ML20010B737
| ML20010B737 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/10/1981 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Check P Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20010B738 | List: |
| References | |
| NUDOCS 8108170486 | |
| Download: ML20010B737 (4) | |
Text
,
go. m y
to m
6 AUG 10 8
p]n ~=._- m
!!UG 1319815 e
MEMORANDUM FOR:
Paul S. Check, Assistant Director for N
g.
l Piet Systems DSI g
g
~
i FROM:
Thomas M. Novak, Assistant Director for Operating Reactors, DL i'
SUBJECT:
EMERGENCY DIESEL GENERATOR (DG) FAILURES DURING R. G.1.108 TESTINfi AT FARLEY NUCLEAR PLANT Your attention is directed to the er. closed minutes of a meeting held in Bethesda on August 3,1981. Alabara Power Company (APCO), licensee for Farley Nuclear Plant Units No. i and No. 2, had (within less than three months) requested two emergency Technical Specification (TS) changes to i
. preclude shutdowns of both units.
In both cases one of five DG's became inoperable with water in the piston cylinders.
The TS's for Unit No. : 1ssued by the staff October 23, 1980 for fuel load and reissued in March 31, 1981 for full power implemented R. G.1.108 surveillance test requirements. A copy of the TS is enclosed. Based on test results. APC0 has experienced significant problems with the site emergency power DGs. A special APC0 Task Group was established to recommend changes to enhance the DG reliability. The report will be provided to the j
NRC staff as indicated in the conclusions section of the minutes, i.
]
At the meeting, very candid discussions were held with APC0 representatives on the best testing program to establish and maintain reliable DG power availability. It was stated by the Licensee that in their judgment, the surveillance requirements of Reg. Guide 1.108 did not improve DG reliability, but over the long haul may, in fact, be harming the machiny.
In this case, the DG is an opposed piston, Fairbanks Morse type 38D8-1/8, series OP, 2850KW, 900 RPM maching. A question can be raised as to whether all diesels regardless of their design should be tested to Reg. Guide 1.108 and -
t 4
l whether the action statement for any diesel should be set at 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The licensee has objected to including the R. G.1.108 tests that are in Unit 2 TS's into an upgraded Unit 1 TS. Both APC0 and the DG vendor are convinced that the testing as required on Unit 2 is not proper for the DG's.
i For these reasons your assistance is requested in the following areas:
4 i
i 1
.l
"'c ' >
! 5""" >
g10s170486 810810 om)
PDR ADOCK 05000 4
e
- NRC FORM 3t8 tIO 80p NRCM O240 OFFICIAL RECOliD COPY
' uwm wasa29 m.
~
2 run y
y-or o.
b w
o y
Paul S. Check 1.
Review of the R. G.1.108 testing as it has been applied to Unit 2.
Refer to enclosed Unit 2 TS. If possible, we should assure that the tests do not degrade the emergency power system over an extended period of time.
2.
Review of the participation of DG vendors in the finalization of R. G. 1.108. The Colt Industries representative stated he had not consuented on it previously. He has strong objections, as it is currently applied to Farley.
3.
Review the Standard Technical Specification (STS) allowable outage time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as plant shutdown is now required if one DG becomes inoperable.
Farley Plant has five DG's with a total of more than 17 megawatts of emergency power. The site also has five offsite power lines of which one can provide all site shutdown loads as needed.
I will be glad to meet with you to further discuss these issues at your earliest convenience.
As a final note, it is recommended that some consideration be given to the actual demands placed on DGs in the event of loss of offsite power.
Certainly, several minutes are available for an orderly startup of sy;tems to bring the plant into a stable hot shutdown condition.
I recognize t. tat in treating LOCA plus loss of offsite power severe demands are placed on DG units. In a sense licensees are placing a severe design requirement on DGs for a rather low probability event but achieve benefits in plant flexibility, etc.
