ML20056D665
| ML20056D665 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/06/1989 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20056D475 | List: |
| References | |
| NUDOCS 9308170300 | |
| Download: ML20056D665 (20) | |
Text
{{#Wiki_filter:- . l 3.0 SURVEILLANCE REOUIREMENTS l I 3.0.1 Each surveillance requirement shall be performed within the specified l l time interval with :
- a. a maximum allowable extension not to exceed 25'S of the '
surveillance interval, -but- %L :
- b. the combined time interval for any three consecutive ;
surveillance intervals shall not exceed 3.25 times the ! specified surveillance interval. l 3.0.2 The surveillance intervals are defined as follows: l Notation Title Frequency ; i S Shift At least once per 8 hours D Daily At least once per 24 hours W Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days l R Refueling At least once per plant operating cycle P Start up Prior to Reactor Start up, if not l completed in the previous week. 1 Exceptions to these intervals are stated in the individual Specifications. 3.0.3 The provisions of Specifications 3.0.1 and 3.0.2 are applicable to - l all codes and standards referenced within the Technical Specifications. The requirements of the Technical Specifications l- shall have precedence over the requirements of the codes and l standards referenced within the Technical Specifications. 3.0.4 Failure to perform a Surveillance Requirement within the allowed l surveillance interval, defined by Specifications 3.0.1 and 3.0.2, L shall constitute noncompliance with the OPERABILITY requirements for the corresponding Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
- i. The ACTION requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowable outage time-limits of the ACTION requirements are less than 24 hours.
Surveillance Requirements do not have to be performed on inoperable equipment, l ph[ DD 3-0a P I.-
I 3.0 SURVEILLANCE REQUIREMENTS l BASIS Specifications 3.0.1 through 3.0.4 establish the general requirements - applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3): ;
" Surveillance requirements are requirements relating to test,_
calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation i will be within safety limits, and that the limiting condition of ' operation will be met." Specification 3.0.1 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended. Item a. permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable i for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 3.0.1 are based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability demonstrated through actual surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. 9 The provisions of Specification 3.0.2 define the surveillance intervals for use in the Technical Specifications. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications. A few surveillance requirements have uncommon intervals, for example, Table 3-9 requires sampling of fish once per season. In such a case the surveillance interval shall be performed as defined by the individual specifications. Specification 3.0.3 extends the testing interval required by codes and standards referenced by the Technical Specifications. This clarification is provided to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities. Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the codes and standards referenced therein. Specification 3.0.4 establishes the failure to perform a Surveillance i Requirement within the allowed surveillance interval, as defined by the provisions of Specifications 3.0.1 and 3.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for the corresponding Limiting Condition for Operation. Under the provisions 3-Ob
i 3.0 SURVEILLANCE REOUIREMENTS l BASIS (continued) ! of this specification, systems and components are assumed to be. ! OPERABLE when Surveillance Requirements have been satisfactorily i performed within the specified time interval. However, nothing in (' this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable even though the Surveillance Requirements are met. This specification also clarifies that the ACTION requirements are ' applicable when Surveillance Requirements have not been completed , within the allowed surveillance interval and that the time limits of ! the ACTION requirements apply from the point in time it is identified- ; that a surveillance has not been performed and not at the time that
- the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 3.0.4. However, this does not negate the fact that the -
failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification of 3.0.1, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification of 3.0.1 is a violation of a Technical Specification : requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the plant's Technical Specifications. If the allowable outage time limits of the ACTION requirements are Me less 't@e 24 hours or a shutdown is required to comply with the ACTION requirements, e.g., Specification 2.0.1, a 24 hour allowance is provided to permit a delay in implementing the ACTION [ requirements. This provides an adequate time limit to complete ' Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or , before other remedial measures would be required that may preclude ' completion of a surveillance. The basis for this allowance includes ! consideration for plant conditions, adequate planning, availability I of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. If a surveillance is not completed within the 24 hour i allowance, the time limits of the ACTION requirements are applicable at this time. When a surveillance is performed within the 24 hour ! allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated. Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial : measures that apply. However, the Surveillance Requirements must be met to demonstrate that inoperable equipment has been restored to operable status. 3-Oc
n' 2.0 IURVE!*_* 'J:C" 2ECUIREME!Tr* 3.1 Instrumentatien snd Centrei Apeli cabill t:r Applies to the reacter protective system and other crttical instru-centatien snd centrols. Objective To specify the mini =um frequency and type of surveillance to be applied to critical plant instrumentation and centrols. Seeci fic atiens Calibration, testing and checking of instrument channels, reactor prctective system and engineered safeguards system logic channels and , miscellaneous instrument systems and cant el eb 'b *fer=ed j as specified in Tables 3-1 to 3- : " x j ee + * - * * - ca ' ' ""' " "' ;
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cer::: tir: ::_.;ill;::: furetierr net te crc::d 3.2E - timer th: p::ified inte..;1. l 1 Basis Failures such as blevn instrument fuses, defective indicators, and faulted a=plifiers which result' in " upscale" or "downscale" indica- ; tien can be easily recognized by st=ple observation of the functiening i of an instru=ent or system. Further=cre, such failures are, in many cases, revealed by alarm or annunciater action and a check supple- .{ rents this /pe of built-in surveilinnce. 1 3ased en the District's experience in operation of conventional power plants and cn reported nuclear plant experience, a checking frequency of ence-per-shift is deemed adequate for reactor and 1 steam system instrumentation. Calibrations are performed to j ensure the presentaticn and acquisition of accurate infor=ation. I The power rsnge safety channels are calibrated daily against a calcrt=etric balance standard to account for errors induced by ; changing red patterns and core physics parameters. j Other channels, subject caly to the " drift" errors, can be expected to remain within acceptable tolerances if recalibration is perfor=ed l I st eacn refueling shutdown interval. 1 3-1 Chance No. 9 August 23. 197h
. i TABLE 3-1 (ccatinued)
MTNIMUM FREQUENCIES FOR CHECKS. CA1,IBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTD4 k m lh 13 Axial Power a. Check S a. 1. Comparison of four separate axial l Distribution index indications.- ; u
,o 2. ' Comparison of four separate' upper ~
4 trip set point indications.
-a
-a
-3. Comparison of four separate lover i trip set point indications.
- b. Calibrate R b. Known currenta applied to input of axial shape index calculator.
- c. Test M c. Trip test known axial shape index ' applied to input of axial shape intex csiculator.
t T' Notes: (1) The bistable trip tester injects a signal into:the bistable and provides a precision readout of the trip set point. (2) All monthly tests will be done on' only one or four channels at a time to prevent reactor trip. (3) Calibrate using built-in simulated" signals.
.(h) Not required unless the reactor' is in.the power operating condition and is therefore not -
required during plant startup and shutdown periods. 4 - Ebr5 Shift-9 - ! !y-1 Q- 5:rterly-0 18 ';2r
- h=-
P Prior _tc Sr.3 Ctartup if r,ct acrc prc.-icuc x;ch
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TAELE 3-2 (Continued) P N tillillRIM FREQUEfiCIES FOH CilECKS. CAIIllH ATIOils AND TESTTilG OF y EllGiliFFEED G AFCTY FEATITHL'S, INSTRilt.!FilTATION AfiD C0fiTROIS N N Surveillance a Channel Description Function Frequency Survei 1 l ance Het bort O
- s. 2?. Auxiliary l eedwat er
_. ) n, u. Jteam Generat or Uster a. Check 8 a. Campere independent levtl (
"' l.e ve l 1. m ( 411'1E I:ance ) readings.
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- b. Culibration 11 b. 1:nr.vn sicnal applied to uccisor. (
)
- b. Steam Generator a. Check S h. Compare inlepetident lires;ure g Pressure icy readings.
)
- 1. n ivre Hirnal applied to sensor.
';> b. Calibration H L. . ( U n. i.ncun sicr.nl applied to sensor. ) P t. Jteam Generator u. Cullbrate 11 Dif fereritial Pressure ( llich ) Test u. Functional checi; of initiation (
- d. Actuation Circuitry a. 11 circuits. )
(
- b. Test R b. System functional test of AFki initiation circuits. )
S--i:.neh Shi f t 1+ Daily-H ~-Honthly-9- --Quarterly-itHB-Months-ri o-2 cb 0^ Not- e-Previeue L 3 HP - Monthly during designated modes and prior to t ing the reactor critical if not completed within the previous 31 days (not applicable to a fast trip recovery)
TABLE 3-3 (Continued) MINIMUM FREQUENCIES FOR CllECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description function frequency Surveillance Method , i
- a. Check 5 a. Comparison of readings from redun-YlS-6287A&B (H24 N ' NN3 ) dant channels,
- b. Calibrate Q b. Gas calibration.
