ML19339D040
| ML19339D040 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/05/1981 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8102170102 | |
| Download: ML19339D040 (13) | |
Text
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- Jtbima PowIr Compiny 600 Norin 18th street Post Offics Box 2641 Birmingham. Alabama 35291 Telephone 205 250-1000 m
F. L CLAYTON. JR.
Senior vice President Alabama Power the southem electrc system February 5, 1981 Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Connission Washington, D. C.
20555 Attention: Mr. A. Schwencer Gentlemen:
JOSEPH fl. FARLEY NUCLEAR PLANT - UNIT 2 CHANGE TO OPERATING LICENSE N0. flPF-8 TO PERFORM THE AUGMENTED LOW POWER STARTUP TEST PROGRAM Based on discussions with NRC Staff personnel on February 4, 1981, additional information was requested with regard to the issues requiring resolution prior to issuance of the subject license change. Alabama r
Power Company submits the enclosed positions on each of these issues.
These positions have been discussed with the NRC Staff and are considered by Alabama Power Company to satisfy the Staff's questions.
If you have any questions, please advise.
Yours very truly, A
F. L. Clayton, Jr/
FLC/BDM:de cc: Mr. R. A. Thomas
!!r. G. F. Trowbridge Mr. L. L. Kintner Mr. W. H. Bradford OO/
5 i /
4 mee 8102170 4 w
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3 I.A.l.1 SHIFT TECHflICAL ADVISOR 6-D P D
- D h 3
o1 b3 Previcus Response An individual on shift has been designated for Unit I to serve as Shift
'~-
. Technical Advisor (STA) during emergency conditions since January 1,1980.
An STA will be av'ilable for Unit 2 whenever the unit is in tiode 4 or above.
The STA's have received additional training as stated in APCo letters dated June 20 and August 1,1980.
By letters to the NRC dated June 20, 1980, August 1,1980 and August 14, 1980 for Unit 2 and October 24, 1979, November 21, 1979, December 31, 1979, and March 14, 1980 for Unit 1, ',
Alabama Power Company has previously submitted commitments and documented f '
action taken related to.STA for the Farley Nuclear Plant.
_ Clarification Response
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A.
Shif t Technical Advisor Training Program - Short Term 1.
Training Prior to January 1,1981, Alabama Power Ccmpany shift technical advisors met the requirements listed below as specified in Enclosure 2 of NRC letter dated September 13, 1979, which was referenced by the October 30, 1979 letter, e
a.
General technical education equivalent to about 60 semester i
hours at the college level in basic subjects of engineering
.T-and science.
Desirable basic subjects include mathematics, chemistry, metallurgy, reactor physics, heat transfer fluid flow, thermodynamics and electricity.
b.
Reactor operator training in the design function, arrangement and operation of plant systems including the capabilities of instrumentation and controls in the control room.
~
c.
Transient and accident response training as an aid in accident.
assessment and diagnostics, recognition of multiple failures of inadequate core cooling.
2.
Specifically, the above training and qualification have been completed as follows:
a.
Each candidate completed a four week STA training course coverir.g the following subjects; chemistry, metallurgy, reactor physics, heat transfer, fluid flow, thermodynamics, instrumentation and controls and transient and accident response.
b.
Selecting candidates with a minimum college level training
~
equivalent to about 60 semester hcurs in basic subjects of engineering and science.
fs 6
b.
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Each candidate completed simulator training covering:
- 1) Control board familiarization.
ii) Transient demonstrations.
iii)
Instrument failure response.
iv) Accident diagnostics.
The transient and accident response training enhances the ability for prompt recognition of major accident transients and bases for appropriate emergency actions. -The training included observation of actual abnormal and accident conditions in the following areas:
- flatural circulation
- Subcooling
- Inadequate core cooling
- liajor reactivity transients instrument failures
- Small and large loss of coolant accidents
- ATWS
- Steam generator secondary breaks
- Small and multiple equipment failures
- PORV operation and failures
- Loss of all feedwater d.
Candidates completed training on the design, function, arrangement and operation of plant systems in one of the following ways:
i) Completion of a six-week systems training course, ii) Completion of an individually tailored self-study program including instructor assistance and periodic examinations.
This form of training is used for experienced personnel only.
iii) Completion of f(RC license training.
e.
Section 0 describes the detail training received by the shift technical advisors.
i. A.l.1 (continued) 2a 3.
Retraining Shift technical advisors will attend licensed requalification training and annual simulator retraining to maintain their level of proficiency.
B.
Shift Technical Advisor Training Program - Long Term 1.
Qualification Alabama Power Company will select ~ personnel for the STA position that have one year nuclear power plant experience, of which at least two months must be at an operating plant and six months at the plant where the position is to be filled. Additionally, the STA must have a degree in an engineering or scientific discipline or 60 semester hours of college level training in basic subjects in engineering and sciences as described in A.2.b above. The basis for applying college credit to SRO and STA training is outlined in Attachment 1.
