Text

Proposed Tech Specs Re Fire Protection
	ML17352A204
Person / Time
Site:	Turkey Point
Issue date:	08/17/1993
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17352A203	List: ML17352A201; ML17352A204;
References
	NUDOCS 9308300170
	Download: ML17352A204 (78)
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ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-Up Technical Specification Pages, License Condition 3 G. (DPR-31)

License Condition 3 F. (DPR-41)

Vi xi xviii 3/4 3-47 3/4 3-48 3/4 3-49 3/4 3-50 3/4 3-51 3/4 3-52 3/4 3-53 3/4 3-54 3/4 3-55 3/4 3-56 3/4 3-57 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 7-24 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34 6-2 6-7 B 3/4 3-3 B 3/4 3-4 B 3/4 7-8 9308300179 930817 PDR, ADO'5000250

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U dated throu h Amendment 154 dated 6 15 93 DPR-31 Page 3 Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 154, are hereby incorporated in the license.

The Environmental Protection Plan contained in Appendix B is hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

~Re orts FPL shall issue certain reports to the NRC in accordance with the requirements of the Technical Specifications.

Records FPL shall originate and maintain facility operating records in accordance with the requirements of the Technical Specifications.

Steam Generator Ins ections DELETED Ph sical Securit DELETED Fire Protection g l+Qg IL+ A ~~ ~ )

licensee may proceed with and is required to provide a schedule for to complete the modifications identified in Paragraphs 3. 1. 1 throug . 19 of the NRC's Fire Protection Safety Evaluation, dated Harch 21, for the facility. These modifications are to be completed prio o December 1980. If any modifications cannot be completed on sche the licensee shall submit a report explaining the circumstances toge r with a revised schedule.

In addition, the licensee sh submit the additional information identified in Sections 3. 1 in accordance with the schedule con and 3.

'd the related Safety Evaluation therein. In 'the event these dates for submittal cannot be met, licensee shall submit a report, explaining the circu tances, to er with a revised schedule.

g yg gg g ssr The licensee is required to develop and implement the adm 'strative controls which are consistent with the licensee's le s of August 28 and November 7, 1978 within three months from the da f this amendment.

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L-93-192 XNSERT A G. Fire Protection FPL shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report (FSAR) for Turkey Point Units 3 and 4 and as approved in the Safety Evaluation Report (SER) dated March 21, 1979, and supplements thereto 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.

U dated throu h Amendment 148 dated 1 08 93 DPR-41 Page 5 F. Fire Protection (, I~ $ g~~ % HKR.K)

The licensee may proceed with and is required to provide schedule for and to complete the modifications i ified in Paragraphs 3. 1. 1 through 3. 1. 19 of the NRC's Fire otection Safety Evaluation, dated March 21, 1979 for the ility. These modifications are to be completed prior to D mber 1980. If any modifications cannot be completed on edule the licensee shall submit a report explaining the 'rcumstances together with a revised schedule.

In addition, the licens shall submit the additional information identified in tions 3. 1 and 3.2 of the related Safety Evaluation in a rdance with the schedule contained therein. In the event t e dates for submittal cannot be met, the licensee sha submit a report, explaining the circumstances, togethe with a revised

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The licensee is required to develop and impl nt the administrative controls which are consistent wi the licensee's letters of August 28 and November 7, 8 within three months from the date of this amendment.

G. Safe uards Contin enc Plan DELETED Steam Generator Re air Pro ram (I) The Turkey Point Plant steam generator repair program as described in the licensee's "Steam Generator Repair Report" dated September 20, 1977, as supplemented on December 20, March 7, April 25, June 20 and August 4, 1978, January 26, 1979 and March 28, 1980, and the affidavit of A. J. Gould dated June 12, 1981, for Unit No. 4 is approved pursuant to the Atomic Safety and Licensing Board Final Order dated June 19, 1981.

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L-93-192 INSERT B F. Fire Protection FPL shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report (FSAR) for Turkey Point Units 3 and 4 and as approved in the Safety Evaluation Report (SER) dated March 21, 1979, and supplements thereto 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.

I INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE TABLE 3. 3" 4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS......,.......................:....., 3/4 3-36 TABLE 4.3"3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS........ 3/4 3-39 Movable Incore Detectors.......................,.... 3/4 3-40 Accident Monitoring Instr umentation................. 3/4 3-41 TABLE 3. 3-5 ACCIDENT MONITORING INSTRUMENTATION.............. 3/4 3"42 TABLE 4. 3-4 ACCIDENT MONITORING INSTRUHENTATION SURVEILLANCE REQUIREMENTS....... 3/4 3"46 Fire Detection Instrumentation " > ~>

CLE. T6'C> LIMITING CONOITION FOR OPERATIO 3.3.4 As a minimum, the fire detection instrumentation for each fire detectio zo shown in Table 3.3-6 shall be OPERABLE. APPL BILITY: Whenever equipment protected by the fire detection instrument is requsr to e OPERABLE. ACTION: a0 Wi any, but not more than one-half the total in any fire zone, Func 'on A fire detection instruments shown in Table 3.3-6 inoperable, restor the inoperable instrument(s) to OPERABLE status within 14 days within the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect th zone(s) with the inoperable instrument(s) at least once per hour, u ess the instrument(s) is located inside the containment, then inspect at containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (or monitor the con inment air temperature at least once per hour at the locations listed 'pecification 4.6. 1.5).

b. With more than one- lf of the Function A fire detection instruments in any fire zone show in Table 3.3-6 inoperable, or with any Function B fire detects instruments shown in Table 3. 3-6 inoperable, or with any o or more adjacent fire detection instruments shown in Table .3-6 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patro to inspect the zone(s) with the inoperable instrument(s) at le t once per hour, unless the instrument(s) is located inside e containment, then inspect that containment zone at least on per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (or monitor the containment air temperature at ast once per hour at the locations listed in Specification 4. . .5).

