ML17223B280

Proposed Tech Specs Deleting Sections 3/4.3.3.7,3/4.7.11, 3/4.7.12 & 6.2.2.e & Adding Section 6.5.1.6.n

ML17223B280
Person / Time
Site:	Saint Lucie
Issue date:	10/17/1991
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17223B278	List: ML17223B277 ML17223B280
References
NUDOCS 9110240120
Download: ML17223B280 (92)

Text

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendment Fire Protection Technical S ecifications ATTACHMENT 1 St. Lucie Unit 1 Marked-up Technical Specification Pages UNIT 1 TS PAGES License Condition 2.C. (3) 3/4 3-37 3/4 3-38 3/4 3-39 3/4 3-40 B 3/4 3-3 3/4 7-40 3/4 7-41 3/4 7-42 3/4 7-43 3/4 7-44 3/4 7-44a 3/4 7-44b 3/4 7-44c 3/4 7-44d 3/4 7-45 B 3/4 7-7 6-2 6-5 6-8 PDR ADOCH, PSOOOS 5

ted e Ame dme t 08 t 06 9 D~7 Page 3 (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act, and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate,. such byproduct and special nuclear materials as may be produced by the operation of the facility.

This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Sections 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is sub)ect to the additional conditions specified or incorporated below'1) w v The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2700 megawatts (thermal), provided that the construction items, preoperational tests, startup tests, and other items identified in Enclosure 1 to this license have been completed as specified in Enclosure 1. Enclosure 1 is an integral part of, and is hereby incorporated in this license.

(2)

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 108 are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

e e DERW7 Page 4 (3) o ct'o licensee may proceed with and is re a schedule for and to comber ete the

'd t prov modifica ion and

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Paragraphs for the

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~ evaluations through 3.15 o Protection Safe Evaluation, facility. If

'htified he NRC's Fire ed August 17, 1979 ny modifications or in evaluation cannot be pleted on schedule the licensee shall sub a report explaining the circumstances t Ker with a re, ised schedule.

The licen e is required to im lement the adminis tive controls identified in Sec n 6 of the ety Evaluation. The administrative co ols s l ssu nce be in effect within 90 days from the date of this amendment.

(4) DELETED PER AMENDMENT 488, DATED JANUARY 13, 1988 488, DATED JANUARY 13, 1988

'5)

DELETED PER AMENDMENT licensee shall fully implement and maintain in effect all 'he provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "St. Lucie Plant Security Plan," with revisions submitted through April 11, 1988g "St. Lucie Plant Training and Qualification Plan", with revisions submitted through August 8, 1985; and "St. Lucio Plant Safeguards Contingency Plan," with revisions through December 8, 1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

DELETED PER AMENDMENT $ 46, DATED NOVEMBER 3, 1981.

The licensee shall implement the following requirements for the protection of the environment:

(1) The licensee will plant Australian pine or other suitable plants as a light screen along the beach dune line bordering its property to minimize turtle disorientation.

In addition, perimeter fence lighting will be shielded so that none of the light is diverted skyward.

(2) DELETED PER AMENDMENT f50 ~ DATED MAY 2 1 J 1982 ~

(3) DELETED PER AMENDMENT $ 39, DATED MARCH 10, 1981 ~

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New Unit 1 Standard License Condition 2.C.(3)

(3) Fire Protection The Licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility (The fire protection program and features were originally described in licensee submittals L-83-514 dated October 7, 1983, L-83-227 dated April 22, 1983, L-83-261 dated April 25, 1983, L-83-453 dated August 24, 1983, L-83-488 dated September 16, 1983, L-83-588 dated December 14, 1983, L-84-346 dated November 28, 1984, L-84-390 dated December 31, 1984, and L-85-71 dated February 21, 1985) and as approved in by NRC letter dated July 17, 1984 and supplemented by NRC letters dated February 21, 1985, March 5, 1987, and October 4, 1988 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

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INSTRUMENTATION RE DETECTION INSTRUMENTATION LIMI NG CONDITION FOR OPERATION 3.3.3.7 s a minimum, the fire detection instrumentation for each ire detection one shown in Table 3.3-10 shall be OPERABLE*.

APPLICABILIT Whenever equipment in that fire detection zone s required to be OPERABLE.

ACTION:

With the number of PERABLE fire detection instruments ess than required by the minimum instrume ts OPERABLE requirement of Tabl 3.3-10:

a. Within 1 hou establish a fire watch pap ol to 'inspect the zone(s) with e inoperable instrumen ('s) at least once per hour (unless t detectors are locat d inside the annulus, zone ll, then in pect the zone at J east once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />); or monitor the conta 'nment air tempgf ature at least once per hour at the locations 1 sted in Specification 4.6.1.5 1noperahI e Instrome ts are In@ted 1nsIde the contatnment if the (zone 13/14/15A 8 B)..

Restore the inoperable strument(s) to OPERABLE status within 14 days or prepare and s bmit a Special Report to the Comission pursuant to Specific ion 6.9.2 within the next 30 days outlining the action taken, e caus of the inoperability and the plans and schedule for estoring e instrument(s) to OPERABLE status.

c. The provisio of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE REMENTS 4.3.3.7.1 Ep h of the above required fire detect n instruments which are accessible guring operation shall be demonstrated ERABLE at least once per 6 months detector f performance of a CHANNEL FUNCTIONAL TES which shall be demonstrated except for thermal OPERABLE in acc rdance with Specifica-tion 4. .3.7.2. Fire detection instruments which are t accessible during opera on shall be demonstrated OPERABLE by performance TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except f a CNNNEL FUNCTIONAL ti need not be performed more often than once per 6 mont hat such demonstra-

<<The emergency power source may be inoperable in Modes 5 or 6.

ST. LUCIE - UNIT 1 3/4 3-37 Amendment No. 2SAHlo 9

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INSTRUMENTATION SUR ILLANCE RE UIREHENTS Continued 4.3.3.7.2 he NFPA Code 72D Class A supervised circuits supervision

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associated 'th the detector alarms of each of the above required fire

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detection ins ments shall be demonstrated OPERABLE at Feast once per 6 months.

ST. LUCIE - UNIT 1 4 3-3 Amendment No. 25

T. l O

TASLE 3.3-10 FIRE OETECT ION INSTRUMEMTATION MINIMUM OKTECTORS OPERABLE ZONE THERMAL SMOKE LOOATIOH 1.02.01 6 ZONE-1B REACTOR AUX. BLDG. KL.0,50 1.02.02 3 ZONK-28 REACTOR AUX. BLDG. KL. 0.50 1.02.03 12 ZONE-3B )EACTOR AUX. BLDG. EL.19.50 1,02.04 2 ZONE-48'EACTOR AUX. BLDG. KL.43.00 1.02.05 4 REACTOR AUX. BLDG. KL.19.50 'ONK-5B 1.02.06 7 ZONE.-6B REACTOR AUX. BLDG. KL.43.00 1.02.07 9 ZONE-7B REACTOR AUX. BLDG. EL.43.00 1.02.08 1 ZONE-8B REACTOR AUX. BLDG. EL.62.00 1.02.09 ONK-9B REACTOR AUX. BLDG. KL.43.00 1.02.10 ZONE-10B REACTOR AUX. BLDG. EL.43.00 1.02.11 ZONK-llB ELECT. PENET. REC. (ANNULUS) 1.02.12 ZONK-12B ELECT. PENET. REC. AUX. BLOS.

EL.19.60 1.02.13 1 ZONE-138 REACTOR TUNNEL BELOM EL.18.00 1.02.14 9 ZONK-148 REACTOR KL.18.00 1.02.15 10 ZONK-158 REACTOR KL.45.00 1.02.20 2 Z )E-20B FUKL HANDLING BLDG. EL.19.50

.1.02.21 3 ZONE-218 FUEL HAHOLSHO SLOG. EL.48.00 f~'Or 22 1 ZONE-22B DIESEL BEN. BLD6.

1.N.01 6 ZONE-1+ REACTOR 4UX. BLDG. EL.0.50 1.01.02 6 ZONE-2A~ EACTOR AUX. BLDG. EL.0.50

l. 01.03 12 ZONE-3A R OR AUX. BLDG. EL.19.50

• Includes pre-action detectors.

ST. LUCIE - UNIT 1 3/4 3-39

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TABLE 3.3-10 (Cont'd)

FIRE DETECTION INSTRUMENTATION MININJN DETECTORS OPERABLE ZONE THERNAL SN)KE LOCATION 1.01.04 ZONE-4A REACTtm AUX. BLDG. EL.19.50 1.01.05 ZONE-5A REACTOR AUX. BLDG. EL.19.50 1.01.06 ZONK-6A TOR AUX. BLDG. EL.43.00 1.01.07 ZONE-7A REACTOR AUX. BLDG. EL.43.00 1.01.08 ZONE;BA REACTOR AUX. BLDG. EL.62.00 1.01.09 ZONE-9A REACTOR AUX. BLDG. EL.43.00 1.01.10 ZONK-1OA REACTOR AUX. BLDG. EL.43.00 1.01.11 1.01.12

. ONK-11A ELECT. PKNET. RKC. (aeULUS ZONE-12A ELECT. PKNET. RKC. AUX. B j

EL.19.60 1.01.13 3 ZONE-13A REACTOR TUNNEL BELN EL.18.

1.01.14 10 ZONE-14A RKACTN EL.18.00 1.01.15 7 ZONK-15A REACTOR EL.45.00 1.01.20 ZONK-20A FUEL HANDLING BLDG. EL.19.50 ~

1,01.21 ZONE421A FUEL HANDLIS BLDG. EL.48.00 1.01. 22 ZONE-2 DIESEL .GEN. BLDG.

