ML20212F823
| ML20212F823 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/23/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212F828 | List: |
| References | |
| NUDOCS 9909280389 | |
| Download: ML20212F823 (1) | |
Text
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.w 4.5.4 ENGINEERED SAFEGUARDS FEATURE (ESF) SYSTEMS LEAKAGE Applicability Applies to those portions of the Decay H tat, Building Spray, and Make-Up Systems, which are required to contain post accident sump recirculation fluid, when these systems are required to be operable in accordance with Technical Specification 3.3.
I Ob_iective To maintain a low leakage rate from the ESF systems in order to prevent significant off-site i
exposures and dose consequences.
Specification 4.5,4.1-The total maximum allowable leakage into the Auxiliary Building from the applicable portions of the Decay Heat, Building Spray and Make-Up System components as measured during refueling interval tests in Specification 4.5.4.2 shall not exceed 15 gallons per hour.*
4.5.4.2 Once each refueling interval the following tests of the applicable portions of the Decay Heat Removal, Building Spray and Make-Up Systems shall be conducted j
to determine leakage:
The applicable portion of the Decay Heat Removal System that is outside a.
containment shall be leak tested with the Decay Heat pump operating, except as specified in "b" b.
Piping from the Reactor Building Sump to the Building Spray pump and Decay Heat Removal System pump suction i.mhtion valves shall be pressure tested at no less than 55 psig.
c.
The applicable portion of the Buildint Spg system that is outside containment shall be leak tested with the 13. AE..g Spray pumps operating and BS-V-1 A/B closed, except as specified in "b" above.
d.
_ The applicable portion of the Make-Up system on the suction side of the Make-Up pumps shall be leak tested with a Decay Heat pump operating and DH-V-7A/B open.
e.
The applicable portion of the Make-Up system from the Make-Up pumps to the containment boundary valves (MU-V-16A/D,18, and 20) shall be leak tested with a Make-Up pump operating.
f.
Visual inspection shall be made for leakage from components of these systems. Leakage shall be measured by collection and weighing or by another equivalent method.
- NOTE: This leak rate limit is only applicable for the Cycle 13 operating cycle.
Bases The leakage rate limit of 15 gph (measured in standard room temperature gallons) for the accident recirculation portions of the Decay Heat Removal (DHR), Building Spray (BS), and Make-Up (MU) systems is based on ensuring that potential leakage after a loss-of-coolant accident will not result in off-site dose consequences in excess of those calculated to comply with the 10 CFR 100 limits (Reference 1 and 2). The test methods prescribed in 4.5.4.2 above for the
- applicable portions of the DH, BS and MU systems ensure that the testing results account for the highest pressure within that system during the sump recirculation phase of a design basis accident.
(
References (1) UFSAR, Section 6.4.4
" Design Basis Leakage;" and, Table 6.4-3
" Leakage Quantities to tiie Auxiliary Building" (2) UFSAR, Section 14.2.2.5(d)
" Effects of Engineered Safeguards Leakage During Maximum Hypothetical Accident" 4-45 Amendment No. 47,205,2:5 Corrected by letter dated 99o9280389 990923 PDR ADOCK 0500o2e9 P
Thr:3 Mila Island Nucl:ar Station, Unit No.1 cc:
Michael Ross David J. Allard, Director
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Director, O&M, TMI Bureau of Radiation Protection l
GPU Nuclear, Inc.
Pennsylvania Department of P.O. Box 480 Environmental Resources Middletown, PA 17057 P.O. Box 2063
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Harrisburg, PA 17120 j
John ~C. Fornicola Director, Planning and Dr. Judith Johnsrud f
Regulatory Affairs -
National Energy Committee GPU Nuclear, Inc.
Sierra Club 100 Interpace Parkway 433 Orlando Avenue Parsippany, NJ 07054 State College, PA 16803 Edwin C. Fuhrer Peter W. Eselgroth, Region I Manager, TMI Regulatory Affairs U.S. Nuclear Regulatory Commission GPU Nuclear, Inc.
475 Allendale Road P.O. Box 480 King of Prussia, PA 19406 Middletown, PA 17057
- Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.
J Washington, DC 20037 Chairman Board of County Commissioners l
of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors l
of Londonderry Township i
R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident inspector (TMI-1)
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U.S. Nuclear Regulatory Commission P.O. Box 219 l
Middletown, PA 17057 Regional Administrator Region I '
U.S. Nuclear Regulatory Commission
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475 Allendale Road i
King of Prussia, PA 19406 Robert B. Borsum B&W Nuclear Technologies Suite 525 1700 Rockville Pike Rockville, MD 20852