C. With the fire watch patrol not establis at the 18 foot level of the turbine area, restore the fire watch trol within one hour, or prepare and submit a Special Report to the mmission within 30 days.

d. The provisions of Specifications 3.0.3 are not pplicable.

SURVEILLANCE RE UIREMENTS 4.3.3.4. 1 Each of the above required fire detection instruments ich are accessible during plant operation shall be demonstrated OPERABLE at east once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL T . Fire detectors which are not accessible during plantioperation shall be dern trated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST ring each COLD SHUTDOWN exceeding 24 hours unless performed in the previous 6 months. 4.3.3.4.2 The NFPA Standard 72D supervised circuits supervision associated the detector alarms of each of the above required fire detection 'ith instruments shall be demonstrated OPERABLE at least once per 6 months. TURKEY POINT - UNITS 3 8c 4 3/4 3-47 AMENDMENT NOS. 145 AND 140 (,vw'")a'w)) ~~yevl~~vy~ ~ ~ ~~~~+~ ~ F ~,j~,, <. <<~~~~ttg &'+ OWCIPORDCIQ'C4lgypsPSL~AVAWWANLl%%W41Ft ~'f%4I ~i~'~~~~~~ver 4V~~~~ ypvP~ ~g~gW% i L e a ~ 0 ~ t~ ~ ~ t ~ ~ ~ ",gF TABLE 3.3"6 FIRE DETECTION INSTRUMENTS TOTAL NUMBER IN UMENT LOCATION OF INSTRUMENTS FIRE E AREA ~xy)" ~xi yP +xy+y* 4 - Aux. ldg. Corridor E. 10' (2/0) - Chem. ain/Laundry/Shower Tank Room (2/0) 9 - Laundry emical Drain Tank Room (1/0) 10 - Pipeway (11/0) 11 - Unit 3 RHR at Exchanger Room (5/0) 12 - RHR Pump 3A om (2/0) 13 - RHR Pump 3B Ro (2/0) 14 - Unit 4 RHR Heat changer Room (5/0) 15 - RHR Pump 4A Room (2/0) 16 - RHR Pump 4B Room (2/0) 19 - Unit 3 W Elect Penet oom (5/0) 20 - Unit 3 S Elect Penet m (11/0) 21 - Instrument Shop (2/0) 22 - Radioactive Laboratory .(2/0) 25 - Aux. Bldg. Elect. Equipmt. oom (6/0) 25A- Spare Battery Room (2/0) 26 - Unit 4 N Elect Penet Room (8/0) 27 - Unit 4 W Elect Penet Room (6/0) 30 - Unit 4 Piping and Valve Room (4/0) 40 - Unit 3 Piping and Valve Room (4/0) 45 - Unit 4 Charging Pump Room (0/4) (3/0) 47 - Unit 4 Component Cooling Water Area (0/4) (5/2) 54 - Unit 3 Component Cooling Water Area (0/4) (4/2) 55 - Unit 3 Charging Pump Room (0/4) (3/0) 58 - Aux Bldg Corridor, El. (18/0) - Unit 4 Containment Electrical 18'9 (10/0) Penet. Area"* 60 - Unit 3 Containment Electrical (16/0) Penet. Area*" 61 - Reactor Control Rod Eqpmt Room - Unit 4 (4/0) 62 - Computer Room (11/0) 63 - Reactor Control Rod.,Eqpmt Room - Unit 3 (4/0) 67 -. 4160V Switchgear 4B (10/0) 68 - 4160V Switchgear 4A (6/0) 70 - 4160V Switchgear 3B (10/0) 71 - 4160V Switchgear 3A (6/0) 72 - Diesel Generator 3B (0/3) (1/0) (1/0) 73 - Diesel Generator 3A (0/3) (1/0) (1/0) 74 - Day Tank Room 3B (1/1) 75 - Day Tank Room 3A (1/1) 76 - Unit 4 Turbine Lube Oil Reservoir (1/0) 79A- North-South Breezeway (0/6) 81 - Unit 4 Main Transformer (1/0) 82 - Unit 4 Aux Transformer Area (1/0) 84 - Unit 3 and 4 Aux Feedwater Pump Area (3/0) (DC Enclosure Bldg.) TURKEY POINT - UNITS 3 8c 4 AMENDMENT NOS. 149 AND 144 m~"'~me ~ ll&JC41+~ ~~~~~aea~im~ TABLE 3.3-6 Continued FIRE DETECTION INSTRUMENTS TOTAL NUMBER I TRUMENT LOCATION OF INSTRUMENTS FIRE ONE AREA ~y) * ~x]~y* ~xi yy'" 87 - U 't 3 Aux Transformer Area (1/0) 93 - 480 Load Center 4A and 4B (1/0) 94 - 480V oad Center 4C and 4D (2/0) 95 - 480V L d Center 3A and 3B (1/0) 96 - 480V Loa Center 3C and 3D (2/0) 97 - Mechanica Equipment Room (1/0) 98 - Cable Sprea ing Room (16/15) 101- RPI Inverter nd MG Sets (1/0) 102- Battery Rack (1/0) 103- Battery Rack 3A (1/0) 104- RPI Inverter and Sets (2/0) 106- Control Room (1/0) (16/0) 108A- Train A Inverters (3/4) 108B- Train B Inverters (4/4) 109- Battery Rack 4A (1/0) 110- Battery Rack 3B (1/0) 113- Unit 4 Feedwater Platform (2/0) 116- Unit 3 Feedwater Platform (2/0) 119- Unit 4 Intake Cooling Mater P p Area (4/0) 120- Unit 3 Intake Cooling Mater Pu Area (4/0) 132- Control Room Electrical Chase (1/2) 133- Diesel Generator 4B (5/5) (3/0) (5/0) 134- 4160V Switchgear 3D Room (2/0) 135- Diesel Generator 4B Control Panel Room (2/0) 136- Diesel Generator 4B Fuel Transfer Pump (2/0) 138- Diesel Generator 4A /5) (3/0) (5/0) 139- 4160V Switchgear 4D Room (2/0) 140- Diesel Generator 4A Control Panel Room (2/0) 141- Diesel Generator 4A Fuel Transfer Pump (2/0) N/A - 18'evel of the Turbine Area (N/A)f N/A)8 iN/A)8 TABLE NOTATIONS x is number of Function A (early warning fire dectect n and notification only) instruments. y is number of Function B (actuation of Fire Suppression ystems and early warning fire detection and notification) instrument The fire detection instruments located within the containmen ar'e not required to be operable during the performance of Type A Cont 'nment Leakage Rate Test. A fire watch patrol shall be established to inspect the 18 foot 1 el of the Turbine Area once each hour. TURKEY POINT - UNITS 3 4 4 AMENDMENT NOS. >49 AND 144 'tel g I 4 M~y~~ ~ 1i~~+~ Q~ ks't~:~~ P', INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-7 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3. 11. 1. 1 are not exceeded. The Alarm/ Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: At all times, except as indicated in Table 3.3-7. ACTION: a0 With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above spe-cification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With'ess than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-7. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.4 why this inoperability was not corrected in a timely manner.

C. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE RE UIREMENTS 4.3.3.5 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-5. TURKEY POINT " UNITS 3 8E 4 3/4 3 AMENDMENT NOS. l37ANDl3~ r ~ <+) ~4 ~ h3 TABLE 3.3-7 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Li qui d Radwaste E ffluent Line 35

b. Steam Generator Blowdown Effluent Line 36

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 37

b. Steam Generator Blowdown Effluent Line 1""/Steam 37 generator "Applicable during liquid effluent releases.

""Applicable during bl owdown operations. TURKEY POINT - UNITS 3 8 4 3/4 3 AMENDMENT NOS. 137AND 132 TABLE 3. 3-7 Continued TABLE NOTATION ACTION 35- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4. 11. 1. 1. 1, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36- With the number of channels OPERABLE less than required by the Minimum Chan'nels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross (beta or gamma) radioactivity at a lower limit of .detection of no more than 1 x 10-~ microcuries/ml or analyzed isotopically (Gamma) at a lower limit of detection of at least 5 x 10-~ microcuries/ml:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE E(UIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies/gram DOSE E(UIVALENT I-131.

ACTION 37 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow. 0 TURKEY POINT - UNITS 3 8( 4 3/4 3 AMENDMENT NOS337 AND 132 pgA'g tt+t tg (,c TABLE 4.3-5 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATIOH SURVEILLANCE RE UIREMEHTS ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATIOH TEST

1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluents Line R(2) Q(1)

b. Steam Generator Blowdown Effluent Line R(2) Q(1)

2. Flow Rate Measurlent Devices

a. Liquid Radwaste Effluent Line 0(3) N.A.

b. Steaa Generator Blowdown Effluent Lines O(3) H.A.

TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control rooe alara annunciation occurs if the instrument indicates measured levels above the Alana/Trip Setpoint. (2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating-the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the instial calibration shall be used. (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made. I (";pc ~l 'I Q INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3.11.2.l and 3. 11.2.5 are not exceeded. The Alarm/Trip Setpoints of these channels meeting Specification 3. 11.2. 1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM. APPLICABILITY: As shown in Table 3.3-8 ACTION: 'a ~ With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable or change the setpoint so it"is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if. unsuccessful explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9. 1.4 why this inoperability was not corrected in a timely manner.

C. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE RE UIREMENTS 4.3.3.6 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6. TURKEY POINT " UNITS 3 & 4 3/4 3 AMENDMENT NOS. 137AND 132 0 III TABLE 3.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. GAS DECAY TANK SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (Plant Vent Monitor) 45

b. Effluent System Flow Rate Measuring Device 46

2. WASTE GAS DISPOSAL SYSTEM (Explosive Gas Monitoring System)

a. Hydrogen and Oxygen Monitors 49

3. Condenser Air Ejector Vent System a~ Noble Gas Activity Monitor (SPING or PRHS) 47

b. Iodine Sampler 48 C. Particulate Sampler 48

d. Effluent System Flow Rate Measuring Device 1 46

e. Sampler Flow Rate Measuring Device

I I ,'$ jl H Q"Q P C I TABLE 3.3-8 Continued C m RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION C