• Inc1udes pre-action detectors.

ST. LUCIE - UNIT 1 3/4 3-40

IN ST RUt lEtl TAT I OH BASES 3/4.3.3.6 DELETED 3/... IRE OETECTIOtl IHSTRUtlEtlTATION OPERABILITY of the 1r ction instrumenta--i ensures that adequate warning capability is available for tre p omp~etection of fires. This capability is required ir, order to dete an R te fires in their early stages. Prompt detection of f~eMwill reduce the p ~e ial for damage to safety related equipment~nd ss an integral element in the rail facility fir e protection pro am In th cent that a portion of the fire detec ion ins rumentation i inope e, th establishment of frequent fire p trois in the affected areas equired to provide de ection capability until the inooerable instrumenta-tion is restor ed to OPE? ILITY.

3 4.3.3.8 ACCIQEtlT tlOHITORIHG ItlSTRUNEHTATIOtl The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accidert. This capability is consistent with the recommendations of tlUREG-0578, "TNI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

ST. LUG IE - UHIT 1 B 3/4 3-3 Amendment,'lo ~ R$ . 37~ 5 <

P ANT SYSTEMS 3/4 7.11 FIRE SUPPRESSION SYSTEMS FIRE PPRESSION WATER SYSTEM*

LIMITING ONQITION FOR OPERATION 3.7.11.1 Th fire suppression water system shall be OPERABLE~ with:

a. Two bligh pressure pumps, each with a capacity of 2350 gym, with their'discharge aligned to the fire suppression heade,

b. Separate water supplies, each with a minimum conta'ned volume of 300,000 g lions, and

c. An OPERABLE flowpath capable of taking suctiop from the city water storage tank IA and the city water storage tink 1B and transferring the water throu h distribution piping withfOPERABLE sectionalizthg control or isola )on valves to the yard~ppdrants, and the last valve ahead of th water flow alarm device on each sprinkler or hose standpipe req red to be OPERAB E per Specifications 3.7.11.2, 3.7.11.3, and 3.7.11 4.

APPLICABILITY: At all times.

ACTION:

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a. With one pump and/or one wa er supply inoperable, restore the inoperable equipment to>OPERA LE status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 @(thin the ext 30 days outlining the plans and procedures to be used to res ore the inoperable equipment to OPERABLE status or. to provide an alternate backup pump or supply.

The provisions of Specifications 3. .3 and 3.0.4 are not applicable.

b. With the f re suppression water system otherwise inoperable:

l. Establish a backup fire suppressio water system within 24 hours, and

2. Submit a Special Report in accordance ith Specification 6.9.2; a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgram or f csimile transmission no later than the first working day fo'owing the event, and This system is shared between St. Lucie Units 1 and 2.

The normal or emergency power source may be inoperable for each" rain in Modes 5 or 6.

ST. LUCIE - UNIT 1 3/4 7-40 Amendment No. g$ , Py ~~ e 69

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PLANT SYSTEMS

'LIMITING COND!TION FOR OPERATION Continued) c) In writing within 14 days following the event, out-1 ining the action taken, the cause of ihe inopera-bility and the plans and schedule f r restoring the system to OPERABLE status.

SURVEILLANCE RE. UIREMENTS 4.7.11.1 The fire uppression water system shall be demonstrated OPERABLE:

a ~ At least onc per 7 days by v rifying the contained water supply volume.

b. At least once pe - 31 days on a STAGGERED TEST BASIS by star ting each pump and opelating~it for at 'least 15 minutes on recircu-lation flow.

c ~ At least once peril ays by verifying that each valve (manual, power operated oy automatic) in the flow path is in its correct position.

d. At least once per 12 months by performance of a system flush.

e. At leas once per 12 months b cycling each testable valve in the flo path through at leas one complete cycle of full travel.

At/east once per 18 months by p qforming a system functional test which includes simulated autoqatic actuation of the system throughout its operating sequence, 'and:

1. Yerifying that each automatic va ve in~the flow path actuates to its correct position,

2. Verifying that each pump develops at least 2350 gpm at a system head of 232 feet,

3. Cycling each valve in the flow path that 's not testable during plant operation through at least on complete cycle of full travel, and

4. Yerifying that each high pressure pump starts equentially) to maintain the fire suporession water system pr sure

> 85 psig.

ST. LUG IE - UNIT 1 3/4 7-41 Amendment No. 2

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,P SYSTEM fIRE HOSE STATIONS LI ITING CONOITION FOR OPERATION 3.7.11 2 The fire hose stations shown in Table 3.7-3 shall be OPERABLE.

APPLICAB ITY: Whenever equipment in the areas protected b the fire hose stations is required to be OPERABLE.

ACTION:

a. W ith oqe or more of the fire hose stations shown in Table 3.7-3 inoperable, route an additional equivalent capacity fire hose to the unprotected area(s) from an OPEINBL'E hose station within I hour if~ he inoperable fire hose lsfthe primary means of fire suppression',, otherwise route the add'itional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore the fjre hose station to OPERABLE status within 14 days or, in lieu o5 any other report~required by Specification 6.9.1, prepare and su it a Special Report to the Comnission pursuant to Specification 6.9.2 withig<the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restor 'ng the station to OPERABLE status.

b. The provisions of Spe fications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.11.2 Each of the fi~hose stati ns shown in Table 3.7-3 shall be demonstrated OPERABLE:

a. At least once per 31 days by v sual inspection of the station to assure all required equipmen is at the station.

b. At least once per 18 months by:,

1. Removing the hose for inspection and re-racking, and Replacement of all degraded gaskets in coupIings.

C. At least once per 3 years by:

I. Partially opening each hose station val e to verify valve OPERABILITY and no flow blockage.

2. Conducting a hose hydrostatic test at a pres ure of 150 psig or at least 50 psig above maximum fire main op rating pressure, whichever is greater. (Hoses on exterior hose tations shall be hydrostatic tested once per year.)

ST. LUCIE - UNIT I 3/4 7-43 Amendment No. g$ , 66

TABLE 3.7-3 FIRE HOSE STATIONS A. Hose S tati ons (Turbine Bui 1 ding)

Operating Floor (northeast corner)

2. Operating Floor (southeast corner)

3. Ope ating Floor (middle east side)

B. Hose Statio s (Reactor Auxiliary Building) 43 ft. le 1 south wall of HVE room

2. 43 ft. level 'B" switc."gear roon by, ro',1-up door

3. 43 ft. level sout west corner of: '8" switchgear room near door.

4, 43 ft. level cable sp,eading room west wall

5. 19.5 ft. level east end o east-west hall

6. 19.5 ft. level middle of east-west hall

7. 19.5 ft. level sogu/end of north-south hall

8. 19.5 ft level.entrance hall on so th walI

9. -5 ft. level ast end of hall

10. -5 ft. leve"I south wall of hall near MCC B2

-5 ft. evel west end of hall S . LUCIE - UNIT 1 3/4 7-44 Amendment No. g$ ,

PLANT SYSTEHS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES L HITING CONDITION FOR OPERATION 3.7. .3 The yard fire hydrants and associated hydrant hose houses shown in Table .7-4 shall be OPERABLE.

APPLICABILITY: Mhenever equipment in the areas protected by 'he yard fire hydrants i required to be OPERABLE.

ACTION:

a. With o e or more of the yard fire hydrants or associated hydrant hose houses shown in Table 3.7-4 inoperab'le, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> have sufficient additional lengths of 2 1/2y>inch diameter hose located in an adjacent OPERABLE hydrant hose>house to provide service to the unprotected area(s) if the inoperable fire hydrant or associated hydrant hose house is the primary means of fire suppression; ot'herwise provide tfie additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the hydrant or hose house to OPERABLE status within 14 days or+in lieu of any other report required by Specification 6.9.1$ prepare and submit a Special Report to the Commission pursuant to, Specification 6.9.2 within the next 30 days outlining the actfon'aken, the cause of the inoperability, and the plans and schedu'le for restoring the hydrant or hose house to OPERABLE status.

b. The provisions of~Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.11.3 Each of the/yard fire hydrants and<associated hydrant hose houses shown in Table 3.7 shall be demonstrated OPERABLE:

a. At least once per 31 days by visual inspection of the hydrant hose hous to assure all required equipment 's at the hose house.

b. At least once per 6 months by visually inspecting each yard fire hydrant and verifying that the hydrant is not damaged.

c At least once per 12 months by:

1. Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure ava lable at any yard fire hydrant.

2. Inspecting all the gaskets and rep1acing any degr ded gaskets in the hose coupl ings.

3. Per forming a flow check of each hydrant to verify its OPERABILITY.

ST. LUCIE - UNIT 1 3/4 7-44a Amendment No. 66

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TABLE 3.7-4 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES LOCATION H YDRANT NUMBER East of intake fence enclosure Fire Hydrant 810 5 Hose House 83 North of CCM fence enclosure gate, F~i e Hydrant d4 5 Hose house on east 'all of Fuel Hose House 81 Handling Building East wall of Diesel Generator Fire Hydrant f6 5 Hose House f7

<<Southeast corner RAB ~

Fire Hydrant 87 ST. LUCIE - UNIT 1 3/4 7-44b. Amendment No. 66

PLANT SYSTEMS

<SPRAY ANO OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11. The following spray and/or sprinkler system(s) shall be OPERABLE:

a. OieseI Generator Bui1ding 1A.

b. Oi etc/generator Building 18 APPLICABILITY: Whenever equipment protected by the<spray/sprinkler system is required to be OPERABLE.

