ML17213B386

Forwards Responses to NRC 830118 Request for Info Re Accident Monitoring,To Aid in post-implementation Review of NUREG-0737,Items II.F.1.4,II.F.1.5 & II.F.1.6

ML17213B386
Person / Time
Site:	Saint Lucie
Issue date:	05/19/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM L-83-10, NUDOCS 8305240372
Download: ML17213B386 (21)

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Dear Mr. Clark:

Re:

St. Lucie Unit 1

Docket No. 50-335 Post TMI Requirements Addi tional Accident Monitoring Information In your letter which we received on January 18, 1983, you'indicated that the NRC staff was conducting a post-implementation review of NUREG-0737 Items II.F.1.4., II.F.1.5 and II,F.1.6.

Our letter of February 17, 1983 provided you with a date by which time our response would be submitted and a brief

~

summary of the approach we would take.

Please find enclosed our response to the staff's request for information.

We trust that this information will aid the NRC staff in ccmpleting their review.

Very truly yours, Robert E. Uhrig Vice President Advanced System and Technology REU/PKG/js Enclosure cc:

Mr. James P. O'Reil ly, Region II Harold F. Reis, Esquire 8305240372 8305i9 PDR ADOCK 05000335 P

PDR PEOPLE... SERVING PEOPLE

EN'LOSURE

'E: 'T. LUCIE UNIT 1 DOC KET NO. 50-335 POST-TMI RE(U IR EVENTS ADDITIONAL ACCIDENT MONITORING INFORMATION

Response

to Item 1

Exceptions Being Taken to NUREG-0737 Re uirements The requi rements of NUREG-0737 for Items II.F.1.4, Contairment Pressure Monitor; II.F.1.5, Containment Water Level Monitor; and II.F.1.6, Containment Hydrogen Monitor have been met.

No exceptions are requested for St. Lucie Unit l.

BACKGROUND INFORMATION FOR ITEM 1

The Containment Pressure Monitors and Containment Water Level Monitors are redundant safety grade channels.

All major ccmponents are qualified to IEEE 323-71 and IEEE 344-71 or IEEE 323-74 and IEEE 344-75.

The Contairment Hydrogen Analyzer System consists of two hydrogen analyzers

-that meet the following Reg.

Guide 1.97 and NUREG-0737 requirements.,

1)

A continuous indication of hydrogen concentration in the containment atmosphere shall be provided in the Control Room

. within 30 minutes of the initiation of safety injection under design basis accident conditions.

2)

Measurement and read-out capability shall be provided over the range of 0-1(5 by volume of hydrogen with operating capability frcm 10 psia to maximum contairment design pressure.

3)

Class IE qualification to Reg.

Guide 1.89 and Seismic Category I

qualification to Reg.

Guide 1.100 is required.

~Res onse to Item 2

Pressure Monitorin S stem 2a)

The Containment Pressure Monitor System block diagram with the equipment number for each module noted is provided in Figure l.

The manufacturer and model number of each module are listed in Attachment l.

2b)

Attachment 1 provides the range,

accuracy, and time response for each module of the Containment Pressure Data. Sheet.

2c)

The individual parameters were used to calculate (using the square root of the sum of the'squares) the overall loop indicating and recording accuracies for the Pressure Monitoring System.

These accuracies are listed in Attachment l.

2d)

The 63% time response for each module is provided in Attachment l.

Since these loops only provide indication and they do not actuate any equipment, rapid time response is not a problem.

The longest 63%

time response for any module is 0.5 sec.

This is more than an order of magnitude shorter than the time for an operatior to read the indication and use the information to assess the present conditions.

Res onse to Item 3 Water Level Monitorin S stem 3a)

The Containment Level (wide range) Monitoring System block diagram is shown in Figure 2 and the Containment Sump Level (narrow range)

Monitoring System block diagram is shown in Figure 3.

The manufacturer and model number of each module are listed in Attachments 2 and 3.

.3b)

Attachments 2 and 3 provide the range and accuracy for each module of the two le'vel monitoring systems.

Res onse to Item 4

3c)

The individual module parameters were used to calculate (using the square root of the sum of the squares) the overall loop indicating and recording accuracies for both the wide range and narrow range level monitoring systems.

These accuracies are listed in Attachments 2 and 3.,

H dro en Monitorin S stem 4a)

The Hydrogen Analyzer Monitoring System block diagram is shown in Figure 4.

4b

& 4c)

Accuracy of each block module is not available since the manufacturer specifies only an overall instrument accuracy of +2% of the full scale of 0-10% hydrogen.

In addition, overall system accuracy can be affected by conditions in the inlet sample lines from the containment sample points.

4b

& 4c)

Accuracy of the Hydrogen Analyzer from the sample inlet of the analyzer to and including the local indicating meter and the control room indicating meter and recorder is determined from site calibration records.

Since an improved calibration procedure is used, the original manufacturer's data is no longer applicable.