4. Plant Vent System (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Monitor (SPING 47 Qo or PRMS)

b. Iodine Saipler

c. Particulate Sampler

d. Effluent System Flat Rate Measuring Device

e. Sampler Fler Rate Measuring Device

5. Unit 3 Spent Fuel Pit Building Vent

a. Noble Gas Activity Monitor 47

b. Iodine Saspler 48

c. Particulate Sampler

d. Sampler Flat Rate Measuring Device

I PQ 4 TABLE 3. 3-8 Continued TABLE NOTATION At all times. During GAS DECAY TANK SYSTEM operation. ¹ Applies during MODE 1, 2, 3 and 4. Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected as indicated by condenser air ejector noble gas activity monitor. ACTION 45- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be'released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via 4S this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ACTION 47- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ACTION 48 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4. 11-2 and analyzed at least weekly. ACTION 49- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the GAS DECAY TANK SYSTEM may continue provided that grab samples are collected and analyzed for hydrogen and oxygen concentration at least a) once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during degassing operations, and b) once per day during other operations. TURKEY POINT - UNITS 3 4 4 3/4 3 AMENDMENT NOS. 137AND TABLE 4.3-6 0 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS ANALOG CHANNEL MODES FOR MHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST RE UIRED

1. GAS DECAY TANK SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (Plant Vent Monitor) R(3) Q(1)

b. Effluent System Flow Rate Measuring Device N.A.

2. G AS DECAY TANK SYSTEM (Explosive Gas Monitoring System)

a. Hydrogen and Oxygen Monitors N.A. Q(4,5)

3. Condenser Air Ejector Vent System

a. Noble Gas Activity Monitor (SPING or PRMS) R(3) Q(2)

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. N.A. N.A.

d. Effluent System Flow Rate Measuring Device N.A. N.A.

Ik W3 TABLE 4.3-6 0 Continued RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS ANALOG CHANNEL NODES FOR NILICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST RE UIRED

3. Condenser Air Ejector Vent Systee (Continued)

e. Saeple Flow Rate measuring Device N.A. N.A.

4. Plant Vent Systea (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Honitor (SPING or PRIS) R(3) Q(2)

b. Iodine Saipler N.A. N.A. N.A.

c. Particulate Saapler N.A. N.A. N.A.

d. Effluent Systea Flow Rate Neasuring Device N.A. N.A.

e. Saiipler Flow Rate Neasuring Device 0 N.A. N.A.

a TABLE 4. 3-6 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST RE UIRED

5. Unit 3 Spent Fuel Pit Building Vent

a. Noble Gas Activity Monitor R(3) Q(2)

b. Iodine Sajapler N.A. N.A. N.A.

c. Particulate Smnpler N.A. N.A. H.A.

d. Saepler Flow Rate Measuring Device 0 N.A. N.A.

TABLE NOTATION

At all times.

- During GAS DENY TANK SYSTEM operation.

Applies during MODE 1, 2, 3 and 4. Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected as indicated by condenser air ejector noble gas activity monitor. (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control rootI alara annunciation occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint. (2) The ANALOG CHANNEL OPERATIOHAL TEST shall also demonstrate that if the instrument indicates aeasured levels above the Alarm Setpoint, alarm annunciation occurs in the control roon (for PRHS only) and in the coliputer rooe (for SPING only). (3) The initial CHANNEL CALIBRATION shall be performed using one or sere of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with HIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. Pc~ 0 'C., 5" p 4 I TABLE 4.3-6 (Continued) TABLE NOTATIONS Continued (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal.

a. One volume percent hydrogen, balance nitrogen, and

b. Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a. One volume percent oxygen, balance nitrogen, and

b. Four volume percent oxygen, balance nitrogen.

TURKEY POINT - UNITS 3 8 4 3/4 3 AMENDMENT NOS. 149 AND 144 ~ ~, C p-~) G " It NT SYSTEMS 3/4. FIRE SUPPRESSION SYSTEMS FIRE WAT SUPPLY AND DISTRIBUTION SYSTEM LIMITING COND I ON FOR OPERATION 3.7.8.1 The Fire Wat Supply and Distribution System shall be OPERABLE with:

a. At least two fi suppression pumps, one electric driven and one diesel driven wit their discharge aligned to the fire suppression header,

b. Two separate water supp es, each with a minimum contained volume of 300,000 gallons, and

c. An OPERABLE flow path capable f taking suction from the Raw Water Tank I and Raw Water Tank II an transferring the water through dis-tribution piping with OPERABLE se ionalizing control or isolation valves to the yard hydrant curb va s, the last valve ahead of the water flow alarm device on each sprin er or hose standpipe, and the last valve ahead of the deluge valve on ach Deluge or Spray System required to be OPERABLE per Specification 3.7.8.2, 3.7.8.3, and

3. 7. 8. 4.

APPLICABILITY: At al 1 times ~ ACTION: With one pump and/or one water supply inoperable, resto the inoper-able equipment to OPERABLE status within 7 days or provid an alter-nate backup pump or supply. The provisions of Specificatio .0.3 are not applicable. This ACTION applies to both units simult ously.

b. With the Fire Water Supply and Distribution System otherwise inop able, establish a backup fire water capability within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Ths ACTION applies to both units simultaneously.

