ML13323A172

Forwards Revised Pages 5,Q-1 & R-4 to Feb 1981 Reactor Bldg Containment Integrated Leak Rate Test Rept. Changes Reflect Instrument Accuracies & Typographical Error in Equation 9a

ML13323A172
Person / Time
Site:	San Onofre
Issue date:	10/28/1981
From:	Baskin K Southern California Edison Co
To:	Miraglia F Office of Nuclear Reactor Regulation
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ML13323A173	List: ML13323A172
References
NUDOCS 8111090609
Download: ML13323A172 (7)

Text

REGULATJR INFORMATION DISTRIOUTION SYSTEM (RIOS)

ACCESSIO N3R;8111090609 DOCDATE: 81/10/28 NOTARIZED: NO )OCKET' #

FACIL:50-361 San Onofre: Nucleart station, Unfit 2,. Southern Californ, 05000361 AUTHNAME! AUTHR AFFILIATION BASKIN',XI.P, Southern California Edison Co.

RECI?. NJAM!Ei RECIPTENT AFFILIATIONV WIRAGLIAIF. LUicensing, ranch 3

SUBJECT:

Forwards' revised: Pages5S9*- & R-4 to Feb 1981 "Reactor Bldg, Conta-inpit Integrated, Leak Rate Test Rept." Changes reflectt inlstrjmeht accuracies & typographical error in-Equatlhon 9a.e D'lSTRIBJTION CO DE1: B001 COPIES RECEIIVE::LITR ENCUi SIZE:;

TITLEi:: PSAR/FSAR AMOTS and Related Correspondence NOTES:L Chandler:all FSAR & ER amends-o cy:J Hanchett(Region V), 05000361 D Scaletti:1 cy a;l envirtinfo, RECIPIENT COPIES RECIPIENT COPIES 101 CODEVNAMWl LTTR ENCUt ID CODE/NAME. LTTR ENCL ACTION:; A/Di LICENSNG 1 0 LIC:BR 03 BC 1 0 LICi BR #3 LA 1 0 R000,Hl. 01 1 I INTERNAL: EL)' 1 0 I&EI 06, 3 3 IE/DEP/EPDB: 3j 1 1 IEVDEP/EPLB 36, 3 3 MPA1 0 NRR/DE/CE8 11 1 1 NR'/DE/E9B 13 3 3 NRR/DE/GBt 28 2 21 NRRVDEVMEGBE 30. 2 2 NRRVDE/E8 18 1 1 NRR/DEYIMTE i1 1 NRRVDE/'QAB 21 1 1 NRRVDE/AB 24 1 1 NRRVDE/SE8 25 1 1 NRRVDHFS/HFE340. 1 1 NRR/DHFS/LQB 32' 1 1 NR VDHFS/,)L8 34 1 1 NRR/DHFS/PTR820- 1 1:

NRRV/DSIVAE 3 25' 1 1 NRR/DSI/ASB, 27 1 1 NRRVDSIVCPB 10, 1 1 NRRVDSI/CS8 09 1 1 NRRVDSIVETSB 12 1 1 NRR/DSI/CSB 16 1 NRR/DSIVPSB 19 1 1 NR R/DSI/RAB 22 1 1 1, 23 1 1 NRR/DST/LG8 33 1 1 E E 04 1 1 EXTERNAL: ACRS 41 16 16 BNL(AMDTS'ONLY) 1 1 FEMA-REP DIV 39 1 1 LPDR 03- 1 1 NR i PD 02, 1 1 NSIC 05 1 1 NT1I 1 1 TOITAL NUq1BEIR OF COPIES' REQUiRED:: LTTR 9 ENCL ,;8

Southern California Edison Company P. O BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING October 28, 1981 Director, Office of Nuclear Reactor Regulation Attention: Mr. Frank Miraglia, Branch Chief Licensing Branch No. 3 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

Subject:

Docket No. 50-361 San Onofre Nuclear Generating Station Unit 2 In accordance with the requirements of 10CFR50 Appendix J, SCE's letter of March 6, 1981 submitted sixty-three (63) copies of the San Onofre Unit 2 "Reactor Containment Integrated Leak Rate Test Report", dated February 1981. Pages 5 and Q-1 have subsequently been revised to reflect instrument accuracies and page R-4 has also been revised to reflect a typographical error in equation 9a.

Enclosed please find sixty-three (63) copies of revised pages 5, Q-1 and R-4, which superscede and replace the corresponding pages previously provided in the February 1981 report.

