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i August 27, 1980
,. MD10 RAND'C: TOR: All Merbers - Reactor Operations and Nuclear Support Branch TROM: R. F. Heish=an, Chief, Reactor Operations and Nuclear Support Branch
SUBJECT:
, POSITION ON " LICENSED PO'w'ER LEVEL" The attached temorandu f ro::: Mr. E. L. Jordan to the Reactor Operations and Nuclear Support Branch Chiefs, subject as above, contains a position to be utilized by all branch personnel in situations where licensed power levels are used as a basis for detercining compliance with regulatory requitecents.
If you have questfons about this position, please discuss them with your supervisor or =e.
R. F. Heish=an, Chief Reactor Operatfons and Nuclear Support Branch En clos ure : As stated cc v/ enclosure:
J. G. Keppler 4
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2 2 ED SSINS #0200 ME.Si3RANJUM FOR: E. J. Brunner, Chief, RO&NSB, RI R.,C. Lewis, Acting Chief, RO&NSB, RII X. F. Heishman, Chief, RO&NSB, RIII G. L. Madsen, Chief, RO&NSB, RIV J. L. Crews, Chief , ROLNSB, RV FRDH: -
E. L. Jordan, Assistant Director for Technical Programs Di.'ision of Reactor Operations Inspec+ ' .rIC i
SUBJECT:
DISCUSSION OF " LICENSED POWEP. /EL" (AITS F145B0H2) th' Dating back at least to 1974, there have been many lengthy " discussions" regarding the exact meaning of " full, steady-state licensed power level" (and similarly worded power limits). We do not believe the real safety benefits that might be derived from an NRC-wide agreerrent would be worth the further expenditure of manpower in meetings, etc. that would be required to achieve a consensus.
We do realize that sore common unifort basis for enforcing raximur licensed po.er is needed by I&E inspectors. Therefore, until and unless an NRC-wide position is put fosard and agreed upon (and as stated, IEE does not propose to initiate pro:eedings to tnet end), ILE will use the following guidance.
The average power level over any eight hour shift should not exceed the " full steady-state licensed power level * (and similarly worded tercs). The exact eight hour periods defined as " shifts" are up to the plant, but should not be varied from day to day (the easiest definition is a normal shif t manned by a particular " crew"). It is permissible to briefly exceed the " full, steady-state licensed power level" by as much as 2% for as long as 15 minutes. In no case shoule 100% pc-e- be exceeded, but lesser power " excursions" for longer periods should be allo-ed, with the above as guidan:e (i.e. ,1% excess for 30 tinctes,1/2% for one hour, etc. , should be allowed). There are no limits on the number of times tnese " excursions" tay occur, or the tire intenal that must se:erate su:h "ex:ursions," except note that the above requirement regarding ine eight hour average po-er will prevent abuse o' this allowance.
CONTACT: H. W. Woods, IE 49-2E180
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The abcve is considered to be within the licensing basis and, therefore, acceptable to us, and it is also fair to the ' utilities and their ratepayers.
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.. . J rdan, Assistant Director for Te aical Programs Division of Reactor Operations Inspection Office of Inspection and Enforcement cc: R. C. DeYoung, IE
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GLEN f LLYN. ILLINotS 60137 October 2, 1980 F, k . MB l
MEMORANDUM FOR: E. L. Jordan, Assistant Director for Technical Programs, Division of Reactor Operations Inspection THRU: E shman, Chief, Reactor Operations and Nuclear upport Branch FROM: J. F. Streeter, Chief, Nuclear Support Section 1
SUBJECT:
POSSIBLE DESIGN DEFICIENCY IN LASALLE EMERGENCY DIESEL GENERATOR AIR STARTING SYSTEMS (AITS-F03110380)
During preoperationa.1 testing inspections of the emergency diesel generators at LaSalle, the inspectors identified what appears to be a design deficiency in the air starting systems. The apparent design deficiency is the inter-connection of the two redundant air starting systems via a.1/4" copper line to the governor booster (see attached sketch). The purpose of the 1/4" line is to supply air to operate a piston which injects an extra amount of fuel daring starting. The interconnection appears to violate the independence acceptance criterion described in Paragraph II.9.a of Standard Review Plan Section 9.5.6.
To determine the effect on diesel start time of a break in the 1/4" line, LaSalle performed two tests to simulate a break in that line. The line was disconnected at point A and the starting time was measured. The line was then reconnected at point A and disconnected at point B and.the starting time was measured again. A test was not run which simulated a break in the single line to the governor booster. The test results showed that the starting time was increased by 0.5 seconds due to the simulated breaks. The total time to achieve full voltage during the simulated break conditions was 10.3 seconds which exceeded the LaSalle FSAR requirement of 10 seconds or less.
We have determined that the apparent design deficiency is generic to General Motors diesels supplied by Steward and Stevenson. Other suppliers could possibly have similar piping. We do not know if all machines have the same size piping. Tae piping size will affect the magnitude of the increase in start time due co a line break.
We request an NRR position as to whether or not this matter constitutes a design deficiency for LaSalle. If NRR decides it is a design deficiency, we re-N .
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E. L. Jordan October 2, 1980 quest NRR disposition the matter with the licensee. In addition, if NRR decides it is a design deficiency, Region III will draft a bulletin to be issued for action to those plants that are required to meet the independence requirements of Paragraph II.9.a of Standard Review Plan Section 9.5.6.
L J. F. Streeter, Chief Nuclear Support Section 1
Attachment:
Sketch cc w/
Attachment:
R. L. Spessard, RIII R. D. Walker, Resident /LaSalle V F. A. Maura, RIII L. G. McGregor, RIII t
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