TURKEY POINT - UNITS 3 8 4 AMENDMENT NOS.137 AND 132 ~vied ~'lt'<~ ~el@ ~.'W+~1 ~i%If 4w CLei@g~+& NT SYSTEMS SURV LLANCE RE UIREMENTS 4.7.8. 1. 1 he Fire Mater Supply and Distribution System shall be demonstrated OPERABLE:

a. At lea t once per 7 days by verifying the contained water supply volume,

b. At least on per 31 days by starting the electric motor-driven pump and operatin it for at least 15 minutes on recirculation flow,

c. At least once pe 31 days by verifying that each valve (manual, power-operated, or autom ic) in the flow path is in its correct position,

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

e. At least once per 12 mont by cycling each testable valve in the flow path through at least e complete cycle of full travel,

f. At least once per 18 months by erforming a system functional test which includes simulated automat actuation of the system throughout its operating sequence, and:

1) Verifying that each automatic va e in the flow path actuates to its correct position,

2) Verifying that the electric-driven pu develops at least 1880 gpm at a system pressure of 130.2 psig, nd the diesel-driven pump develops at least 2350 gpm at a syst pressure of 130.2 psig, by verifying 3 points on the p performance curve.

3) Cycling each valve in the flow path that is no testable during plant operation through at least one complete cy e of full travel, and

4) Verifying that each fire pump starts sequentially to maintain the Fire Mater Supply and Distribution Syst pressure greater than or equal to 125 psig.

g. At least once per 3 years by performing a flow test of the system n accordance with Chapter 5, Section 11 of the Fire Protection Handbo 14th Edition, published by the National Fire Protection Association.

TURKEY POINT - UNITS 3 8 4 AMENDMENT NOS.137 AND 132 ~ ~ '4~~~" ~ ~~~~~aes~~~~~ f e~w<m~ CMk~Z P NT SYSTEMS SURV LANCE RE UIREMENTS (Continued) 4.7.8. 1.2 e fire pump diesel engine shall be demonstrated OPERABLE:

a. At l st once per 31 days by verifying:

1) The uel storage tank contains at least 375 gallons of fuel, and

2) The dies starts from ambient conditions and operates for at least 30 'tes on recirculation flow.

b. At least once per days by verifying that a sample of diesel fuel from the fuel storag tank, obtained in accordance with ASTM-0270-1975 is within the acceptab limits specified in Table 1 of ASTM 0975-1977 when checked for viscos and water and sediment; and

c. At least once per 18 months y subject'ing the diesel to an inspec-tion in accordance with proce res prepared in conjunction with its manufacturer's recommendations or the class of service.

4.7.8. 1.3 The fire pump diesel starting 24- lt battery bank and charger shall be demonstrated OPERABLE: aj At least once per 7 days by verifying t t:

1) The electrolyte level of each battery 'bove the plates, and

2) The overall battery voltage is greater th or equal to 24 volts.

b. At least once per 92 days by verifying that the s cific gravity is appropriate for continued service of the battery, a C. At least once per 18 months by ver ifying that:

1) The batteries, cell plates, and battery. racks show no isual indication of physical damage or abnormal deterioratio and

2) The battery-to-battery and terminal connections are clean, tight, free of corrosion, and coated with anticorrosion mat ial.

TURKEY POINT - UNITS 3 8 4 AMENDMENT N05337 AND I32 ~s~ ' ~ J ~ l ~ tf ~ ~ ILee ~ C14~PDMPP LANT SYSTEMS SP Y AND/OR SPRINKLER SYSTEMS LIMITI CONDITION FOR OPERATION 3.7.8.2 Th following Spray and/or Sprinkler Systems shall be OPERABLE: aO Fire ones 47 and 54 - Component Cooling Mater Areas

b. Fire Z es 45 and.55 - Charging Pump Rooms C. Fire Zone 79A - North - South Breezeway (Unit 3 and Unit 4)

d. Fire Zones , 73, 74 and 75

- Emergency Diesel Generator and Day Tank Rooms ( t 3)

e. File Zones 133, 36, 138 and 141-Emergency Diesel Generator and Fuel Transfer Pump Roo (Unit 4)

APPLICABILITY: Whenever equip nt protected by-the Spray/Sprinkler System is h IIPERABLE. ACTION: ao With one or more of the abov required Spray and/or Sprinkler Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months est lish a continuous fire watch with backup fire suppression equipme . This ACTION will apply to both units simultaneously for 3.7.8.2.

b. The provisions of Specification 3.0. are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.8.2 Each of the above required Spray and/or Sprin er Systems shall be demonstrated OPERABLE: aO At least once per 31 days by verifying that each lve (manual, power-operated, or autmmatic) in the flow path is in its rrect position,

b. At least once per 12 months by cycling each testable v ve in the flow path through at least one complete cycle of full t el, C. At least once per 18 months:

1) By performing a system functional test which includes sim ated automatic actuation of the systea, and:

a) Verifying that the automatic valves in the flow path act to their. correct positions on a test signal, and b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel. TURKEY POINT - UNITS 3 Ec 4 AHENDNENT NOS.l 38 AND 133 ~ ~~JR~~ 40~ C ,f ma~~~~ p~p++ 1 <<4 .i'Wl+g@, ' SYSTEMS SURVEILLANCE RE NTS (Continued

2) By a visual inspectio the dry pipe spray and sprinkler headers to verify their in 'ty; and

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

d. At least once per 3 years by performing an air or water f st through each open head spray/sprinkler header and verifying eac open head spray/sprinkler nozzle is unobstructed.

TURKEY POINT - UNITS 3 5 4 AMENOMENT NOS.]37 AND 132 ~~gCAA~ ~~I~~~ ~~ p J' MlranAOea7~~~ ~W~a~~g~y~~~ ~p~e5sl5$ 40 RE HOSE STATIONS LI ING CONDITION FOR OPERATION

3. 7. 8. 3 e fire hose stations given in Table 3. 7-4 shall be OPERABLE.

