L-84-389, Forwards Rev 4 to Fire Hazard Analysis.Submittal of Formal Disposition of All Deviations Through Rev 4 by Second Wk of Jan 1985 Requested
| ML17215A725 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-84-389, NUDOCS 8501030079 | |
| Download: ML17215A725 (8) | |
Text
REGULATOR, INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:8501030079 DOC ~ DATE ~ 80/12/31 NOTARIZED:
NO FACIL:50-389 St, Lucie Plant~
Unit 2< Florida Power L Light Co.
AUTH,NAME AUTHOR AFFILIATION WILLIAMSgJ.W, Florida Power 8 Light Co, RECIP ~ NAME RECIPIENT AFFILIATION EISENHUTgD ~ G ~
Division of Licensing
SUBJECT:
Forwards Rev 0 to fire hazard analysis, Submittal of formal disposition of all deviations through Rev 0 by second wk of Jan 1985 requested, DISTRIBUTION CODEo A006D COPIES RECEIVED:LTR ENCL SIZE:
TITLE'.
OR Submittal: Fire Protection N0TEs:
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~/I6l+s OL:00/06/83 DOCKET ¹ 05000389 05000389 RECIPIENT ID CODE/NAME NRR ORB3
. BC 01 INTERNAL: ACRS 'l ELD/HDS2 NRR FIORAVANT07 EB 09-REG FILE OQ COPIES LTTR ENCL 3
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2 1-1 REC IP IENT ID CODE/NAME ADM/LFMB IE WHITNEY' NRR WAMBACH 06 NRR/DL DIR RGN2 COPIES LTTR ENCL 0
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1 EXTERNAL: LPDR NSIC 03 05 1
1 1
1 NRC PDR NTIS 02 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 18
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. BOX 14000, JUNO BEACH, F L 33408
~yIil I/Z xiii~4 Office of Nuclear Reactor Regulation Attention: Mr. Darrel G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 FLORIDAPOWER & LIGHTCOMPANY
"..;OS 1 N84 L-84-389 Dear Mr. Eisenhut RE:
ST.
LUCIE UNIT 2 DOCKET NO. 50"389 FIRE PROTECTION Attached is Revision 4 to the Fire Hazard Analysis for St. Lucie Unit 2.
Please replace the previous pages 20, 44, and 47 with the revised pages attached.
All additions and changes are identified by, revision bars in the margins.
The Nuclear Regulatory Commission audit is presently scheduled'or
- February, 1985.
Resolution of these deviations will be an integral part of the audit.
Florida Power 6 Light requests that the Nuclear Regulatory.
Commission provide formal disposition of all the deviations thru Revision 4 requests by the se"ond week in,January, 1985.
Your cooperation in this effort would be greatly appreciated.
Should you have any questions regarding this submittal, please advise.
Very truly yours, J.W. Williams, Jr.
Group Vice President Nuclear Energy Department JWW/SJR/mp Attachment cc:
JAP. O'Reilly, Region II Harold F. Reis, Esquire
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aluation Ionization type smoke detection is provided (as shown on Drawings-2998-G-413) and an automatic suppression system is provided in fire zones 39 and 51E.
2)
Portable fire extinguishers and a fire standpipe syst: em with hose tations are available for use in the area.
3)
See Evaluation A4, items 4 through 7.
Conclusion H4 See Conclusion A4.
Deviation H 5 A deviation is requested from Section III-G.2.a of Appendix R for mechanical penetrations to the conta'nment from the RAB fire zones 25 (Containment Purge),
39 (RAB HVAC Equiprqent Room) because no penetration fire seals are
~
X provided.
All of the penetr tions are sealed air,tight, however they do not constitute a typical fire rat d assembly.
Evaluation H5 0
2 ~
Portable fire extinguish rs and a fire standpipe system with hose stations are available fo use in this area.
Ionization type smoke detection system is provided as shown on Drawings 2998-G-413.
3 ~
All mechanical penetrations are ~ealed air tight and penetrate a
36 inch thick concrete'hell from the RAB into the containment.
This seal has been air tested at
.25" wg.
