ML19308D775
| ML19308D775 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/07/1978 |
| From: | Griffin B FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19308D776 | List: |
| References | |
| NUDOCS 8003130820 | |
| Download: ML19308D775 (4) | |
Text
Co? /p W I:FOULA1 ORY If > 0Rf1AT 7 ON DI STR ? Pt I f 104 YS TFr. (hlDS)
I!ISTRILUTION FOP ItiCONINO r1ATERt Al 50-992 PEC: REI9 R H ORG. CDIFFIN D I.
DOCDATE:
O' 07/79
!!RC FL PUN Di i ! !.
RCVD' O'
10/7' DOCTYFE: LfL'1TER NOTf.RITFD YES CC&IEi ;:ECE I'/EO Sf lRFCT -
!TR 1 EACL 40
- PFCPONEC TO NRC REQUEFT OF 06/07/7.3 FURN I C!!I NG IMF0 RE DEOAY HEAT PUMP PE!.I ABILITY A T SUDJECT Fr.C ILI'i Y.
NOTARIZED 07/07P U/ATT SUMMAP'r PEET ADEPE55JNG IECEN! sHOFT FAILURE ON DECAY ME_i',T PilNP--1 A, AND INCf.UDING DRAWINGS.
1 PL ANT NNE. CRYSTA: CIVER #3 REVIEWEt: I NI T Ii-L :
- ??
DISTRIBUTOR INITIAL: %
n*44444 m M " 444 + H+ DISTRIEUTIUM OF T!!!?. MATERI AL I S AS F OLL OWS * **r'e +-*4 +-4^ * *"^'-* *
- I GENERAL DISTRILUTION FOR (:FTER ICSUANCF OF OPERAT'ING LICENEE.
( D15 TEII:UI J ON CODE AOOi )
FOR ACTION.
m r t " ci- <mut! q pccaW/7 ENCL INTERN /.L:
rFP Ft r t r.i rm --
nge ppg 4.wfguct 1
. r W.' J t-NUL OELIi*LTR ONLi NANAUER4-4 U/Ef1CL CORE PERFORhi4NCE E '*-*:U/ ENCL AT1 FOR SY:
PROJ4eu/ ENCL ENOINEERINO BR "W' ENCL REACTOR 5.AFETY PRr..W/ ENCL PLANT SYSTEMO IB'< U/E!!CL EEB**U/ ENCL EFFLUENT TREAT 'E Yi+ #>W/ ENCL J.
t1CGOUGH 4;W/ ENC!.
EXTERNfiL:
!.PDR 'O CRYSTAL RIVER, FL**l1&NCL TIC.U/FNCL NS I C* 'tlJ./CNC L ACP?
CAT B4-H/16 FNCL
=s a&4
.e
... c.4_
m 4..... -......
- 4..
- 4., 4 -,.. m....,.. - 4. m 1Hrz ENn
.... m m.. _ m 4 4...
8003180 (
O
o o
_,k^
?'~
e-
- v~
V 2
4
+,4 M
Power C O A F O 8* a T e O fe July 7, 1978 Mr. Robert W.
Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors e
U.S.
Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Crystal River Unit No. 3' Docket No. 50-302 Operating License No. DPR-72
Dear Sir:
This is in response to your letter of June 7, 1978 requesting in-formation regarding Decay Heat Pump (DHP) reliability at Crystal River Unit No. 3.
Attached for your information is a summary report which address-es the recent shaft failure on DHP-1A, some background infor-mation, as well as corrective action taken.
The following additional information is offered for completeness:
A.
Subsequent to the first DHP-1A shaft failure, several para-meters were considered to be involved in the failure mode.
These were 1) operation of the pump in a los-flow recircula-tion mode (approximately 85-100 gpm); 2) the possibility of improper heat treatment of the shaft material; and 3) the
^
design of the shaft keyway.
As a result, the shafts in both DHP-1A and IB were replaced with shafts having documented correct heat treatment, with a modified keyway design, and operating restrictions were enforced to assure that pump operation in the low-flow recirculation mode would be limited to fifteen (15) minutes of continous operation.
We still feel that these three items are contributary factors to pump shaft lifetime.
However, based on recommen-dationc from the pump supplier and manufacturer, the time restrictions for operation in the low-flow recirculation mode ha ve been modified.
Operation at low-flow is allowed for fifteen (15) hours continbously and up to eighty (80)
~
hours total within the life of the pump.
m et AAP General Office 3201 Thiny fourin sneet soutn. P O Box 14042. st Petersburg Fionda 33733 813 - 866-5151
Robert.W. Reid Page Two July 7, 1978 B.
Based'on the successful operation of similar pumps at other l-reactor facilities, the specific nature of the problem identified in the attached report which caused the recent shaft failure oc DHP-1A, and.the successful operation of DHP-1B at CR-3 (over 3,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of successful operation),
we are confident that-the current problem is limited to DHP-1A.
Therefore, the corrective actions involving modifi-cation to the impeller hub and casing on DHP-1A are not l
necessary on DHP-1B.
C.
We are confident that the improved pump shaft design in-
~
stalled in both DHP-1A and IB, the suitable low-flow oper-ating restrictions, and the corrective action defined in the attached report for solving the specific impeller-casing interference problem on DHP-1A, will result in reliable operation of the pumps.
We appreciate your consideration.
Feel free to notify us if further discussion or information is desired.
Very truly yours, FLORIDA POWER CORPORATION B.L.
Griffin Senior Vice President BLG/ECS/ emf 5/6a File: 3-0-3-a-3 0
STATE OF FLORIDA COUNTY OF PINELLAS B.L._ Griffin, Senior Vice President of Florida Power Corporation; states that he is authorized on the part of said company to sign
~
and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowl-edge, information and belief.
B.L.
Griffin l
Subscribed and sworn to before me, a Notary Public in and for the State and. County above named, this 7th day of July, 1978.
)
\\
/
r
.n
/..
'm Notary Public Notary Public, State of Florida at Large, My Commission Expires:
July 25, 1980 e
t