APPLICABILIT Whenever equipment in the areas protected by the fire hose stations is re uired to be OPERABLE. ACTION: With one o more of the fire hose stations given in Table 3.7-4 inoperable, rovide an equivalent capacity fire hose from the nearest equivalent OP ABLE water source. The fire hose shall be of a length of hose suffici nt to provide coverage for the ar ea left unprotected by the inoperabl hose station, and shall be stored in a roll at the outlet of the OPE LE water supply. The above ACTION requirement shall be accomplish within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of ire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . his ACTION applies to both units simultaneously.

b. The provisions of Specifi tion 3.0. 3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.8.3 Each of the fire hose stations giv in Table 3.7-4 shall be demonstrated OPERABLE:

a. At least once per 31 days, by a visual 'nspection of the fire hose stations accessible during plant operati s to assure all required equipment is at the station.

b. At least once per 12 months, by:

1) Visual inspection of the stations not acces ible during plant operations to assure all required equipment at the station,

2) Removing the hose for inspection and re-racking, and

3) Inspecting all gaskets and replacing any degraded kets in the couplings.

C. At least once per 3 years, by:

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

2) Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

TURKEY POINT - UNITS 3 8 4 AMENDMENT NOS.137 AND 132 I gl ~ 't ~~r ~5CNX~~~J" ~~~~~ g~~ ( ~ ~T~ ~AC~' ~ ~ +~Ate y~~~fa~~~~~ g~i~~c~ I ."'ABLE 3. i-4 FIRE HOSE STATIONS NT IF ICATION FIRE ZONE HS - East of HS"03-02 EL. 42'OCATION 18'L. - West of >>"160V SWGR Room on Column 3A Condensate Pump on Pedestal 88 87 HS-03-03 Passageway South of SG Feed Pump Room 18'L. 83 HS-03-04 18'L. - East of 480V Load Center on Column 105 HS"03-05 30'0'L. - South End of Mezzanine Deck 105 HS-03-06 - NW End of Turbine Deck 117 HS-03-07 42'L. - North of 6A HPFW Heater 117 HS-03"08 EL. NW Corner of Entrance to Elevator 79 HS-04-01 EL. 18' So of 4160V SWGR Room on Column 82 HS-04"02 EL. 18' Passa way South of SG Feed Pump Room 78 HS-04-03 EL. 30' East of OV Load Center at Stairway 105 HS-04-04 EL. 30' South End Mezzanine Deck 105 HS-04-05 EL. 42' West End of bine Deck 117 HS-04-06 EL. 42' East Side of Tu 'ne Deck and North of 117 6A FW Heater HS-04-07 EL. 42' East Side of Turbine ck and North of 117 6B FW Heater HS-04"08 EL. 42' Southwest Corner of Turbin eck 117 HS-04-09 EL. 18' Entrance to Unit 4 Diesel Ge ator 999 Building HS-AB-01 EL. 18' East-West Passageway at West End 58 HS"AB-02 EL. 18' East-West Passageway at East End 58 HS-AB-03 EL. 18' North-South Passageway Outside Unit 3 58 Charging Pump Room HS"AB-04 EL. 50' Roof of Unit 3 New Fuel Storage Area 1 HS-AB-05 EL. 50' Roof of Unit 4 New Fuel Storage Area 118 TURKEY POINT - UNITS 3 8c 4 AMENDMENT NOS. 145 AND 140 ~ ~ IO 0 ANT SYSTEMS FIR YDRANTS AND HYDRANT HOSE HOUSES LIMITI CONDITION FOR OPERATION 3.7.8.4 The fire hydrants and associated hydrant hose houses given in Table 3.7-5 s ll be OPERABLE. enever equipment in the areas protected by the fire hydrants ~E APPLICABILITY: ERABLE. ACTIDN: a ~ With one or mor of the fire hydrants or associated hydrant hose houses given in le 3.7-5 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months have sufficient additional lengths f 2 1/2 inch diameter hose located in an adjacent OPERABLE hydrant hos house to provide service to the unprotected area(s) if the inoper le fire hydrant or associated hydrant hose house is the primary me s of fire suppression; otherwise, provide the additional hose withe 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. The provisions of Specificat n 3.0.3 and are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.8.4 Each of the fire hydrants and associat hydrant hose houses given in Table 3.7-5 shall be demonstrated OPERABLE:

a. At least once per 31 days, by visual inspe ion of the hydrant hose house to assure all required equipment is at he hose house,

b. At least once per 6 months by visually inspecti each fire hydrant and verifying that the hydrant is not damaged, an C. At least once per 12 months by:

1) Conducting a hose hydrostatic test at a pressure o 50 psig or at least 50 psig above maximum fire main operating p ssure, whichever is greater,

2) Inspecting all the gaskets and replacing any degraded gas ts in the couplings, and

3) Performing a flow check of each hydrant to verify its OPERABILITY.