Core Exit Thermocouple a. Check M a. Comparison of readings from redun-
- 30. dant channels. ( !
)-
- b. Calibrate R b. Calibration of A/D converters from known voltage sources. ,
( w
)
l L 31. Ileated Junction Thermocouple a. Comparison readings from redun-
- a. Check M R (YE-116A and YE-1168) dant channels.
)
- b. Calibrate R 'b. Calibration of A/D converters (
from known voltage sources. t E
$ ^ C=rter%y.
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S,=== rJer t= :: E -!:-tr- 4 et-e=': n:ff tt' :rrieusmky whenever temperature remains below 300"f and E PM - rior to sche u ed co d leg too down below 300F;
" reactor vessel head is installed.
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'.nnlictcility appliea ta plant e paipment, m c.;mtiticn: related to safety.
bie-ttie ' To soecify the minimum frequency and type c: surveillance to be [ tpplie1 to critical picnt equipment and conditions. .
.: cec t ri cations Equipment nne sar all ba acn + c t as e ified in ~' ables
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"'he ecuipment testing and system sampline frequencies specified in Tables 3-h and 3-5 are considered adequate, based upon- experience, to maintain the status of the equipment and systems so as to assure safe operation. "*hus, those systems where chances mir.ht occur relatively rapidly are sampled frequently and those static systems not sub, ject to changes are sa. pled less frequently. (
/'
"'he control room air treatment system consists of high efficiency '
particulate air filters (F. EPA) and the charcoal adsorbers. HEPA filters are installed before the charcoal adsorbers to prevent clog;;ing of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of iodine to the control room. "'he in-place test results vill confirm system inter.rity and performance. "'he laboratcry carben sample tests results should indicate methyl iodide removal efficiency of at least 90 percent for ;
.:xpected accident conditions. 3
/ l The cpent fuel storage-decontamination areas air treatment system is (
lesirned to filter the building atmosphere to the auxiliary building ) : vent during refueline, operations. The charcoal adsorbers are instalied to reduce the potential release of radiciodine to the j
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envircnment. In-place testing is performed to confirm the integrity. of the fliter cyntem. The enarcoal adsorbers are periodically sampled ) j l
*c. insure capability for the removal of radioactivity iodine.
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4 3.0 3URVEII.* AIICE REQUIRE *4E!ITC f 3.10 Feacter Core Parameters J l Aceli:abilitt- ' Applies to reacter core parameters that affect shutdown margin. 24TC. ,
=(y -
linear heat rate and DIiB margin. J. l Obieetive ( l To require evaluation of reactor core paramecers. Scecification i
" : 2111brmtion, ch::hing, and t : ting :;::ifi:d in +'.: fell n'i" pr2 IS
;rsp : i =bject to: ;
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- utiv: cr;;ill;;;; f=: tic .: act :: cx:::i L 25 .
ti the r;erified '2t (1) Shutdown Margin N
/-
- a. The shutdown margin'shall be determined: -
- 1. By verifying that the CEA group withdrawal is above the ~( I!
Transient Insertion Limits of Specification 2.10.2'when- ) ever the reactor is in hot standby or power operation con- / ditiens at least ence per shift, or ~ j s
- 2. By considering the following factors whenever the re- l actor is in hot or cold shutdown at'least cnce per day.- )
(1) Reactor coolant system boron concentration;- ( (ii) CEA position; ) (iii) ' Reactor coolant system temperature;
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(iv) Fuel burnup;
'(v). Xenon concentration; and a
(vi) Samarium concentration. ;
- b. The overall core reactivity balance shall' be ecmpared to pre-dicted values 'to demonstrate agreement'vith + 1.0% ak/k at.
least once per 31 ETPD. The predicted reactivity values shall ( be adjusted (nomalized) to correspond to the ' actual [ core con-ditions prier to exceeding a cycle burnup of 2000 IND/MTU after each refueling. Amenc=ent ::o. J5I, pf, 22 g
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,- 3.12.1 ~.1:uid ana Oasecus Effluent: (
Acelicability ( i Applies t.c the sa:plig,, apari tS " ed *':r 'i;udd and ; ras ~~ ,; S pe c.fi;; . r::uene::: 12'; ': 12;u" cc 20- [ c;;::=^:::: Orcr2:icn ::hedule :.ce p that 2 ric.n;; :ncu.; ' : . . . . . - t,
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To ensure that radicactive liquid and gaseous releases frem the . l facility are maintained as lov as reasonably achievable and within ; the l' 4ts specified by Specificatien 2.9.1(1) and 2.9.1(2). . i Steeifiestiens ! i i (1) licuid Effluea+- 1
- a. Radicactive liquid vaste sa=pling and activity analyses shall !
