ML20002E461

Responds to NRC Re Violations Noted in IE Insp Rept 50-155/77-08.Corrective Actions:Reviewed & Approved Procedure Change Re Calibr of Incore Detectors Will Be Issued Prior to 770910

ML20002E461
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/10/1977
From:	Skibitsky W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20002E459	List: IR 05000155/1977008 ML20002E461
References
NUDOCS 8101280096
Download: ML20002E461 (13)

Text

N c0nsumers

~

Par.'Et t

C0mpany o.n.,.

omc..: so w.., uscua.n 4..no.. uca.on. uien.g.n.92cn. 4,.. coa. so 7ee-osso August 10, 1977 Mr James G Keppler US Nuclear Regulatory Com:nission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - RE3PONSE TO IE REPORT 50-155/77-08 By letter dated July 14, 1977, Consumers Power Company was aquested to respond to one infraction, one deficiency and one ' tem of concern discussed in IE Repcrt 50-155/77-08.

The purpose of this letter La to provide the required responses.

INFRACTION t.

" Technical Specification 6.8.1 states ' Written procedures shall be established, implemented and maintained for all structures, systems, components, and safety actions defined in the Big Rock Point Quality List.'

Section 17 3.2 of the Big Rock Point Quality List states that procedures will be developed for operations involving reactor safety such as instrument set points.

" Contrary to the above, a procedure has not been written to address the calibra-tion of in-ecre detectors."

RESPONSE

A reviewed and approved procedure change vill be issued prior to September 10, 1977 Since the plant is presently in a refueling outage, no in-core calibra-tions are expected prior to this date.

There are not any apparent procedural changes nteessary, in our opinion, to pre-vent recurrence, since the present plant procedures adequately address items en the Big Rock Point Q-List.

The item of noncompliance arose, in our opinion, due to a different interpretation of the above-referent.d documents. Our reasoning is presented ar follows:

The Big Rock Point reactor contains a relatively small, highly coupled, high leakage core. Because there is no flow control capability, power level re.nd etion of the' control rod pattern distribution at any given time is ol 1 a s?**

,,.p sge

2

(

and exposure distribution. Due t9,its high leakage characteristics, the core is very stable, analytically predictable and not subject to power oscillations.

The FHSR attests td the ' stability of the core and the lack of a need to connect the in-cores to the safety system in Section 7.6.2.

Because of inherent uncertainties in the instruments themselves, such as cable and chamber leakage properties and U-235 burnup Big Rock Point in-cores serve little function in the determination of safety limit margins. The R!G deviation of the in-cores, based on the most recent calibration, is evaluated on a daily basis only to examine general trends in the power distribution. Fluxvire irradia-tions and in-core recalibration are performed periodically, based on these evalu-ations. However, overall compliance with Technical Specification limits is based almost exclusively on thermal hydraulic computer analyses (GROK) normalized to actual flux distribution measurements (flux vires) without reliance on in-core calibration.

Based partly on the following Big Rock Point operating practices, the in-cores were not included as a part of the Big Rock Point Q-List:

a.

In-cores are used to monitor trends in the power distribution. No reliance is placed on in-core calibration in the determination of safety limit margins.

b.

The core is highly coupled and stable and is not subject to power oscillations.

Work associated with the completion of an in-core calibration is straight-c.

forward and we.1 within the capabilities of plant personnel performing the

duties, d.

Any errors mt e in the setting of in-core readings would tend to increase RMS deviation and only result in an increase in the frequency of flux vire irradi-ation.

While the existing procedure establishes the requirement for in-core recalibration, it is admittedly lacking in specifying what groups within the plant perform the work.

DEFICIENCY

" Technical Specification 6.8.2 states 'Each procedure...and changes thereto, shall be reviewed by the PRC...and approved by the Plant Superintendent prior to implementation.'

" Contrary to the above when a shutdown margin test was performed on May 3, 1976, a change was made to Procedure BRP-RE-8, Step 83, without the change being re-viewed or approved."

RESPONSE

A reviewed and approved change to Procedure BRP-RE-8 was subsequently made to f

(

update the procedure. A staff training effort vill be completed prior to September 30, 1977 to reiterate the importance of issuing reviewed and approved procedure changes.

l

d 3

(

('

ITEM v

"Dudng our inspection, it was revealed that you are using steam flow to determine core thermal. power. Please in your response address what measures you are taking to assure that values for core thermal power are conservative when calculated using steam flow values."