2.
Selection Alabama Power Company will continue to select personnel for the STA position based on their education training, experience and interest.
3.
Training
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Completion of training as described in D below which includes:
a.
Classroom lectures.
b.
On-the-job training.
c.
Simulator training.
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FARLEY IWCLEAR PLANT E
SYSTEMS TRAINING PROGRAM M
5%
&*8 Reactor Coolant System Main and Reheat Steam k
Chemical and Volume Control System Condensato System g-h Boric Acid System Main Feedwater System Residual Heat Removal System Main Generator and Auxiliaries Containment Structure & Isolation Liquid Waste System Y
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g n%
Containment Spray System Maste Gas System Emergency Core Cooling System Containment Ventilation Systems men:
Post LOCA Ventilation System Auxiliary Building Ventilation System ji?
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Component Cooling Water System Control Room Vent.ilation System pf as.
. Auxiliary Feedwater System Turbine Building Ventilation System M
Jih 4160 Volt A.C. Distribution Penetration Room Ventilation System g
_.600 Volt A.C. Distribution Spent' Fuel Pool Ventilation System lffs w.
---120 Volt A.C. Distribution Compressed Air System m
-y$
125/250 Volt D.C. Distribution Auxiliary Boiler x
ar Diesel Generators and Auxiliaries Spent Fuel Pool Cooling System jffl w.
Diesel Generator Sequencers Plant Hot Water Heating System Mm m :na g
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.!fia BASIS FOR ' COLLEGE ' CREDIT AUnRDED k'
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SRO 'Trainirig *Pfogram W
u The Farley Nuc1 car Plant SRO Training. program has been
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!E:E reviewed and accredited by Troy State University, Troy, Alabama.
g The course work accreditation is equivalent to 27 semester hours g
in the nuclear science field.
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STA Training Program M
Ti The 4 week' STA Training program was developed and presented K
under the direction of Dr. R. S. Rudland of the Westinghouse R
Nuclear Training Center Staff and was presented as college level training to augment the Parley Nuclear Plant SRO Training program and/or other college training.
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/1/81 REQUIREMENT CANDIDATEf5 B.S.N.E.
Univ.
Type of Degree s
1.
General Technical Training I.
General Technical Equivalent to about 60
[.$
Semester Hours.
Credit assigned for SS Desirable Areas:
general technical training as follows-College STA SRO 3*
College 103 g
A.
Mathematics 36 B.
Chemistry 6
1.3 5.2
~STA 4.8 C.
Metallurgy 6
.8 SRO 43.0' M
kN TOTAq m 8 D.
Reactor Physics 9
.52 3e E.
Heat Transfer 6
.67 2
(Equivalent Sem. Hrs.
yD
- g_
F.
Fluid Flow 3
.67 2
gq m
C.
Thermodynamics 3
.8 1.5
[] D M
D n
j g
H.
Electricity 12 6.0
- a 15*
. ids.
5.3 I.
Other Sciences 22 g
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and Nuclear Eg::
E Technology g.
rm.
il.
Reactor Operations Training 11.
Reactor Operations-Gil Training A.
Design 2
FNP SRO Training Program (6 mch B.
Function h%
C.
Arrangement r.u D.
Operation M
$5s E.
Control Room I/C 1er l
Fi f
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Transient & Accident III.
Transient & Accident el Recponse Training Response Training g.(
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STA Training Program (4 wks)
$i A.
Accident Assessment
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B.
Accident Diagnostic SRO Training Program (2 wks) M STA Simulator Training (16 hr@(T C.
Multiple Failure
- 35 D.
Inadequate Core Cooling
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- Accredited by Troy State University I7 15 Contact Hours Equal 1 Sem. lir.
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Ceneral Sciec B.S.
E CAHDIDATE 14
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Type of Degree Troy State U A h_
3/81 REQUIREMENT
-ET I.
General Technical Training I.
General Technical c+
- @'O Equivalent to about 60 Credit assigned for I
Semester Hours.
general technical 35E Desirable Arcas:
tr ining as follows:
College STA SRO,USN college 39
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3*
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[A.
Mathematics 18
- ' (at 3
~STA 4.8 6
1.3 S.3 D.
Chemistry SRO 43.0-
.8 C.
Metallurgy USN
' '6. 0
.5 3*
D.
Reactor Physics g$
TOTAE 92.8
~
.6s 2
E.
Heat Transfer (Equivalent Sem. Mrs.)'
%m
.67 2
F.
Fluid Flow
- g1
.8 1.5 C.
Thermodynamics M
O hy0 pD 55E 6.0*
6 H.
Electricity 5.3
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A
) S. 0*
1.