be perfor=ed in accordance with Table 3-11. "'he results of ( these analyses shall be used with the calculational methods in . , the CDCM to assure that the concentration at- the point of , release is limited to the values inLSpecification 2.9.l(lla. q
- b. Prior to release of each batch of liquid effluent, the batch f shall be mixed,' sampled, and analyzed for principal gamma t emitters . '4 hen operational. or other limitations preclude l specific gn==a radienuclide analysis of each batch,; gross )
radioactivity measure =ents shall be =ade to estimate the ; quantity and concentrations of radioactive materials released- j in the batch, and a weekly sample ce= posited from proportional' ; aliquots fres each batch released during the week shall be analytea fer the' principal 6-a-emitting radionuclides,
- c. "'he overbcard header radiation monitor shall have a:
(i) Source check prior to any release of radioactive materials frc= the nonitor or the hotel vaste tanks. i (ii) Quarterly channel functional test. r . . . w ... c ... a .__. 5...,
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- d. .ae. stEEE generator b ovdcun radiation monitors snall have:
(i)' Daily channel checks. d 1 i (ii) Monthly scurce cheeks. i 1 2-69 Amenc=ent no. 28, 36 i i l 1 l
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3.12 2: 11c1ccica_ hste Sanchne 'nd "onitorine ( Cont nucc) 3.12.1
- i::uic o.nn Gaseous Effluents ( COntinuec)
(iii) C.uarterly channel functiera' *aste. S.-V r (iv) 0'.annel calibrm -- et Y frequency ' u r; ? nonteet. FE rvE.u~ 0')
- e. '"he stea= ceneEr 1 .racun a ' 3e.qt ev rate vill be tfrequency (c'erf 1S :enthr 5 and visually calibrated at [ N deter =ined ope (s
- f. Records shall be maintained of the radicactive cencentrations /
and volu=e before dilutien of each batch of liquid effluent wa' eased md of the average dilution flov and length of time ( W ich. h - . . ee-~r eacn discharge occurred. Analytical results shall be submitted to the Cc==issicn in accordance with Section 5.9.L.a of these specifications . [
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(2) Gaseous Erfluente
- a. Radicactive gaseous vaste sampling and activity analyses shall be perfor=ed in accordance with Table 3-12. S e results of these analyses shall be used with the calculational =ethods in the CDCM to assure that the concentration of radicactive
=aterials in unrestricted areas is li=ited to the values in Specificatien 2.9.l(2)a.
- b. (1) A ventilation stack radiation =cnitor shall have a source (,
check prior to any release of radioactive materials frc= i a gas decay tank or the containment. A monthly source check vill be performed during refueling cutages if a purge or gas decay tank release is not done during that (;'
=c-ch.
(ii) Each ventilatien stack menitor shall have a quarterly ; char- ' '"- d nal test. .
%I (iii) g.ventilati *1 hall be calibrated at WFvm4
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4;;;FVEWV (iv) The ventilation stack f'~ . ate vill b ce ih at d - functionally tested a e- 'requen ( m rf 19 ner:'-) The stack radiatien meni cr cv rate wi' e ca $ " ate and functicnally tested at frequenc .(_c;.f 1S ........ ,. Both vill be deter =ined oper"" ~ e b visuaJ. inspectic. daily. qcruw& 1
- c. '"he ecndenser air ejector =cnitor shall have a:
(1) Daily channel check. (ii) Monthly source check. ! 3-70 A=end=ent no. e6 l l
L g 3.0 SURVEILLANCE REQUIREMENTS L 3.12 Radiolocical Waste samosino and Monitorina (Continued) 3.12.1 Lioula and Gaseous Effluents (Continuec) + (iii) ,_:cterly cnannel func.:..:: " it. : Re vo cu- e-(iv) Channei calibration at 2%$V'recuency (^n '" ~0ntn:l
- d. The hydrogen and oxygen monitoring system for the gas decay 1 tanks shall have a:
(i) Daily channel check (when in service). $>'! (ii) Monthly cross comparison with a grab sample, i (iii) Quarterly channel calibration using gas mixtures with , concentrations in the range of interest. ;
- e. Records snall be maintained and reports of the sampling and l results of analyses shall be submitted to the Commission in accordance with Section 5.9.4.a of these specificaticns. t Basis ,
The surveillance requirements given under Specification 3.12.l(2) provide i assurance that radioactive gaseous effluents from the . station are properly controlled and monitored over the life of the station in conformance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A. These surveillance requirements provide the data for the licensee end the Commission to evaluate the performance of the station relative to radioactive gaseous wastes released to the environment. The existing minimum sensitivity of airborne effluent monitor RM-062 is SE-06 mci /cc/100 cpm and this minimum sensitivity shall be maintained if the monitor is replaced. Reports on the quantities of the radioactive materials released in gaseous effluents shall be furnished to the Commis-sion on the basis of Section 5.9.4.a of these Technical Specifications. On the bas.is of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from . time to time require the licensee to take such action as the Commission deems appropriate.
