ML20128M673
| ML20128M673 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/17/1993 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20128M672 | List: |
| References | |
| NUDOCS 9302220246 | |
| Download: ML20128M673 (14) | |
Text
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- 6 2 LS-92-001 Page 4 of 16 DEFINITIONS FREQUENCY NOTATION 1.17 The FREQUENCY NOTATION specified for the performance of survelliance requirements shall c6rrespond to the intervals defined in Table 1.1.
1.18 DELETED IDENTIFIED LEAKAGE 1.19IDENTIFIEDLEAKAGEshallbe:
- a. Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting ' tank or t.* Leakage into the dryvell atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.
LIMITING CONTROL ROD PATTERN 1.20 A LIMITING CONTROL ROO PATTERN shall be a pattern which results in the core being on a thermal hydraulic ilmit, f.e., operating on a limiting value for APUlGR, U1GR, or HCPR. LINEAR HEAT GENERATION RATE 1.21' LINEAR HEAT GENERATION 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 MSTEM FUNCTIO'NAL TEST 1.22 A LOGIC SYSTEM FUNCTIONAt. TEST 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 through and including the actuated device to verify OPERABILITY. ' The LOGIC SYSTEM FUNCTIONAL TEST may be per-formed by any series of sequential, . overlapping or total system steps such that the entire Icgic system is tested. 1.23 [ DELETED) HEMBER(5) 0F THE PUBLIC= 1.24 HEMBER'(5) 0F THE PUBl.IC shall a nclud: 211 p;r: n: uhe :re n+t :: cup:t!:n:11y -
-:::0 !:ted !th th: planL. Th!: ::teger; de:: net 4 n: hde employe : ef th e
cen::c, !t: centracter: er tender:. ":: cichd:d in; tW-eategor/ r: '
v , - - k <tn incl lvsk) n a.' ccMrclied cw LhlRecinucrst> AceA . $owaver, c1s kdlvldal is notct MdMEcg oF 7thE.TuBLtc duf etny geAad.
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9302220246 930217 A PDR' ADOCK-05000461 , -- N P PDR .1-4
. Attachment 3
- to U-602099 Page 2 of 14 83 Guy lEmeM {rtNING.5 no CL c b b M .i C 6.
AW}&b b WIS Attacionent 2
^ ^ > ;.s.E%f' Par,e 5 of 16 DEFINITIONS C
-WMUlf4)-OF-TifE-Af0 EIC-{Co n t4e e d 1--
-pe r sono s-kho-en ter-the-s4 te-to-s e rvi ce-equ i pmen t-o r-to.aa ke-del 4 v e ri e s.---This-.
-categ' ry-dces-include-persons-who-use-poet 4ons-of-the-site-foe-recreationah.
--oc<upa ti onal-o e-e t hee-pu rpo s e s-no t- a s soc i a ted -w i th-the-pl a n t,.---
HI IMUN CRITICAL POWER RATIO 1.25.The exists HIAINUM in the core. CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which OFFSITE DOSE CALCULATION HANUAL (OOCH) 1.26 The OFFSITE DOSE CALCULATION MANUAL (0.0CH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Ala6a/frip Setpoints, and in the conduct of the Environmental Radiological Honitoring Program. The 00CH shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating Specifications and Semiannual 6.9.1.6 andRadioactive 6.9.1.7. Effluent Release Reports required by OPERABLE - OPERABILITY 1.27 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) andyhen all necessary attendant instrumentation, controls, electrical power,' cooling or seal v'ater, 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 function (s). OPERATIONAL CONDITION - CONDITION 1.28 An OPERATIONAL CONDITIOM, i.e., CONDITION shall be any one inclusive com-. bination specifiedofinmodeTableswitch 1.2. position and average re, actor coolant temperature as PtifSICS TESTS 1.29 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core 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 approved by the Commission. PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a 'nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall. CLINTON - UNIT 1 1-5 l
Attachment b to U-602099 g . Ttds suppe-nenp pvides no Page 3 of 14 CL t\ bha C 6f . h.}CS N ~ 073;;;2 LS-92-001
- DEFINITIONS Page 6 of 16 TURBINE BYPASS SYSTEM RESPONSE TIME (Continued) until initial movement of the turbine bypass valv.e. Either response time may be measured by any series oT sequential, overlapping, or total steps such that a
- the entire response time is eneasured.