ACTION:

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a. With one or moreof the above required spray and/or sprinkler systems inoperablie, within one, hour establish a continuous fire watch with backup>pire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly@'fire watch patrol. Restore the system to OPERABLE status wikhi&14 days or, in lieu of any other report required by Specificati~on 6.9.1, prepare and submit a Special Report to the Commissionl~ursuant to Specification 6.9.2 within the next 30 days outlining~the action taken, the cause of the inoperability andthe plan and schedule for restoring the system to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.11.4 Each of the above required spray and/or sprinkler systems sha11 be demonstrated OPERABLE:

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

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position.

b. At least once per 12 months by cycling each tqstable valve in the~

flow path through at least one complete cycle of ull travel.

c. At least once per 18 months:

ST. LUCIE - UNIT 1 3/4 7-44c Amendment No. 66

PLANT SYSTEMS S RVEILLANCE REOUIREHENTS Continued By performing a system functional test which, includ'es simulated automatic actuation of the system, and'.

a) Verifying that the automatic valves in~the flow path actuate to their correct positions ort/a test signal, supplied from a thermal detector, and b Cycling each valve in. the flow path that is not testable during plant operation through at least one omplete cycle of full travel~

2. By a vis al inspection of the>dry pipe spray and sprinkler headers to verify their integrity, and

3. By a visual qspection ofEeach nozzle's spray area to verify the spray patt rn is not obstructed.

ST. LUCIE - UNIT 1 3/4 7-44d Amendment No. 66

PLANT SYSTEMS I 3/4.7.12 PEHETRATIOH FIRE BARRIERS LI ITING CONOITION FOR OPERATION 3.7.12 gll electrical penetration fire barriers protecting safety related a eas shall be intact.

APPLICABILITY: At all times.

ACTION:

With one~or more of the above reg ired electrical penetration fire barriers not intact and with'he area of the affected barrier(s) onitored by OPERABL'E (pursuant to Specification 3.3.3.7) fi <e detection instru'mentation, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> es-tablish a fir'e watch patrol@'fo inspect at least one side of the affected penetration a't least once per hour.

b. With one or more of the above required electrical penetration fire barriers not%ntact and with the area of the affected barrier(s) not moniYored by OPERABLE (pursuant to Specifica-tion 3.3.3.7) fire~d tection instrumentation, establish a continuous fire,,watch>on at least one side of the affected penetration wi,thin 1 hour.

C. The provisions of Specifications 3.0.3 and 3.0.4 are not app1 i cab e>

1 SURVEILLANCE RE IR MENTS 4.7.12 The above required electrical penetra -ion fire barriers shall be verified to be intact:

a, At least once per 18 months by a visual inspection.

~be Prior to returning a penetration fire barrier to intact status following repairs or maintenance by performance visual inspection of the affected electrica penetration fsre o~

barrier(s).

ST. LUCIE - UNIT 1 3/4 7-45 Amendment No. 25

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PLANT SYSTEt/S BASES 4.7.11 FIRE SUPPRESSION SYSTEMS he OPERABILITY of the fir@suppression systems ensures that adequ te fire upprespion capability is available to confine and extinguish fires~occurring in ny portion of the facility where safety related equipment is lo ted. The fire uppression~system consists of the water system and fire hose tations. The ollective ca ability of the fire suppression systems is ad quate to minimize otential damag to safety related equipment and is a maj8r element in the facility fire pro ection program.

In the event tha portions of the fire supyyession systems are inoperable, lternate backup fire fighting equipment is req6ired to be made available in the ffected areas until the operable equipme 'K is restored to service.

~s In the event the fire suppqessio~n ster systma becomes, inoperable, immediate orrective measures must. be taken since this system provides the major fire uppression capability df the plan%< The requirement for a twenty-four hour aport to the Commission provides+fan prompt evaluation of the acceptability of the corrective measures to propre adequate fire suppression capability for the ontinued protection of the Oclear plant

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7.12 PERETRATION .F'E BARRIERS The functlona)+integrity of the penetration fige barriers ensures that.

fires will be confined or adequately retarded from spLeading to adjacent por-tions of the facility. This design feature minimizes "the possibility of a single fire rapidly involving several areas of the facilitty prior to detection

. and extinguishment. The penetration fire barriers are a passive element in the facilHy fire protection program and are subject to periodic inspections.

Ouring periods of time when the barriers are not intact, roqtine fire atchfpatrols in conjunction with OPERABLE fire detection instrume tation or a continuous fire watch are required to be maintained in the vicini of the affected barrier until the barrier is restored to intact status.

ST. LUCIE - UNIT 1 B 3/4 7-7 Amendment No. g$ , 44

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5.0 ADMI.'ll.'LUSTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

')NIT S AFF l 5.",2 The unit organization shall be subject to the following:

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a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is in NODE 1, 2, 2, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

C ~ A health physics technician'hall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be observed by a licensed operator and supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

The SRO in charge of fuel handling normally supervises from the control room and has the flexibility to directly supervise at either the refueling deck or the spent fuel pool.

e. A te Fire Sri ade>of at ast five g bers sh 1 be ma tafned o site at all imes . T Fire Brigpde shall ot inclu e the ift superv'r, the S , nor the two other embers the The health physics technician i.re- a e c o may be less than the minimum requirement/ for a period of t me not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomnodate unexpected absence, provided imediate action is taken to fill the required positions.

ST. L'JCIE - 'JNIT 1 6-2 Amendment No. JH~gSISF'tltlt

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ADMINISTRATlVE CONTROLS minimum s 1 w neGeMi~fp s4QMhutdOQn F e Un1t and any personnel re ui er esse~A- - '-during a fire e Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, hea]th physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be 'author ized by the Plant Manager or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individ-ual overtime shall be reviewed monthly by the Plant 'Hanager or his-designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

g. -The Operations Supervisor shall hold a Senior Reactor Operator license.

SHIFT TECHNICAL AOVISOR 6.2.3 The Shift Technical Advisor function is to provide on shift advisory technical support in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

ST. LUCIE - UNIT 1 6-'6 Amendment No. Qo

AOHINISTRATI VE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the FRG Chair man to serve on a temporary basis; however, no more than two alternates shall participate as voting members in FRG activities at any one time.

MEETING FRE UENCY 6.5.1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.

QUORUM 6.5.1.5 The quorum of the FRG necessary for the performance of the FRG respons-ibility and authority provisions of these Technfcal Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Facility Review Group shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specfffcatfon 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determfned by the Plant Manager to affect nuclear safety.

b. Review of all proposed tests and experfments that affect nuclear safety.

C. Review of all proposed changes to Appendix A Technical Specifications.

d. Review of all proposed changes or modfffcatfons to unit systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications, fncludfng the preparatfon and forwarding of reports covering evalua-tfon and recoamendatfons to prevent recurrence to the Presfdent-Nuclear Ofvfsfon and to the Chafrman'of the Company Nuclear Review Board.

f. Review of all REPORTABLE EVENTS.

g. Review of unit operations to detect potential nuclear safety hazards.

Performance of special reviews, investfgatfons or analyses and reports thereon as requested by the Plant Manager or the Company Nuclear Review Board.

ST. LUCIE - UNIT 1 6-7 Amendment No. yy. ~ N. 'O7

AOHINISTRATI VE CONTROLS Review of the Security Plan and implementing procedures and submittal of recottmtended changes to the Company Nuclear Review Board.

j. Review of the Emergency Plan and implementing procedures and submittal of recomnended changes to the Company Nuclear Review Board.

k. Review of every unplanned on-site release of radioactive material to the environs including the preparation of reports covering evaluat1on, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the President - Nuclear Division and to the Coepany Nuclear Review Board.

1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION NNUAL and RAGNSTE TREATMENT SYST95.

m. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed fn bypass since the last FRG meeting.

n AUTHORITY RcEoacE.u> ok t4cE acro 'Pro&o4o~lroqrr ~ a~8 cwpieo e~4~g Ecroarccckcarrccg acccE <o4cacclolca~ r+ocaac cac<~ccg ogca<<gcccs*+cE Cop)occambloc(cattr RRcaIeq Boo~.

a. Recoaeend fn writing to the Plant Nanager, approval or disapproval of items considered under Specifications 6.5.1.6.a through d above.

b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6 a through e above constitutes an unreviewed safety question.

C. Provide written notification within 2l hours to the President-Nuclear Division and the Company Nucleai Review Board of disagreement between the FRG and the Plant Nanager; however, the Plant Nanager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 6.5.1.8 The Facility Review Group shall maintain written minutes of each FRG meet1ng that, at a minimum, document the results of all FRG activities performed under the responsibility and authority provisions of these Technical Soeeificatfons. Copies shall be provided to the Pres1dent-Nuclear Division and the Chairman of the Company Nuclear Review Board.

