ML20150F304

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Proposed Tech Spec 3.4.8 Re RCS Specific Activity
ML20150F304
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 07/06/1988
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20150F302 List:
References
NUDOCS 8807180223
Download: ML20150F304 (6)
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ATTACHMENT III  ;

PROPOSED TECHNICAL SPECIFICATION CHANGE l

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I 8807180223 880706 PDR ADOCK 05000482 P PDC

c.  :. Attachment III to WM 88-0181 Page 1 of 5

. July 6 ,1988

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( 3 ; J. ! 3:ECI;iC ACTIVITY

.:MIT !,3 CO'DIT10r! COR OPERAT10f1 3.4.E The specific activity of the reactor coolant shall be limited to:

a. Less than or equal to 1 microcurie per gram DOSE EQUIVALENT I-131, and
b. Less than or equal to 100/I microCuries per gram of gross radioac:ivit:.

ADPLICASILITY: MODES 1, 2, 3, 4, and 5.

ACTION:

MODES 1. 2, and 3*-

With the specific activity of the reactor coolant greater than

. -icroCurie per gram DOSE EQUIVALENT I-131 but within the 2 -aale limi low and to the left of the line) shown on Fi . s.4-1.

operation .. . continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provid 6 at the cumula-tive operating under these circumstanc oes not exceed

( 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any con ive 12-month 1 od. The provisions of Specification 3.0.4 are no 1 e;

b. With the total cumula operating at a reactor coolant specific activity greater n 1 microcurie per gr SE EQUIVALENT l-131 exceeding ~ ours in any consecutive 6-montn 'od, prepare ano submi pecial Report to the Commission pursuant t 'ecification l

'. within 30 days indicating the number of hours above . 's limit.

The provisions of Specification 3.0.4 are not applicable; a , .e- With the specific activity of the reactor coolant greater than  !

1 microcurie per gram DOSE 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 ,j on Figure 3.4-1, be in at least HOT STANDBY 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 />; and avg l

b. .c,- With the specific activity of the reactor coolant greater than 100/E microCuries per gram of gross radioactivity, be in at least HOT STANDBY with T avg 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 />. 4

'With T greater than or equal to 500 F.

q WOLF CREEK - UNIT 1 3/4 4-25

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Attachment III to WM 88-0181 Page 2 of 5 July 6, 1988

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REACTOR COOLANT SYSTEM '

LIMITING CONDITI0tl FOR OPERATION l

ACTION (Continued) I 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 cf gross radicactivity, 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. o rcp re-and ubmit c Special Report t0- th: Oc=i::f en pur uant tc Speci'icatico-5.0.2,within 20 days with a copy to the Oirector, Nuclear Reactor Regule--

tien, Attentien.

Chief, Core Pe,-Ter mence Grencii, and Chief, Accident.

Evaluation Branch, U.S. Nuclear Regulatory Oc=ission, 'Jashington, 0.0.

20555.

This report shall contain the result: cf the specific acti.ity

-analysc: tcgether ith the fe!!ce:%g infer-nien-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 te the first sample ich the limit was exceeded,

b. Results -

(1) the last isotopic analysis for radi ine performed prior to ex in the limit, (2) analysis while and (3) one ana ,,g s after the radiofodine mit was exceeded vity was reduced to [

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T less than the limit, ' ciuding for each otopic analysis, the date and time of sampling an e radici ne concentrations,

c. Clean-up flow history star g
  • ours prior to the first sample in which the limit was e ded,
d. History of der sing operations, if any, sta the firs g 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to ample in which the limit was exceeded, d e.

time duration when the specific activity of tha prima coolant

- exceeded 1 microcurie per gram 00SE EQUIVALENT I-131.

SURVEILLANCE REOUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determinec :.c be within the limits Oy performance of the sampling and analysis program of Table 4.4-4 WOLF CREEK - UNIT 1 3/4 4-26

w  : .' Attachment III to WM 88-0181 Page 3 of 5

, July 6, 1988 REACTOR COOLANT 5 '

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i BASES SPECIFIC ACTIV!] (Continued) s The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than ,

1 microcurie / gram 00SE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon whicn may occur following changes in THERMAL POWER.

levels exceeding 1 micr:Curic/ gram 00SE EQUIVALE."T I-131 but 'ithi- th: Operation w

?'-it:

hcr er c i g u r e 3. A '. mu t be re:tricted te ne mere ther SCO heur: per y::r ( ppr:H=t:!y 10" Of the unit'; y:Orly operating time) :ine: th :ti..

1:;;!: 11:ntd by cigur: 3.'-1 'ncre :: the 2-hour thyreid de:: at the :f:: ,

toundary rupture. by a f;;tcr ;f up t; 20 f;11: wing a postulo".ad stcam gcacratcr tu:.e Th; utis E :: nth cen;;; r:p;rting ;f cumulatia cperating tim ever 500 h;ur; 'r any

-!-131 ili all;w  ;;riod ,;ith gr: ster than 1 micr; Curis / gram 005: :0 UI'/A L:N' prior t; reaching sufficient the SCO-hour tir.a for M C;maission

.- avaluation of th; circ;;;;;n:c3 Reducing T,yg 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 ccolant 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 phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified 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 heatue anc cooldown limited in rates (with the exception of the pressurizer) shall ce accordance with Figures 3.4-2 and 3 4-3 for the servic e period specified thereon: .

a.

Allowable combinations of pressure and temperature for s ecific temoerature change rates are below and to the right of the limit lines shown. Limit lines for cooldown rates between those presented may be ootained by interpolation; anc l

WOLF CREEK - UNii 1 B 3/4 4-6 4

N Attachrnsnt III to WM 88-0181 Page 4 of 5 July 6,1988 ADMINISTRATIVE CONTROLS

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ANNUAL REPORTS (Continued) assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work func-tions; and bu _ Ooc mentation of all challenges to the PORVs or safety valves.

ANN OL ICAL 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 by May 1 of each year. The initial report shall be submitted by May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activites 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 the Land Use Census required by Specification 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiclogical environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the 00CM, 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 for inclusion with the report, the report shall be submitted noting and explaining the reasons for the 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 the reactor; the results of licensee participatien in the Interlaboratory Comparison Program and the corrective actions being taken if  !

the specified program is not being performed as required by Specification 3.12.3; reasons far not conducting the Radiological Environmental Monitoring Program as  !

i required by Specification 3.12.1 and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measure-ments that exceed the reporting levels of Table 3.12-2 but are not the result of plant effluents, pursuant to Specification 3.12.1; and discussion of all analyses in which the LLO required by Table 4.12-1 was r.ot achievable.

  • 0ne map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations. f N

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Attachment 111toWM8p-0181 7 Page 5 of 5

, July 6,1988 lkj sE AT- A

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The results of specific activity analysis ih which the primary coolant exceeded the limits of Specification 3.4.8.

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 performed 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 co'olant exceeded the radiciodine limit.

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