L-83-238, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capabilities.Status & Implementation Schedule & List & Description of Reg Guide 1.97,Type a Variables Encl
| ML17213B286 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/15/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, L-83-238, NUDOCS 8304210399 | |
| Download: ML17213B286 (11) | |
Text
REGULATORY;ORMATION DISTRIBUTION SY
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ACCESSION NBR 830421 0399 'OC ~ DATE 83/04/15 NOTARIZED NO fsACIL:50-389 St. Lucie Plant, Unit 2F Florida Power 8 Light Co.
AUTH ~ NAMIE AUTHOR AFFILIATION UHRI GER, E ~
Flor ida Power 8 Light Co, REC IP ~ NAME RECIPIENT AFFILIATION EISENHUTFD.G, Division of Licensing DOCKET 05000389
SUBJECT:
Responds to Generic Ltr 82-33 re requirements for emergency response capabilities. Status 5 implementation schedule 8
list 8 description of Reg Guide 1.97iType A variables encl.
DISTRIBUTION CODE:
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TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)
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~y>ll//i FLORIDAPOWER & LIGHTCOMPANY April 15, 1983 L-83-238
.Office of Nuclear Reactor Regulations Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Eisenhut:
Re:
ST.
LUCIE UNIT NO.
2 DOCKET NO. 50-389 SUPPLEMENT 1 TO NUREG-0737 (GENERIC LETTER 82-33)
Your letter dated December 17,
.1982, transmitted Supplement 1
to NUREG-0737 (Generic letter No.
82-33).
This supplement provided clarification of five NUREG-0737 items regarding the requirements for Emergency
Response
Capabilities and requested each plant to develop plant specific schedules for implementing those requirements.
The St.
Lucie Unit No.
2 plant has proceeded with the implementation of those requirements.
The portions of those items which we have not completed, FPL has developed specific schedules for their completion, as requested by your letter.
The majority of the schedules which we have provided to you on Attachment 1
to this letter have been submitted to your staff and found to be acceptable.
Therefore, providing, for those
- provided, of the St.
as required per Supplement 1
to NUREG-0737, FPL is on Attachment 1,
the status and implementation schedule items outlined in the supplement.
Additionally, we have on Attachment 2
to this
- letter, a list and description Lucie Unit No.
2 R.
G. 1.97, Type A Variables'hould you have any questions regarding this submittal, please do not hesitate to contact us.
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OR,
- mal, Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/RJS/PPC/rms Attachments cc:
J.P. O'Reilly, Region II Harold F. Reis, Esquire 4
PEOPLE... SERVING PEOPLE
ATTACfRKNT 1 ST.
LUCIE UNIT NO.
2
RESPONSE
TO SUPPLEMENT 1
TO NUREG-0737 SAFETY PARAMETER DISPLAY SYSTEM 1.
CURRENT STATUS The parameter selection in accordance with NUREG-0696 completed.
The functional design specification completed.
The hardware has been factory tested and to the site for installation.
" The computer system installed and powered from vital AC systems.
The Unit of the package software has been delivered to the site.
has been has been delivered has been 2 portion As previously mentioned in our letter L-82-434, dated October 8,
- 1982, and found acceptable; the SPDS will be operable and the operators will be trained by the end of the first refueling outage.
2.
SUBMITTAL OF PARAMETER SECTION BASIS AND SPDS IMPLEMENTATION PLAN REPORT The reports describing the parameter selection and definition along with the implementation plan will be submitted by March 1,
1984.
DETAILED CONTROL ROOM DESIGN REVIEW CURRENT STATUS A preliminary design assessment of the St.
Lucie Unit No.
2 Control Room has been completed.
The summary report was submitted to the NRC in a
FPL letter dated July 15, 1981 (L-81"295) and was supplemented in a letter dated September 30, 1982 (L-82-424).
As conditioned in our St.
Lucie Unit'o.
2, Low Power License,
- FPL, prior to exceeding 5%
power, will complete correction of the human engineering discrepancies as noted in Appendix E to the license.
Additionally, prior to start-up after the first refueling
- outage, FPL will rearrange the instruments described in Appendix F to the license.
2.
SUBMITTALS FPL will submit its management plan to the NRC by June 30, 1983.
It is anticipated that the detailed Control Room design review effort will be completed by April 30, 1983, with Human Discrepancy Reviews and Assessments complete by May 31, 1983.
FPL will submit a
summary report of the completed review to the NRC by September 30, 1983.
REGULATORY GUIDE 1.97 REVISION 2 1.
CURRENT STATUS FPL has reviewed all the plant instrumentation and control systems against the requirements of Regulatory Guide 1.97, Rev.
2.
We are presently assessing the deviations found and are developing the schedules for any required modifications.