ST. LUCIE - UNIT 1 6-8 Amendment No. Q.T8D U. 197

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendment Fire Protection Technical S ecifications ATTACHMENT 2 St. Lucie Unit 2 Marked-up Technical Specification Pages UNIT 2 TS PAGES License Condition 2.C. (13) 3/4 3-44 3/4 3-45 3/4 3-46 B 3/4 3-3 3/4 7-30 3/4 7-31 3/4-7 32 3/4 7-33 3/4 7-34 3/4 7-35 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 B 3/4 7-7 B 3/4 7-8 6-2 6-9

NPF-16 Page 4 U dated er Amendment 50 dated 5 23 91 5~ DELETED PER AMENDMENT $ 34 DATED SEPTEMBER 13, 1988 6 ~ DELETED PER AMENDMENT f34 DATED SEPTEMBER 13, 1988

7. DELETED PER AMENDMENT f34 DATED SEPTEMBER 13, 1988

8. DELETED PER AMENDMENT 434 DATED SEPTEMBER 13, 1988 9 ~ DELETED PER AMENDMENT 434 DATED SEPTEMBER 13, 1988

10. DELETED PER AMENDMENT $ 41 DATED MAY 17, 1989

11. DELETED PER AMENDMENT f41 DATED MAY 17, 1989

12. DELETED PER AMENDMENT f34 DATED SEPTEMBER 13, 1988 13 'ELETED PER AMENDMENT f34 DATED SEPTEMBER 1 , 1988 14 ~ DELETED PER AMENDMENT $ 34 DATED SEPTEMBER 13, 1988 15 ~ DELETED PER AMENDMENT f3 4 DATED SEPTEMBER 1 3 I 1 988 16 ~ DELETED PER AMENDMENT $ 34 DATED SEPTEMBER 13, 1988

17. DELETED PER AMENDMENT $ 34 DATED SEPTEMBER 13, 1988 18 ~ DELETED PER AMENDMENT f34 DATED SEPTEMBER 13, 1988

19. Unit No. 1 spent fuel may be transferred from the Unit No.

1 spent fuel pool to the Unit No. 2 spent fuel pool, as necessary, until completion of all activities related to the increase in capacity of the Unit No. 1 spent fuel pool to 1706 spent fuel assemblies. Spent fuel assemblies transferred from the Unit 1 spent fuel pool to the Unit 2 spent fuel pool may remain in the Unit 2 spent fuel pool or be transferred back to the Unit 1 spent fuel pool.

D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: St. Lucie Plant Security Plan," with revisions submitted through April 11, 1988; "St. Lucie Plant Training and Qualification Plan, "with revisions submitted through August 8, 1985; and "St. Lucie Plant Safeguards Contingency Plan," with revisions through December 8, 1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

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New Unit 2 Standard License Condition 2.C.(13)

(13) Fire Protection The Licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (The fire protection program and features were'originally described in the Final Safety Analysis Report, and supplemented by Licensee submittals L-82-282 dated July 14, 1982, L-83-89 dated February 25, 1983, L-83-425 dated July 22, 1983, L-83-603 dated December 27, 1983, L-84-347 dated November 28, 1984, L-84-389 dated December 31, 1984, and L-85-72 dated February 21, 1985 for the facility) and as approved in the NRC Safety Evaluation Report Supplement 3 dated April 1983 and supplemented by NRC letter dated December 5, 1986 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

STRUMENTATION FIR DETECTION INSTRUMENTATION LIMITIN CONDITION FOR OPERATION 3.3.3.7 As minimum, the fire detection instrumentation for eac fire detection zon shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: henever equipment protected by the fire det tion instrument is required to be OPERABLE.

ACTION:

ao With any, but ot more than one-half the-tot 1 in any fire zone, Function A fir detection instruments show in Table 3.3-11 inoper-able, restore th inoperable instrument(s -to OPERABLE status within 14 days or within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establ sh a fire watch patrol to inspect the zone(s) with the inoperabl instrument(s) at least once per hour, unless the nstrument(s) is located inside the containment, then inspect that con inment zone y least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperjture at least once per hour at the locations listed in Specific tion 4.6.1.5.

With more than one-half of e Function A fire detection instruments in any fire zone shown in Ta <e 3.3-11 inoperable, or with any Func-tion B fire detection instr ments shown in Table 3.3-11 inoperable, or with any two or more a acentgfire detection instruments shown in Table 3.3-11 inoperable, ithin l>(our establish a fire watch patrol to inspect the zone(s) ith the inoperable instrument(s) at least once per hour, unless he instrument( ) is located inside the contain-ment, then inspect t at containment zo e at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the cont; inment air temperat e at least once per hour at the locations usted in Specification .6.1.5.

c. The provisions f Specifications 3.0.3 and 0.4 are not applicable.

SURYEILLANCE RE UIREM TS 4.3.3.7.1 Each of he above required fire detection instrum ts which are accessible durin plant operation shall be demonstrated OPERA E at least once per 6 months by erformance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not ccessible during plant operation shall be demonst ted OPERABLE by the perfor ance of a CHANNEL FUNCTIONAL TEST during each COLD UTDOWN exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless performed in the previous 6 months.

4.3.3.7. The NFPA Standard 720 supervised circuits supervision assoc ated with th detector, alarms of each of the above required fire detection instr ents shall be demonstrated OPERABLE at least once per 6 months.

4.3 3.7.3 The nonsupervised circuits, associated with detector alarms, bet een tl) instrument and the control room shall be demonstrated OPERABLE at least dhce per 31 days.

ST. LUCIE - UNIT 2 3/4 3-44

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TABLE 3.3-11 FIRE DETECTION INSTRUMENTS IN TRUMENT LOCATION TOTAL NUMBER OF INSTRUMENTS*

HEAT SMOKE (x/y) ~(X W)

REACTOR UXILIARY.BUILDING ZONE-1A REA QOR AUX. BLDG. EL. 0.50 6/0 ZONE-2A REAC1'Og AUX. BLDG. EL. 0.50 4/0 ZONE-3A REACTORiAUX. BLDG. EL. 19.50 6/0 ZONE 4A REnCTOR QUXi BLDG ~ EL' 1.9 ~ 50 2/0 5/0 ZONE-5A REACTOR AQ . SLOG. EL. 19.50 8/0 ZONE-6A REACTOR AUX. BLDG. EL. 43.00 5/0 ZONE"7A REACTOR AUX. LOG. EL. 43.00 7/0 ZONE-8A REACTOR AUX. 8 G. EL. 62.00 1/0 6/0 ZONE-9A REACTOR AUX. BLDG. EL. 43.00 2/0 ZONE-10A REACTOR AUX. BLOK, EL. 43.00 2/0 ZONE-12A ELECT. PEN. ROOM E5 19.50 3/0 ZONE"18 REACTOR AUX. BLDG. EL. 0.50 6/0 ZONE-28 REACTOR AUX. BLDG. EL. 0,.50 5/0 ZONE"38 REACTOR AUX. BLDG. EL. 19>>50 6/0 ZONE-48 NSCP-1 BEC. AUX. BLDG. ELi43.0 1/0 ZONE-58 REACTOR AUX. BLDG. EL. 19.50 6/0 ZONE-68 REACTOR AUX. BLDG. EL. 43.00 4/0 ZONE-78 REACTOR AUX. BLDG. EL. 43.00 6/0 ZONE-88 REACTOR AUX. BLDG. EL. 62~00 5/0 ZONE-98 REACTOR AUX. BLDG. EL. 43.00 2/0 ZONE-108 REACTOR AUX. BLDG. EL,/43.00 2/0 ZON >>128 ELECT. PEN. ROOM EL.z'f9.50 4/0 ZONE-1F FAN ROOM EL. 43.00 0/2

. ZONE-2F CABLE LOFT EL. 19.50 0/26 ZONE-3F IODINE REMOVAL/WASTE GAS/

HALLWAYS EL. 0.50 0/15 ZONE-4F 8 ELECTRICAL P AETRATION ROOM EL. 19.50 0/2 EL. 19. 50 /

ZONE-5F A ELECTRICAL PENETRATION ROOM ZONE-6F CABLE SP EADING ROOM EL. 43.00 0/1 0/9

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FUEL HANDLING,BUILDING ZONE-20A FUgL HANDLING BLDG. EL. 19.50 1/0 ZONE-21A OEL HANDLING BLDG. EL. 48. 00 3/0 ZONE-208 FUEL HANDLING BLDG. EL. 19.50 0 ZONE"2 FUEL HANDLING BLDG. EL. 48.00 2 DIES L GENERATOR BUILDING NE-22A DIESEL GEN. BLDG./0.0. STORAGE TANK 2/2 2/0 ONE-228 DIESEL GEN. BLDG./0.0. STORAGE TANK 2/2 2/0 ST. LUCIE - UNIT 2 3/4 3-45 Amendment No. 45

TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS INSTR UMEN LOCATION TOTAL NUMBER F INSTRUMENTS" HEAT SMOKE

~xy) ~(x Y)

SAFETY RELATED PUMPS ZONE-17A COMPONENT OLING AREA 4/0 ZONE-18A INTAKE COOL G WATER PUMP AREA 1/0 ZONE-19A STEAM TRESTL REA-AUX.

FEEDWATER PUMP 2/0 ZONE-178 COMPONENT COOLING, AREA 2/0 ZONE-18B INTAKE COOLING WATER PUMP AREA /0 ZONE-19B STEAM TRESTLE AREA-AUX.

FEEDWATER PUMP 2/0 TURBINE BUILDING/SWITCHGEAR ROOM ZONE-16A TURBINE BLDG. SWITCHGEAR ROO 3/0 ZONE-16B TURBINE BLDG. SWITCHGEAR ROOM 3/'0 CONTAINMENT ZONE-11A ANNULUS 1/0 ZONE-13A REACTOR TUNNEL. BELOW E . 18.00 2/0 ZONE-14A REACTOR EL. 18.00 5/0 ZONE-15A REACTOR EL. 45.00 2/0 4/0 ZONE-llB ANNULUS 1/0 ZO."IE-13B REACTOR TUNNEL BESOM EL. 18.00 1/0 ZONE-14B REACTOR EL. 18.00% 5/0 ZOiVE-15B REACTOR EL. 45.00 2/0 5/0 (x/y): x is number of early warning fire detection and notification only instruments.

y is number of actuation of fire suppression systems and early warning notification instruments.

