ML19284A417
| ML19284A417 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/21/1979 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19284A418 | List: |
| References | |
| NUDOCS 7903060380 | |
| Download: ML19284A417 (8) | |
Text
.
D 13 1
1
,J ) $
F,
, s.9 0,3 i
e
'- :J, -
JA
> )
)i*
> n,,,.,a' Florida Power a a sTe* ar oiaecro' POWER PRODUCTIOtJ con,on.<,n=
February 21, 1979 Mr. J. P. O'Reilly, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. O ' Re illy :
Enclosed please find two (2) copies of the Annual Operating Report on personnel exposure and the reactor vessel material surveillance capsules as required by CR #3 Technical Specification 6.9.1.4.
Two (2) copies of the report on the steam generator tubing inservice inspection as required by Technical Specification 4.4.5.5(b) and two (2) copies of the annual report on facility changes, tests and experiments as required by 10 CFR 50.59(b) are also enclosed for your review.
If you have any questions concerning these reports, please contact this o f fice.
Very truly yours, FLORIDA PORER CORPORATION 1
U W. P. Stewart WPS/hewT06 Enclosures cc: Director Of fice of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 (40 copies)
Director Of fice of Management Informetion and Program Control U.S. Nuclear Regulatory Commission 7903 060 23 2fC!
Washington, D.C. 20555 (2 copies)
File: 3-0-3-a-3 General Office 3201 Thirty-fourtn Street Soutn. P.O. Box 14042. St. Petersburg. Florida 33733 813 - 866-5151
6 REPORT ON PERSONNEL EXPOSURE
S'leto/FD F11(4144 td48:t I (+' 1 t t14011. MU F/&FIF h) kOFF Al.D J(I t t:lCi l(#4 iiilE Filoll lAl IllN IFf 0Al-ID M llOUllf D I Y l'IS 0.9.1.51 0 1976 8 Ol' }E F1(JNII, Oll'Oell):)
- 1UI AI. P Alci Ib tOlk & JJ EUTCIIQ4 111 A'llOJ IDFifTif E 1711L11) IfflLYtti Et t/lf M1 lOi FEFS f1 Allo Ill!Oiti$ t/Ill,lli Iti!LilIE lu.11/t1 liikki!
if AC'IOF Of E F A'llOS & 141I4illLAt1L L PAIN 1FI AtKL lif f utalL 0
0 0
0.0) 0.(0 0.03 (tilAllNt Pi tf uNil.
25 0
0 6.04
- 0. (\\.
U. (,o 11AI.1lliD)510!' ItFlO NEL 21 0
0 1,32 0.00 0.00
!O!!!VI!OFY FEI!Lt:4E t 0
0 0
0.(C 0.00
- 0. t.o IltlNIEFit( Ell 1044t L 0
0 0
0.tAJ 0.00 0.Lt f(Ul lNI P Altrif f4tCf f Alit!II. Alt! I I F1HNI L 49 21 61 13.93
- 5. })
42.6's (4 l F A'l lti E l Fluh f L 7
0 0
j.22 0.L4.
0.00 f tAL1h E H)Ll(1-I t FFONEL 7
0 13 1.74 0.(0 u.00
!UI I F/l!05 ) F F F!GUI L 7
0 9
1.59 0.30
- 6. t 4, INilNIEfalt4 t il10tNE L 0
1 9
0.07 0.45 4.4k It6f tvlO lt6f t(1]u.
S AINa f t. Art i I n tf atif'L 1
0 14 0.f4 0.03 5.40 (4 t F Allt.C Fil!ON!!.
0 0
0 0.04 0.00 0.( (
II/l.1H lii)SKE. It Flottatt.
0 0
0 0.04 0.to 0.01
!Ultivl!OFY lif!0tt.F L 0
0 1
0.03 0.00 0.29 Itd INf El Ite( l iI! UNI 1.
3 0
1 0.00 0.02 0.51 f tI C1/I, # Allfil'tJt(&
I Altr.fiMt. fil!44 NIL 25 6
9' 14.40 2.43 12f.33 (4I FAlltO lIFfGNIL 6
0 0
1.L2 0.00 0.( 0 IUL1;I iit)Sl(! If FtONIL 1
0 0
12.30 0.00 10.92 2 001 FVi!LI Y I II!(INE!.
4 0
10 1.27 0.05 I.35 IIK:ltJirRit< PEI!CINil.
2 0
15 0.35 0.00 10.03 6 AS11 If(CEESitC FAlt/lf t4/ft t 6 il!OtNt!.
3 3
4 0.95 0.23
- 1. ] t,
[if I A11NC l F l101011.
0 0
0.16 0.00 p.21 14 AL1H 114)610- 11I!util 2
0 1
0.79 0.00 4.40 10liFVlfoFY Fil<tttNtt 1
0 0
0.20 0.00 0.)?
EAf ttafbitC PtFluNFL 0
0 0
0.00 0.00 0.u1 i t F Ut Lit.C 1
1.10 u.21 0 34 vlAlttil W rJCL l'I FiONil.
4 3
0
.57 0.00 0.00 JiII A11tJC I E F!cNtJIL 1
0 0
2 /L1H E Hi!>llb 1 t F10tNIL 0
0 0
0.00 0.00 o.ov
- 05 i FVl!<M & 1 t! UNI L 1
0 0
0.25
(,. o b O 00
- fflNEFFitt PtI!Uttill.
0 0
2 0.00 0.00 1,41 KYi Al.
