ML20204C783

Proposed Tech Specs Deleting Unnecessary Reporting & Requirements Re Primary Coolant Activity

ML20204C783
Person / Time
Site:	Davis Besse
Issue date:	03/17/1987
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20204C541	List: ML20204C537 ML20204C733 ML20204C783
References
TAC-64970, NUDOCS 8703250365
Download: ML20204C783 (8)

Text

-

pocket No.'50-346 License No. NPF-3 Serial No. 1345 REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMIT!hG CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

< l.0 uCi/ gram DOSE EQUIVALENT I-131, and b.

< l'00/f uti/ gram APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1, 2 and 3*.

.m With the enseif te activ{tv af the n.4=

-u

,,u 1...

1 a.f a s_._

m

~~

UO5d 505!95[55E! '35 bethithEt.E.: id.dt;i[5f;;;'it]E,;5A'9,[.

te te left er the u :) :he = ri;.r; :.ci, as.. tier, my centinue fer up to 48 heers previM th-t :gr:ti= gr.d;7 th:::

cire" stances th:!' net ex ::d 10! Of the a, itis :tel y;;rly l

eaaretiaa t4==.

Th= previsieas of Sa--iricetien 3.0.' ::: =t

-applic 510.

8.-6,-

With the specific activity of the primary coolant > 1.0 uCi/ gram l

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 on Figure 3.4-1, be in at least HOT STAND 8Y with T,,9 < 530*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.-s, With the specific activity of the primary coolant > 100/f l

uC1/ gram, be in at least HOT STAN08Y with T"'8 < 530*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1, 2, 3, 4 and 5:

a.

With the specific activity of the primary coolant > 1.0 uC1/ gram DOSE EQUIVALENT I-131 or > 100/E uC1/ gram, perfom the sampling and analysis requirements of item 4 a) of Table 4.4-4 until the specific activity of the crimary coolant is restored to within its limits. !? : " ort 1 i;;;ir;d Fr 10 Cf" M.73, it :hil.

car,teir, th; i;;;14e of th; :F;ifi; ;;tivity ;;;13 3 el;;; ^;ith -

7 th: ' 1? = ies: For re.poc L3 cequire.mc.ots reb 4o hbon b.9 1. 5 c, k nvag ope.cck ng gort,

'With Tavg > 530'F.

DAVIS-8 ESSE. UNIT 1 3/4 4-20 Amendment No. 93 8703250365 B70317 PDR ADOCK 05000346 p

PDR

- - ~... - - -

o

• Docket No. 50-346 License No. NPF-3 Serial No. 1345 REACTOR COOLANT SYSTEM ACTION:

(Continued) 1.

Re:cter power history starting 48 heurs prior to the

._--,. s..x. a. u s.u

,a a.s.

--. s 2.,

.ma...

,n

.,y 9

c...i.. w_._.. m, u.,,,, ~... -. 3. m 3.

04ean-up-f4ew-histor-y-srtarting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the da which the 'imit was exceeded, first 52mple 4.

History Of de-;2 sting operations, i' 2ny, star, ting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior-4c-th:

rst campic in.-nich the limit

1. 4

-was-excccded, and The,_ time duratf 0n when the specific activity of th; 5.

-- 2_; i n ra,____

nner e n,,, u.. c ur yi asuvus y wvv wwwwwu sev ww s p y s ursa vvJ6 byv & y m6641 s

--b4&

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

DAVIS-BESSE, UNIT 1 3/4 4-21

L 1

E' E E' l

289-58a l

E l

028 cas TABLE 4.4-4 l

PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE E

AND ANALYSIS PROGRAM mM TYPE OF MEASUREM MT SAMPLE AND MODES IN WHICH SAMPLE i

AND ANALYSIS ANALYSIS FREQUENCY AND ANALYSIS REQUIRED 1.

Gross Activity Determination At least once each' 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1, 2, 3, 4 2.