Calibration of both Hydrogen Analyzer 'units is performed quarterly using Chemistry Operating Procedure No.

1"C-80 Revision 6.

Calibration gases are:

a) 4.5%H2, 3.0% 02, Bal N2 b) 2.9%H2, 2.0% 02 Bal N2 c) 100% N2 (Zero gas)

The calibration gases are piped directly into the sample inlet line.

The calibration is performed at the Control Room panel by first adjusting the zero potentiometer using gas c) to zero the meter.

Gas a) is then introduced and the span potentiometer adjusted.

Linearity is checked by introducing gas b).

Calibration records show that meters and recorder read within +0.1%

hydrogen after calibration at span gas concentrations a) and b).

This meets the calibration tolerance requirements as well as the Hydrogen Analyzer specification requirement of +0.2% Hydrogen (2%

of full scale).

4d)

The placement of the seven (7) hydrogen monitor intake ports are listed in Attachment 5.

4e)

An in-containemnt inspection of the sample ports was performed on April 19, 1983 as part of a system walk downq Site support engineers (I&C) visually inspected the sample ports and verified tlie absence of any physical barriers that would obstruct the hydrogen flow path to the sample ports.

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ATTACHMENT 1 Containment Pressure Data Prepared by: r44M hate:

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ATTACHMENT 2 Containment Level (wide ran e)

Data ate:

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Descri tion Mfr.

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Time

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In Sec LT-07-13A,13B Cont Level transmitter ITT Barton 764

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NA ES-07-1A,lB Cont Level Lambda LM-229 Power Supply 3 0-6 OVDC Adjustable Set 45VDC

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-1 to 26 ft 4762 Shelf (4-20 MADC)

.685 Overall Loop Accuracy Indication Overall Loop Accuracy

>> Recording 1.96 (2 )

1.72 (2 )

Notes:

(l)

Accuracy without LOCA Accuracy within 5 min after 1OCA is 5%

Accuracy after 5 min of LOCA is 108

Prepared by:+>~ Avesta: K/i/'g Reviewed by~WM~~ate: P/es/g~

Page 2 of 2

ATTACHNE2FP 2 Containment Level (wide ran e)

Data Cont d (2)

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indication b.

recording 5.13%

5. 05't Overall accuracy after 5 mi:n of LOCA xs:

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recording 10.02%

NA Not Applicable

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ATTACHMENT 3.

Containment Sum Level (narrow ran e)

Data Date: y/~~gg Pege 1 of 2 Ta No.

Descri tion Mod No.

an e

Accurac 63%

Time

Response

In Sec LT-07-14A Cont Sump Level transmitter ITT Barton 764 0-.7 ft (4-20 MADC)

1. 58 (2)

NA ES-07-1A LIS-07-14A'S-07-2A Cont Sump Level Power Supply Cont Sump Level Indi-cator Cont Level Rec Power Supply Lambda LM-229 Sigma 9262X Bailey 7000 AC/DC 8080BOC 30-60 VDC'djustable Set 45VDC 0-7 ft (4-20 MADC) 25VDC/24VAC

.51 1.166

.5 NA NA NA LR-07-13/14A Cont Sump Level Re-corder Bailey 771 C/N 4762 Shelf 0-7 ft (4-20 MADC)

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+~Date: yg~>/gp ATTACHMENT 3 Rage 2 of 2 Containment Sum Level (narrow range)

Data Cont'd Notes:

(2)

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Accuracy after 5 min of LOCA is 10%,

(3)

Overall accuracy within 5 min after LOCA is:

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indication b.

recording Overall accuracy after 5 min of LOCA is:

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indication b.

recording NA Not Applicable 5.13%

5.05%

10.06%

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FLORIDA POWER 8 LIGHT COMPANY INTER-OFFICE CORRESPONDENCE TO FROM

, R.

E. Uhrig J.

W. Williams, Jr.

sUELIEOTr St. Lucie Unit 1

Post-TMI Requi rements Additional Accident Monitoring Information RECEIVED MPV 'I 'I'9&3 Nuclear LIcensuIg LOCATION DATE COPIES TO Nuclear Energy Hav 161983 D. K. James C.

S.

Kent R. J. Acosta/910.13 SL H.

S.

Ruff C.

M. Wethy J.

A. Yespica W.

R. Klein P.

K. Green R EA-SLN-510 P NS-LI-83-344-1/2 The subject information is attached for your review and forwarding to the NRC.

The attachment was prepared in accordance with the requirements of 0.2.

f >><<1~

ff The information contained in the attachment to this letter was prepared by Power Plant Engineering.

Except for the following, the attachment is fully responsive to the NRC requirements or differences are clearly noted in the attached:

None.

J.

W. Williams, Jr.

JWW/PKG/j s Attachment PEOPLE... SERVING PEOPLE Form 1008 {StooctredI Rev. 8/81