If you have any questions or comments concerning this information please contact me.

Very truly yours, Enclosures 8111090609 811028 PDR ADOCK 05000361 A PDR)

NRC-SONGS Box NRCSONGS0065 Accession 8111090612

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 DOCKET NUMBER 53-361 Revised Pages 5, Q-1 and R-4 to Reactor Containnt Building Integrated Leak Rate Test Report February 1981 Revision 1 October, 1981

. I LOCAL LEAKAGE RATE I IPENETRATION SYSTEM, /VALVE I SCCM l I I I I I 45 I Normal A/C Chill Water/2HV-9990 & 2HV-9920 I 1267.5 I 46 Normal A/C Chill Water/2HV-9971 & 2HV-9921 0+2.0 1 I P I 10B I ILRT Pressure Sensor/S21500MU038 0+2.0 l 10lB l ILRT Pressure Sensor/S2 1500 MU039 I0+2.0 (

34 l ILRT Test Connection 0+0.2 I 68 I Manual Aux Spray Bypass/S21208MU 129 & 130 1 637 I I _ _ _ _ I _ _ _ _ _ _ __ _ _ _ _ I _ _ _ __ I I I II Total I 1910.7 1 I I I II

%/ Day I 0.000864 I E. Integrated Leakage Rate Measurement System

1. Absolute Pressure (1 + 1 backup)

Make: Mensor Model: 10100-001 Range: 0-100 psia Accuracy: +.015% of reading Repeatability: +.0005% of full scale Gage S/N 1487, Capsule S/N 2317 Calibration Due Date: May 14, 1981 Gage S/N 1489, Capsule S/N 2349 Calibration Due Date: May 14, 1981 Calibration Standard:

Texas Instruments S/N 2741, Capsule 834 Calibration Due Date: May 10, 1981

2. Drybulb Temperature (18 plus 2 spares)

Make: Rosemount 100 ohm platinum Model: 78-65-17 Range: 0-150* F Accuracy: + 0.10 F (60-120*F)

+ 0.15"F (0-150 0 F)

Repeatability: +.1F S/N S/N S/N S/N S/N 120063 116020 120071 120070 120064 117228 116025 120058 117227 117238 120060 117233 117244 117240 120061 120073 120062 117241 117229 117230 Calibration Due Date: April 23, 1981 Calibration Standard:

Burns RTD S/N 84939 and VMC 202. Keithley 191 DMM DH-037 -5 Revision

APPENDIX Q INSTRUMENT SYSTEM ERROR ANALYSIS The instrument system error analysis is based on the Figure of Merit, also known as Instrument Selection Guide (ISG), formula in BN-TOP-l, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants." The formula is:

ISG =

140 2

e 2 2+ 2 ev2 2 2 ]

2T 1e~

12

%/Day

where, ep = absolute pressure measurement repeatability error divided by the square root of the number of sensors.

= (.0005%) (100 psia)/(1)1/2

= .0005 psia epv = vapor pressure measurement accuracy error divided by the square root of the number of sensors. (NOTE: Accuracy is conservatively used rather than repeatability.)

(.54 0F) (0.0124 psia/OF)*/(4)1/ 2

= .00335 psia

• From steam tables at dewpoint temperature range 69-71 *F et = drybulb temperature measurement repeatability error divided by the square root of the number of sensors.

= (0.1F)/(18)1/2 . .0236 0 F P Test pressure

= 71.9 psia T Test temperature

. 540* R DH-037 Q-1 of 2 .

Revision 1

b. Calculated leakage rate from regression analysis:

L = a + bkN (5) where:

L = Calculated leakage rate, %/day, as determined from the regression line.

(ELi) (Eki 2

) - (Eki) (ELiki a = _ _ _ _ _ _ _ _

N (Eki 2 ) - (Eki) 2 (6)

N(ELiki) - (ELi) (Eki) b- NEi 2 -(7)

N(ki)-(ki ki = Elapsed time at time of ith data point N Number of data points N

i ==1

c. Calculated leakage rate at the 95% confidence level including error associated with the test).

Total-Time Method per BN-TOP-1.

L9 5 = a + bk + S- (8)

L where:

L95= Calculated leakage rate at the 95% confidence level.,

%/day, at elapsed time k.

For kN < 24 22 1+ 1 1 (kN (Li-L S . tO.025;N-2 - (9a)

N-2 N (k -k) 2.37 2.82 where, tO.025;N-2 = 1.96 + J N-2 (N-2) 2 DH-039 R-4 of 7 Revision 1