' RESPONSE-A detailed error analysis was performed and is included as Attachment I.

Attach-ment II, the summary of results, indicates that the error due to steam compres-sibility at 1250 psia is increasingly conservative above 71% of full flow.

I.

W S Skibitsky Nuclear Licensing Engineer

~

m ATTACHMENT I i

Current Bailey ID Component Type S/N Accuracy Instrument Spec ID09 Flow Transmitter CR168XAX 552750 I.5% Range P22-3 0-30g"lbm/hr, HO Mod B (20+100%

2 0-10

(

Full scale)

(integral Textractor) 1 ID26C Remote Adjustable AR8062A 419114 1%

P92-7 Relay Hod B FR ID06 Recorder KMSSA 440188

.5% Range M22-1 Mod E100

& Integrator

.5% (Between 20-100% Full scale)

PT-151 Pressure Transmitter 1260

.5% (full scale)

Aschrof t Manual 0-2000 psi for pressures above 15 psi.

Form 250-1358 6

Flow Element Pfow Transmitter - SQ Extractoj Como Relay-Recorder Integrater One Unit Transmitter 1

I i

ACIDENT I (Coned) 2.

Error Analysis foID26C I

a (% full scale) =

+

o 6

+ 1/2

+

+ oiNT 2+

00PER g

g accuracy of instrumentation (fraction of full scale) o =

% Range fraction of full scale output (ID09, ID06 based on 106

=

~

lba/hr, PT-151 based on 2,000 pei)

There is no % Range associated with integrator, as there is no full scale reading associated with this instrument.

ID06 serves simply as a " multiplier" independent of other steam flow instrtment ranges and is assumed to have constant accuracy (or inaccuracy) over its full range.

00PER Error associated with interpolating the integrator in the 104

=

lbm/hr range. (*.005)

OPT-151 The correction associated with the steam density is assumed to be proportional to the square root of the pressure. ' Die following table verifies this assumption.

Pressure Steam Density psia Correction Pressure Ratio Density Corr 1000

.8787 31.6 36.0 1200

.9765 34.6 35.5 1250 1.000 35.4 35.4 1350 1.0480 36.7 35.1 1400 1.0716 37.4 34.9 1600 1.1664 40.0 34.3 A

w

~

CHENT I (Contd) 3.

i The differential pressure across a flow orifice is used to determine the volumetric flow rate through the orifice.

The flow orifice in the main steam line will see a 300 in H O full scale dif ferential pressure 2

at 106 lba/hr steam at 1250 psia. To correct for the fact normal steam pressure at the flow orifice is other than 1250 psia, the steam density correction factor is applied to the output of the flow transmitter.

fy, 4 / Density at orifice pressure' 3

jg Den ity at designed 1250 psi Steam density correction Square Root sum of squares is used to determine total instrument accuracy.

It is assumed the following formula applies to steam flow readings:

St Flow = I (ID09)(PT151)1/2 (KID 26C)(kFRID06)(kOPR).

s-Int dat flow f st flo\\2 3

se flow L31909 )

ID09)2 + (f ast floj2f

/

2 ast flo 2 (6

ID06) 2 + fast fiolZ 3

3PT151/ (6PT15 1,3k 2+

gg (ID26C 3

/

4 INT 2+

3 INT

')

fast flo \\Z 2

\\a0PR

/

OPR (ID09)(PT-151)l/2 (KID 26C)(kFRID06) 7 6

Absolute accuracy of instrumentation

=

h (6ID09

+ 1/2 6PT-151 +

2 1

=

6ID26C +

6ID06 +

6 INT +

,g fy 1

D26Cj p

at flow 60PR' W

.ACHMENT I (Contd) 4.

I.p = % accuracy full scale. Adjusting appropriata instruments for part'ial scala readings 2.e c o

=

x g+1/2f0P

. ID26C 2+

IDO 8NTf+a0PR c t flow *

+

2 a

+

ng I

% Range for ID09 (Flow Transmitter) and ID06 (Flow Recorder) will be proportional to total steam flow. Normal steam pressure at PT-15 1s "1300 psia ors 65% full usage (0-2000 psi)

ID09 Steam Flow

% Range & ID06

% Range PT-151 o at flow %

.20 x 106

.2

.65 3.78

. 3 x 106

.3 2.71 4

e

.4 x 106

.4 2.22

.5 x 106

.5 1.95

. 6 x 106

.6 1.78 6

.7 x 10

.7 1.68 6

.8 x 10

.8 1.61

.9 x 106

,9 1.55 1.0 x 106 1,o 3g '

1.52 0

0 e

9

_a

ATTACIDENT II Conservatism associated with using Steam as basis for heat balance.

