ML20080E876
| ML20080E876 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Brunswick |
| Issue date: | 11/23/1976 |
| From: | Cantrell F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20079D981 | List: |
| References | |
| FOIA-83-728, RTR-NUREG-75-067, RTR-NUREG-75-67 NUDOCS 8402100187 | |
| Download: ML20080E876 (1) | |
Text
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~J UNITED STATES
' '4 NUCLEAR REGULATORY COMMISSION o
j REGloN 11 f
230 PE ACHTR EE STREET. N. W. SulTE SIS ATL AL f A. GEORGI A 00303 November 23, 1976 i
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F. J. Long, Chief, Reactor Operations and Nue? ear Support Branch, IE:II THRU:
H.'C. Dance, Chief, Reactor Projects Section No. 1, Reactor Operations and Nuclear Support Branch, IE;II MAXIMUM' PRIMARY SYSTEM LEAK RATE
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The current Technical Specifications for Brunswick limit unidentified j
leakage to 5 GPM (TS 3.6 C).
The GE Standard Tech Specs (STS) and the Proposed Standard Tech Specs for Brunswick limit the unidentified leakage to "5 GPM Unidentified Leakage Averaged Over a 2h Hour Period." Based on the wording in the STS, the leakage rate could suddenly increase from some steady low value,ie.2 GPM to 50 GPM the last hour without a require-ment to initiate a shutdown (2 GPM for 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> and 50 GPM for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is k GPM averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
This does not appear to be compatible with i
the FSAR which states that 50 GP'4 h" been calculated as the minimum leakage from a crack large enough to propagate rapidly. "The unidentified
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leakage rate limit is established at 5 GPM which is far enough below the 50 GPM leakage rate ho allow time for corrective action.
(Geet. h.10 3 2)
Further, DUREG 75/067, Technical Report Investigation and Evaluation of j
Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactor Jlants, October 1975, Section G, Recommendations, Paragraph 2 b.' Leak Detection Systems states " Plant shutdown should be initiated ~ for inspection and corrective a2 tion when the leakage system indicates, within a period of four (.4) hours or less, an increase in the rate of unidentified leakage in excess of two (.2) gallons per minute or when the total unidentified leakage attains a rate of five (.5)' gallons 'per minute, l
vhickever occurs first."
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It is reccamended that thid.' inconsistency be referred to NRR for resolution.
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F.:S. Cantrell l
Reactor Inspector i
8402100187 831230 k
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MADDENS 3-728 PDR.
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