ML17301A019

Forwards Revised Fire Protection Sys Commitment Schedule & Responses to NRC Requests.W/Two Oversize Charts.Aperture Cards Are Available in PDR

ML17301A019
Person / Time
Site:	Saint Lucie
Issue date:	02/09/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-83-65, NUDOCS 8302150706
Download: ML17301A019 (22)

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AOCESSION /BR:6302150706 DOCiDATEs 83/02/M, NOTARIZED: NO DOCKET ¹ FACIE:5W-'$89 St. Lucie Plant~ UniIt '2i Flor ida Power L Light Co. 05000389 AUTH ~ NAME AUTHOR AFF ILIATION UHRIG p R ~ E ~ Fl or ida Power 8 Li'ght Co, REC IP. NAME REC IP IENT AFFILIATION

-EISENHUTiD<G ~ Division of .Licensing p~W /~~~

SUBJECT:

For war ds rev'ised fire protection sys commitment schedu e L responses Ito NRC Irequests H/two oversize charts,

~ Aper tur e car ds are .avai l ab I e in .PDR ~

DISTRIBUTION CODEX'OORS COPIES RECEIVEDoLTR + ENCL + SIZE'..

TITLE: Licensing "Submittal: Fir e >PL otection NOTES:

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FLORIDA POWER 8( LIGHT COMPANY February 9, 1983 L-83-65 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 Fire Protection System Schedule/ -Res onses On October 8, 1982, Florida Power 8 Light Co. submitted a list of engineering and construction tasks that were not expected to be completed by core load but would be completed by the end of first refueling. The list included several portions of the Fire Protection System. The information contained in Attachment 1 supercedes the previous Fire Protection system commitment schedule and provides our best estimate of completion for all Fire Protection system tasks.

In addition during recent meetings between FPSL and NRC, several issues were raised for which responses were requested. Attachments 2 through 6 are provided in order to respond .to those requests.

If you have any questions regarding any of the attachments, please contact us.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/RJS/PPC/Alp Attachment cc: J.P. O'Reilly, Region II Harold F. Reis, Esquire 8302i5070h 830209 PDR ADQCK 05000389 PDR PEOPLE... SERVING PEOPLE

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INDEX OF ATTACHMENTS

1) Fire Protection System Schedule

2) QA/QC requirements for Phase I RAB Sprinkler- System and Fire Protection Seals,

3) Justification for interim operation with non-seismic RAB sprinkler systems

4) Fire Protection Interim Technical Specification

5) Source Range Nuclear Instrumentation

6) Containment Flame Inpingement Shields

ATTACHMENT 1 FIRE PROTECTION SYSTEM SCHEDULE The attached schedules provide FP&L's best estimate of completion of engineering and construction for the St. Lucie Unit /!2 Fire Protection System. This schedule'upercedes that which was submitted by FPL letter L-82-434 dated October 8, 1982

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ATTACHMENT 2 A/ C RE UIREMENTS This attachment provides a brief description of the Quality Assurance program that will be implemented on the St. Lucie Unit 2 Phase I sprinkler system and fire protection seals. With the exception of the Phase I sprinkler system and the fire protection seals, FP&L will implement SQP-99 "Fire Protection Systems".

The quality assurance program for the Phase I sprinkler system and the fire protection seals will utlize vendors'A manuals. These manuals have been compared to FP&L's SQP-99 and have been judged to satisfactorily implement all the quality assurance requirements set forth in this Site Quality Procedure.

Once the Phase I sprinkler system is installed and Phase II (Expansion Anchor) installation begins, SQP-99 will replace the vendor's QA manual.

The above Quality Assurance program will ensure that the Phase I sprinkler system will be installed per the requirements of NFPA 13.

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ATTACHMENT 3 JUSTIFICATION FOR INTERIM OPERATION WITH NON-SEISMIC RAB SPRINKLER SYSTEMS Fire suppression systems are being installed in the RAB to meet Appendix R III.G.2 requirements regarding separation/enclosure of cables and equipment in safe shutdown areas. Agreements as to the location of these sprinkler systems were finalized in the second quarter of 1982. Although design, procurement and installation of these systems is being accomplished on an accelerated schedule, detailed installation schedules have been the subject of several discussions with NRC in late 1982 and early 1983. On January 27, 1983, FP&L and NRC agreed that installation of the sprinkler systems would proceed such that all operable sprinklers are in place..priorto achieving five percent power; although installation of the seismic support and restraints will be initiated as soon as designs/fabrications are complete. The final seismic restraints will be completed by third quarter 1983 (October, 1983 for elevation 28.5'). Justification for operation pending completion of seismically restraining these operable sprinkler systems is given below:

1 The strongest earthquake felt in the State of Florida during the 200 years of historic record was the 1886 Charleston, South Carolina earth-quake, centered about 380 miles to the north. It was probably felt at the site as an intensity IV-V Modified Mercalli (MM) event. Analyses to determine the maximum surface acceleration resulting from an intensity VI MM earthquake occurring adjacent to the site resulted in a conservative value of 0.05g. Ideally this would be the maximum Safe Shutdown Earth-quake (SSE) surface acceleration defined for the St. Lucie site (since none of the three conditions relating to selection of the SSE, per 10CFR100 Appendix A Section V.(a) (1) (i) (iii), are considered applicable; see FSAR Subsection 2.5.2). However, the NRC Standard Review Plan, Section 2.5.2, states that the SSE seismic design acceleration should be at, least as conservative as the 1975 Trifunac and Brady mean relationship; values of 0.084g for intensity VI and about 0.09g for the trend of the mean defined by intensities IV-VII result. Furthermore, 10CFR100 Appendix A, Section V(a) (1) (v) requires that 0.10g acceleration be assumed as a minimum. Thus by edict the St. Lucie SSE is defined as 0.10g.

Since 10CFR100 Section V(a) (2) requires that the Operating Basis Earthquake (OBE) be no less than one half the SSE, ; the St. Lucie OBE is defined again by fiat as 0.05g. The annual probability for a seismic event greater than or equal to 0.05g (recall that this should have been an SSE acceleration)was computed and the analyses indicate that the probability of occurrence of this event is once per 3,000 years.

ATTACHMENT 3 (COND')

As shown en FSAR Figure 2.5-31 and CESAR Table 2.5-2, earthquakes in Florida have been infrequent, of low to moderate intensity (III-VIMM), and have epicenters at least 100 miles from the site. Several small earth-quakes have been felt in the vicinity of Green Cove Springs, located near Jacksonville, more than 180 miles north of the site. The other minor earthquakes within the state have'een randomly scattered and there is no evidence that any are related to observed structural features. FSAR Table 2.5-3 indicates the insignifiance of I-VI MM earthquakes.

The Uniform Building Code (the US Edition, Volume 1, as approved by the International Conference of Building Officials) designates the site vicinity as Zone 0 on the map entitled, "Map of the United States Showing Zones of Approximate Equal Seismic Probability." The US Coast and Geodetic Survey indicates Zone 0 as an area of no earthquake damage. Hadly and Devine (FSAR Section 2.5, Reference 49) also place this portion of Florida in a zone where the seismic frequency approaches zero. Furthermore, an examination of the epicentral map (FSAR Figures 2.5-31 and 2.5-32) shows a broad segment of south central Florida in which possible epicenters are entirely absent. The St. Lucie site is in the middle of this region.

Geologic conditions of the site and surrounding area, geologic structure and hypothesized faulting in the region, as discussed in FSAR Subsection 2.5.1, indicate that no seismic-generative faults exist within 200 miles of the site.

Based on the above, plus the short duration when the sprinkler systems are being seismically restrained and supported, it is believed that the occurrence of an earthquake which could potentially damage the sprinkler systems in the RAB is extremly unlikely, and the occurrence of an earth-quake of lesser intensity is not likely to affect any St. Lucie buildings or systems regardless of their seismic classification.

ATTACHMENT 4 FIRE PROTECTION/TECHNICAL SPECIFICATIONS FP&L is committed to have all sprinkler systems and fire rated assemblies installed, operational and under Technical Specifications by 5% power. Prior to 5% power, FP&L will comply with the following:

I. SPRINKLER SYSTEMS A. LIMITING CONDITION FOR OPERATION

1. The following sprinkler systems shall be OPERABLE:

a. Fire Zone 19 RAB. East Hallway and Miscellaneous Equipment Areas

b. Fire Zone 20 RAB East-West Common Hallway

c. Fire Zone 22 RAB Electrical Penetration Area

d. Fire Zone 23 RAB Electrical Penetration Area

e. Fire Zone 34 ZONF. I RAB Electrical Equipment Room

f. Fire Zone 39 RAB HVAC Equipment Room

g. Fire Zone 51 RAB Ceiling and Hallways

2. APPLICABILITY: Whenever equipment protected by the sprinkler system is requied to be OPERABLE.

3. ACTION:

With one or more of the above required sprinkler systems inoperable,,

with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire suppression required for safe shutdown could be damaged; for other areas, establish an hourly fire watch patrol.

B. SURVEILLANCE RE UIREMENTS

l. Each of the above required sprinkler systems shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated or automatic) in the flow path is in its correct position.

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

c. At least once per 18 months:

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1) By performing a system functional test which includes simulated automatic actuation of the*system, and a) Verifying that the automatic valves in the flow path actuate to their correct positions on a thermal test signal, and b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

2) By a visual inspection of each sprinkler system to verify their integrity, and

3) By a visual inspection of each sprinkler spray area to verify the spray pattern is not obstructed.