4 From the continuity Eqn., the Euler Eqn and acoustic velocity correction:

f =

yg ge (1-M )

Ref pg 3-39 Piping handbook - Croker & King 2

Mass Flow' Rate

- where A cross sectional Area m -

=

Specific - Heat Ratio Fluid Pressure k

P

=

=

Gas Constant Fluid Density R

p

=

=

Fluid Velocity T

V Temperature

=

=

ge = Universal Cravitational Constant Mach i M

=

V/C V//gekRT ~

IBID pg 3-38 M

=

=

(

00 hr/sec)

~

39 bm/ft3 10.75 ftg

[32.2 lbmf t/lbf sec2 (1.3)(85.9 f t Ib f/lbmR)(580 + 460 R) 4.4 x 10-3 Mach i may be ignored flow is very sub-sonic

=

(

Data A1 10.75" (12" Sch 120)

=

1 2

A2 8.625" (Nozzle Srec 2/7/61

=

PO #205.68711) g P1 1285 psig (Typical of BRP operation)

=

P2 1155 psig (Assuues 300" dP at rated

=

flow,106 lba/hr) 3

.3293 ft /1 V

=

1 Keenan & Keys 3

v2

.3692 ft /lbs

=

s

AT7" t""rrnnnoccalcefy 2.

Ignoring sonic velocity correction dA

~[dP }

't A

\\ PVZ/

P Let P

RT 3

and v - A RT_

PA then dP

=

A EC

/P\\[6RTj2 (RT / ( PA /

PdP dA

=

Ec AJ

&ZRT (A2dA 2-(Assumes Temperature does not change as a PdP 7"m function of Pressure, i.e.,

Steam is super-P1 heated as it passes through nozzle.)

Al 2

-1/2 A-2

= n!RT (1/2 P

)

2 2

- 1/A1 "m

(P1 - P2 )

1/A2 "2

(P12 _ p,2) ge (p101

- P o9) ge 9

2 - 1/A2)

(1/A1 - 1/A2)

RT (1/A1 2

s = [P 2 _ p22

. / p p1 _ p2P2 y

1 e

4

.c -

ATTACIDIENT II (C:ntd) 3.

(

Nozzle dP Pi P2 in inches H O (psia) psia

[Py 2

b-P2 41-P2 Power

=

Erroc 2

30G 1250 1120 555 11 1.0 48.7 1.2 250 1142 508 10.4

.92

. 48.8 1.0

~

200 1163 458

'9. 3

.82 4':.1

.4 150 1185 398 8.1

.71 4S.3 0

100 1207 325 6.6

.59 49.6

.6 50 1278 233 4.7

.42 49.8

-1.0

.a P1 and P2 are bascd on 1250 psia steam flow where nozzle was designed.

Corrections to steam flow are proportional to the ratio of the squarr roots of the density.

This has little effect on error analysis, d 2 _ p22 1

is proportional to power level vil-P2 is proportional to pressure transnitter output

% Potier is normalized to d 2 _ p2 at 300" 1

ratio of /P 2 - P22 and is a measure of error due to stean flow

1 g1_ p2 compressibility.

% error is based on the most accurate measurements being made at 71% flot. (Ref Bailey Spec G99-2, pg 4 - attached).

The analysis is reperformed using methods recommended by Bailey Spec G99-2.

Note that their analysis shows the conservatism above 71% to be less than half that of this analysis. In any event, the trends of each analysis show that the higher the steam flow is above 70% power, the more conservative the flow measure-ment and the subsequent heat balance will be.

f

(

~ ' ' '

- ~ ~

~

m -- --,

099 2 Y

7 9ese 4 <

i l

13 should bc made as described above for pres.

gases h'aving different specific gravitics, in 4 l v3 correction curses, the proportions of the mixturc may change :.

L.,t)ECIFIC GRAVliY CORRECTION FACTORS 4 wmal peration. Figure 14 shows the correeg..

i,rj, A correction for speci6c gravity may be neces.

factors necessary for variations m spec Sc graq g,

sary if the sneasured gas consists of a mixture of from the designed value.

