (i.e., qualified in radiation pro-tection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency l j4g specified by the Radiation Protection Supervisor in the RWP.

.12.2 In addition to the requirements of Specification 6.12.1, areas access-ible to.penonnel with radiation levels such that-a at er pertic ref the bed)-

could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .t dos 3 greater than 1000 mrem *A shall be provided with 4 /,, locked doors.to prevent unaathorized entry, and the keys shall be maintained i p. an Individvol

" Radiation prot.cction personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement for fields of less than 3000 mrem per hour during the performance of their assigned radiatiori pro-tection duties, provided they are otherwise following plant radiation protec-tion procedures for entry into high radiation areas.

" Measurements made at 18 inches from sources of radioactivity.

CLINTON - UNIT 1 6-23

Attachment 2  !

to 11 >602052 '

LS-92-001 l' age 14 of 16

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ADMINISTRATIVE CONTROLS U)

. under the administrative contr61 of the Shif t Supervisor or duty and/or the lim *y}clua f, Radiation Protection Supervisor. Doors shall remain locked except during W periods of access by personnel under an approved WP.* for .4n44444al- areas  ;

accessible tot;:enene!= with radiation Icvels such that -a-nfee-pa*4A+a ,

,n -tk- he:PI-could receive in I hour a dose in n excess of 1000 mrem ** that are uwcleh located within large areas, such as the containment, where no enclosure

  • exists for purposes of locking, and no enclosure can be reasonably constructed around tSe individual areas, then that area shall be recea off, conspicuously

, ,- posted, and a flashing light shall be activated as a warning device, mchvidvd .12.3 In addition to the requirements of Specifications 6.12.1 and 6.12.2, for -indivkiwe areas accessible tBewsand such that 2 ej; po44en-+4 +

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$y'4.J bthe be+/- could receive in I hour a deseain excess of 3000 mrem,^ entry shallrequire a work area and require that stay times .shall be established. g jggjgA In lieu of the stay time specification of the RWP, continuous surveillance, dirert or remote (such as use of closed circuit TV cameras), may be made by personnel qualified in radiation protection procedures to provide positi,ve exposure control over the activities within the area. ,

6.13 PROCESS CONTROL PROGRAM (PCPl Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.n. This documentation i shall contain:
1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and
2. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of federal, State, or other applicable regulations,
b. Shall become effective after review and acceptance by the FRG and the approval of the Manager - Clinton Power Station.

I

  • Radiation protection personnel or personnel escorted by radiation protection pomonnel shall be exempt from the TNP issuance requirement for fields of less than 3000 mrem per hour during the perfornnce of their assigned radia-tion protection duties, provided they are otherwise following plant radiation.'

protection procedures for entry into high radiation areas.

" Measurements made at 18 inches from sources of radioactivity.

CLINTON - UNIT 1 6-24 l'

l.

Attachmont 2 to U-602052  ;

, LS-92-001 Page 15 of 16 ADHl's!STPATIVE CONTROLS v.14 ,0FFSITE DOSE CALCUIATION MANUAL (00CM)

Change' to the OOCH:

l

a. Shall De documented and records of reviews performed shall be  !

retained as required by Specification 6.10.3.n. This documentation l shall contain: 1

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying th e(s),and

/302.

2. A determination that the change will maintain the ve f radioactive effluent control required by 10 CFR 20A0 ,' 40 CFR Part ]90, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and

. not adversely 16 pact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective af ter review and acceptance by the FRG and the approval of the Hanager - Clinton Power Station.
c. Shall be' submitted to the' Commission in the form of a complete, legible copy of the entire OOCH as a part of or concurrent tith the Semiannual Radioactive Effluent Release Report for the period of the report in whicn any change to the OOCH was made. Each change shall be identified by markings in the margin uf the affected pages, clearly indicating the area of the page that was changed, and shall -

indicate the date (e.g., month / year) the change was implemented.'

1 l

i CLIN 10N < UNIT 1 6-25

. Attachment 2 to U-602052 LS-92-001 )

Page 16 of 16 Pt ANT SYSit'HS BASES 3/4.7.4 TVUBBERS(Continued] 9 etc. . . . The requirement to monitor the snubber service life is included to ensu.a that the snubbers periodically undergo a performance evaluation in vie.,

of their age and cperating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

3'4.7.5 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that Icakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups a: cording to their use, witt surveil-lance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often th.

  • hose which are not. Scaled sources which are continu-ously enclosed withi shielded mechanism, i.e., sealed sources within radia-tion monitoring devices, are considered to be stored and need :.ot be tested unless they are removed from the sh Nided mechanism.

3/4.7.6 MAIN TURBINE BYPASS SYSTEM

. The main turbine bypass system is required to be OPERASLE consistent with the assumptions of the feedwater controller failure analysis in FSAR Chapter 15.

3/4.7.7 t!0VID STORAGE TANKS The tanks listed in this Specification include all those outdoor storage tanks that are not surrounded by liners, dikcs, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in each of the specified tanks provides assurance that in the event of an unct.ntrolled release of the contents frou any of these tanks, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B Table 44,% l Column 2, at the nerest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

1 CLINTON - UNIT 1 B 3/4 7-3 s -

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