UNIDENTIFIED LEAKAGE 'g 1.47 UNIDENTIFIED LEAXAGE shall be all leakage which is not IDENTIFIED LEAXAGE UNRESTRICTED AREA h$ b IN Mr [ 1.48 An UNRESTRICTED AREA shall be any area t er $0y:cd the-SITE-BOUNDARY-- ! access to whict. is-not. controlled by the It;:ensee.f;r c purp;se: c(-peetection-of-l 1
.indiv4Mk fron-exposure-to-radiatien :nd r-adioactive-eaterials-oc-any Orc =
i
-within-the-SITE SOUM0?2Y esed-for-resident 4a1 q:: rice :r fee-Gdvitelab
=ctr ct:MastitutionaWod?cr recreat4enal purp;ses.-
, 1.49 DELETED VENTING 1.50 VENTING is the controlle'd process of discharging air or gas from a con-finement to maintain temperature , pressure, haaldity, concentration or other operating condition, in such a manner that replacement air or gas is not pro-vided or required during VENTING. Vent, used in system names, does not imply a l VENTING process. r 4 4 4 i 4 i 4 a t 3 CLINTON - UNIT 1 1-9 )
)
Attachment 3 to U-602099
- e. Page 4 of 14 I 5 $4PflbeM ptdtdes no AdM$
Cbf\ges, b btb m ._ e A_ / Attachment 2 to U-602052 ] 1.S-92-001 e cbges. hWded & con +;nvig cmly. . & ^ A ADHINISTRATIVE CONTROLS PROGRAMS 6.8A The following programs shall be established, implemented, and maintained
- a. Primary Coolant Sources outside Containment A program to reduce leakage' free those portions of systems outside con dent to as low as practical levels. The systems include the 1.PCS, !{PCS, RHR, RCIC, Suppression Pool Hakeup, Combustible Gas Control, Containment Monitoring and Post-Accident Sampling. The program shall include the following: '
L- 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 Honitoring 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. fraining of personnel,
- 2. Procedures for monitoring, and
- 3. Provirions for maintenance of samp1 trig and analysis equipment.
- c. Postaccident Samoling A pr'o gram s.hich will ensure.the capab(11ty to obtain and arGlyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The' program shall include the foliciing:
- 1. Training of personnel,
- 2. Procedures for sample and analysis, and
- 3. Provisions for maintenance of sampling and analysis equipment.
- d. Ultimate Heat sink Erosion. Sediment Monitoring and Dredginq Program in the i A program to provide maintenance ,on the ultimate heat sink (MIS)line event inspections of the mis. dam, its abutments or the (At5 shoie
' indicates erosion or local instability. This program shall ensure that'
~
the utS is maintained in such a way to achieve the following objectives: (1) During normal operation, theie will be a volume of water in the uts below elevation 675 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 meteorological conditions of the severity suggested by Regulatory Guide 1.27.
- e. Fire Protection Program A program to implement and maintain in effect all provisions of the approved fire protection program as described in the Fina'1 Safety A dated February 1982 as supplemented. Moncompilance with the above Fire Protection Systems described in plant procedure CPS Ho. 1893.01 shall be reported as a REPORTABLE EVENT in accordance with Section 6.6.1 of these Technical Specifications.
6-16 Ct.INTON - UNIT 1
Attachment 3
, to U-602099 Page 5 of 14 Attachment 2 to U-602052 LS-92-001 Page 8 of 16 ADMINISTRATIVE CONTROLS PROGRAHS
- f. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive ef fluents and for r.alntaining the doses to HENBERS OF THE PUBLIC from radioactive effluents as low as reasonably 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 are exceeded. The program shall include the following elements:
- 1. Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint t n accorchnee_vith the methodo]oov in_the_0 *
+rn-HMes f e C*ncen+6HvWo.tues ivs' IOc$ic i%.it 0] t 0e _- t.O, 'L40 I n
2. Limitations onUNRESTRICTED in liquid effluents to the concentrations of radioactive AREAS conforming to @6-CfC"d materialreleaseu@ Appendix B, Table -Ig, Column 2; Q j
- 3. Honitoring, sampling, and: analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.-106 and with the methodology and parameters in the OOCH;
- 4. Limitations on the annual and quarterly doses or dose ~cocultment to a HEMSER OF THE PLSLIC from radioactive materials.in liquid effluents released from the unit to UNRESTRICTED AREAS confonains to Appendix I to 10 CFR Part 50;
- 5. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quartier and current calendar year in accordance with the methodology and parameters in the 00Cil at least every 31 days;
- 6. Limitations on the operability and use of the liquid and gaseous effluent treatment systems to 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 or dose commitment conforming to Appendix I to 10 CFR Part 50;
^
i V
- 7. Limitations on the dose rate resulting from radioactive material released in gaseous ef fluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B.
