ML20205S275
| ML20205S275 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/30/1987 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20205R377 | List: |
| References | |
| NUDOCS 8704060561 | |
| Download: ML20205S275 (6) | |
Text
_
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3/4.4.8 SPECIFIC ACTIVITY x.
LIMITING CONDITION FOR OPERATION l
3.4.8 The specific activity of the reactor coolant shall be limited to:
Less than er equal to 1 microcurie per gram OOSE EQUIVALENT I-131, a.
and b.
Less than or equal to 100/I microcuries per gram of gross radioactivity.
APPLICABILITY: H0 DES 1, 2, 3, 4, and 5.
ACTIO.i MODES 1, 2 and 3*:
<n---4+i th th: :pe:!ffe ::tivity f th: re :ter :::1:nt greater than* - - *
-2
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swi www' ss yw u 14*4t (DeleM and te the 10ft Of th; IIne) ShG-n eJ-IiquTe 3.41, 0;e-atica -?y centinue for up t: 1S h:gr: pcovided that the cumul:-
tiv: c?erating ti:: under th::: cir;uastei.c a Jcos..v; emceed 000 heur;
- Cy 000 :stiV: 12 L0 nth periGd.
IU. pguvisiuna vi 3peciii44-tiGn 3.0.4 eie nGt &pplic4ble; b.
"ith the teta! cume!:tive eperatiag ti : :: : r::: tor esclant :pe f#f
- titity greater th:n 1 -fer:Curi: per graa 00SE EQUIVALE.1T I-131 ex:: ding 500 heur: ' :ny con::cuti:: 5 month peried, p. pe. und
- bmit : Special Report te th: C r-i::fon pur u;nt to Specificsticc.
0.0.2 within 30 days indicating the number cf hears abc;e this
'4-it.
The previ:iene of 5;cci'icatica 3.0.
- cre not epp;ic.bl.,
I With the specific activith of the reactor coolant greater than ou,abr 1 microcurie per gram 005.E EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T less avg than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and
- b. 46-With the specific activity of the reactor coolant greater than 100/E k
microcuries per gram of gross radioactivity, be in at least HOT STANOBY with T less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
avg
" With T,yg greater than or equal to 500*F.
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CALLAWAY - UNIT 1 3/4 4-25 8704060561 070330 yDR ADOCK 05000403 PDR
RevigI()hl j
LIMITING CONDITION FOR OPERATION
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ACTION (Continued)
MODES 1, 2, 3, 4, and 5:
With the specific activity of the reactor coolant greater than 1 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram of gross radioactivity, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.
"r:p r: :nd cub-it : Sp::i:1 ".: pert te th: Cc--fes ca pu-sueat te Speci+4cetfea 6.9.? withia 30 days with a cary i
te the Directe, ucc! ear eacter egel:tien, ett:ntien-Chi ', C:r:
ee-'.e--eace B-=ach. =ad Chie#, Accidaat Evaluatica Breach. " S. Muries-
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th: r:: alt: Of th: :pe:f'!: 20t't"ity analy::: te; ether with th: 'Oll wing i-f r::ti:n-h4e+nry c+=r+4nn an hayre nr<n, te the r4rst 5..mie 3.
Deme +ne nnm.e
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s-
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e._n M_ 4. m. E. nM_ I. n..-.m#Amm A s
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4-it e : enceeded, g.
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- mpling and the r:dictedine cencentr: tion;
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Clean-up
c" history sta-ting AB hours prier te the #irst :- ple s/
i-ubich th: -it u : :::^ d:d;
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u t.,. -.,o n_ a x_ _ n, m e_ e_ i n n n_ n o_ r s t i n n e. if m n,v, e t a rt i nn, AR hniere neine
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c._2r+n, e_nnlan*
cxeceded 1 -icr Curi per gre: 005C CQUIVALENT I-131.
l SURVEILLANCE REOUIREMENTS I
l a
4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.