T fire detection instruments located within the containment are not required o be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

ST. LUCIE - UNIT 2 3/4 3"46 Amendment No.45

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3. 3. 6 ACCIDENT MONITORIHG IHSTRUMENTATIOH h

The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide l. 97, "Instrumentation for Light-Water Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and HUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

~ 4. 3. 3. 7 FIRE DETECTION INSTRUMENTATION OPER I*- of the fire detection instrumentation ensures that adequ warning capabili 'ailable for the prompt detection of fires.

capability is required 1n to detect and locate fires in t m early stages. Prompt detection of fire 'educe the pote for damage to safety-related equipment and is an integ a= e n the overall facility fire protection program.

In the event that a n of the fire detection instr m rC~tion is inoperable, the est s ment of frequent fire patrols in the affected eas is required ovide detection capability unti 1 the inoperable instrumen tjon is r ed to OPERABILITY.

3/4. 3. 3. 8 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water"Cooled Reactors," May 1981.

3/4.3.3.9 RADIOACTIVE LI UID'FFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/

trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

ST. LUCIE - UNIT 2 B 3/4 3-3

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PLANT SYSTEMS 3/8. I 11 .FIRE SUPPRESSION SYSTEMS FIR SUPPRESSION WATER SYSTEM" LIHITI G CONOITION FOR OPERATION 3 .7.11.1 he fire suppression water system shall be OPERABLE ith:

a. Two fire suppression pumps, each with a capacity of 2350 gpm, with b.

the j discharge aligned to the fire suppressio header, Separa e water supplies, each with a minim contained volume of 300,000 allons, and

c. An OPERABL( flow path capable of taking suction from the city water storage tang lA and the city water st~orage tank 1B and transferring the water th>ough distribution pipigg with OPERABLE sectionalizing control or is lation valves to thegjard hydr ants, the last valve ahead of the w ter flow alarm device on each sprinkler or hose standpipe requi,yd to be OPERABLE per Specifications 3..7. 11.2, 3.?.11. 3 and 3.7>Q. 4.

APPLICABILITY: At al 1 times; ACTION:

With one pump and/or on water supply inoperable, restore the inoperable equipmen to ERABLE status within 7 days or prepare and submit a Speci'al Repor to the Conmission pursuant to Speci-fication 6.9.2 w>ithin the negt 30 days outlining the plans and procedures to be used to res%ore the inoperable equipment to OPERABLE status or to provide%n alternate backup pump or supply.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b. With the fire suppression ~ater sys gm otherwise inoperable, establish a backup fire suppression 4 ter system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This system is shared between St. Lucie Units 1 and 2.

ST. LUCIE - UNIT 2 3/4 7-30 Amendment No. pA 18

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PL NT SYSTEt1S SURVE LLANCE REOUIREt1ENTS 4.7. 11. 1 The fire suppression water system shall be demonstrated OP RABLE:

a. A least once per 7 days by verifying the contained wa er supply vo ume.

b. At 1 ast once per 31 days on a STAGGEREO TEST BASIS by starting each elect <ic motor driven pump and operating it for at least 15 minutes on recirculation flow.

C. At least nce per 31 days by verifying that each valve (manual, power-oper ted or automatic) in the flow ath is in its correct position.

At least once er 12 months by perfor, ance of a system flush.

e. At least once pe 12 months by cy>cling each testable valve in the flow path through at least one complete cycle of full. travel.

At least once per. 18 months pb performing a system functional test which includes simula ed automatic actuation of the system throughout its operating sequence, and:

Verifying that eac utomatic valve in the flow path actuates to its correct position,

2. Verifying tha, each pump develops at least 2350 gpm at a system head of 232 feet,

3. Cycling e ch valve in the fl w path that is not testable during plant op'eration through at le st one complete cycle of full travel)'nd Verifying that each fire suppresssgn pump starts (sequentially) to maintain the fire suppression wa%er system pressure greater

@an or equal to 85 psig.

g. A least once per 3 years by performing a flo test of the system in

'ccordance with Chapter 5, Section 11 of the F> e Protection Handbook, 14th Edition, published by the Nationa Fire Protection Association.

ST. LUCIE " UNIT 2 3/4 7-31

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P5LNT SYSTEMS SPRI KLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 The ollowing sprinkler systems shall be OPERABLE:

1. Fire Zone 8 " Diesel Generator Building 2A

2. Fire Zon~9 - Diesel Generator Building 2B

3. Fire Zone>19 - RAB East Hallway and Miscellaneou Equipment Areas

4. Fire Zone 2 - RAB East-West Common Hallway

5. Fire Zone 22 " RAB Electrical Penetration Are'a

6. Fire Zone 23 RAB Electrical Penetration F~ea

7. Fire Zone 39 - gAB HYAC Equipment Room

8. Fire Zone 51 - RAB Ceiling and Hallways 9 Fire Zone 52 - Cable Spreading Room APPLICABILITY: Whenever equipment protect by the sprinkler system is required to be OPERABLE.

ACTION:

a~ With one or more of the abo e required sprinkler systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establishpf coqtinuous fire watch with backup fire suppression equipmentgor those areas in which redundant systems or components could be dimaged; fo other areas, establish an hourly fire watch patrol.

b. The provisions o. Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMEN S 4.7. 11.2 Each of he above required sprinkler systems shall be demonstrated OPERABLE:

a. At 1 ast, once per 31 days by verifying that e ch valve (manual, pow r-operated, or automatic) in the flow pathos in its correct po ition.

b. t least once per 12 months by cycling each testabl valve in the flow path through at least one complete cycle of ful travel.

ST. LUCIE - UNIT 2 3I4 7-32 Amendment No. 45

A PEDANT SYSTEMS SVRYEIL ANCE REOUIREHENTS (Continued)

C. At le st once per 18 months:

l. By performing a system functional test wh'ich includes simulated automa%.'c actuation of the system, ands.

a) Yerify. g that the automatic@Salves in the flow path actuate o their correct positions on a thermal test signal, and b) Cycling each valve iy the flow path that is not testable during plant oper ion through at least one complete cycle of full travel.

2. By a visual inspec ion of each prinkler system to verify its integrity, and

3. By a visual >i spection of each sprink e 's spray area to verify the spray pattern is not obstructed.

ST. LUCIE " VNIT 2 3/4 7-33

s RLANT SYSTEMS FI E HOSE STATIONS LIHI'MG CONOITION FOR OPERATION 3.7. 11.3 he fire hose stations shown in Table 3.7-4 shall be OPE ABLE.

APPLICABILIT " 34hhnever equipment in the areas protected by t e fire hose stations is re ui red to be OPERABLE.

ACTIOIi:

a ~ Mith one o more of the fire hose stations sho n in Table 3.7-4 inoperable, rovide gated wye(s) on the nea>est OPERABLE hose station(s). e outlet oi the wye shall b~r'connected to the standard length<of hose provided for the pose station. The second outlet of the wy shall be connected toff length of hose sufficient to provide covera for the area left unprotected by the inoperable hose station. '<</her it can be demonstrated that the physical routing of the iire ose would resulg in a recogni.zahle hazard to operating technicians, lant equip ent, or the hose itself, the fire hose shall be stored in a roll a the out',et of the operable hose station. Signs shall be qounte) above the gated wye(s) to identify the proper hose to use. 7'bove action shall be accomplished within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperabl'e fire hose is the primary means of fire suppression; otherwise oute the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7. 11.3 Each of the fir hose stations shown in able 3.7-4 shall be demonstrated OPERABLE: I At least once per 31 days by visual inspect'on of the stations accessible+during plant operation to assure a~ l required equipment is at the~station.

For a l fire hose stations located in the turbine building, at least once er 12 months by:

1. Partially opening each hose station valve to vers y valve OPERABILITY and no flow blockage.

2. Conducting a hose hydrostatic test at a pressure of $ 0 psig or at least 50 psig above maximum fire main operating pres ure, whichever is greater.

ST. LUCIE - UNIT 2 3/4 7"34

PLANT SYSTEMS SURVEIL FACE REQUIREMENTS C. At least. once per 18 months by:

1. Visua~nspection of the stations not acce sible during plant operation to assure all required equ~i ment is at the station.

2. Removing the hose for inspection anEre-racking, and

3. Inspecting all gaskets and rep1acing any degraded gaskets in the couplings.

For all fire hose stations no 'located in the turbine building, at least once per 3 year s~by:

1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2. Coyd cting a hose hydrostatic test at%a pressure of 150 psig or at" least 50 psig above maximum fire mai"n operating pressure, whichever is .greater.

ST. LUCIE - UNIT 2 3/0 7-35

TABLE 3.7-4 FIRE HOSE STATIONS ATIO ELEVATION HOS RACK 0 A. Hose tations (Turbine Building)

l. Op rating Floor (northeast corner) HS-15-4

2. Oper ting Floor (southeast corner) HS-15-10

3. Operat'ng Floor (middle east side) HS" 15-7 B. Hose Stations (Reactor Auxiliary Building)

1. 62 ft leve east wall entrance HS-15-44

2. 62 ft level est wall entrance HS-1S-4S

3. 62 ft level we t wall entrance to HEY~room HS" 15-46

4. 43 ft level S.E. corner cable sprea ang room HS-15" 36

5. 43 ft level south ll of H8V roo HS-15-37

6. t 43 f 1 ave 1 cab 1 e spr di ng ro m HS-15-31

7. 43 ft level southwest co ner of "S" switchgear room near door HS-15-42

8. 19.5 ft level east end o ea t-west hall HS-15-38 19.5 ft level middle o east-w st hall HS-15-4.0

10. 19.5 ft level south nd of north south hall HS-15-33 19.5 ft level entr nce hall on sou wall HS-15-34

12. -0.5 ft level ea t end of hall HS-15"41

13. -0.5 ft level South wall of hall HS-15"28

14. -0.5 ft lev west end of hall HS-15-43 C. Hose Stations Reactor Containment Building)

1. RCB at 3 ft level (near stairway no. 3) HS-15-47

2. RCB 45 ft level (near stairway no. 1). HS-15"48

3. RC at 45 ft level (near stairway no. 2) HS-15-54

4. B at 62 ft level (near stairway no. 3) 5-15-49

0. Ho's Station (Fuel Handling Building) ft level northwest corner HS-15~ 5 ST. LUG IE - UNIT 2 3/4 7-36 Amendment No. 45

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NT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES LIMITING'ONDITIONFOR OPERATION 3.7. 11.4 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7-5 s all be OPERABLE.