Table % Column 1;
~ / sN RF.ftAct vJm) ATTAdko Ct.IhTON - UNIT 1 6-16a
-. . , , - = .. . . . . . .. . ..-. . . . - - - .. .-.- . _ . . .
t d Attachment 3 , to U-602099 l . Page 6 of 14 Insert for pare 6-16a
- 7. Limitations on the dose rate resulting from radioactive material
- releaseu in gaseous effluents from the site to areas at or beyond l-the SITE BOUNDARY shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrem /yr to the i total body and less than or equal to 3000 mrem /yr to the
! skin, and 4 i
- b. For Iodine-131, for Iodine-133, for tritium, and for all i radionuclides in particulate form with half-lives greater
- than 8 days
- Less than or equal to 1500 mrem /yr to any l- crgan; i
i i 4 i 1 i 4 t i 4 i i a 4 4 a 5 i c
+ nn,. , e - ,ve, e-, , ~e -e- . < 4 .+m-. , ,ne,,m---.e, emme, e -. ~ , +-w-, y
Attachment 3
. to 'JF602099 ff fNe s KO Page 7 of 14 Qdhl tka.p -
d r 4ki pge. Attachment 2 to U-602052 LS-92-001 ra" ' " 6 No thaap . Proviaea & ce&og miy. A - ADMINISTRATIVE CONTROLS PROGRAMS Radioactive 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 areis 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-133, tritium, and all radionuclides in particulate form with t alf-lives gre .ter than 8 days in gaseous effluents released from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR rart 50; and
- 10. (imitations on the annual dose or dose commitment to any MEMBER 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 Honitoring Procram A program shall be provided to monitor the radiation and 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 methodology and parameters in the ODCH;
- 2. A Land Use Census to ensure that. changes in the use of areas at and beyond the SITE'BOU::DARY are identified and that modifications to the monitoring program are made if required by the results of this census; and
- 3. Participation in an Interlaboratory Comparison Program to ensure that '
independent checks on'the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. CLINTON - UNIT 1 6-16b
Attachment 3 ,
' to U-602099 '
Page 8 of 14 Attachment 2 to U-602052 LS-92-001 Page 10 of 16 l ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIRFMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted. STARTUP REPORT
, 6. 9.1.1 A summary report of plant startup and power escalation testing shall be s'ubmitted 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 different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
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 values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-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 be 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 following resumption or com-mencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initlal criticality, completion of startup test program, and resumption or commencem,ent of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to Harch 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality. 6.9.1.5 Reports required on an annual basis _shall include:
; fer Lh cWm em Wm wo re un r ed 3
- a. A tabulation on an annual basi the\ number of station, 'tility, n other. personnel (including contractorsFreceiv'ing exposures greater than 100 mrem /yr and thsir associated man-rem exposure according to work and job functions" (e.g. , reactor operations and surveillance, inservice in-spection, routine maintenance, special maintenance, vaste processing, and refuelings). The dose assignments to various duty functions may be i
2.7.o fa "This tabulatio3 supplements the requirements of $20. of'10 CFR Part 20. CLINTON - UNIT L 6-17
w y < Attachment 3
%Is SL/pg enenY l p myidg M d
- M *n d t h njes k k p e. to U-602099 Page 9 of 14 r .y.
Attachment 2 N o C h o n 3 c*., . rov [ded -fov ConNnus onb. / to U-602052 LS-92-001 Page 11 of 16 A ADMINISTRATIVE CONTROLS NONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety / relief valves, shall be submitted on a monthly basis to the Document Control Desk U.S. Nuclear Regulatory Comission, Washington 0.C. 20555, with 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 LIMITS REPORT 6.9.1.9 Core operating limits shall be estabitshed and documented in the CORE OPERATING LlHil5 REPORT before each reload cycle er any remaining part of a reloa'd cyc,le. The' analytical methods used to detennine the core operating limits shall be those previousily reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel (GESTAR), NE0E-24011-P-A-8, as amended (latest aoproved version) and Maximum Extended Operating Domain and feedwater Heater Out-of-Service Analysis for Clinton Power Station, NEDC-31546P, August 1988. The core operating limits shall be detennined so that all application limits (e.g., fuel thennal-mechanical limits, core thermal-hydraulic' limits ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met. THE CORE OPERATING LlHITS REPORT, including any mid-cycle revision or supplements i thereto, for each reload cycle, shall be submitted upon issuance to the NRC Occument Control Oesk with copies to the Regional Admi'nistrator and Resident inspector. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report. l 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 The following records shall be retained for at least 5 years: 4 i a. Recordt and logs of unit operation covering time 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,
- c. All REPORTABLE' EVENTS.
i d. Records of surveillance activities, inspections, and calibrations required l by these Technical Specifications and the Fire Protection Program. CEINTON . UNIT 1 6-21
- Attachment 3
' to U-602099 55 l SVffervunY fy0Vtdes hO addNeul tkges -b % ge . ,te.cu.ene 2 to U-602052
-W- LS-92-001 Page 12 of 16 ADMINISTRATIVE CONTROLS 4 RECORO RETENTION (Continuedl
- e. Records of changes made to the procedures required by Specification 6.8.1.
