ML13331B041
| ML13331B041 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/04/1988 |
| From: | Medford M Southern California Edison Co |
| To: | NRC Office of Administration & Resources Management (ARM) |
| References | |
| TAC-68170 NUDOCS 8805110239 | |
| Download: ML13331B041 (3) | |
Text
ACCELERATED DIS1IBUTION DEMONSTR ON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8805110239 DOC.DATE: 88/05/04 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 AUTH.NAME AUTHOR AFFILIATION MEDFORD,M.O.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Informs that util will submit proposed change to NRC which will revise Tech Spec 4.3.1 to be similar to Westinghouse.
R DISTRIBUTION CODE: A017D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Append J Containment Leak Rate Teiting NOTES:License Exp date in accordance with 10CFR2,2.109.
0500 0 206D S
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
PD5 PD 5
TRAMMELL,C 1
A INTERNAL: ACRS 10 1
ARM/DAF/LFMB 1
NRR/DEST/PSB 8D 1
NUDOeS=ABSTRACT 1
OGC 15-B-18 1
g00FILE 01 1
1 RES TELFORD,J 1
RES7DE/SEB 1
1 D
RES/DRAA/SAIB 1
RES/DRPS DEPY 1
1 RES/DRPS/RPSIB 1
S EXTERNAL: LPDR 1
NRC PDR 1
NSIC 1
A I
D S
A S
TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL
Southem California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M. 0. MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING (818) 302-1749 AND LICENSING May 4, 1988 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Containment Leakrate Testing San Onofre Nuclear Generating Station Unit I San Onofre Unit 1 Technical Specification 4.3.1, Containment Testing, requires Type A integrated leakrate tests be performed on the containment sphere. As part of the acceptance criteria for the Type A test a supplemental test is performed to determine the accuracy of the Type A test. This is specified in Section 4.3.1.I.B of the technical specifications. A part of that acceptance criteria is:
"...(2) requires the quantity of air bled from or injected into the containment during the supplemental test to be equivalent to at least 75 percent of the total allowable leakage rate at 49.4 psig."
As discussed with the NRC Staff, this requirement, as written, provides some confusion since it discusses quantities of air that should be equivalent to leakage rates (i.e. equates mass of air with leakage rate).
Therefore the purpose of this letter is to describe SCE's implementation of the technical specification and plans for revision of the technical specification.
As indicated in the references for the technical specification SCE employs the methodology described in ANSI/ANS 56.8-1981 for performing the supplemental test. The standard indicates that the supplemental test can be performed one of two ways, by an imposed leakrate test or by a pump back test. This standard requires that for the supplemental test the imposed leakrate must be between 75% and 125% of the maximum allowable leakrate. Or in the case that a pump back test is used, the quantity of air pumped back into the containment must be between 75% and 125% of the daily allowable leakage for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. It is obvious that the imposed leakrate supplemental test is based on leakage rates, whereas the pump back supplemental test is based on a mass of air. This agrees with the Westinghouse Standard Technical Specifications and ANSI/ANS 56.8-1981.
Therefore, SCE's implementation of the above technical specification will be in accordance with this description.
8805110239 880504 PDR ADOCK 05000206 Jo P
Document Control Desk May 4, 1988 In order to resolve this confusion in the Technical Specifications, SCE will submit a proposed change to the NRC which will revise this particular technical specification to be similar to that in the Westinghouse Technical Specification. Until this change is submitted SCE will continue to perform containment leakrate supplemental tests in accordance with ANSI/ANS 56.8-1981 as described above.
If you have any questions regarding this matter please let me know.
Very truly yours, cc:
- 3. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3