Isotopic Analysis for DOSE 1 per 14 days 1

EQUIVALENT I-131 Concentration 3.

Radiochemical for T Determination 1 per 6 months

• 1

~

N

?

4.

Isotopic Analysis for Iodine a)

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever l,2,3!,4,5 M

Including I-131 I-133, and I-135 the specific activity exceeds 1.0 pCf/ gram DOSE EQUIVALENT I-131 or 100/T pCi/ gram, and b)

One sample between 2 and 6 1, 2, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> following a THERMAL POWER change exceeding 15 per-cent of the RATED THERMAL POWER within a one hour period.

1. ntil the specific activity of the primary coolant system is restored within its limits.

U

• Sample to be taken af ter a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

f g

Dockst,No. 50-346 l

M p{,

gllpq {

i jk g g*g gt License No. NPF-3 g ; g ltg j

Serial No. 1345 hh N

L Y

i h1 4~I I 8 II Iiil l _

6 i

L !,s_

'.i

'.' t.

T

'~

E l '

t I f

i I

e i

eI

-i e

i T*~

gg X

i

i i

i I

i li i

i i+

1 l

e i i e 4 e

i 3

'l'

'[I f.

t l i i t i b

i

',i i

T i i i.

ei!

i

, e i.

\\i i

i i

g

i.s siet i

i e

~3

e e i.T 2

s i

l

. s e i.

! j t.

vi i

!i!

ti i

.l.'

3 t

1:

i U

.',l'i

1'

! UNACCEPTABLE l'8-i 4

!6 i

iait i

OPERATION i t o

ei i

.!.T i

!i.

1 i

i,

[

l 6

3 8

i

't i_

i' i

! t t

==

s..

ie a a

1 it i

! j j i{

r 6 6 6

,\\1 I.

1 i

' I I1 I

I A.

M TI 1

I iT l

i ii e

t) i l t

' ' l' H 150

' ' i 6 i ?

.I i '1 I

t t t

• L.

I t i i li i l tT I

6 f. '

I Jl l i

.i e

i 6

i

,t i 'LI i i i tii.

8 i -. i t

i 1'

1i i e i i 6 g

i t

U i

i a

g ii k

1.

3 e a 8 i l gi E

i '

i 1

L i

f t

8 i i I

i i

T e

3, g

• I i 6 I i t i t

• t L

t,

g I i e

1 l 6 i

.i I i i6 i

i g,

i 3

ge 6 ?

l

.'i i

s e l

• t e i ti i

tot P

6.

i : 6e 6 i e

T 4 4 i e.

d.

i i !

l I

l 3

k i t,

i

+

y

.' l ACC'Eh'TAhLE

\\

t I

4.

OPERATION l

l

< 50 i

i i

i.

>ir i i

i i

ii:

5 6

i -.

i '

I O

i e

i I

,. 6 4 >..

t w

i i i t e

i i

i t i.

t t !.

8 i,

ij i

i il l

l I i&

i j i

i, e #

l 23 30 40 50 80 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4=1 DOSE EQUlVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0uC1/ gram Dose Equivelant 1131 DAVIS-8 ESSE, UNIT 1 3/4 4-23 m--

--,w,--

pocker No. 50-346 License No. NPF-3 Serial No. 1345 ADMINISTRATIVE CONTROLS power operation). supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUALOPERATINGREPORT1/

.c m.n,

.mw.pm e,, e w

g 6.g.1.4 Annual reports covering the activities of the unit during the previous calendar year shall be submitted prior to March 31 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

i 6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their agociated man rem exposure according to work and job functions,-

e.g.. reactor operations and surveillance, inservice inspection. routine maintenance. special maintenance (described maintenance). waste processing. and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLO. or film badge measurements. Small exposures totalling less than 205 of the j

individual total dose need not be accounted for. In the aggregate.

at least 801 of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube inservice inspections (Specificatiqn4.4.5.5.b).

c.

usert "c '

MONTHLY OPERATING REPORT 6.9.1.6 Routine' reports of operating statistics. shutdown experience and challenges to the Pressurizer Power Operated Relief Valve (PORV) and the Pressurizer Code Safety Valves shall be submitted on a monthly basis to the Director. Office of Management and Pr ram Analysis. U.S. Nuclear Regulatory Comunission. Washington, D.C.

