ML18025B560

Amend 67 to License DPR-52,removing Power Spiking Penalty from Linear Heat Generation Rate Limits for 8x8,8x8R & P8x8R Fuel Assemblies

ML18025B560
Person / Time
Site:	Browns Ferry
Issue date:	06/12/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML18025B561	List: ML18025B560 ML18025B563 ML18025B564
References
NUDOCS 8106250195
Download: ML18025B560 (10)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROMNS FERRY.NUCLEAR PLANT, UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No.

DPR-52 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated February 2Q, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulati'ons set forth in 10 CFR Chapter I; B..

The facility will operate in conformity with the application, the provisions of the Act, and the rules; and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangeri'ng the health and safety of the publi:c, and (ii}that such activities wi'll be conducted in compliance wi'th the Commission's regulations",

D.

The issuance of tfus amendment will not be inimi'cal to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is: in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly; the li,cense ie amended 4y changes. to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facil.ity License No.

DPR-52 is hereby amended to read as follows:

(2) Technical S ecifications.

The Technical Spectfi.'cations contained in Appendices; A and B, as revised through Amendment No.

67, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

This license amendment is effective as: of the date of its issuance.

FOR THE NUCLEAR REGULATORY'OMMISSION

Attachment:

Changes-to the Techni:cal Specifications Date of Issuance:

June 12, l98l Thoma.. Ippoli.to, Chief Operating Reactors Branch 82 Di'vision of,Licensing

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ATTACHMENT TO LICENSE AMENDMENT NO.

67 FACILITY OPERATING LICENSE NO.

DPR-52 DOCKET NO. 50-260 Rev ise 'Appendix A as follows:

1.

Remove the following pages and replace wi'th. identically numbered, pages:

'\\

159/16O Y

TG9ITT0 2.

The underlined pageos are. than Being changed; marginal lines on these pages indicate the revised area.

Tlie overleaf pages are provided for convenience.

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LIIIITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.li Maintenance of Filled Dischar e Pine The suction of the RCIC and HPCI pumps shall be aligned to the condensate storage

tank, and the pressure suppres-.

sion chamber head tank shall normally be aligned to serve the discharge piping of the RHR and CS pumps.

The condensate head tank may be used to serve the RHR and CS discharge piping if the PSC head tank is unavailable.

The pressure indicators on the discharge of the RHR and CS pumps shall indicate not less than ],isted below.

Pl-75-20

-48 psig Pl-75-48 48 psig

'Pl-74-51 48 psig Pl-74-65 48 psig I.

Average 'Planar Linear Heat Generation Rate During steady state power operation, the Maximum Average Planar Heat Generation Rate (iIQ'HGR) for each type of fuel as a function of average 'planar exposure shqll not exceed the limiting value shown in Tables 3.5.I-1, -2, -3, -4, and -5.

If at any time during operation it is dete mined by normal surveillance that the limiting value for APLIIGR is being exceeded, action shall be initiated within 15 minutes to res'tore operation to within the prescribed limits. If the.APLHGR is not returned to within the prescribed limi.ts within two (2) hours, the reactor shall be brought to the Cold Shutdown'ondition 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 operation is within the prescribed limits.

J.

Linear lleat Generation Rate (LHGR)

During steady state power operation, the linear heat generation rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the following limits:

4.5.H Maintenance of Filled Dischar e Pine Every month prior to the testing of the RIIRS (LPCI and.Containment Spray) and core spray system, t".,e discharge piping of these systems shall be ven'ted from the high point and water flow determined.'ollowing any period where the LPCI or core spray systems have not been required to be operable',

the dis-charge piping of the inoperable sys-tem shall be vented from the high point prior to the return,.of the system to service.

3.

Whenever the HPCI or RCIC syste= is lined up to take suction from the condensate storage tank; the dis-charge piping of the HPCI and RCIC shall be vented from the high point of the system and water flow observe on a monthly basis.

Mhen the RHRS and the CSS are re; quired to be operable, the pressure indicators which mon 'or the dis-'harge lines shall be monitored daily and the pressure recorded.

I.

Maximum Avera e Planar L near Heat Generation Rate (ifAPLIIGR)

The iIAPLIIGR for each type of fuel as a

function of average planar exposure shall be determined daily during reactor operation at ~ 25/ rated thermal power.

J.

Linear Heat Generation Rate

'(LHGR)

The LHGR as a function of core heicht for 7x7 fuel and as a constan for

Bxg, BxBR, and PBxBR fuel shall be checked daily during reactor operation at+25/ rated thermal power.

for Bv8; BxBR, and PBxBR fuel 13.4 Kw/ft; for 7x7 fuel, the maximum allowah'. LHGR as ca1culated by the following equation:

Amendment No. Q, g, pf, 67 159

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t 3.5.J

.Linear Heat Gener on Rate (LHCR)

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This specification assures that the linear heat generation. rate in any rod is less than the design linear heat generation if fuel pellet densification is postulated.