,g COMPRESSIBLE FLUID CORfdCTION FACTORS i

4 For a compressib!c fluid, the relation of flow to meter error or span of the meter correction fac.,,

diffarential scruss a Primary Element deviates for compressibility is I.S per cent.

e eN clightly from the square root relationship beciouse Since the error diminishes a* rates of flow in, cf the different specific weights or volumes than maximum, and is a linear i nction of the e.

cpplying at the different pressures at inlet and ferential pressure drop between inlet and oude.

.).~

outht. The amount of the error which results the standard Dailey procedure is to minimize en

. from this deviation for different difTerential snaximun,i error by including in the Primary ih N

mitrrs and different Primary Elenients at maxi.

inent design the correction facior for the imdrarr.

mum flow rate can he det rmmed from Figure la_.

value of the differential pressures applied to r.,

t This curve may be used for flow nozzles and con-meter-i.e., for about 70 per cent of maxirnu.

'h flow. At.this flow rate, therefore, the meter redy cintric or:6ces with steam and gascs which have correctlv.I 1 he correction factars which appiv - ~.

S.

o 4, sci 6c heat ratio of 1.3.

For air and other other rates of flow can then be determined he ~

dis tc.:'ie gases with a speci6c heat ratio of 1.4, plotting a line on the grid shown in Figure is,

N muidply -he indicated span by.93.

The line is drawn thru two points as follows:

Ec.

w*. r Tc illustrate the use of the curve,

1. Point @-fixed point for all meters

.,]

cssume en installation measuring steam at 100 psig

2. Point @-correction factor at 0% flow, en:.

,A

~' (115 psia) with a.80 ratio flow nozzle and a max; culated as follows for the particular meter:

,i,_

mum meter differential of 53 inches. For these 1.000

• e rrecti n act r span (%) fr m Figure i.: '.

{..j D mditions, Figure 15 shows that the maximum 200

'4 PlPE INTERNAL DIAMETER CORRECTION FACTORS i

I.,".c.".

Tio fundamental flow formula used in the de.

for variations in pipe diameter may be determine 1 v g

d' 7 cign of Primary Elements is based on a specified I.E mternal pipe diameter. If the actual internal pipe Example: To illustrate the use of the curve. s* I sume an orifice designed for six-inch Scheduie 4

?

')

diameter difiers from the value specified for tlje pipe (6.065' l.D.) and a diameter ratio g of.G.

b I remary Element, design, there is a change m but actually insta!!cd in Schedule 80 pipe (5161*

A,M dirmeter ratio with a consequent effect on the I.D.). The ratio of 5.761 to 6.065 is.95, and n

. r(.S coproach f..cror F, in the flow formula. Figure curve shows that a correction factor of lKi ;

;, ^

17 shows a curve from which correction factors should be used for these conditions.

j

',,,Q

. 3.m.

INDEX OF CORRECTION FACTOR CURVES W.

1

g!N Fibre dr~er.itint CanW'sas Pate 1

Steam Flow, O to 60 psi,200F to 600F 5

J

• ' h 2

Steam Flow,50 to 250 psi,300F in 1000F 6

,"%'Mp 3

Steam Flow,200 to 800 psi,350F to 1000F 7 and 8 4

~.

4 Steam Flow,600 to 2000 psi,450F to 1100F 9

5 Steam Flow,1500 to 5400 psi,550E to 1200F 10

.1

}

,,[iM"Wj 6

Steam Flow, O to 15% Aloisture. 0 to 200F Superheat 11 7

Water Flow,32 to 300F 12

• YM

t 8

Water Flow O to 600 psi 32 to 600F 13 and 14 4

9 Petroleum Oils,60 to 500F 15 and 16 I

e-10 Air or Gas Flow,28 to 43 Inches of Siercury 17

i P y>

11 Air or Gas Flow -S to 55 psig 18 L

12 Air or Gas Flow,10 to 310 psict 19 1

j.

13 Dry Air or Gas Temperature Correction Factors 20

'4 j

14 Gas Flow, Specific Gravity Correction Factors 21

- (

15 Compressibility Correction Factor Span 22 y

l. w.

16 Grid for Compressibility Correction Factors 23

.g

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17 Variations in Pipe Internal Diameter 24 P00R OR GM i

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