APPLICABILITY: whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.

ACTION:

a. With one or more of the yard fire hydrants or associated hydrant hose houses shoyn in Table 3.7"5 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> have sufficient additsonal lengths of 2,1y/2 inch diameter hose located in an adjacent OPERABLE hydrant hose, house to provide service to the unprotected area(s)/if the inoperable fire hydrant or associated hydrant hose house is/~the primary means of fire suppression; otherwise provide the additiona'1 hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. The provisions of Specifi't ons 3.0.3 and 3.0.4 are not applicable.

/

SURVEILLANCE RE UIREMENTS 4.7.11.4 E ach of the yard fire h drants and associated hydrant hose houses shown in Table 3.7-5 shall be demonstrate OPERABLE:

a. At least once per 31/days by visualyinspection of the hydrant hose house to assure allyrequired equipma t is at the hose house.

b. At least once per, 6 months by visuall inspecting each yard fire hydrant and ver~iffying that the hydrant~ arrel is dry and that the hydrant is not~damaged. ~

At least once per 12 months by: ~

1. Cond cting a hose hydrostatic test at a pr~essure of 150 psig or atJ1east 50 psig above maximum fire main operating pressure, w ichever is greater.

2. Inspecting all the gaskets and replacing any raded gaskets in the couplings.

3. Performing a flow check of each hydrant to verify ~ts OPERABILITY.

.ST. LUCIE " UNIT 2 3/4 7-37 Amendment No. 45

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TABLE 3. 7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE. HOUSES LOCAT GN HYDRANT NUMBER RCB NE FH¹6 RCB FH¹7-CST FH¹9 '

CCMB FH¹20 DGB(2A) FH¹21'-

DGB(2B) FH¹22 RAB

'H¹23 Intak S ructure SE FH¹25 +

ST SW F ¹26 ST. LUCIE - UNIT 2 3/4 7-38

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P g NT SYSTEMS 3/4.. 12 FIRE RATEO ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.12 All pire rated assemblies (walls, floor/ceilings, an/ other fire barriers) separating safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire/area and all sealing devicesWjn fire rated assembly penetrations (fire~doors, fire dampers, cable, piping, an ventilation duct penetration seals) Eall be OPERABLE.

APPLICABILITY: At a l times.

ACTION:

a~ With one or moreof the above required fire rated assemblies and/or sealing devices spoperable, within lrhour either establish a continuous fire watch on at least ona side of the affected assembly, or verify the OPERACBILITY of the fire detectors on af leas.t one side of the inoperable assembly and establish an hourly fire watch patrol.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~ ~ ~ ~

SURVEILLANCE RE UIREMENTS 4 7 12 1 At least once per/18 months thereabove required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by:

a. Performing a vipual inspection of theh,exposed surfaces of each fire rated assembly~

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

c. Performing a visual inspection of at least 10K' each type of sealed penetra'tion. If apparent changes in appearance oq abnormal degrada-tions/are found, a visual inspection of an additional ION of each type)of sealed penetration shall be sade. This inspection process sha)'1 continue until a 10K sample with no apparent ch'anges in appear ance or abnormal degradation is found. Samples shall be selected s4ch that each penetration seal will be inspected every 5 years.

ST. LUCIE - UNIT 2 3/4 7-39 Amendment No. 25

BAHT SYSTE SURVEI hHCE REQUIREMENTS Continued) 4.7.12.2 Each o'/the above'equired fire doors shall be v~e-ified OPERABLE by inspecting the auYogatic hold-open, release and closing~mechanism and latches at least once per 6 onths, and by verifying:

a. That each unlocked fire door without~~e'lectrical 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 old-open and release mechanisms are free of ohstructions at least nce 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 dieted fire oor is closed at least once per 7 days.

4.7. 12.3 At least once per 18 months, perform functional test of each automatic hold-open and release mechanism.

ST. LUCIE - UNIT 2 3/4 7-40

PLANT SYSTEMS BASES SNUBBERS (Continued)

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions 'and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc. . .). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

3/4. 7. 10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. ~ Those sources which are frequently handled are required to be tested more often than those which are not. 'ealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring ot boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.

4. 7. 11 FIRE SUPPRESSION SYSTEMS The~~ERABILITY of the fire suppression systems ensures that adequate fire suppressiqy capability is available to confine and extinguisf fires occurring in any+ortion of the facility where safety-related equipment is located. The fire suppression system consists of the-water system, sprinklers, fire hose stations, and yard~fire hydrants. The.col'lective capability of the fire suppression systems is adequate to minimize potential damage to safety-related equipment and is a major element'n the facility fire protection program In the event that portionsof 'the fire suppression systems are inoperable, alternate backup-.fire fighting equipment is required to be made available in the affected~areas until the inoperable equipment is restored to service. Mhen the inoperable fire fighting equipment .is intended for use as a backup means of fi.re suppression, a longer period of time is al:lowed to provide an alternate means of fire fighting than is the primary means of fire suppression.

if the inoperabl'e~equipment The Surveillance Requirements provide assurance that the minimum OPFPABILITY requirements of the fire suppression systems are met.

ST. LUCIE " UNIT 2 B 3/4 7"7

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PLANT SYSTEMS BASES

~IRE SUPPRESSION SYSTEMS Continued) n -~e event the fire suppression water system becomes inoperable, immediate correc'tive measures must be taken since this system provides he major fire suppression capability of the plant.

3/4.7.12 FIRE RATED ASSEMBLIES The OPERABILITY of the fire barrier and=barrier penetrations ensures that fire damage will be limited. ~Tese design featur'es=minimize the possibility of a single fire involv~in =more than one fire area prior-to-detection and extinguishment. The-fire barriers, fire barrier penetrations for-conduits, cable trays ~an ~piping, fire dampers, and fire doors are periodically i spected to veri f ~their OPERABILITY.

ST. LUCIE " UNIT 2 8 3/4 7"8

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AD.IINISTRATIVE CONTROLS 6 2 ORGANIZATION (Conti nued )

V')IT SiAFF 5.2.2 The unit organization shall be subject to the following:

a..Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. 4t least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is'in

!<O0E 1, 2, 3, pr 4, at least one licensed Senior Reactor Operator shal 1 be in the control room.

c ~ A health physics technician'hall be on site when fuel is in the reactor.

d. 'll CORE ALTERATIONS shall be observed by a licensed ooerator and bilityy supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. The SRO 'in charge of fuel handling normally supervises from the control room and has the flexi-to directly supervise at either the refueling deck or the spent fuel pool.

e.~mteMge Brigade ~f at least five members shall be ma~fained onsite at all ti~me . ~pe Fire Brigade shall no~~cTude the Shift Supervisor, the STA, nor theMMa~other~emmmers of the minimum shift crew necessary~tor~satfe shutdown of the uni't and~apy~ersonnel recyared for other essential fun tions during a fire emergency.

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of over time. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

health physics technician " e less than 4The d B  :

a4 composition may be the minimum requirement for a per o of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to the required positions.

fill ST. LVCIE - UNIT 2 6-2 Amendment No. 2g

ADMINISTRATIVE CONTROLS MEETING FRE UENCY 6.5. 1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.

UORUM 6.5. 1.5 The quorum of the FRG necessary for the performance of the FRG responsibtlity and authorfty provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The.Facility Review Group shall be responsfble for:

a. Review of (1) all procedures required by Specfffcatfon 6.8 and changes thereto, (2) all programs required by Specfffcatfon 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.

b. Revtew of all proposed tests and experfmnts that affect nuclear safety.

C. Review of all proposed changes to Appendfx A Technfcal Specifications.

Review of all proposed changes or oodfffcatfons to unit systeas or equipaent that affect nuclear safety.

Investfgatfon of all violations of the Technical Spectftcatfons, includfng the preparation and forwardfng of reports covering evalua-tion and recoamendattons to prevent recurrence to the President-

'Nuclear Division and to the Chafrman of the Company Nuclear Review Board.

Revtew of all REPORTABLE EVENTS.

g. Review ~f unit operations to detect potential nuclear safety hazards.

h. Perfotsance of special revfews, inveitfgatfons or analyses and reports thereon as requested by the Plant Nanager or the Coapany Nuclear Review Board.

i. Revtew of the Security Plan and tsplesentfng procedures and submittal of recommended changes to the Company Nucleal Review Board.

j. Review of the Esergency Plan and impleaentfng procedures and subefttal of recommended changes to the Coapany Nuclear Revfew Board.

ST. LUCIE - UNIT 2 6-8 Amendment No. i8. ~~'<7

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0 ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the President-Nuclear Ofvisfon and to the Company Nuclear Review Board.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE OOSE CALCULATION MANUAL and RAOWASTE TREATMENT SYSTEMS.

Review and documentatfon of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defectfve protection channels of rocess variables aced i ,ass sg c ast FRG me ting.