- The surveillance requirements given under Specification 3.12.l(l) provide assurance that liquid wastes are properly controlled and monitored in conformance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A, during any planned release of radioactive materials in liquid effluents. These surveillance requirements provide :
the data for the . licensee and the Commission to evaluate Ine station's ' performance relative to radioactive liquid wastes released to the environ-ment. Reports on the quantities of radioactive materials released in liquid effluents shall be furnished to the Commission on the basis of 3 Section 5.9.4.a of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or otners, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate. 3-71 Amenament No.6 / t/, 106
I' ABL ' ~ .1 RADICi. ~ '" : '. U I P ' ! ET '- iJIPI.iMO ;;;D A:: ALYSIS A. Mon: tor s Metei ' in t e ~' in r.s Beleuses Lower La.tt of [ Type of Detection (LLD) \ Samtline Frecuen: ac ti eity Anal rsis (L) fuC1/ml) Each Eatch Pr:neiral Oa:=a F-itters( 2)( 5 ) S,o 907 (
)
1-1 !1 f2) 1.0 E-06 Monthly From 2ne Dissolved Noble Cases 52) 1. 0 E-0 5 Batch (Gamma Emitters } ) r, Montnly Compocite -) H1 1.0 E-0 5 % ( 1ross a 1.0 E-07 j Quarteri r Comeos ite!1) SE-60, Sr C0 5. 0 E-08
- 3. Steam Generator Elevnown Lower Limit of Type o f Detection (LLD) j 3ameline Frecuency Activity Analysis (h) (uCi/ml) ,
Lleer.ly Composite (1) Princi cal Gamma Emitters (5) 5.0 E-07 I- 131 (6) 1.0 606 Weei:1't ( 'l Dose Eaui talent I-131 1.0 506 ( Gs=mn E=itters ) Monthly Dissol ted Noble Gases 1.3 E-05 [ donthly Composite (1) t!- 3 1. 0 E-0 5 ( Grono a 1.0 E-07 Qua:- erly remens ite { l) 3 r H9 , Jr GO 5. 0 E-0 8 NOTEC: (1) To be representat ce of the average quantities and concentraticns of radioactive materials in liquid effluents , samples should be collected in proportion to the rate of flov of the effluent stream. Prior to analyses, all samples to. ken for the composite snould be mixed in order for the composite sample to be representative of the average effluent release. 3-72 Amendment *:o . 2d, t6
1 l_
"'.TLi .-1; l RADICACTI'IE LI::UIL ;STE J/?iPLI::G Il;D 'd ALISIS ( Continuec>
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- LOTE 3 :
(C 6 (2) er .; recs radioactivity ;; descricea in :pectricatica 3.12.1(1)b. , (1) *Then :tcam ::encevar iodine ac t. i v i ty <_ c.:la 50 percent i,0 timit.:; in i Specificatica 2.20, the s acpling and analysis frequency chall be increased ,. to a minimum of five times per week. 'Then the steam Generator iodine
/
activity exceed; 75 percent 0; th u Limit, the samplin4; and analysis \ frequency shall be increases to a :nnimum of once per day. (L) Tae lower limit c: Jetection (LLL) la cerined in the CDC1 based on IIUREG Ob72, Rev. 3.