SlffitJeNCL I'IFILINEL 02 33 194 31.35 9.55 177.01 ttFAllt( iff!OtNFL 39 0
5 9.64 0.00 5.21
'f AL1H l'H)Sl(T 11 P!O4htL 31 0
14 16.I6 0.00 13.32 Ol'l TVi!OFY fil10tolt 13 0
20 3.33 0.43 15647 t/ int El<ltJC l'E F10tNil, 5
1 27 1.22 0.47 16.43 1AND 1UIM.
170 34 260 61.92 10.46 2 L t<. 24 Ll; AITKli>I FIl 6( Is f4 iCI AL F'Altlifl4Alft EA10!Of L I)t I AhA1ICti, it AIIIICAPIJ.
CbYSTAL blVEk UN11 43 b.sOLt LOO) EXIObult (fIH) t'UE ilit i&Ab 197b 11t IS REPOET HAS DEEN FI LPAbtD AS E1001Flo EY 10C F b 20. 40 7 ( t ) (1) (ii)
ClOUP = 1llE 101 AL PLAN 1 ( 1277 F EliSONNE L )
634 NUEDFR OF FLOPLE W1111 NO EXFOSUFt.
=
1.XPOSilbE CBt A1ER 111AN 0.001 AND 121S 'lilAN 0.099 NdMDLE 0F IiOFIE = 2L6 114 EXPO 50FE CREA1ER illAN 0.100 AND LP.sS 'lll AN 0.249 NUhDLE CF PLOPlt
=
EXPOSulE CREAThit lil A N 0.250 AND LESS illAN 0.499 NUEliLR OF FIOPI.L = 69 30 LXP OSU st E CFi.ATER illAN 0.500 AND LLSS lisAN 0.749 NUFFLh OF Pt0PLE
=
22 t XPOSUFE CbEATER 1HAN 0.750 AND LESS 4tlAN 0.999 hubbEF OF FtOPLL
=
5 's EXPOSUFt. CREA1ER 1HAN 1.000 AND LESS 4tlAN 1.999 HUMBLE OF PLOFIL
=
33 EXFOSUbE ChtA1ER 1HAN 2.000 AND LESS illAN 2.999 hDMbt.h OF PEOPLE
=
IXPOSURE CRLATER 1HAN 3.000 AND LESS ill AN. 3.999 huMDLE Of FE00LL = tl EXFOLUFE CBt.ATER 1HAN 4.000 AND LESS TillN 4.999 huimt.R OF FtOPLE = 3 1
LAFOSUFt Obf ATt.R 11 SAN 5.000 AND LESS tllAN 5.999 NUNDLE OF PLOPLE
=
0 iXFOSUFL Cbt.ATER 1HAN 6.000 AND LESS TilAN 6.999 NUObEli OF FLOPLE
=
EXFOSUFE Cbf ATER 1'! AN 7.000 AND LESS 1HAN 7.999 h0PbEP OF F10PLE
= 0 EXPOSUEE CFLA1LR THAN b.000 AND LESS 111AN 8.999 hDMUER OF ELOPLt.
0
=
EXPOSUI t; CHLA1LR lilAN 9.000 AND LESS 1HAN 9.999 NUEDLI OF FtOPLL = 0 0
1:XPOSUEE CELATER illAN 10.000 AND LESS TilAN 10.999 NUPFLI4 OF FIOPLE
=
EXI OSukE CHEATE R ill AN 11.000 AND !.FSS 111 A14 11.999 NutbEP OF FtOPa.E = 0 NUNDFR OF Pt'OPLL CEFATth 111AN ON tOUAL 10 12.000 = 0
Attachment (STS 6.9.1.5 Report) 1978 Report of Special Maintenance Exposures Special Maintenance exposures recorded during calendar year 1978 were created by an incident involving a failed burnable poison rod hold-down fixture which carried over from the reactor vessel into the "B" once through steam generator and damaged the upper tube ends. The exposure was received during burnable poison rod retrieval, and the steam generator damage evaluation and repair ef fort.
REPORT ON REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULES
STANDARD ANNUAL, REPORT ON REACTOR VESSEL ttATI: RIAL SURVEILLANCF, CAPSULES AS REQUIRED BY STS 6.9.1.5(b)
Reporting Period March 1, 1978, to December 31, 1979 Capsules Currently Installed Ifolder Capsules Closure Assembly Tube Installed (1)
Installed WZ T-CR3-L1 27-113-2007-60-6 B-CR3-L2 ZY T-CR3-C 27-113-2007-60-3 B-CR3-A YZ T-0CII-A 27-113-2007-60-2 B-0CI-A YX T-0CII-E 27-113-2007-60-1 B-0CIII-D XW T-CR3-E 27-113-2007-60-5 B-CR3-D WX T-0CIII-B 27-113-2007-60-4 B-CR3-F Insertions / Withdrawals D,uring Report Period Insertions:
T-CR 3-L1, B-CR 3-L2, T-CR3-C, B-CR3-A, T-0C II-A, B-0C I-A, T-0CII-E,
B-0CIII-D, T-CR3-E, T-0CIII-B, B-CR3-F Withdrawals:
T-CR3-B Ownership of Capsules Florida Power Corporation:
T-CR3-L1, B-CR3-L2, T-CR3-C, B-CR3-A, T-CR3-E, T-CR3-D, T-CR3-F Duke Power Corporation:
T-0CIII-A, B-0Cl-A, T-0CII-A, T-0CII-E, B-0CLII-D, T-0CIII-B Irradiation Location See lloider Tube listing Note:
(1) T= top B= bottom
REPORT ON STEAM GENERATOR INSERVICE INSPECTION
.