ML20206P963

Proposed Tech Specs 3.4.5,6.9.1.5 & Bases 3/4.4.5,reducing Reporting Requirements on Primary Coolant Iodine Spikes & Deleting Shutdown Requirements Re Specific Activity,Per Generic Ltr 85-19

ML20206P963
Person / Time
Site:	Fermi
Issue date:	06/27/1986
From:	DETROIT EDISON CO.
To:
Shared Package
ML20206P961	List: ML20206P955 ML20206P963
References
GL-85-19, VP-86-0028, VP-86-28, NUDOCS 8607020312
Download: ML20206P963 (6)

Text

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REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION ,

3.4.5 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT I-131, and l

b. Less than or equal to 100 4 microcuries per gram.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and 4.

! ACTION:

a. In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of the primary coolant;

1. Greater than 0.2 micro r1 pe ram DOSE EQUIVALENT I-131 but

.mWT :: LiZIRM Z;;,";L.Z].- tin

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less than or equal to

7. . . u . . .. , . . ._ m _ G ' aa bE ftime der these ci umst c does t excee 80030 s Ii1 an W) 6 consecu 've 12- h perio . Wit he total c ul ve operat' bM-di y coola'nt spe i c activity grea r than 0.2 ic -

time at a ri curie per DOSE EQUIVALEN -131 exceedin 5 hours i any a Spe ial consecut 6- nth period repa and su Repor o the Co ission ursuant t Spec' ication 6. 2 ithin 30 ys indicating e umber of hour operation ab e this h.it. The p evisica_ ef Specift:: tie, 3.v. , are noi. .ppli;;tle d

[ f eiter tha microcur' er gra EQUI ENT I- for mo tha ho s dur g one o nuous i int rv or f more n 800 hou umulativ erating me in a nsecuti 12- period treate han mict ur s gr ,

i t le t SHUTA ith the steam ne isola on valves

(

osed wit n 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

. Greater than 100 4 microcuries per gram, be in at least HOT SHUTDOWN with the mainG t::rli Q isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, rpm g

b. In OPERATIONAL CONDITION 1, 2, 3, or 4, with the specific activity of the primary coolant greater than 0.2 microcuria(fper gram vu5ii 4, EQUIVALENT I-131 or greater than 100 4 microcuries r gram, perform the sampling and analysis requirements of Item 4. f Table 4.4.5-1 e until the specific activity of,the crimary coolan is restored to '

within its limit. JA 5pecia ort shall b repared and mitted F 'the commiss' pursu to Sp ifica 6. 2 with 0d s. s rep t sha onta e results o e specific c ity ana s and the ti uration the spe c tivity of e cola xce d 0.2 cro is p gr DOS QUIVALE -13 ogether h.the fol-1 ing addit 1 info on. j L ~

FERMI - UNIT 2 3/4 4-16 8607020312 860627 1 PDR ADOCK 0500 P

A2-2 VP-86-0028 Insert 1 4.0 microcuries per gram DOSE EQUIVALENT I-131 for more than-48 hours during one continuous time interval, or greater than 4.0 microcuries per gram DOSE EQUIVALENT I-131, be in at least HOT SHUTDOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I 4

4 J

. l REACTOR COOLANT SYSTEM i

LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

c. In OPERATIONAL CONDITION 1 or 2, with:

1. THERMAL POWER changed by more than 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> *, or

2. The off gas level, at the delay pipe, increased by more than 10,000 microcuries per second in I hour during steady-state operation at release rates less than 75,000 microcuries per second, or

3. The off gas level, at the delay pipe, increased by more than 15%

in one hour during steady-state operation at release rates .

greater than 75,000 microcuries per second, perform the sampling and analysis requirements of Item 4b of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit. Tcep r :nd ri-it 1 the Ce.;i::i n : Sp;;ici ";;;rt pursu r.t 0; Sp;;i'i;;ti:n 5.0.2 :t 1 ::t :n:: ;:r ^2 d:y: ::nt: fring th: 7; ;1t: f th; :p;;ifi:

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SURVEILLANCE REQUIREMENTS 4.4.5 The specific activity of the reactor coolant shall be demonstrated to be within the limits by performance of the sampling and analysis program of Table 4.4.5-1.

i l

! *Not applicable during the startup test program.

FERMI - UNIT 2 3/4 4-17

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 6.9.1.5 Reports required on an annual basis shall include: -

a. A tabulation on an annual basis of the number of plant, utility, and 1 other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,* (e.g. , reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance

[ describe maintenance), waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket or thermoluminescent dosimeters (TLD) dosimeters or film badge measurements. Small exposures totalling less than 20% of the indi-vidual 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 functions; and

b. Documentation of all challenges to main steam line safety / relief valves, and l

A summary of ECCS outage data including:

c.

i Add 1. ECCS outage dates and duration of cutages, Cause of each ECCS outage, 2.

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3. ECCS systems and components in the outage, and

-thg 4. Corrective action taken.

h MONTHLY OPERATING REPORTS

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6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.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.

i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT **

6.9.1.7 Routine Annual Radiological Environmental Operating Reports covering l the operation of the unit during the previous calendar year shall be submitted l 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, j interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compar-l ison as appropriate, 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.  ;

1 The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental l ,

t l *This tabulation' supplements the requirements of $20.407 of 10 CFR.'Part 20.

• • A single submittal may be made for a multiple unit station. -

FERMI - UNIT 2 6-16 l

l l -

A2-3 VP-86-0028 Insert 2 The reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5. 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 radiciodine performed prior to exceeding 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 radioiodine 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 and one other radioiodine isotope concentrations 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 radioiodine limit.

REACTOR COOLANT SYSTEM BASES 3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters, such as site boundary location and meteorological conditions, were not considered in this evaluation.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 micro--

curies per gram DOSE EQUIVALENT-I-131, accommodates possible iodine spikina '

phenomenonwhichmayoccurfollowingchangesinTHERMALPOWER./0;r:ti:nwith pect'ic ::tiv;ty 1;:::: = :n : ; :.: ;;;r::r;;; p;r ;. ; 000: CQUIVAL 70

{ :I-131 but ?:n th = rr :;r:? t '.0 ci r = ri n e n ;;;; 000 :QU: VAL:l0 : l';; .

:t 5: = :tricted t: :: =r: th= 000 h = n ; r y n r, ;; n ni::t:13 10 prn t '

c' the unit's y = rly Opt r t' ; tir , eine: th::: ::tivity 1:=1: ' : =:= th:

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2 h: r thyr:id d::: :t th: :it: i n nd ry by : '::t r :" ; i: 00 ':ll =in; ;

j (, p::t:1:t:d :t::: l' : =;tr: . Th: =p r tin; ef e r rl:t! = 0;: = tin; ti r

=:r 500 h:r: in : y S ;=th ;===tiv: p ri:d .ith en :t:r th= 0.2 i: n-Ouri:: ; r ;rr ^^SE E^UIV.5" ?-??? ri" :1?= ="f:i=t tin 'n Crini:n evelretie- ef th: circ r:t = := ;ri r e = = h' ; th: 000 h: r 'f:it.

Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of j

isotopic analysis following power changes may be permissible if justified by the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the environs should a steam line rupture occur outside containment.

The surveillance requirements provide adequate assurance that excessive specific e activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

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