;5) Tae principal gr.ma emittere for .hien the LLD specification applies h exclusi tely are tne r ll;ving r aienue:.ilen : Mn-Sk, Fe-59, Ca-5d, Co-o0, En-05, :1o-99, Os-13L , CJ- 137 , de- lL 1 .m a Ce-14 k . l (6) A weekly grab aumple and analynes prot'rrun including gamma isotopic t identificaticn vill be initiated for the turbine building sump effluent when the steam donerator blevaevn water composite analysis indicates the "
I-131 concentration is .' renter thnn 1.0 E-06 microcurie / milliliter. 1-. .- 1 3-73 Amencment 2. 23, d6
( : LO :URVETLLANCE PCOUIREMENTm
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3 13 MDICAC*IVE MATERIAL COURCES SURVEILLANCE i Aoplicability l I Applies to leakage testing of byproduct, source, and special nuclear radioactive material sources. , Objective To assure t. hat leakage from byproduct, source, and special nuclear radioactive material sources does not exceed allovable limits.
- 1peci ficati on
). :
Tests for leakane and/or contaraination shall be performed by the- ; licensee or by other persons specifically authorized by the NRC or f- ; an acreement Otste. as follows:
- 1. Esen sealed source. except startup sources subject to core flux.
containing radioactive material, other than Hydrogen 3. with a ! half-life greater than thirty days and in any form other than gas- l shall be tested for leakage ' and/or. contamination at intervals '
- et * -
---d six months. ;
of
- 2. The periodic leak test required does not apply to sealed sources / j
'.. that are stored and not being used. The sources. excepted frma '
I this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak-tested within'cix months prior to the date of use or transfer. . In
)' 'l the sbsense of a certificate from a transferor indicating . -
that a test has been made within six months prior to the transfer, . i seales sources shall not be put into use until tested. } , 2 f 3 Ctartup sources shall be leak tested prior to and following any / f repair or maintenance and before being subjected to core flux. \ ,
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Amen 1:ent No. 11 3-76 Dated: February k, 1976 ,
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l r : .' . a 3.15 ?!re Pretection svetem '
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P 4 l Acclicacilitr Applies to fire cetecti:n ana : ire er.tinnutshinz :uesystems in nue- . ; lear cafety relatea areas ana ;ther areas nich ~nay i= pact On safety l relatea cyste= .
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i Obiective j l To ensure the operability cf the *'-e retecti_en,;xstan in n"alaar s 'e" related sv tems. Eur- :_1 ne_ frequenci : ap :ified ber;r ' ch; -aaec---eci;rar. : :: Soecificatiens (1) Each fire detecter listed in Table 2-7 and in containment shall be uemonstratea operacle: l
- 2. At least cnce per 6 montns by perfer=ance of a channel functional test and a test of the supervision circuitry.
- b. Testing interval fer fire detectors which are inaccessible due to high radiation or require an equipment alignment (g not used in power operation may be extended until such / ,
time as the detectors become accessible for a minimum , of 36 hours. However, the shutdown need not be extended ) solely for the purpose of this testing. Such detectors shall be functionally tested at a =aximum interval of I once per refueling cycle. (2) The fire suppressien water system shall be de=cnstrated oper- i able:
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- a. At least once per month by starting each pump and cper-ating it for at least 15 minutes.
- b. At least once per month by verifying that each valve in i the flow path is in its correct position.- l
- c. At least once per 12 months by cycling each testable valve (those which can be cycled without endangering the safety of equipment ) in the flow path through at least one ec=plete cycle of full travel.
- 4. At least once per 10 months by performing a system fune- l tional test which includes: i
- 1. Verifying that each pu=p develops at least 1800 gpm at a system head of 260 feet ,
- 2. Cyclinn each valve in the flev path that is not testable during plant cperation througn at least one cc=plete cycle of full travel, and Amennment 3. .0 3-80 l
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3.0 ' 5URVFII.1.!ME REOUIRD!ENTS f I 3.16 Recirculation Heat Removal System Intecrity Testinc { I Applicability Applies to determination of-the' integrity of the shutdown cooling '
/ f system and associated components.
{ Obiective '[ To verify that the leakage from the recirculation heat removal. f l e system components is within acceptable limits. ) 3 Specifications I (1) a. The portion of the shutdown cooling system that is { l o
- eide..the conen h erit shall be i ed at "O si ee-l teen r,efueling e hI % 21 i
- $;l c h : ier; in:; . . .L . .
we : c we 2r inter: 1; gic :u zua . yes m ! b. Piping from valves HCV-383-3 and HCV- M3-4 to the dis-f ! i
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charge isolation valves of the safety injection pumps \,{ and containment spray pumps shall be hydrostatically / ) l tested r.t no less than 100 psig at the resting fre- j quency specified in (1)a. above. ( -{
- c. Visual inspection of the system's components shall be performed at the frequency specified in (1)a. above to uncover any significane leakage. The 3eakage shall be
)l! l j
measured by collection and weighing or by any other ! l equivalent method. ; The maximum allowable leakage from the recirculation (2) a. heat removal systein's components (which include valve- )-l' [ stems. flanges, and pump seals) shall not exceed one gallon per minute, under the. normal hydrostatic head from the SIRW tank.- .