TURKEY POINT - UNITS 3 8 4, AMENDMENT NOS337 AND 132 ~ yl ~ ~ac/ ~ey ~~+isv, ~ / %'POt~ lA~~~ ~ltt~0%lWPIs~gfggpp~~~~ ~ ~lgVCp~ g Q~~~~Vtt '. YO ~ TABLE 3.7-5 FIRE HYDRANTS NVMBER OF I TIF ICATION FIRE ZONE LOCATION HYDRANTS HY-0 124 Nf Corner of Unit 3 near Vehicle Gate into RCA HY-07 86 Unit 3 Transformer Area HY-08 Unit 4 Transformer Area HY-09 76 Unit 4 Turbine-Generator Area HY"10 77 it 4 Condensate Storage Tank Area HY-ll 125 SW C er of Unit 4 near equipment hatch HY-12 Unit 4 New 1 Storage Area HY-13 123 Refueling Water rage Area HY-17 Nuclear Dry Storage A HY-16 Steam Generator Storage Ar HY-18 Unit 3 Containment Access Rasp Area HY-26 86 Unit 3 Diesel Generator Building Area TOTAL TURKEY POINT - UNITS 3 4 4 AHEN~NT NOS.138 AND 133 ~ yl ~ l~ NT SYSTEMS 3/4. 9 FIRE RATED ASSEMBLIES LIMITIN CONDITION FOR OPERATION 0 3.7.9 All e rated assemblies (walls, floor/ceilings, and other fire barriers) sep ting safety-related fire areas or separating portions of, redun-dant systems im rtant to safe shutdown within a fire area and all sealing devices in fire r ed assembly penetrations (fire doors, fire windows, fire dampers, cable, pip g, fire barrier penetration seals, and ventilation duct penetration seals) s ll be OPERABLE. APPLICABILITY: At all t es. ACTION: a ~ With one or more of t above required fire rated assemblies and/or sealing devices inoper le, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either establish a continuous fire watch on t least one side of the affected assembly, or verify the OPERABILITY fire detectors on at least one side of the inoperable assembly and tablish an hourly fire watch patrol.

b. The provisions of Specification .0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.1 At least once per 18 months the above requ ed fire rated assemblies and penetration sealing devices shall be verified OP BLE by performing a visual inspection of:

a. The exposed surfaces of each fire rated assembly,

b. Each fire window/fire damper and associated hardware, and

'C. At least 10K of each type of sealed penetration. If ap rent changes in appearance or abnormal degradations are found, visual inspection of an additional 10K of each t e of sealed pene ation shall be made. This inspection process shall continue until 10K sample with no apparent changes in appearance or abnormal degr ation is found. Samples shall be selected such that each penetration 'll be inspected every 15 years. TURKEY POINT - UNITS 3 8L 4 AMENDMENT NOS. 149 AND 144 ~~J%CtWIe a ~ Pg ~ ~eW'W>> I ~ 4IJCk VAS ICWug NT SYSTEMS SURVEIL CE RE UIREMENTS Continued) 4.7.9.2 Each of th bove required fire doors shall be-verified OPERABLE by inspecting the release closing mechanism and latches at least once per 6 months, and by verifying.

a. The OPERABILITY of the door supervision system for each electrically supervised fi oor by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at lea once per 31 days,

b. That each locked closed fire door is sed at least once per 7 days,

c. That doors with automatic hold-open and release hanisms are free of obstructions at 'least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and a tional test is performed at least once per 18 months, and

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

TURKEY POINT - UNITS 3 8 4 AMENDMENT NOS.137 AND 132 fusA ~nas4 ~+e4ALQ.'o'l ADMINISTRATIVE CONTROLS PLANT STAFF 6.2.2 The plant 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. At least one licensed Operator shall be in the control room when fuel is in either reactor.

c. At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips. In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room;

d. A Health Physics Technician" shall be on site when fuel is in the reactor;

e. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handlin s no other concurrent responsibilities during this operation; d

Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety.-related functions (e.g., licensed Senior Operators, licensed Operators, health 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 shut-down for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed: "The Health Physics Technicia composition may be less than the minimum requirements for a o not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions. TURKEY POINT - UNITS 3 8( 4 6"2 AMENDMENT NOS.137 AND 132 O~ f( lg j+ lt ~ '< '"~x .N~ <<~~~-;+~~i +~ "J kh. ~ WW1 3 . J".I e 'I'.4I1~ at+ l1 <<% CA l' eOa ts J 2 1 Ik h. =Ca~: t L=asC ate%10:kc l 1 F I . ' 0 Of'. '= R 'f W 2 . 0%~ ~ EA f Dt1 1 le ate IP 4 k>- '3 ~<~ ~) ~~ KW gpQRICg~ "K Q f~gSL~~t%AIW~l~ v ~~~ ~~~ 4&V. "o 4O.ll~t ~Aa. ADMINISTRATIVE CONTROLS RESPONSIBILITIES Continued)

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering,evalua-tion and recommendations to prevent recurrence, to the President-Nuclear Division and to the Chairman of the Company Nuclear Review Board;

f. Review of all REPORTABLE EVENTS;

g. Review of reports of significant operating abnormalities or deviations .from normal and expected performance of plant equipment or systems that affect nuclear safety.

h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant General Manager or the Chairman of the Company Nuclear Review Board; Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Chairman of the Company Nuclear Review Board; Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL;

k. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to pre-vent recurrence and the forwarding of these reports to the President-(.~<~CRY) Nuclear Division and to the Chairman of the Company Nuclear Review Board.

6.5.1.7 The PNSC shall: Recommend in writing to the Plant General Manager approval or f disapproval of items considered under Specification 6.5.1.6a. through

d. prior to their implementation and items considered under Specifica-tion 6.5.1.6i through

b. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Plant General Manager, President-Nuclear Division and the Company Nuclear Review Board of disagreement between the PNSC and the Plant General Hanager; however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6. 1. l.