II FIRE RATED ASSEMBLIES A) LIMITING CONDITION FOR OPERATION

1) All fire rated assemblies (walls, floor/ceilings, and other fire barriers) separating safety-related fire areas or separating portions of redunant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire dampers, cable, piping, and ventilation duct penetration seals) shall be OPERABLE.

2) APPLICABILITY: At all times

3) ACTION:

With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of the fire detectors on at least one side of the inoperable assembly and establish an hourly fire watch patrol.

B) SURVEILLANCE RE UIREMENTS

1) At least once per 18 months the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by:

a. Performing a visual inspection of the exposed surfaces of each fire rated assembly.

b. Performing a visual inspection of each fire damper and associated hardware.

AT'ZACHMENT 4

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c. Performing a visual inspection of at least 10% of each type of sealed penetration. Xf apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penetration shall be made. This inspection process shall continue until a 10%

sample with no apparent changes in appearance"'or abnormal degradation is found. Samples shall be selected such that each penetration seal will be inspected every 15 years.

2) Each of the above required fire doors shall be verified OPERABLE by inspecting the automatic hold-open, release and closing mechanism and latches at least once per 6 months, and by verifying:

a. That each unlocked fire door without electrical supervision is closed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. That doors with automatic hold-open and release mechanisms are free of obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. That each locked closed fire door is closed at least once per 7 days.

3)At least once per 18 months, perform a functional test of each automatic hold-open and release mechanism.

ATTACHMENT 5 SOURCE RANGE NUCLEAR INSTRUMENTATION As a result of a meeting between NRC and FP&L on October 21, 1982 regarding fire protection, FP&L informally commited to provide remote source range nuclear instrumentation existing at the Hot Shutdown Panel independent of the control room.

This attachment is written in order to formally commit to this modification. The modification will be completed before the end of the first refueling.

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ATTACEKNT 6 CONTAINMENT FLAME IMPINGEMENT SHIELDS FP&L committed to install flame impingement shields beneath the lowest

~ cable tray in each stack containing safe shutdown cable in the containment building. This commitment was agreed upon late in the review process, and cannot be fulfilled until the first refueling outage. The reasons for, this schedule involves the time to determine layouts, engineering design details, verification and quality assurance of seismically analyzed design.

Ju'stification for operation in the interim period before this work task is completed is as follows:

1) A new Reactor Cooling Pump Oil Collection System is being provided to collect pressurized and unpressurized leaks from each of the Reactor Coolant Pump Lube Oil Systems. This installation will confine the major portion of combustible inventory to a separate oil collection tank in accordance with Appendix R., Section III-0 The remaining combustible loading in the fire area is light.

2) Fire detection is provided at various key locations of consequence.

3) Hose stations are strategically located in Containment, with water source being the existing primary water tank and piping.

4) Redundant safety-related equipment is protected from exposure to localized combustible sources by spatial separation and/or the use of existing barriers/partitions (i.e. concrete walls, floors and ceilings) having greater than three hours fire resistive rating.

Separation of electric circuits in Fire Area "K" meets the requirements of RG 1.75 Rev 1. Separation is provided to maintain independence of electrical circuits and equipment so that the protective function required during any design basis event can be accomplished. The degree and method of separation varies with the potential hazards in a particular area. This is accomplished by use of spatial separation, barriers, and radiant energy shields where required.

5) Electrical cables are concentrated at the Penetration Areas of Zone I at El *23.00 ft. between Column Lines 6 and 8 and adjacent Zone III. The cables trays are immediately separated upon entering Zone II and routed to the several items of equipment.

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Radiant energy shields are being provided between safety-related A and B cable trays in the cable penetation area to provide separation.

6) Verical cable tray runs are being provided with fire stops installed every 20 feet along the vertical rise.

7) Fire Area "K" is a high radiation area and personnel access is limited. thus minimizing the probability of introducing transient combustibles.

8) The large free volume (2.5 million cubic feet) of Fire Area for dissipation of hot off-gas temperatures and reduces "K'llows the effect of stratified hot gases at essential components.

9) All redundant cable trays containing safe shutdown cables will be protected by horizontal flame iihpfngement shields located below the lowest tray in each stock, 'when twenty (20) foot separation criteria is not met. The flame impingement shield width shall be 13 inches or the width of the cable tray, whichever is larger.

(Note that cable tray separation at the minimum is 7 feet).

10) All conduit containing safe shutdown cables which cross within twenty feet of a cable tray containing, redundant cable will be protected with a 1 hour wrap. The wra'p will extend 2 feet beyond both sides of the cable tray.

ll) All instrument cable .trays are-covered.

12) All cable in containment is IEEE-383 1974 qualified.

13) All cable trays are of the solid bottom type.

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