ML20236X794
| ML20236X794 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/01/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 3864K, NUDOCS 8712100270 | |
| Download: ML20236X794 (2) | |
Text
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[D Comm:nwrith Edison 4
O ) One First National Plaza Chicago, Illinois I
4 Address Reply to: PoTOffice Box 767-(\\
Chicago, liknois 60690 - 0767 i
December 1, 1987 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Subject:
Braidwood Station Unit 2 Containment Leakage NRC Docket No. 50-457 Reference (a): NUREG-1276, Technical Specifications for Braidwood Station, dated July, 1987
Dear Mr. Murley:
Pursuant to 10 CFR 50 Appendix J, Commonwealth Edison Company is providing the value of the maximum allowable leakage rate (L ) at the t
containment vessel reduced test pressure (P ), obtained during the i
t containment integrated leakage rate test (ILRT).
This value is to be included in reference (a).
A The value of LT for Braidwood Unit 2 is 0.07%.
Attachment A includes a marked-up Technical Specification page 3/4 6-2 with this value added.
Please address any questions concerning this matter to this office.
Very truly yours
+vP &
S. C. Hunsader Nuclear Licensing Administrator cc:
S. Sands NRC RIII Bra $dwood Resident Inspector a
3864K v
k B712100270 871201 PDR ADOCK 05000457 f
PDR i
)
1 I
1
o CONTAINMENT SYSTEMS l'
CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION
~
- 3. 6.1. 2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1)
Less than or equal to L,, 0.10% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 44.4 psig, or a
L j
2)
Less than or equal to' L, 0.0
- eight of the containment g
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 1 (kates y weight of the contain-mcnt air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Un W P, 22.2 psig.
t O. o ]
b.
A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type 8 and C tests, when pressurized to P
- a APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With either the measured overall integrated containment leakage rate exceeding 0.75 L r 0.75 L, as applicable, or the measured combined leakage rate for a
t all penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable, and the combined leakage rate for all penetrations t
subject to Type B and C tests to less than 0.60 L prior to increasing the a
Reactor Coolant System temperature above 200 F.
SURVEILLANCE REQUIREMENTS I
1 I
- 4. 6.1. 2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance w';h the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
Three Type A tests (Overall Integrated Containment Leakage Rate) a.
shall be conducted at 40 1 10 month intervals during shutdown at a pressure not less than P, 44.4 psig, r P, 22.2 psig, during
{
a t
each 10 year service period.
The third test of each set shall be I
conducted during the shutdown for the 10 year plant inservice inspection; 1
BRAIDWOOD - UNITS 1 & 2 3/4 6-2 1
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