Other Sciences 15 and Nuclear g.
m Technology 11.
Reactor Operations.
M 11.
Reactor Operations Training Training
. _ -g q
A.
Design FNP SRO Training Program (6 m:
B.
Function C.
Arrangement
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D.
Operation g
E.
Control Room I/C
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Transient S Accident
.I I.
Tranulent & Accident Response Training g
Response Training M
A.
Accident Assessment STA Training Program (4 wks') fy*.5
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.F3 B.
Accident Diagnostic SRO Training Program (2 wks) g Fr%
C.
Multiple Failure STA Simulator Training (16 hrE
- wgg, D.
Inadequate Core Cooling mN T
+Candidn'te will graduate Spring Qtr. 1981
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- Accredited by Troy State University
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15 Contact Hours Equal 1 Sem. Mr.
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.B.A.S. Nuclea k
/1/81 REQUIREMENT CANDIDATEJ3 mS42"c"F""8G T
Type of Degree Troy State U.I3 y
I.
General Technical Training 1.
General Technical g'
Equivalent to about 60
.2 Semester Itours.
Credit assigned for'-
Desirable Areas:
general technical
, $E training as follows:
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College-26 y
.A.
Mathematics 12 II.
Chemistry l'. 3 5.3
~STA
'4. 8 lEE x
t m
. ($
.8 SRO 43.0 C.
Metallurgy w
.53 3*
USN' 6
Q D.
Renctor Physics
'_,-Wh
.67 2
TOTE 7_.79.8 -
E.
Ileat Transfer
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P.
Fluid Flow
.67 2
(Equivalent Sem. Hrs.
(!I G.
Thermodynamics
.8 1.5 N
D h
n H.
Electricity 6.0*
6 hD 5.3 G
T and Nuclear J
i-1.
Other Sciences 14 15*
wt CL Technology h
3 II.
Reactor Operat. ions Training II.
Reactor Operations.
Training y
A.
Design n
FNP SRO Training Program (6 mt$
B.
Function g.
w.
C.
Arrangement g
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Operation
.re P..
Control Rooct 1/C
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- 11.
Tratisient & Accident 111.
Transient & Accident M
Response Training Response Training g
da A.
Accident Assessment STA Training Program (4 wks) $
SRO Training -Program (2 wks). W B.
Accident Diagnostic d
is C.
Hultiple Failure STA Simulator Training (16 'brt$
D.
Inndequate Core Cooling T
M.
- Accredited by Troy State University Eli 15 Contact Hours Equal 1 Sem..Hr.
s:
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-3 (1/81 REQUIRl'MBUT CANDIDATEf2 B.S.M.E.
Type of Degre,eUniv. of Ala..
1
,2.
M General Technical Training I.
General Technical 1
Equivalent to about. 60 Semester Hours.
Credit assigned for
.tg Desirable Areas:
general technical training ac follows: - N Co11cge STA
- College, 75 A.
Mathematics 27 11.
Chemistry 6
1.3
'STA
~4. 8
[$
C.
Metallurgy 3
.8 SRO D.
Reactor Physica 3
.53 TOTAL 79.8 i$$!
4 E.
Heat Transfer 6
.67 (Equivalent Sem. Hrs. SW c'n-F.
Fluid Flow 6,
.67 0
G.
Thermodynamics 6
.8 g
0g
.a U
H.
Electricit.y 15 j//
p S'
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Ot.her Sciences 3
T and Nuclear E
. #5 Technology
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II.
Reactor Operations Training II.
Reactor Operations Training A.
Design M.
I FNP Systems Training Program-B.
Function (6 wks - in progress) flote: An outline of the system M
C.
Arrangement training course'is provided in g.
D.
Operation D
E.
Control Room I/C 11.
Transient & Accident III.
Transient & Accident y
Response Training Response Training A.
Accident Assessment STA Training Program (4 wks)' [$
Ei%
B.
Accident Diagnostic STA Simulator Training (16 hr $
n+
N:s Fi C.
Multiple Failure Aw D.
Inadequate Core Cooling R
D 2-E P,*G 15 contact Hours Equal 1 Sem. Itr.
rg-bhl-Im:.:
$5
f.wp -A%14%sw=f,M~ X.~__.T_'.Ta6MMMEEG _ic=atd.el :4:(u,2=+'MT
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' D.
Detail Shift Technical Advisor Training
'N
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CANpIDATE 11 g
/1/81,ItEQUIREMENT Type of Degre(B.S.N.E. Gn. Tar M
&;r
- k.. General' Technical Training 1.
General Technical t.
e Equivalent to about 60 m
Semester Hours.
Credit ass $gned for.'-
M Desirable Areas:
general t.cchnical E
I" "U "" '
College SR6 :STA.
A.
