ML19319D283
| ML19319D283 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/18/1978 |
| From: | Nelson C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130925 | |
| Download: ML19319D283 (3) | |
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Januar/ 18, 1978 l
. Docket tio. 504302 e
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,e LICENSEE:
FloridalPoder, Corporation
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FACILITY: Crystal River Unit !!o. ':
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SUIk!ECT:
.SLWELY GF MEETIl$ liELD O!! J/dUARY.11.1978..TO. DISCUSS APPLICAT1051 FOR STRETCH POWER mo m
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q A list of attendees is attaci:ed.
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PC intends td apply for authorizatica to ir. crease !!.a 11cc.scd core pouce level at CR 'i frca 2452 fSt to 2542 Pr They cesira. to effect this increase at the start cf Cycle 2 operaticns. presently ccheduled for A nuary 1979. Their current schedule is tn sutcit tha reload analy:is including @ysics and therN1-hydraulic considuations for tne stretch power level, by October i.1978.
They also mtend to address t.he four rucp coastdown and locked roter accidents, not previously analyzed at tire stretch pcver level. In their submittal.
-Babccck and Milco,t stated.that all other. accidents except the LOCA were previously analyzcd.at 2568 !@t and while this does not meet "
current requirements: to'porfom analyses at 1027, of maximum power -
. level it has been ' sufficient' for other BMI plants operating-at powers up to 2568 4Nt:and therefore should be adequate for CR-3.
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We stated that in~ previous applications ^forl stretch' p6wer all accidents have beeri analyzed at no Tess than' 102" of stretch power. Therefore, we stated that we would Atemine if this was nec5issary for CR-3
.and, within.30 days, inform fFC of our position.
' With recard to FPC's schedule.~for subc:ittal ye stressed the importance J.
of submitting their application.for stretch:powercas soon as possible
,and requested that they su': nit' updated meteorological data 6through
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1977, prior to' October T,1978.
FFC: indicated thatdhey could not,
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~ $ would subnitithe cetidata as[scon as~it has; processed.' i.
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. We informed FPC that the en'vironmental' impacts of operation at stretch power, as compared with the inpacts addressed in the Final Environcental Statement, should be analyzed and addressed. This should include any necessary changes to the Envirnmental Technical Specifications.
The finallitem discussed was' the design of'the Reactor Coolant Puap Power Monitorito be installed at CR-3 to decrease the P.cactor Protec-tion System response time fc a loss of flow accident. The CR-3 design.is identical to that used at another B&W plant except that two wattmeter ei ments, rather than one, are necessary because RCP power is monitored from cutside the reactor building. FPC intends to propose this rnHitcation M aopropriate TechnicM 'beciilcation changes by about February 13, 1970.
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ENCLOSURE LIST OF ATTENDEES E. R. Kane B&W Licensing G. R. Westafer Florida Power Corporation Q. B. DuBois Florido Power Corporation K. B. Baker Florida Pcwer Corporation J. O. Howard B&W Licensing R. B. Borsum B&W M. Stephens B&W C. E. Barksdale B&W
~ Bert Simpson Floride Power Corporation L. M. Kolonay B&W Chris Nelson NRC Sy Weiss.
NRC Joan Giannelli NRC Dred liardin NRC Elinor Adenr.ca NRC L'elt Drcioks f P.C lbnte Conner NRC e
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