ML18022A428
| ML18022A428 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/16/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-340, NUDOCS 8609230089 | |
| Download: ML18022A428 (7) | |
Text
RE('ULA,Y INFORMATION'ISTRIBUTIC.
SYSTEM (R IDS)
ACCESSION NBR: 8609230089 DOC. DATE: 86/09/16 NOTARIZED:
NO DOCKET FACIL:50-400 Shearon Harv is Nucleav Power Plant>
Unit i. Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ZIMMERMAN>S. R.
Cav olina Powev Zc Light Co.
RECIP. NAME RECIPIENT AFFILIATION DENTON> H. R.
Office of Nuclear Reactor Regulation.
Div ectov'post 851125
SUBJECT:
Forwards dv aft v evised FSAR Page
- 13. 2. 1-8> v'eflecting v eactov opev'atov'~
senioveactor operatov'uties 5 tv'aining to include initiation> maint 0 recovery fv'om natuv'al ci v'culat ion on plant simulator.
DISTRIBUTION CODE:
BOOID COPIES RECEIVED: LTR J.
ENCL J SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR *mdts Zc Related Cov respondence NOTES: Application for pev mit v enewal filed.
05000400 RECIPIENT ID CODE/NAME PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB INTERNAL: ADM/LFMB XE FILE IE/DGAVT/GAB 21 NRR PWR-B ADTS NRR/DHFT/MTB R('N2 EXTERNAL: BNL(AMDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
1 1
1 0
1 1
1 0
1 3
3 1
1 1
1 RECIPIENT ID CODE/NAME PWR-* EICSB PWR-A PD2 LA BUCKLEY> B 01 PWR-A RSB ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTS NRR OE. M. L FIL 04 I/MIB DMB/DSS (AMDTS)
NRC PDR 02, PNL ('RUEL> R COP IES LTTR ENCL 2
2 1
1 2
1 1
0 1
1 Q
1 0
1 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 30 ENCL 25
I
'I J
't I
C J
9<<, g, 4
$ f y
H 1
d
SNK Carolina Power 8i Light Company
'SEP 1 6 198e SERIAL: NLS-86-3((0 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 - DOCKET NO.50-000 NATURALCIRCULATIONTRAINING
REFERENCE:
Letter dated October 23, 1981 from Mr. H. R. Denton (NRC) to Mr. E. P. Rahe (Westinghouse).
Dear Mr. Denton:
Carolina Power R Light Company hereby submits a draft copy of a revision to the Shearon Harris Nuclear Power Plant Final Safety Analysis Report (FSAR). The attached change to Section 13.2.1.1.2 reflects that Reactor Operators (RO) and Senior Reactor Operators (SRO) who perform RO and SRO duties shall be required to participate in the initiation, maintenance, and recovery from Natural Circulation on the Plant Simulator.
This is in accordance with the Westinghouse Special Low Power Test Program approved by the NRC via the reference letter.
This revision willbe formally incorporated into the FSAR via a post-fuel load amendment.
If you have any questions, please contact me at (919) 836-6202.
Yours very truly, GB/vaw
(((0803DK)
Attachment cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
S.. Zim erman ager Nuclear Licensing Section Sb09230089 BbOtttlb PDR ADOCK 05000400 V
PDR Q
<>o 411 Fayettevitte Street o P. O. Box 1551 o Raleigh. N. C. 27602
SHNPP FSAR Ayo 6)
Review of Industry Events 7)
Review of plant and procedure changes since initial training j)
Other Cold License Training Required - Cold License Candidates will receive training in the following areas:
1)
Fire Brigade Team Training (Selected personnel as determined by the Senior Specialist Fire Protection) 2)
Emergency Plan Training 3)
Securi.ty Training 4)
'anagement Training for Licensed Supervisors (for personnel
'equiring SRO Licenses) a)
Leadership b)
Interpersonnel Communication c)
Command Responsibility d)
Motivation of Personnel e)
Problem and Decision Analysis f)
Administr'ation Requirements g)
Aberrant Behavior Training 5)
Specific Plant Experience 6)
Fuel Handling Operations Training g
ac 1
26 13.2.1.1.3 Shift Engineer (Shift Technical Advisor) Training Shift Engineers will be provided with training in the following areas, as a
minimum.')
2) 3)
4)')
6)
Duties and responsibilities of the Shift Engineer Plant design and layout Accidents analyzed in this FSAR and their consequences Thermodynamics and fluid flow Integrated plant response Capabilities and limitations of plant instruments and controls 13.2.1-8 Amendment No.
26
g)
) ~oi~i~ cN5pec~o.( LomP~ev lc-+~g ~cW(irene~
FgCEC~ Q~"am (RO) c>P S~LQR R~CAo&~C. (SRO) uhc yavke~w P>Q ~ S6O du+~ ~Ko.(( ~c+c ~~M r
im ( hc+ow ~cu~~cvnce ce&C~ UBzcouev'g~~
/AGhu~l Greco.(~+a~ Q~ -5w p(~+ Ki~vdo~e.
Vev i Scj~c ~uL Qcc.cph~ce CQ.(+evic~ v ced i~ GcM Power ~~s(D~ Ww+ M M ~w d,ue.mq
<<e 6 ~g&~. 4(l VqQo ~d S~a p~Qp~
('LM~~se. 6w+ies WAG. ((
IoQ. scku2cMed Qe ~(s exv~W.
TheSe. nc+c~s ~~(( (ow Connrpicp&d, QP(c>fZ+C) ~( ( Poooerr Hp~ a+0~~.
5~ ~~+ QM~ Qu3~ ~c~siom&wC ckcce'p~ce Q Iz c+e'YLA c"I
)etc.v
+c0 all,llcehse ha(~ ~ha ( I 4e.
issuuu9 deMM(v c Wm CVX~gea ~~~~ ai~~cdeL c5t, P(a +~ (~~
~Pg+ey'('~.Cgi~~Q>~), ~e. +i~Qcx+w mi ((
leap~ MS'~Q p(~M Da 43
~~o=bDRD
+QADI
~to 62~ed. ~ -tb~
Kl~(A(cd%-0M QM<~Pg AAoEAAGE( ~Vcr ($1+~+Q~