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6.5.1.7

~<4~~4'4 w~ <"4'm< @f e fee'co~~co geg e lkewgu The Facil f ty Review Group shall: <4~M~ 4~~>~ ~4'<W~ @~~,

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a. Recommend in writing to the Plant Manager approval or dfsapp 1 items considered under Specifications 6.5.1.6a. through d. and m.

above.

b. Render determinations in wrfting with regard to whether or not each

~

item considered under Specifications 6.5.1.6a. through e. above constitutes an unreviewed safety question.

c~ Provide wrftten notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> te the Presfdent-Nuclear Division and the Company Nuclear Revfew Board of disagreement between the FRG and the Plant Manager; however, the Plant Manager shall have responsibility for resolutfon of such disagreements pursuant to Sped)ffcatfon 6.1.1 above.

RECORDS 6.5.1.8 The Facility Review Group shall maintain wrftten minutes of each FRG meeting that, at a mfnimum, document the results of all FRG actfvftfes performed under the responsibility and authority provisions of these technfcal speciffca-tions. Copies shall be provided to the Presfdent - Nuclear Ofvfsfon and the Chairman of the Company Nuclear Review Board.

6.5.2 COMPANY NUCLEAR REVIEW BOARD CNRB FUNCTION 6.5.2.1 The Company Nuclear Review Board shall function to provide independent review and audit of desfgnated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering C. chemfstry and radiochemistry

d. metallurgy ST. LUCIE - UNIT 2 6-9 Amendment No.45. Z$ . "7'

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendment Fire Protection Technical S ecifications ATTACHMENT 3 UNIT 1 SAFETY ANALYSIS Introduction Generic Letter 86-10 requested that licensees incorporate the NRC approved Fire Protection Program in their Updated Final Safety Analysis Reports. Generic Letter 86-10 encouraged licensees, upon completion of this program, to apply for an amendment to their operating licenses (1) to replace current license conditions regarding fire protection with a new standard condition and (2) to remove unnecessary fire protection Technical Specifications (TS).

Generic Letter 88-12 issued additional guidance for the preparation of a license amendment request to implement Generic Letter 86-10.

Discussion Generic Letter 88-12 provided the elements a licensee should include in a license amendment request to remove fire protection requirements from TS. The five elements are:

(1) The NRC approved Fire Protection Program must be incorporated into the UFSAR and submitted with the certification required by 10 CFR 50.71(e)(2), as requested by Generic Letter 86-10.

(2) The Limiting Conditions for Operation (LCO) and Surveillance Requirements associated with fire detection systems, fire suppression systems, fire barriers, and administrative controls that address fire brigade staffing could be relocated from the TS.

(3) The operational conditions, remedial actions, and test requirements presently included in the TS for these systems, as well as the fire brigade staffing requirements, shall be incorporated into the Fire Protection Program.

(4) The standard fire protection license condition in Generic Letter 86-10 must be included in the license.

(5) The Administrative Controls section of the TS shall be augmented to support the Fire Protection Program.

Safet Anal sis (1) Amendment 5 of the UFSAR incorporated the St. Lucie Fire Protection Program, including the fire hazards analysis and major commitments that form the basis for the NRC approved

I II J '0%i 0

Fire Protection Program, into the UFSAR. Amendment 5 of the UFSAR was submitted under 10 CFR 50.71(e)(2) in January 1987.

(2) The LCO and Surveillance Requirements associated with the fire protection program are being relocated by this proposed license amendment to appropriate plant procedures.

(3) The operational conditions, remedial actions, and test requirements included in the TS for these systems have or will be incorporated into the Fire Protection Program and program implementing procedures by this proposed license amendment.

Each item of, this element is addressed below.

(4) The standard license condition is incorporated by this proposed license amendment. This element is discussed below.

(5) The Administrative Controls section of the TS is being augmented to support the Fire Protection Program. The requirement for Facility Review Group review is being added by this proposed license amendment and is discussed below. TS section 6.8 "Procedures and Programs" currently includes the suggested requirement in TS section 6.8.1.f.

(6) In accordance with Generic Letter 86-10 paragraph E and 88-12, the Special Report requirements of the LCO Action Statements for fire protection impairments are being replaced by the standard requirement to report deficiencies in the Fire Protection Program which meet the criteria of 10 CFR 50.72 and 10 CFR 50.73. Other conditions which represent deficiencies of this program and are not encompassed by the above reporting criteria will be evaluated to determine the appropriate corrective action.

The proposed changes to the St. Lucie Unit 1 Operating License and Technical Specifications are discussed below:

Item: License Condition 2.C.(3)

Action: This amendment proposes to delete License Condition 2.C.(3) and replaced shown it with the standard license condition as in Generic Letter 86-10, Section F as recommended by Generic Letter 88-12.

Safety Analysis: The previous License condition 2.C.(3) required implementation of modifications and evaluations to the plant as a result of the NRC's Fire Protection Safety Evaluation, dated August 17, 1979. This proposed change to the Unit 1 Operating License is administrative only and is in accordance with the Generic Letter, 88-12 guidelines for incorporating the Fire Protection Program into the Updated Final Safety Analysis Report. This change ensures that the administrative controls for the St. Lucie Fire Protection Program and implementing procedures will be equivalent to those for other plant programs that are implemented by license

1 i iL II t

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condition. Since the existing requirements have been retained, no safety implications are involved with this change.

2 ~ Item: 3/4.3.3.7 Fire Detection Instrumentation TS Pages 3/4 3-37, 3/4 3-38, 3/4 3-39, 3/4 3-40 and B 3/4 3-3.

Action: This amendment proposes to delete Technical Specification 3/4 3.3.7 and its Bases in their entirety.

Safety Analysis: The TS 3/4.3.3.7 Fire Detection System requirements have been relocated into the Updated Final Safety Analysis Report and/or the St. Lucie Fire Protection Program Procedures. The Fire Detection System is described in UFSAR Appendix 9.5A. section 3.5 and the fire detectors listed in TS Table 3.3-10 are listed in UFSAR Table 9.5A-11. The LCO and Action Statements of TS 3.3.3.7 will be incorporated into appropriate plant procedures. The TS Surveillance Requirements of TS 4.3.3.7 are included in the fire protection program procedures for scheduling periodic tests and reports.

3. Item: 3/4.7.11 Fire Suppression Systems TS Pages 3/4 7.40, 3/4 7-41, 3/4 7-42, 3/4 7-43, 3/4 7-44abcd, and B 3/4 7-7.

Action: This amendment proposes to delete Technical Specification 3/4.7.11 and its Bases in their entirety.

Safety Analysis: The TS 3/4.7.11 Fire Suppression Systems requirements have been incorporated into the Updated Final Safety Analysis Report and/or the St. Lucie Fire Protection Program Procedures. The fire suppression water system is described in UFSAR Appendix 9.5A. section 3.1, the standpipes and hose stations are described in section 3.2, and the automatic fire suppression systems are described in section 3.3. The 'minimum required fire hose stations listed in TS Table 3.7-3 are annotated in UFSAR Table 9.5A-6. The yard hydrants and associated hydrant hose houses listed in TS table 3.7-4 have been incorporated in UFSAR table 9.5A-12. The sprinkler systems required by TS 3.7.11.4 are incorporated in UFSAR Section 9.5A.3.3.2(b). The LCO and Action Statements of TS 3.7.11 will be incorporated into the appropriate plant procedures.'he TS Surveillance Requirements of TS 4.7.11 are included in the fire protection program procedures for scheduling periodic tests and reports.

4 ~ Item: 3/4.7.12 Penetration Fire Barriers TS Pages 3/4 7-45 and B 3/4 7-7.

Action: This amendment proposes to delete Technical Specification 3/4.7.12 and its Bases in their entirety.

Safety Analysis: The TS 3/4.7.12 Penetration Fire Barrier

requirements have been relocated into the Updated Final Safety Analysis Report and/or the St. Lucie Fire Protection Program Procedures. The Penetration Fire Barriers are described in UFSAR Appendix 9.5A. section 3.11 through section 3.14. The LCO and Action Statements of TS 3.7.12 will be incorporated into the appropriate plant procedures. The TS Surveillance Requirements 4.7.12 are included in the fire protection program procedures for scheduling periodic tests and reports.

5. Item: 6.2.2.e. Site Fire Brigade TS Page 6-2.

Action: This amendment proposes to delete Technical Specification 6.2.2.e. in its entirety.

Safety Analysis: The TS 6.2.2.e. fire brigade staffing requirements have been incorporated into the Updated Final Safety Analysis Report Section 7.2 and the St. Lucie Fire Protection Program Procedures. The Fire Protection Program procedures incorporate the staffing, training, and fire drill requirements.

6. Item: 6.5.1.6.n Facility Review Group Responsibilities TS Page 6-8.

Action: This amendment proposes to add TS 6.5.1.6.n. as shown in Generic Letter 88-12, Enclosure 2.

Safety Analysis: This proposed change to the TS is administrative only and is in accordance with 'the Generic Letter 88-12 guidelines for deleting the Fire Protection Technical Specifications. This change ensures that the administrative controls for the St. Lucie Fire Protection Program and implementing procedures will be equivalent to those for other plant programs that are implemented by license condition. Since the existing requirements have been retained, no safety implications are involved with this change.

CONCLUSION The intent of the existing specifications remains intact and provides an equivalent level of protection. This proposed change is administrative in nature, does not adversely affect the ability to achieve and maintain safe shutdown, and has no adverse affect on the public health and safety.