• 0555 th a copy to the Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.

1/

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2,/ This tabulation supplements the requirements of $20.401 of 10 CFR Part 20.

)

OAVIS-BESSE. UNIT 1 6-15 Amendment No. f. N. H. N.

R. 87 l

i

_. _ -.,. ~. _ -,.,, __

pocket No. 50-346 Licenzo N3. NPF Seri21 Ns. 1345 INSERT "C" The results of specific activity analysis in which the primary c.

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 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 radiciodine concentrations; (3) clean-up system l

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 radioiodine limit.

l l

l

Docket No. 50-346

' License No. NPF-3 or{Np g}

f "'

I;' '] " '

j Serial No. 1345 G

Q l ' u:

b s.u b L u :.

^?

v r2 ';>

yfijft b i L h[a,, [ +

s4 qw-REACTOR COOLANT SYSTEM _

BASES 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduce the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State limits shown on Table 3.4-1 provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature depcndent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, op to the Transient Limits, I

for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval pennitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

The surveillance requirements provide adequate assurance that con-centrations in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of the Part 100 limit following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. 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 the specific site para-meters of the site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finaliz-ing site specific criteria which will be used as the basis for the This reevaluatien of the specific activity limits of this site.

reevaluation may result in higher limits.

DAVIS-BESSE, UNIT 1 8 3/4 4-5

Dockot No. 50-346

'I;icense No. NPF-3 Serial No. 1345 REACTOR COOLANT SYSTEM _

BASES The A'CTI0fstatement pennitting'P'0WER OPERATION to4 continue for limited time periods with the primary coolant's specific activity > 1.0 uCi/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accomodates possible iodine spikinggg omenon dig g'g occur following changes in THERMAL POWER. OperatioHYw t W e8 m c ac-tivity levels exceeding 1.0 pCi/ gram DOSE EQUIVALENT I-131 but withgn the limits shown on Figure 3.4-1 must be restricted to no more than 10 \\e d l

of-the-units-yearly-operating-times since the activity levels allowed by Figure 3.4-1 increase the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.

Reducing T to 4 S30*F prevents the release of activity should a steam generator,Ube rupture since the saturation pressure of the primary coolant is belcw the lift pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be de-tected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with A reduction in frequency of isotopic analyses follow-spiking phenomena.

ing power changes may be pennissible if justified by the data obtained.

3/4.4.9 PRESSURE / TEMPERATURE LIMITS The pressure-temperature limits of the reactor coolant pressure boundary are established in accordance with the requirements of Appendix G to 10 CFR 50 and with the thennal and loading cycles used for design purposes.

The limitations prevent non-ductile failure during normal operation, including anticipated operational occurrences and system hydrostatic The limits also prevent exceeding stress limits during cyclic tests.

operation. The loading conditions of interest include:

1.

Nonnal operations, including heatup and cooldown, 2.

Inservice leak and hydrostatic tests, and 3.

Reactor core operation.

The major components of the reactor coolant pressure boundary have The closure been analyzed in accordance with Appendix G to 10 CFR 50.

' head region, reactor vessel outlet nozzles and the beltline region have been identifi.J to be the only regions of the reactor vessel, and con-sequently of the reactor coolant pressure boundary, that detennine the pres:ere-temperature limitations concerning non-ductile failure.

DAVIS-BESSE, UNIT 1 8 3/4 4-6 1

- _ - _ - _ _ - _ _ _ _ _ _ _ _ _