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CALLAWAY - UNIT 1 3/4 4-26 S
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fLEVISIOiV i REACTOR COOLANT SYSTEM
.< y BASES SPECIFIC ACTIVITY (Continued)
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than 1 micro-Curie / gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Op:r tie- "4+ h sparifie =r+ivity 1=u=1=
caceeding1-!:r:{'uriefgr:: DOSE EQ"!"^.LEM7 !-131, but withi-th: '! it:
shown en Figur: 3, -1 me:t 5: re:tricted te n: 20r: th:n 900 heur: p:r y::r (eppr;xim;tely 10% ef th: unit': y: rly :p:r: ting tin:) uine: th: ::tiefty le.els elleacd by "igur 3.4-1 incrc::: the 2-h;;r thyrcid d;;e et the !!TC pn r tinaiag 3 pertu 3ted ste3-geeeeste. tyke 1
gggggaev hy 3 roc +ne er
.in
+n e
ruptur:.
The -epe-+ 4 ag er r"-"letioe ape *et a; time eve
- 500 heu-5 ia i
eay S ; cath con::cutive Seriod >tth ;re:ter th:n 1 :!:r: Curie /gr;; OOSE C0"P!ALEM' !-131 ' 2er ruf#icient time fer Cc--!: icn er:luation :# the c i rcu-s t e ace: prie- +c eeechiag the 900-ha"* 14=it.
Reducing T,y to less than 500*F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the reactor coolant is below the lif t pressure of the atmospheric steam relief valves.
The Surveillance Requirements provide adequate assurance that excessive specific activity-levels in the reactor coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomenon.
A, reduction in f requency of isotopic analyses following power changes may be permissible if ju.stified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS The temperature and pressure changes during heatup and cooldown are limited to be consistent with the requirements given in the ASME Boiler and Pressure Vessel Code,Section III, Appendix G:
1.
The reactor coolant temperature and pressure and system heatup and coolcown rates (with the exception of the pressurizer) shall be limited in accordance with Figures 3.4-2 and 3.4-3 for the service period specified thereon:
a.
Allowable combinations of pressure and temperature for specific temperature change rates are below and to the right of the limit lines shown.
Limit lines for cooldown rates between those presented may be obtained by interpolation, and b.
Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only. For normal operation, other inherent plant characteristics, e.g., pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown *$tes that can be achieved over certain pressure-temperature ranges.
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CAllAWAY - UNIT I B 3/4 4-6 l
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ADMINISlRATIVE CON 1ROLS Ibl())E
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f ANNUAL REPORTS (Continued)
- 6. 9.1. 5 Reports required on an annual basis shall include a tabulation nn an annual basis of the number of station, utility, an,d other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated nian-rem exposure according to work and job functions," e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special mainte-nance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosi-meter, TLD, or film badge measurements. Small exposu'res totalling less than 20% of the individual total dose need not be accobnted for.
In the aggregate, g;eg at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions.
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT **
6.9.1.6 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis cf trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Specification 3.12.2.
g' The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available tnr inclusion with the report, the report shall be submitted noting and explaining the reasons for th'e missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program; at least two legible maps ***
covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in alhis tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
- A sinille submittal may be made for a multiple unit station.
- 0ne m.m shall cover stations near the SITE BOUNDARY; a second shall include t hea more distant statinns.
CAllAWAY - UNIT 1 6-18
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ANNUAL 4EPORTS
( Add iirr Tul10w ag te this section)-
T he. report s u l also
't w.el de Jhe results of specific activity analysis i'n which the primary coolant exceeded the limits of Specification 3.4.8-('J :nd C: plents),
3.4.9 (*1M plant:) er 3.4.5 (GE plant:).
The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine perfprmed prior to ex-ceeding the limit-results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and. time of sampling and the radiofodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which' the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine '
limit.
9 STS-ALL PLM!TS
FT 4
ULNRC-1480 Application Fee 804245 CHECK NUMBER UMON ELECTIUC COMPANY sr.LomsRssomu sis 216718 TO CENTERRE BANK OF KENNETT, MISSOURI 1945 DATE AMOUNT PAY U S NUCLEAR REGULATORY 03 10 87
$ * * * *** 150 00 to rac oRoER or COMMISSION l CHECKS OVER i sisoool REQUIRE COUNTERSIGNATURE l 1717 H ST NW WASHINGTON DC THIS CHECK 20555
\\if. j._QQlll$D,U,M,jl VOID AFTER
., [ ^ f,.7 $hYQ. ;ya
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90 DAYS
- " " ^ a' ii' 2 L G 7 LBii' i:08 L 50 2 4 5 9s: 84 035 L ii' l.
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