- f. "ecords-o0-radioac ti ve-shi pmen ts,--
N Recor'ds of sealed source and fission detector leak tests and results. gN 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 Safety Analysis Report,
- b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
Records T of-radiatio'n-exposuee-fee-aM-individuals-enteeing-radiat4en-. c. ! -controbareaw
- d. Records of gaseous and itquid radioactive material released to the environs.
- e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
- f. Records of reactor tests and experiments.
- g. Records of training and qualification for current members of the unit staff.
- h. Records of inservice inspections performed pursuant to these Technical 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.'
- 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. Records of meetings of .the FRG and the HRAG.
~
deSet dM h aN indidclvAft.-b Adm1 Wmdmn
~^ h} Wu- ]Vind . -
CLINTON - UNIT 1 6-22
- . - - _ - ~ . ,
Attachm2nt 3 i . to U-602099 Page 11.of 14 g i Attachment 2 to U-602052 j O. 3econh c# rodoac31W shiprne.ds - [g'e r 16 - ' A
~ -
ADMINISTRATIVE C0hTROLS RECORD RETENTION (Continued
- 1. Records of the service lives of all. snubbers including the date at which
- the service life connences and associated installation 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 effe:tive at specified times l and QA records showing that these procedures were followed. l n. Records of reviews performed for changes made to the OFFSITE OOSE j CALCULATI,0H KWJAL and the PROCESS CONTROL PROGRAM. 6.11 RADIATION PROTECTION PROGRAN 6.11.1 Procedures for persohnel 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" exposure. !' 6.12 HIGH RADIATION AREA
.1 In lieu of the " control device" or " alarm signal" required by paragraph ' M0/ 20. 03(c)(2} of 10 CFE Part 20, each high radiation area in which the intensity l 1 of radiation is greater than 100 mres/hr but less than 1000 ares /hr sh111 be
! barricaded Tnd cons;ricuously posted as a high radiation area and entrance i thereto shall be controlled by requiring issuance .of a Radiation Work Permit' l (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 de area, f b. A radiation monitoring device which contipuously integrates the radiation
- dose rate in the area and alaras 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 knavledgeable 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 l responsible for providing positive control over the activities within the i area and shall perform periodic radiation surveillance at the frequency
. specified by the Radiation Protection Supervisor in the RWP.
i Wdd ' ' I- .12.2 In addition to the requirements of Specification 6.12.1, areas access- _ .
- ible to.per4oane4-with radiation levels such that-a-ma'
- ; pertip cf tb be% -
co.u_id receive in 1 hour a dose.dreater than 1000 arem* shall be provided with
, _ _ _* La tded doors to prevent unauthorized entry', and t 'eys shall be mairitain d l ll 8
l
- "Radiatfori protection personnel personnel escorted by radiation prote'ction
- personnel shall be exempt fr the RWP issuance requirement for fields of less than 3000 arem per hour j 4cring the performance of their assigned radiatfori pro-tection duties, p vfded they are otherwise following plant radi ion tion procedu or' entry into high radiation areas. 3b cm i
/2Ackes) i i
** Measures ts made at nches. rom sources of radioactivity. -
l
-Ct.INTON UNIT 1.
