ML19269C721

LER 79-006/01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised

ML19269C721
Person / Time
Site:	Crystal River
Issue date:	02/06/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19269C718	List: ML19269C717 ML19269C721
References
LER-79-006-01T, LER-79-6-1T, NUDOCS 7902120125
Download: ML19269C721 (2)

Text

.. . - - - . .

/

NaC FCRM ',64 U. S. NUCLEAR REGULATO R Y CC'.t'Al*JCN

+ <7 rn LICENSEE EVENT REPORT EXHIBIT A I

l Contact sLcCie l l l l l 1 mte A$s paint ca tvet ALL accuinto iNeoauaricw i .l@

o i [Fl Ll q R) Pj3Jgl0 10l-l01 0l 0 l 0l0 l -l0 ; O ;gg 4 ; Lic4%54 19 1g l ; 1 gl ,_ ==f Tvet A 67 l_jg34

! 7 . 9 LICtsset C;Cg to M lac &%it % ve64 il 26 CCN'T i 30i 2 glo1 21 Ol1I 719 l@l 012l 0l2l7I 91 @

o ' .C LLJ@l Oi s! DOCOis E10 i

' T w'.s g a 3. 49 tvtNTCATI 74 't mE*04f; ATE 4.

S 63 6l .

EVENT DESCAWTION ANO PRCS ASLE CONSEcutNCES h o 2 IAs a result of Florida Power's review of the Cveln Tun Roln,d Ronnrt- fe J has been determined'that the present Technical Specification 5.7, figure 4 ,

ITTT1 fi or transient limits on Rapid Depressurizations. and hich oressure iniectici o , , tests are in disagreement with that report. Re-tabulated figures are basedt o . lon " State of the Art." No effect noon health and safety of the nublic I

, as the revised figures have not been exceeded in either case. No previous ;

llDJ ' occurrences, ..

i

'E[' "[o'c'e' sLs's$5s covecNENT Ccos su'aEc*cs s$Ne a i, 1 xl xi@ L,,xJ@ aLzJ@ lo7 I zl z I z l zl z 18 LJJ@

. ,o i. o L1)

o @

SEQttNflat OCCgnagNc3 agpogy mg.it:0N g e no SENT vtan m EPC A T NO. C00E fvet No

@ s(jg' 17 l 9 I a

[,- ,-j l o I ol 6 I [f, _j lo !11 LIJ l2 ,.-J Lo.J ai n u 2  ;. , n n u u T 4 'a O ON 8L %f T wou*s 5S i PCs 9 Sup*L E MAN 84 mEm Lx_j@LxJ@ l2J@ L2JO I ol o I of of 37 l.r_J@

el L.N_j@ W@ l z i 9l9 l 9l@

42 eJ aa 47 3J ;4 31 34 4W CAuSE cfSCRIPTION AND CCAREC n%i ACTIONS

, , ;As a result of " State of the rt" calculations and data, revised limit  ;

i i [ figures for Rapid Depressurization and hieh oressure injec*fon en=re %"a 1 emerged. Those areas affected in Tech. Spec's will be revised and submitted to licensing for approval.  ;

I 1

u, ,,L,,,j , , so

's'r'aTs"  % . wn. er-in t rarvs @ oisE:iS v'  : se vaav :ssc=.ar N @

W @ l Of7 l6l@l NA l [D_,j@l D Encineerine evaluation I a[f'u fv CC%? TNT Locat.0% 08 mELigt a g t g as g s agLtast AMUNT Os a: Tis sTV i a

[ z.J NA l l u I

, . , L,,zj@l ,, io PimlON%

s ,,,, =ri:. .r.oN 1 0 ;u.5.. EL Es*0scell0l@[zj@l i 7  ; NA l

' ' ' ..s:s,..'J.m'ii. " '*

Nuv,i. =is..v,e%@

u i i T 1, I, o I oI nl@l.:

, i.

.o

-a,c : ,:ff;;,q,,o ic~e- @

w L,z!@l I

"- vc -

e ..,Slj@i;;;..

[. l ... s @ NA f fII!IIiiII II l

, . , 3 4. .. ..

sa... C. ,.E, An a J. r - o- ,-es, (904) 795-6436 (SEE TTACHED SUPPLEMENTARY INFORMATION S'dEZT)

Lnggg . ._ .

SUPPLEMENTARY INFORMATION Report No.: 50-302/79-006/0lT-0 Facility: Crystal River Unit #3 Report Date: 2 February 1979 Occurrence Date: 1 February 1979 Identification of Occurrence:

Revised component cyclic or Transient Limits based on " State of the Art" data and reported under Technical Specification 6.9.1.8.h.

Conditions Prior to Occurrence:

Mode 1 power operation (76%?

Description of Occurrence:

As a result of Florida Power's review of the Cycle Two Reload Report, submitted b; B&W, it was determined that items 11 and 15 in Table 5.7-1 of Technical Specification 5.7 were in disagreement with the report figures. Item 11, Rapid Depressurizations, according to the Report should now read 40 and the number of test transients for the high pressure injection test, should also read 40. This information was discussed with NRC Region II and per their request is being reported under Technical Specification 6.9.1.8.h.Through communication with B&W it has been determined that the 80 Rapid Depressurizations (item 11) presently addressed in the Technical Specification was based on the initial Reactor Coolant Stress Analysis and is valid. As a result of the " State of the Art" this figure has now been re-tabulated. Similarly, the new figures for test transients, involving the high pressure injection test, were derived.

Analysis of Occurrence:

There is no hazard to the health and safety of the plant or general pub-lic. The number of transients in both cases have not exceeded the revised figures as submitted by B&W.

Corrective Action:

Those areas affected within the Technical Specification will be sub-mitted as a Technical Speciffaation change to NRC licensing for ap-proval. ,

Failure Data:

No previous occurrences.

/rc