2.
SUBMITTALS The implementation requirements of R.
G.
1.97 require plants such as St.
Lucie Unit No.
2, who were licensed prior to June 1,
- 1983, to meet the requirements and schedules outlined in NUREG-0737.
Plant specific schedules have been allowed via Supplement 1
to account for unique aspects of each plant.
Therefore, by November 30,
- 1983, FPL will submit a
St.
Lucie Unit No.
2, R.
G.
1.97 Evaluation Report describing how R.
G.
1.97 has been met and justifications for any deviations to R.
G. 1.97 requirements.
Additionally, provided as Attachment 2 to this letter is a list and description of the St.
Lucie Unit No.
2 R.G.
1.97, Type A variables.
4 UPGRADE EMERGENCY OPERATING PROCEDURES (EOPs) 1.
CURRENT STATUS FPL has been active participants in the Combustion Engineering Owners Group (GEOG) efforts regarding the upgrading and reformatting of the EOPs.
St.
Lucie Unit No.
2 plant specific procedure generation will be based upon the technical guidelines submitted to the NRC by the GEOG.
2.
SUBMITTALS FPL will submit plant specific EOP descriptions by November 1,
1983.
The upgraded EOPs will be implemented by July 1, 1984 and will include SPDS and control room upgrades.
EMERGENCY RESPONSE FACILITIES (ERFs) 1.
CURRENT STATUS Supplement 1
to NUREG-0737 requests an operational schedule for the ERFs.
ERFs present schedule is as follows:
a ~
Technical Su ort Center (TSC)
The TSC is currently operational except for some construction activity for installing the SPDS.
The SPDS will be completed at the end of the first refueling outage.
b.
0 erational Su ort Center (OSC)
The OSC is currently operational.
y ~
1'
,7 c.
Emer enc 0 eration Facilit (EOF)
The EOF is currently under construction and will be completed and operational by October, 1983.
As required by our 1'icense, FPL is maintaining interim emergency support facilities while the construction of the TSC and EOF continues.
ATTACHMENT 2 REGULATORY GUIDE 1.97 REVISION 2 TYPE A VARIABLES PRESSURIZER PRESSURE Indication of p'ressurizer pressure is provided in the control room via pressure instrument loops P-1107 and P-1108.
The control room indication is provided via an indicator, a
recorder and on the Qualified Safety Parameter Display (QSPDS).
Indication is also obtainable through FPL's Safety Assessment System (SAS).
All the equipment excluding SAS is classified as lE.
2.
COLD LEG TEMPERATURE RCS Cold Leg Temperature indication is provided from instrument loops T-1112 CA/CB and T-1122 CA/CB.
These dual element RTD's are of the fast response type which input the Reactor Protection System (RPS) and the QSPDS.
Temperature indication is also provided on indicators and a
recorder located on the Reactor Turbine Generator Board (RTGB).
Additionally, indication is obtainable through SAS.
All of this equipment excluding SAS is classified as 1E.
,3.
HOT LEG TEMPERATURE RCS Hot Leg Temperature indication is provided from instrument loops T-1112 HA/HB and T-1122 HA/HB.
These dual element RTD',s are of the fast response type which input the RPS and the QSPDS.
Temperature indication is also provided on indicators and a
recorder located on the RTGB.
Additionally, indication is obtainable through SAS.
All of this equipment excluding SAS is classified as 1E.
4.
STEAM GENERATOR LEVEL
'team Generator level indication.is obtained from instrument loops L-9013A, B,
C, D and L-9023A, B,
C, and D.
The S/G level inputs the RPS and initiates a reactor trip on low S/G level.
The Auxiliary Feedwater Auto Start (AFAS) also actuates from these signals.
Additionally, these parameters can be read on indicators and recorders located on the RTGB.
S/G level is also available through SAS.
All of the equipment excluding SAS is classified as 1E.
CONTAINMENT HYDROGEN CONCENTRATION Containment Hydrogen Concentration indication is provided in the
- control, room via redundant readouts in the 'control room on the hydrogen analyzer recording panel.
This information is also recorded and annunciation is provided.
All associated equipment is classified lE.
r 1.i
STATE OF FLORIDA
)
)
SSe COUNTY OF'PALM BEACH )
Robert E. Uhri being first duly sworn, deposes and says:
That he is Vice President Licensee herein; of Florida Power & Light Company, the That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information> and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this Rotary Puclic, State of Florida at Large My Cornfnis ion Expirea October 30,.1983 Bonded thru Maynard Bonding Agency My commission expires:
t ""/5, day of l9PQ.
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C~NO'PARQP.
BLIC, in ond for the County tF~< of Palm,Beach, State of Florida.
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