- b. Repairs shall be made as required to maintain-leakage /
within the acceptable limits. \
.Baf t s, ';
1 The limiting leakage rates f rom the shutdown cooling system are l , judgment' values based primarily on essuring that the components: N could operate without mechanical failure for a period on the order \ of 200 days after a design basis accident. The test pressure (250 / psig) achieved either by norral system operation or by hydrostatic , testing gives an ' adequate margin over the highest pressure within the system after a design basis accident.(I) ~Similarly, the - hydrostatic test pressure for the return lines from the contain- . ment to the shutdown cooling system (100 psig) gives an adequate margin ever the highest pressure within the lines after a design [ I basis accident. . 3-84 Amendment No.97
- . .-. . - . - . . - . - . - . . ... . . - - . . - . . = .
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n I Attachment 2 -
DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS : CONSIDERATION ANALYSIS Generic Letter 87-09 provided guidance, in part, to the general requirements on the applicability of surveillance requirements in the Standard Technical Specifications, and encouraged licensees to propose changes to their Technical Specifications that are consistent with the guidance provided. i 0 PPD is proposing to incorporate a general section to the beginning of i Section 3 of Fort Calhoun's Technical Specifications. The proposed change will make the Fort Calhoun Station Technical Specifications closer to the Standard Technical Specification, and fulfills commitments made in LER 88-006 Revision 1, dated September 29, 1988. 1 l i This Amendment will provide the FCS Technical Specifications with the ' following provisions: l
- 1. A 25% extension for surveillance intervals, but the total interval for three consecutive surveillance intervals shall not exceed 3.25 times the >
specified intervals. *
- 2. The regular surveillance intervals are defined. j
- 3. A 25% extension applicable to all codes and standards referenced within.
- 4. The action statements for a Technical Specification can be delayed for up to 24 hours under certain conditions, and; I :
l 5. Inopersble equipment does not need to have surveillance performed on it. 1 l ; Any general items that appear within other surveillance requirements have been removed to avoid duplication. Specifically: pages 3-1, 3-6, 3-12a, 3-16c, 3-17, 3-63, 3-69, 3-72, 3-73 and 3-80. 10 CFR 50.91(a)(1) requires that licensees requesting an Amendment provide an analysis addressing the issue of no significant hazards consideration as I o
l defined in 50.92. This Amencment would not involve a significant hazard for ! the following reasons:
- 1. This Amendment does not involve a significant increase in the '
probability or consequences of an accident previously evaluated. The ! proposed change is a change to achieve consistency throughout Section 3 i of the Technical Specifications as allowed by Example (i) of (51FR7744). l This change is not deemed significant, because it incorporates guidance provided by Generic Letter 87-09. i
- 2. This Amendment does not create the possibility of a new or different kind of accident from any previously evaluated. This is a purely l
administrative change to the Technical Specifications, it does not alter > the manner in which equipment is operated and does not eliminate any l 1 surveillances required by the Technical Specifications, and; h
- 3. This Amendment will not cause a significant reduction in the margin of
{ safety. Providing clarification for the applicability of Surveillance i i requirements does not change the method of operation and, therefore, r does not reduce the margin of safety. This Amendment, based on Generic l Letter 87-09, is consistent with the recommendations of NUREG-1024 l
" Technical Specifications -- Enhancing the Safety Impact" and the i
Commissions Policy Statement on Technical Specification Improvements. l The Commission has provided guidance concerning the application of the $ standards for determining whether a significant hazards consideration exists ! by providing certain examples.(51FR7744) of amendments that are not likely to- ' involve significant hazards consideration. Example (i) relates to administrative changes to Technical Specifications; for example, a change to , achieve consistency throughout the Technical Specifications. This change is '{ similar to Example (i) in that the change is intended to provide consistency l with regard to surveillance intervals. OPPD does not believe this change ! involves significant hazards considerations. i F l
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