!!athematics 52 3*
College.145 q
B.
Cliemistry 10 5.3 1.3
'STA 4.8 lp E
t E_.
't,3
.8 SR0 43l0 C.
tietallurgy 4
$._w D.
Reactor Physics 6%
3*
.53 TOTAL 132.8 sW s
-s t.
Heat Transfer 6
2
.67 (Equivalent Sem. Hrs. E E
P.
Fluid Flow 6
2
.67
?N G.
Therinodynamics 6
1.5
.67 0A
~
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()
D, D
a;:g 11.
Electricity 8
6.0*
.8 t
5.3 6
I.
Other Sciences 47 15:0*
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and Nuclear
((
Technology
. g Lkit 11.
Reactor Operations Training II.
Reactor Operations g
Training g
A.
Design FNP SP.O Training Program ki (6 mos. E B.
Function
.w g
C.
Arrangement S
w l
D.
Operot'. ion m
B.
Contiol Room 1/C t
s w.-
,g
' 11.
Transient: fr Accident Ill.
Transient. & Accident.
re Response Training ItesponseTraining.~~',rh]t d
STA Training Program.
W@
A.
Accident Assessment s
(4 wks)
SRO Training Program
~ p$
B.
Accident Diagnostic (2 wks) t STA Simulator Training n C.
14ultiple Failure (16 hrs)
Ti I
m 5:
D.
Inadequate Core Cooling' W
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- Accredited by Troy State University 5b.
15 Contnet ilours Equals 1 Sem. Hr.
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17 I.C.6 GUIDAtlCE Otl PROCEDURES FOR VERIFYIllG' CORRECT PERFORPRICE OF OPERATIfiG ACTIVITIES Previous Resconse J
This item was formally issued as a part of f UREG 0737, therefore there has been no previous. response.
~
Clarification' Resacnse
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Since the Farley fluclear Plant was placed in service, Alabama Pcwer
.i Company as a matter of good operating practice, has had policies and
.f;)
procedures to insure that the operational status of power plant equipment was controlled by shift supervision, plant operators were informed of the
'g eqcipment's status, and that positive means were employed to insure equipment.
~'
would perfom its intended function when being returned to service.
~'
Shortly after the accident at TMI-2, Alabama Power Compc y strengthened its policies and procedures to require an independeht verification be performed when returning to service equipment important to safety.I This policy also included independent verification following refueling or major.
maintenance cutages.
Specifically, these current procedures include the
.following:
Authority to reiease equipment important to safety
~
for maintenance on surveillance testing or return to service is delegated to the on-shift SRO with the stipulation that the shift supervisor be' kept fully
~
c-informed of such status.
~
2
'l
' Plant operators (control room work location) are
, required to log the removal and return to service 1;
J
- of equipment important to safety.
~
5
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Upon return to service of equipment important to safety, a fomal verification of the lineup is
' conducted. The lineup and the verification are performed by individuals qualified on the equipreent or system. The lineup and verificationincludes valves, switches, and breakers as appropriate.
At this time, Alabama Power Company does not feel that independent verification when ' removing equipment important to safety from service is
~
justified in all cases.
In most cases, the removal of equipment from service is verified from the control room as part of routine shift operation.'
As equipment important to safety is removed from service, alarms are received, meter readings change, status lights change, and/or various light.
indications change.
For removal of equipment important to safety, the shift supervisor is directed by procedure to predetermine whether such indications will give adequate indication of resultant system status and if they will not, he directs a properly qualified individual to verify the resultant lineup. '-
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' I.C.6(Continued) co w
I Equipment important to safety)is defined as the reactor coolant system (pressure boundary components and associated pressurizer and pressure relief system, the residual heat removal system, engineered safety features systems, engineered safety features electric power' systems, and cooling water systems necessary to operate the above systems.
Authority to release equipment important.to safety for maintenance' or surveillance testing or to return equipment important to safety to service is delegated to the on-shift SR0 with the stipulation that the shift-supervisor be kept fully informed of such status. This release or return on the document for controlling the work (y and notification is documentedwork r to service of equipment important to safet Plant operators (control room work location) are required to log'the removal and return to service of equipment important to safety in, the plant operators' log.
Upon return to service of equipment important to safety', a' formal' verification of the. lineup is conducted. The line0p and the verification are performed by individuals qualified on the equipment or system. The lineup and verification include valves, switches, and breakers as appropriate. This verificat.'on is documented on the work request, work authorization or procedure as appropriate.
Farley Nuclear Plant verifi~ cation policies fo'r equipment important to safety include an independent verification by a second person qualified on the system.
7 Alabama power has already implemented procedures for equipment status
'3 verification upon return to service. The verification. procedures for
.;5 equipment removal 'will be implemented prior to issuance of a full pow'er
- - -operating license.-
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