'I I

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendment Fire Protection Technical S ecifications ATTACHMENT 4 UNIT 2 SAFETY ANALYSIS Introduction Generic Letter 86-10 requested that licensees incorporate the NRC approved Fire Protection Program in their Updated Final Safety Analysis Reports. Generic Letter 86-10 encouraged licensees, upon completion of this program, to apply for an amendment to their operating licenses (1) to replace current license conditions regarding fire protection with a new standard condition and (2) to remove unnecessary fire protection Technical Specifications (TS).

Generic Letter 88-12 issued additional guidance for the preparation of a license amendment request to implement Generic Letter 86-10.

Discussion Generic Letter 88-12 provided the elements a licensee should include in a license amendment request to remove fire protection requirements from TS. The five elements are:

(1) The NRC approved Fire Protection Program must be incorporated into the UFSAR and submitted with the certification required by 10 CFR 50.71(e)(2), as requested by Generic Letter 86-10.

(2) The Limiting Conditions for Operation (LCO) and Surveillance Requirements associated with fire detection systems, fire suppression systems, fire barriers, and administrative controls that address fire brigade staffing could be relocated from the TS.

(3) The operational conditions, remedial actions, and test requirements presently included in the TS for these systems, as well as the fire brigade staffing requirements, shall be incorporated into the Fire Protection Program.

(4) The standard fire protection license condition in Generic Letter 86-10 must be included in the license.

(5) The Administrative Controls section of the TS shall be augmented to support the Fire Protection Program.

Safet Anal sis (1) Amendment 2 of the UFSAR incorporated the St. Lucie Fire Protection Program, including the fire hazards analysis and major commitments that form the basis for the NRC approved

V u'l

'~P

Fire Protection Program, into the UFSAR. Amendment 2 of the UFSAR was submitted under 10 CFR 50.71(e)(2) in April 1987.

(2) The LCO and Surveillance Requirements associated with the fire protection program are being relocated by this proposed license amendment to appropriate plant procedures.

(3) The operational conditions, remedial actions, and test requirements included in the TS for these systems have or will be incorporated into the Fire Protection Program and program implementing procedures by this proposed license amendment.

Each item of this element is addressed below.

(4) The standard license condition is incorporated by this proposed license amendment. This element is discussed below.

(5) The Administrative Controls section of the TS is being augmented to support the Fire Protection Program. The requirement for Facility Review Group review is being added by this proposed license amendment and is discussed below. TS section 6.8 "Procedures and Programs" currently includes the suggested requirement in TS section 6.8.1.f.

(6) In accordance with Generic Letter 86-10 paragraph E and 88-12, the Special Report requirements of the LCO'ction Statements for fire protection impairments are being replaced by the standard requirement to report deficiencies in the Fire Protection Program which meet the criteria of 10 CFR 50.72 and 10 CFR 50.73. Other conditions which represent deficiencies of this program and are not encompassed by the above reporting criteria will be evaluated to determine the appropriate corrective action.

The proposed changes to the St. Lucie Unit 2 Operating License and Technical Specifications are discussed below:

1~ Item: License Condition 2.C.(13)

Action: This amendment proposes to delete License Condition 2.C.(13) and replaced it with the standard license condition as shown in Generic Letter 86-10, Section F as recommended by Generic Letter 88;12.

Safety Analysis: The previous Fire Protection License condition 2.C.(13) required implementation of the fire protection program on a schedule specified in section 9.5.1.11(a) and (b) of Supplement No. 3 of the Safety Evaluation Report (SER). That License Condition was deleted by License Amendment 38 dated September 13, 1988. This proposed change to the Unit 2 Operating License is administrative only and is in accordance with the Generic Letter 88-12 guidelines for incorporating the Fire Protection Program into the Updated Final Safety Analysis Report. This change ensures that the administrative controls for the St.

o Lucie Fire Protection Program and implementing procedures will be equivalent to those for other plant programs that are implemented by license condition. Since the existing requirements have been retained, no safety implications are involved with this change.

2 ~ Item: 3/4.3.3.7 Fire Detection Instrumentation TS Pages 3/4 3-44, 3/4 3-45, 3/4 3-46 and B 3/4 3-3.

Action: This amendment proposes to delete Technical Specification 3/4 3.3.7 and its Bases in their entirety.

Safety Analysis: The TS 3/4.3.3.7 Fire Detection System requirements have been relocated into the Updated Final Safety Analysis Report and/or the St. Lucie Fire Protection Program Procedures. The Fire Detection System is described in UFSAR Appendix 9.5A. section 3.5 and the fire detectors listed in TS Table 3.3-11 will be listed in UFSAR Table 9.5A-13. The LCO and Action Statements of TS 3.3.3.7 will be incorporated into appropriate plant procedures. The TS Surveillance Requirements of TS 4.3.3.7 are included in the fire protection program procedures for scheduling periodic tests and reports.

3. Item: 3/4.7.11 Fire Suppression Systems TS Pages 3/4 7-30(

3/4 7 31'/4 7 32'/4 7 33'/4 7 34'/4 7 35'/4 7 36/

3/4 7-37, 3/4 7-38, B 3/4 7-7 and B3/4 7-8.

Action: This amendment proposes to delete Technical Specification 3/4.7.11 and its Bases in their entirety.

Safety Analysis: The TS 3/4.7.11 Fire Suppression Systems requirements have been incorporated into the Updated Final Safety Analysis Report and/or the St. Lucie Fire Protection Program Procedures. The fire suppression water system is described in UFSAR Appendix 9.5A. section 3.1, the standpipes and hose stations are described in section 3.2, and the automatic fire suppression systems are described in section 3.3. The minimum required fire hose stations listed in TS Table 3.7-4 are annotated in UFSAR Table 9.5A-9. The yard hydrants and associated hydrant hose houses listed in TS table 3.7-5 have been incorporated in UFSAR table 9.5A-5. The sprinkler systems required by TS 3.7.11.2 are incorporated in UFSAR Section 9.5A.3.3.2(b). The LCO and Action Statements of TS 3.7.11 will be incorporated into the appropriate plant procedures. The TS Surveillance Requirements of TS 4.7.11 are included in the fire protection program procedures for scheduling periodic tests and reports.

4 ~ Item: 3/4.7.12 Fire Rated Assemblies (Fire Barriers) TS Pages 3/4 7-39,, 3/4 7-40, and B 3/4 7-8."

Action: This amendment proposes to delete Technical

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Specification 3/4.7.12 and its Bases in their entirety.

Safety Analysis: The TS 3/4.7.12 Fire Rated Assemblies requirements, have been relocated into the Updated Final Safety Analysis Report and/or the St. Lucie Fire Protection Program Procedures. The Fire Rated Assemblies are described in UFSAR Appendix 9.5A. section 3.11 through section 3.14. The LCO and Action Statements of TS 3.7.12 will be incorporated into the appropriate plant procedures. The TS Surveillance Requirements 4.7.12 are included in the fire protection program procedures for scheduling periodic tests and reports.

5. Item: 6.2.2.e. Site Fire Brigade TS Page 6-2.

Action: This amendment proposes to delete Technical Specification 6.2.2.e. in its entirety.

Safety Analysis: The TS 6.2.2.e. fire brigade staffing requirements have been incorporated into the Updated Final Safety Analysis Report Appendix 9.5A Section 7.2 and the St.

Lucie Fire Protection Program Pxocedures. The Fire Protection Program procedures incorporate the staffing, training, and fire drill requirements.

6. Item: 6.5.1.6.n Facility Review Group Responsibilities TS Page 6-8.

Action: This amendment proposes to add TS 6.5.1.6.n. as shown in Generic Letter 88-12, Enclosure 2.

Safety Analysis: This proposed change to the TS is administrative only and is in accordance with the Generic Letter 88-12 guidelines for deleting the Fire Protection Technical Specifications. This change ensures that the administrative controls for the St. Lucie Fire Protection Program and implementing procedures will be equivalent to those for other plant programs that are implemented by license condition. Since the existing requirements have been retained, no safety implications are involved with this change.

CONCLUSION The intent of the existing specifications remains intact and provides an equivalent level of protection. This proposed change is administrative in nature, does not adversely affect the ability to achieve and maintain safe shutdown, and has no adverse affect on the public health and safety.

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendment Fire Protection Technical S ecifications ATTACHMENT 5 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves a no significant hazards consideration are included in the Commission s regulation, 10 CFR 50.92, which states that no significant hazards considerations are involved operation of the facility if in accordance with the proposed amendment the would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Each standard is discussed as follows:

(1) 'Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because the changes are administrative in nature.

The proposed changes are in accordance with the guidelines of Generic Letter 88-12 which provide for the removal of the fire protection requirements from the Technical Specifications in four major areas: fire detection systems, fire suppression systems, fire barriers, and fire brigade staffing requirements. The existing administrative control requirements related to fire protection audits would be retained. Additional programmatic requirements have been retained or included in the administrative controls to address the Fire Protection Program equivalent to the requirements for other programs implemented by license condition.

(2) Use of the modified specifications would not create the possibility of a new or different kind of accident from any previously evaluated.

The use of this modified specifications can not create the possibility of a new or different kind of accident from any previously evaluated since the proposed changes do not involve any physical alterations to the facility, any changes to setpoints, or any changes to the operating parameters.

(3) Use of the modified specification would not involve a significant reduction in a margin of safety.

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The proposed changes to the Operating Licenses and Technical Specifications are consistent with the guidelines of Generic letter 88-12, are administrative in nature, and further the goal of Technical Specification improvement as delineated in other NRC policy statements. The proposed changes do not decrease the level of fire safety. The change will provide administrative and operational controls on the fire protection program that are comparable to those for other programs implemented by license condition and also assures an equivalent level of protection.

Based on the above, we have determined that the proposed amendment does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the probability of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety; and therefore does not involve a significant hazards consideration.

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