Between the 36 inch concrete
~
~
shell and the steel containment, there is an annulus of 48 inches which the penerations passes through.<
The annulus has negligible combustible loading.
At the Reactor Containment Building side, there is a
3 5/8 inch thick reinforced steel containment (reinforced 3 5/8 inches for penetrations+urposes).
The penetrations pass through this steel contai ment, sealed air tight and tested at approximately 44 psid.
R3 4.
Six general types of piping penetration assemblages are provided..
The penetration assemblies consist of a containmegt
.vessel penetration
- nozzle, a process
- pipe, a Shield Buildxqg penetration sleeve and a shield building bellows seal.
In the case of cold.
penetrations the containment vessel penetration nozzle is an integral part of the process pipe.
In the case of hot/and semi-hot penetrations, a multiple flued head is provided as an integral part of the process pipe.
A guard pipe, which encloses the process pipe and di.rects any fluid r'eleased back into the containment, is welded to the flued head.
For hot penetrations an expansion joint metal bellows is welded to the flued head and the containment vessel penetration nozzle to accomodate thermal movements.
The containment vessel penetration nozzles are designed to meet the requirements for Class MC vessels under ASME Code,Section III. 023F/03F
FIRE AREA "0" This Fire Area includes fire zones 19 (RAB East Hallway and Miscellaneous Equipment Area at elevation 19.50'),
20 (RAB East-West Common. Hallway at elevation 19.50'),
and 17 below the solid floor at elevation 12.08'Boric Acid Make-up Pump Room) as shown on the attached drawings.
Parameters descriptive of the fire area, including physical description, safe shutdown capability, fire hazard analysis and fire protection are outlined in the'ttached matrix.
Essential equipment within this fire area is shown in the attached essential equipment list.
E
'The following deviations to Appendix R to 10CFR50 are requested:
Deviation Ol A deviation is requested from fire section III-G.2.a of Appendix R for penetrations 2,
3, 12,13, 14 and 17 through the barrier between Fire Areas "L" and "0" because no fire dampers are provided in the ventilation ducts.
Evaluation 01 See Evaluation L2 Conclusion Ol See Conclusion L2 Deviation 03 0
A deviation is requested from Section III-G.2.a Column RAC/2-RA4 because a steel hatch cover of being provided at elevation 19.50 feet.
L Evaluation
.03 See Evaluation Hl of Appendix R for the hatch at 1/4 inch minimum thickness is Conclusion 03 See Conclusion Hl Deviation 04 A deviation is requested from Section III-G.2.a of Appendix R for the hatch at Column RAJ/2-RA5 because a steel hatch cover of 1/4 inch minimum thickness is being provided at elevation 19.50 feet.
Evaluation 04 See Evaluation I3 Conclusion 04 - See Conclusion I3 023F/03F
Conclusion 07 Based on our evaluation the installation of additional automatic fire suppression in the fire area would not augment or materially enhance the safety of the plant.
Therefore, we conclude, this is an acceptable deviation from Appendix R to 10 CFR 50, Section III-G.2.c.
Deviation 08 A deviation is requested from Section III-G.2.a of Appendix R for watertight doors RA 4, 5 and 6 because the fire rating of the custom manufactured doors is not Underwriters Laboratory listed.
Evaluation 08 See Evaluation J3 Conclusion 08 See Conclusion J3 Deviation 09 A deviation is requested from Section III-G.2.a of Appendix R because fire retardant coatings are not provided for the structural, steel supporting the steel conduits which are wrapped to provide separation in accordance with t
Appendix R.
Evaluation 09 2) 3)
Portable fire extinguishers and a fire standpipe system with hose stations are available for use in the area.
3)
See Evaluation A4, items 4 through Conclusion 09 Ionization type smoke detection is provided as shown on Drawings 2998-G-413.
An automatic suppression system is provided in fire zones 19 and 20.
t l
I l
1 iR3 1
See Conclusion A4.
Deviation 010 A deviation is requested from Section III-G.2.a of Appendix R because no fire damper is provided in the ventilation duct located ir. the east wall of the charging pump cubicle access corridor.
Evaluation 010 - See Evaluation N4 Conclusion 010 - See Conclusion N4 t 023F/03F
(I E