The power spike penalty specified is based on the analysis presented in Section 3.2.1 of Reference 1

as Irtodified in References 2 and 3, and assumes a linearly increasing variation in axial gaps between core bottom and top, and assures with a 95/ confidence, that no more than one fuel rod exceeds design linear heat generation rate due to poI~er spiking.

.'7he LHGR

( as a function of core height for 7x7 fuel and as a constant for 8xG.

SxSR, and P8xSR fuel)

~sh 11 'bc clsect'ud cia fly fnt reactor~

oper:stion st 25% pover to dctcrafnc ff fuel burnup, or ron-trol rod cnovuuent hss cou cd chontcs fn povcr dfstrfbutfon.,

Vor LIICR to bc s

1 I of t LnZ, value bclov 25% rated thecal Povcr

~ the R factor would have to 0 24] vhfch Ls precluded by a consfdcroble rarzfn vhen cmployfnZ any pcr~fsafblr control rod pattern.

3.5.t.

Mfe~s Crftfcsl Pover P~cfo MCPR At cor ~ the~1 paver levels less.than or equal to 25, the reactor vill be opsrstfof st nfnhun rccirculstfon palp speed and che..odcrator void content vill bs very s'il.

Fot all decimated control rod patterns vh'ch ~y be em-

,ployed at th'Ls po~~t, operatfnz plant experf~ce and ther al hydraulic anal-ysf ~ fndfcsted that thc resultfnS MCPR value fs fn exc f

e s

n excess o

r'equirwcnts by

~ considerable narSfn.

with thfs lov void content, any fnadvertent core fLov Locrc ~ sc vould only place operation in a nore conservotfve node re'lo-t fvc to MCi R rhe ds ly re;uf. event for calculs tins MCFR above 25K raced the~ ~ 1 s are very ssov vhen there povcr Ls. sufffcf est since power dfstrLbutfon shifts ar h

h hsvc oot been sfgnfffcont pcvcr or control tod chans Th Ses.

e requirement for cslculstfns

..CFR vhcn. a 1f&ti~z control rod patt i

h d

era s approac e

emures that vi 1 be kaovc follovf"s s change fn pover'r pover snape

{resardless of x ~ftude) that could placa operation at 'a ther=al if=it.

~Rr ort'a Recufrcncnts Thc LCO's ossocfstcd v'Lth nonltorfn9 the fuel rod operating conditions are rcquf red to be nct ot o)l tf"es, f.e., there ls ha sllovablc t>e fn vt'.fch thc pinot can bovfnZly exceed the linftinZ value! for dZL3!CR, LBGR, and MCFR.

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~ rcquireoent, as stated Ln Specff fest fons 3.

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CJld that Lf ct any t'"e during steady stote pover operatfcn, f': fa detemined thst 'thc lfnftfnf values for QJ'LHCR, LHCR, or MCFR are cxceec'.cd sct'on is then inf 'sted to restore operation to vithLn the prescr Lbed lfnfts.

Tnfs

~ ct Loo Ls foftfated ss oooo as normal surveillance fn fcstes th=

an cperatinZ 1~s-it bss been reached.

Each event fnvolvinZ steady state ope.stion beyond a spec'.'Lcd 1 Ir L ohs 1

be logged and re port ed quarterly.

It avst bc reccsnf =ed t}'. c

. tl.crc Ls

~ lvsys sn action vhfch vould return aov of the p ra=ctaco

(!~~MCR,

~ UICR ~ or MCpR) to vfthfn prescribed l&fts, noncly pover reduce on.

Lender nost cfrcuns tastes, tl'is v1 not be the only alternatfve.

Rr fcr.n< eo H.

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+4 1 Icos L.'est Lou Effects on Cenera I Electric Sof 1 nrl I'acc R J tot'url,"

Supplements 6,

7 ~

and 8, 'httt'.-10735, Av.Ruat 19.3 ~

5upplrncot 1 to technical Report on Densi. Lest Lena of Conceal Electric Flector Fuels, Decenber 14, 19)4

{LSA RsZulatory Staff)

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C ~af c~tfoo Y

A ~ Moore to 1

5 Mitche 1

MooffLeo CE for Pus] Dcnsif fest foe," Doc'act 50-321,

?birch 27, 1974.

Generic Reload Fuel Application, Licensing Topical

Report, NEDE-24011-P-A, and Addenda.

Amendment No. g, g> gs 67 169

II 41.