~
' N 6-23 m -- W Q bu+ Jess n k xsoc > mis ed we .~-
mLee % wrea d n&oJ;v;9-
Attachment-3
' ~
' to U-602099 Page 12 of 14 Attachment 2 to U-602052 bu+ / css Mr) f5comch, ctY ot1f MPlW[rtn1 Soveth oEv1 dead */4 .s-92+ I 001 m _
/ ' age 14 of 16 O#1 dd dud ADMINISTRATIVE CONTROLS
)
under the ad:ninistrative contrbi of the Sh*ft Supervisor on duty and/or the 1 dc/pa/g Radiation P.rotection Supervisor. Doors sha 1 remain. locked except during j periods of access by personnel under an app ed RVP.", for .4adi+I4uat arca accessible to*percedn 1-with radiation levels h that a-majoe-per-14:n e f=js th: Se+/ could receive in 1 hour a dosenin excess [1000 mrem **gthat are ll
'.;c/;.0,. ' located within large areas, such as the containment.hficiosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas..then that area shall be roped off, conspicuously m- sted, and a flashing light shall be activated as a warning device. ,
M s's18v'edvs .12.3 In addition to the requirements of Specifications 6.12.1' n 6.12.2,
-tien. 06 for indi.ide:L areas accessible toierrer c' such that -: ::jer Dtry shall
-the be+/ could receive in I hour a dosuin excess of 3000 are require an approved RVP which will specify dose rate levels-i e immed te T " ~"
Wrea anel reovire that stav times .shall_ tiemtablis gjgy,gual
- b uF lesr[%n Sco vd<. a+ ene. 'm e te -h reorc es cPruhou&
i In lieu of the stay time specification or the RVP, continuous surveillance, direct or remote (such as use of closed circuit IV cameras), may be made by 4 personnel qualified in radiation protection procedures to provide positive j exposure control over the activities within the, area. t
- 6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP: j a. Shall be documented and records of reviews performed shall be
- retained as required by Specification 6.10.3.n. This documentation shall contain
- 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and l 2. A determination that the change will maintain the overall conformance of the solidified waste product to existing j requirements of Federal,' State, or other applicable regulations.
l b. Shall become effective after review and acceptance by the FRG and ! the approval of the Hanager - Clinton Power Station. h l
- Radiation protection personnel or personnel escorted by radiation protection -
personnel shall be exempt from the RWP issuance requirement for fields of l less than 3000 arem per hour during the'perfomance of their assigned radia-tion protection duties, provided they are otherwise followirig plant radiation i protection procedures t into high radiation areas.
** Measurements made at ISni ch : from source c vit .
l' [C) Cm - ( t *2. mc.h ed - CtINTON J UNIT'l 6-24
I , Attachment 3 l 7
.to U-602099-55 Supplemeh frDkdes no.
de CM) C h}65 k kk[6. {>A} E . At M w 2 A_ ._ to U-602052 LS-92-001 Page 15 nf 16 ADMINISTRATIVE CONTROLS G.14 0FFSITE 00SE CALCULATION MANUAL (00CH) Changes to the OOCH:
- a. Shall be documented-and records _of reviews performed shall be retained as required by Specification 6.10.3.n. This documentation shall contain:
- 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 vill maintain the eve of radioactive effluent control required by 10 CFR 20. , 40 CFR Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely ispact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective af ter review and acceptance by the FRG and 1 the approval of the Manager - C1.inton Power Station.
- c. Shall be subeltted to the Commission in the form of a complete, .
legible copy of the entire 00CM as a part of cr concurrent with the Sealannual Radioactive Effluent Release Report for the period of the report in which any change to the 00CM kas made. Each change shall be identified by markings in the margin of the affected pages, the clearly indicateindicating the date (e.g., area monthof the page
/ year) that Vas the -chahge waschanged, implemented.and shall CLINTON - UNIT 1 25
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- Attachment 3
* ' to U-602099 Page 14 of 14 j
N5, 5*vpplCment pWV[CICS RO nddl'od tbjes. 40% JWje
- Attachment 2 to U-602052 LS-92-001 Page 16 of 16 I PLANT SYSTEMS BASES 3/4'.7.4 SNUB 8ERS (Continued) etc. . . . The requirement to monitor the snubber service life is included to j' ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating 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. i l 3/4.7.5 SEALED SOURCE CONTAHINATION The limitations on removable contamination for sources requiring Icak testing, including al,pha emitters, is based on 10 CFR 70.39(c) limits for plutonium. l This limitation will ensure that leakage from byproduct, source, andSealedspecial nuclear material sources will not exceed allowable intake values. sources are classified into.three groups according to their use, with surveil-lance requirements commensurate with the probability of damage to a source in that,groop, Those sources which are frequently handled are required to be tested more of ten than those which are not. Scaled sources which are continu-i cusly enclosed within a shielded mechanism, f.c., sealed sources within radia-tion monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism. 4 3/4.7.6 NAIN TUR8INE BYPASS SYSTEM The main turbine bypass system is required to be OPERABLE consistent with the assumptions of tM feedwater controller failure analysis in FSAR Chapter 15,
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3/4.7.7 LIQUID STORAGE TANKS The tanks IIsted in this Specification include all those outdoor storage tanks that are not surrounded by liners, dikes, or walls capable of holding the tan,k 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 uncontrolled release of the contents from any of these tanks, the resulting concentratio'n> would'be less than the limits of 10 CFR Part 10, Appendix B, Table 4, l Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA. 2. CLINTON - UNIT 1 B 3/4 7-3
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