Original signed by:
Thomas M. Novak Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing Enclosures :
As stated Distribution #:
Docket File cc:
D. Eisenhut ORB #1 Rdg R. Purple R. Mattson T. Murley F. Schroeder M. Ernst F. Baranowski J. 01shinski E. Reeves (2)
M. Srinivasan A. Thadani S. Israel
/
0[
j, omcch Dt.: N#1 DL:0RB#1
'""')
EReeves m., S AVa r.d.
Tpf,9,vak.
"">..af,,/81 8/ /81 8,r 0/81
- ne-m m o-
_ foImacutJt_nRcoRpropy
c-y w
w o
~.
x i
f l
t i
MEMORANDUM FOR: Paul S. Check Assistant Director for/
Plant Systems, DSI f
FROM:
Thomas M. Novak, Assistant Director' for Operating Reactors, DL
,/
SUBJECT:
EMERGENCY DIESEL GENERATOR (DG).IFAILURES DURING R. G.1.108 TESTING AT FARLEY _ UCLEAR PLANT N
/
Your attention is directed to the enclosed min 0tes of a meeting held at my request in Bethesda on August 3,1981. Alabama Power Company ( APCO),
licensee for Farley Nuclear Plant Units No. ;l and No. 2, had (within less than three months) requested two emergency. Technical Specification (TS) changes to preclude shutdowns of both units. In both cases one of five DG's became inoperable with water in the piston cylinders.
l The TS's for Unit No. 2 issued by the staff October 23, 1980 for fuel load and reissued in March 31, 1981 for full / power implemented R. G.1.108 surveillance test requirements. A copy of the TS is enclosed. Based on this TS testing APC0 has experienced significant problems with the site emergency power DG's. A special APC0 Task Group was established to recommend changes to enhance the DG reliability. The report will be provided soon to the NRC staff as indicated in the conclusions section of'the minutes.
/
At the meeting, very candid discussions were held with APC0 representatives including their Vice-President Nudlear Generation, Mr. R. P. Mcdonald, who is a former nuclear navy submarine and squadron commander. Neither he nor I could understand the reasons for two similar failures on DG 1C within such a short time. The DG is an opp 6 sed piston, Fairbanks Morse type 38D8-1/8, series OP, 2850KW, 900 RPM mac, hine.
}
The licensee has objected to/ including the R. G.1.108 tests that are in Unit 2 TS's into an upgraded Unit 1 TS. Both APC0 and the DG vendor are convinced that the testing as required on Unit 2 is not proper for the DG's.
I am not sure.
For these reasons your assistance is needed in the following areas:
j Review of the R. G.!.108 testing as it has been applied to Unit 2.
1 1.
Refer to enclosed We should assure that tests will not degrade the emerge, Unit 2 TS.
ncy power system.
am=>
4
)5"*"'>
DATEk iNRCFORM 318110 80} NR'"* O240 OFFICIAL RECOFiD COPY
- = '9M-329 824
.~.
,' 9 y
-9
_y y
ev 6.
y, e.
Y C>.
D U.
n.
. 2.
Review of the participation of DG vendors in the' finalization of R. G.1.108 The Colt Industries representative stated he had not commented on it previously. He has strong objections, as it is currently applied to Farley.
3.
Review the Standard Technical Specification (STS) allowable outage time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as plant shutdown is now required if one DG becomes inoperable. Farley Plant has five DG's with a total of more than 17 megawatts of emergency power.
'ie site' also has five offsite power lines of which one can provido cil si.te shutdown loads as needed.
I will be glad to meet with you at your earliest convenience.
Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosures:
As stated DISTRIBUTION:
DOCKET FILE ORB #1 RDG E. Reeves C. Parrish l
l t
l I
l
/
omce>
. DL..:.Q. RB # b....
.. DL:0RB#1
. DL:0R g
.suasar)
,EReeves:ms SAVarga TMNovak
.../.#'/ 81 8/ /81 8/ /81 em ).
8 nuc ronu aie no.ao uncu ono OFFlCIAL RECORD COPY
' um 'S*-32e e24
__