ML19256A838

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Requests Approval by 790112 of Tech Spec Change to Apply Extra Conservatism on Maximum Critical Power Ratio Operating Limit to Limiting Pressure Transient Results in Ge'S Nov 1978 Report
ML19256A838
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 01/08/1979
From: Gilleland J
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
Office of Nuclear Reactor Regulation
References
TVA-BFNP-TS-115, NUDOCS 7901160221
Download: ML19256A838 (1)
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Text

F TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 500C Chestnut Street Tower II TVA BFNP TS 115

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Mr. Harold R. Denton, Director

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Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Q _k Washington, DC 20555

Dear Mr. Denton:

In the Matter of the # ) Docket No. 50-259 Tennessee Valley Authority )

In my letters to yrs of September 8, October 5, and November 30, 1978, we submitted for NRC i eview an amendment request and corrections to the amendmant request to change the technical specifications of Browns Ferry Nuclear Plant unit 1. As a result of a meeting with members of your staff on January 3,1979. TVA has concluded that an extra conser<atism on the MCPR operating limit should be applied to the limiting pressure transient results indicated in General Electric's topical report NEDO-24136, Revision 1, November 1978. This extra conservatism has been justified in the light of any nonconservatism that might exist within the REDY transient code. Therefore, enclosed are requcated changes to the Browns Ferry Nuclear Plant unit 1 tech-nical specifications which supplement the above requests. Also enclosed are changes requested by your staff concerning the recirculation pump trip modification.

In order that startup from refueling is not delayed, we would appreciate receiving approval of all the technical specification changes mentioned in this letter by January 12, 1979.

Very truly yours, h{ '- ^ ij.I

%](LL!prc'

,J. E. Gilleland Assistant Manager of Power Subscribe d sworn to before me this day of Oc7mf m11979.

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$wtth&#um-Not g Public g My Cosmission Expires 1 % 7 #,/792-

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Enclosures cc: See page 2 N0116O M An Equal Opportunity Employer

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Mr. Harold R. Denton 'Jgy 3 ;g7g cc (Enclosures):

Mr. Charles R. Christopher Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Dr. Ira L. Myers State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104

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LT .- Te:al core leng:n e 110 feet t e r . .u...

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= 12.2 feet for 8XS fuel i . = t.xial position above bottom of core If at any time during operation 1: is d et er-

=ined by nor=al surveillance that the i tn i t i n.;

valua f or LHCR is being e.<ceeded, ac t icn shall be initiated within 15 minutes to restore operation to within the prescribed li=1cs.

If the LHGR is not returned to wi:hin ene pre sc r ibed limit s wit h in' two (2) hours, the reactor shall be brough: to the Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor cperation is witnin the prescribed limits. .

K. "intnun Critical Power ,atio n (MCPE) K- Min inum Cri tica l ?nve Ra t io (MC.R)

Ihe !!CPR 0;$erating linit from the beginnin,;

c: cycle 3 to the end of cycle 3 minus 'CPR shall de determined daily 20C0 "'. d / t is 1.20 for 7X7 fuel andl.24 for during reacter pcver operatica at 8:3 and 8XSR fuel; the limit from the end of 125; rated thermal ;cwer and f ol-c.mie 3 ninus 2000 mwd /t to the leving any chen3e in power level er end of cycle 3 isl.25 for 7X7 fuel andl.30 distribution the vould cause opers fer 6X8 and 8X8R fuel. These limits apply to tjoa with a limiting control red

.cteady state power operation at rated power pat tern as described in the bases f and ' low. For cote ficvs other than rated, Specification 3.3.

tha"??R shall be greater than the above limits ti es K.,

l~g is the talue shown in Figure If'at any time during operat ien it is deter,ined by narral surveillance that

Se Ifrlting value for MCTR is being exceeded, action shall be initiated within 15 =inutes to restore operation to 1:nin the prescribed 11:1: 3. If the st'eady r, tate MCPR is not returned :o within the presc ribed limit s within two (2) hours, the re.tetor shall be brough: te the Jo;d Shutdown condition -dehin 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Surveillance and corresponding action shall continue until r e..c : c r e;'e ra t ion 13 within tha prescrib.=d Itcits. .

L. tyfg r : in g Require =ents l

If any cf the limiting 112-9 tdenti ied in

'recifleit!:ns 3.5.1, ,

or M are e.<c e e d mi c n.!

the 3recified recediai ac 1:r. is agen, :ne even: shall be loggec s1 reported in a L'.- d a .c wrd- an re;;r:.

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TABLE 4. .B (Continued) .

Function Fianctional Test Cril ibra t ion Instrument rl.c c k ,

RllR Area Cooler Fan logic Tested during N/A ' N/A functional test of instrument channels, RIIR motor atart and thermostst (RJIK area cooler fan). No other

. test required.

Core Spray Area Cooler Fan Logic Tested during logic N/A N/A system functional test of instrument channels, core spray motor start and therino-stat (core spray area cooler fan). No other test required.

Ins t rument Clannel - Tested during functional N/A N/A t$

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Core Spray Motors A or D Start test of core spray pump (refer to section 4.5.A).

Ins t rument Channel - Tested during functional N/A N/A Core Spray Motora B or C Start test of core spray pump (refer to section 4.5,A).

Inst ru:nent Cha nnel - Tested during logic N/A N/A Core Spray Loop 1 Accident system f unc t iosu l S*,nal test of core spray s y s t ets .

Instruznent Channel - Yested during logic

I(!!R S1T Initiate IAgic once/6 months N/A

  • N/A 1(l'T initiate logie ,,nce/ month N/A g '/ s RPT breaker once/ operating cycle '

N/A n/A

. OT ES Fo -: T OLE 3.2.3 (Centinued)

10. Only one trip system for each cooler fan.
11. In er.ly two of the four 4160 V shutdom boards. See nota 13.
12. In only one of the four 4160 V shutdown boards. See note 13.
13. An emergency 4160 V shutdevn board is considered a trip syste=.

14 RF.RSV pu sp would be inoperable. Refer to section 4.5.C for the require.ents of a RHRSV pump being inoperable.

15. The accident si;;nal is the satisfactory ce=ple' a of a one-out-of-tvo taken twica los;ic of the dryvell high pressure plus lov reactor pres-sure or the vessel lov vater level Q 378" above vessel zero) originating in the core spray system ttip syster..
16. The ADS circuitry is capable of accc:plishing its protective 3ction with one operable trip system, therefore ene trip systa= =ay be taken out of service for functional testing and calibration for a period not to exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

i~. TV: ??T systers exist, either of which c:11 :-ip b n,' recir: ,;s-i:n Funps. During monthly functional testing, caly one RPT syste: nay be pu: in test mede during a single time interval for testing. If b::h ?. systens a"e inoperable or if 1 FF. systen is in perable for core than 3:

ccnsecuti te iays , the ree.ctor pcVer shall be reducei :c tel:v 205 pcVer within 2h hours.

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