JP, WKL'cvJ 04 fQ +I fQ 7 fa4Qg$ [~~ 'Tv cl)gg~ ++ J i'~P I ~~e~h'~P P~ ceases ~~a 4 k~ +~b~i Wc~ l e4 reco~~eMe J ~ka~ges ~~ ~W +~ja~g ~~6. lKer R~Q i g~ So~~g TURKEY POINT - UNITS 3 8( 4 6-7 AMENDMENT NOS.15gAND )48, g a, 8 'w 1 ) 1 li C",'; ~egg)y p; p-qp'cr t cf l I i~~g,$ ~ ygga c> p"g f "'< gA 1'o jlY-~.-'l ~ g ~ CN I yet, ~ I,s k ~ mud.irz <<A 4 iQ ~l zg"~A)a99 C~ ~ r, ~ $ z, ) 4 p~, 0 '4'p4 'V&A"strtu.>9 'f 0 p,h w g~',.9 g1 VQ ) ~h g>>g~)va. ~Cg ~QQMg g~~ Q~ QPJV I 0 INSTRUMENTATION BASES 3/4. 3. 3 MONITORING INSTRUMENTATION '/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that conditions indicative of potential uncontrolled radioactive releases are monitored and that appropriate actions will be automatically or manually initiated when the radiation level monitored by each channel reaches its alarm or trip setpoint. 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve. For the purpose of measuring F~(Z) or F<H a full incore flux map is used. quarter-core fl.ux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT . POWER TILT RATIO when one Power Range channel is inoperable. 3/4. 3.3. 3 ACCIDENT MONITORING INSTRUMENTATION T he 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 consis-tent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumen-tation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980. 3/4.3.3. 4 FIRE DETECTION INSTRUMENTATIO - DC4E~b The OPERABILITY of the fire detection sns ion ensures that both adequ arning ' capability is available for prompt detection of fires and that Fire Suppre Systems, that are actuated by fire detectors, will discharge extinguishing ag in a timely manner. Prompt detection and suppression of fires wH 1 reduce the ntial for damage to safety-related equipment and is an integral element in the all facility Fire Protection Program. Fire detectors that are used to ate Fire Suppression Systems represent a more critically important component of a t Fire Protection Program than detectors that are installed solely for ea ire warning and notifica-tion. Consequently, the minimum number of OPERABLE detectors must be greater. The loss of detection capability for Fire Suppression Systems, a ted fire detectors, represents a significant degradation of fire protection TURKEY POINT - UNITS 3 4 4 B 3/4 3-3 AMENDMENT NOS137 AND132 ((f3d~~si) eh Q.b T'9 >.'>Pi m.ee ~~~V~ <<~Ph44WS~~~~tl&%gr~)AAA~~A~~~~~~ ~> ~ ~ ~<~~~nrc~t~~~~<~~~~>~~~amen-m~~g,~~+~~~~~m aew~w~~~~~~'~~~~~ (~ INSTRUMENTATION BASES TION INSTRUMENTATION (Continued) any area. As a resu tablishment of a fire watch patrol must be ini-tiated at an earlier stage than warranted for the loss of detectors that provide only early fire warning. T e 'shment of frequent fire patrols in the affected areas is required to prove e 'on capability until the inoperable instrumentation is restored to OPERABIL 3/4.3.3.5 RADIOACTIVE LI UID EFFLUENT 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 1iquid effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters 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. 3/4. 3. 3. 6 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous efflu-ents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumenta-tion also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GAS DECAY TANK SYSTEM. The OPERA-BILITY 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. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements of Specification 3. 11.'2.2 shall be such that concentrations as low as 1 x 10-e yCi/ml are measurable. 0 TURKEY POINT " UNITS 3 8( 4 8 3/4 3-4 AMENDMENT NOS.137 AND 132 I

6

~ ~ ~~m~pgnaa~waosa~w~~~~~~ ANT SYSTEMS BASE 3/4. 7.8 F E SUPPRESSION SYSTEMS The OPER ILITY of the Fire Suppression Systems ensures that adequate fire suppressio capability is available to confine and extinguish fires occurring in any rtion of the facility where safety-related equipment is located. The Fire uppression System consists of the water system, spray, and/or sprinklers, e hose stations, and yard fire hydrants. The collective capability of the Fire Suppression Systems is adequate to minimize potential damage to safety-relate equipment and is a major element in the facility Fire Protection Program. In the event that porti s of the Fire Suppression Systems are inoperable, alternate backup fire-fighting quipment is required to be made available in the affected areas until the in erable equipment is restored to service. When the inoperable fire-fighting quipment is intended for use as a backup means of fire suppression, a longe eriod of time is allowed to provide an alternate means of fire fighting tha if the inoperable equipment is the primary means of fire suppression. The Surveillance Requirements provid assurance that the minimum OPERABILITY requirements of the Fire Suppression System are met. In the event the Fire Suppression Water S tern becomes inoperable, immediate corrective measures must be taken sine this system provides the major fire suppression capability of the plant. 3/4. 7. 9 FIRE RATED ASSEMBLIES . The functional integrity of the fire rated assembli and barrier penetrations ensures that fires will be confined or adequately retarde rom spreading to adjacent portions of the facility. These design features minimize th possibility of a single fire rapidly involving several areas of the facility prior to etection and extin-guishing of the fire. The fire barrier penetrations are a pass e element in the facility Fire Protection Program and are subject to periodic insp tions. Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered functional when the visually observed cond'on is the same as the as-designed condition. During periods of time when a barrier is not functional, either: (1) contin-uous fire watch is required to be maintained in the'icinity of the affected arrier, or (2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established until the barrier is restored to functional status. TURKEY POINT " UNITS 3 4 4 AMENDMENT NOS.137 AND 132 <<'khC~~ ~ // fI l~ ~eprN~~ ~'~<CWi~~~

ML17352A204

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