ML20209A835

Proposed Tech Specs,Deleting Fire Protection Requirements & Changing License Condition 2.C(6)

ML20209A835
Person / Time
Site:	Byron
Issue date:	08/29/1986
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20209A660	List: ML20209A655 ML20209A835
References
9416N, NUDOCS 8609080115
Download: ML20209A835 (44)

Text

'

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3.3 MONITORING INSTRUMENTATION l Radiation Monitoring for Plant Operations................ 3/4 3-39 l

i TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS................................ 3/4 3-40 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR Pl. ANT OrERATIONS 2

SURVEILLANCE REQUIREMENTS................................,........ 3/4 3-42 Movable Incore Detectors................................. 3/4 3-43 Seismic Instrumentation.................................. 3/4 3-44 i

TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION.................... 3/4 3-45 Meteorological Instrumentation........................... 3/4 3-47 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............. 3/4 3-48 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................... 3/4 3-49 Remote Shutdown Instrumentation.......................... 3/4 3-50 TABLE 3.3-9 REM 01E SHUT 00WN MONITORING INSTRUMENTATION............ 3/4 3-51 TABLE 4.3-6 REMOTE SHUTOOWN MONITORING INSTRUMENTATION 3/4 3-52 t

SURVEILLANCE REQUIREMENTS...........................

Accident Monitoring Instrumentation...................... 3/4 3-53 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-54 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................' 3/4 3-55 J i. , ^,. m e;ie , In e .. 6a u on........................ .. 2/' 2-50 '

. 3.3-11. rIR; 000-7:0^ IN'T=CNT', G% T 1h ............... 2/' 3-5" * -

TE LE .3 IL '!ai uu cu Aun Anmur>2WT3 (unu z). . . . . . . . . . . . . . . . . / 2 - 01 * --

Loose-Part Detection System.............................. 3/4 3 g 56 i Radioactive Liquid Effluent Monitoring Instrumentation... 3/4 3-Ap 57 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.................................... 3/4 3-S[ 58 JBR9BME SISShi l

, P BYRON - UNITS 1 & 2 VI

l M MITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......... 3/4 3-fd' 60 Radioactive Gaseous Effluent Monitoring Instrumentation. 3/43-7762.

TABLE 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.................................... 3/4 3- d O TABLE 4.3-9 RADIOACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........... . 3/4 3-7 I VI 3/4. 3.'4 PROTECTION.............................

TURBINE OVERSPEED 3/4 3- [ 7/

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation.............................. 3/4 4-1 Hot Standby.............................................. 3/4 4-2 Hot Shutdown............................................. 3/4 4-3 Cold Shutdown - Loops Fi11ed.........'.................... 3/4 4-5 Cold Shutdown - Loops Not Ft11ed......................... 3/4 4-6 Loop Isolation Valves-Operation.......~.................. 3/4 4-7 Loop Isolation Valves-Shutdown........................... 3/4 4-8 3/4.4.2 SAFETY VALVES l Shutdown.......................... .................... 3/4 4-9

! Operating............................................... 3/4 4-10 3/4.4.3 PRESSURIZER.............................................. 3/4 4-11 .

3/4.4.4 RELIEF VALVES............................................ 3/4 4-12 3/4.4.5 STEAM GENERATORS......................................... 3/4 4-13 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION......................... 3/4 4-18 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION....................... 3/4 4-19 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Le a kage Dete::ti on Sy s tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-20 Operational Leakage...................................... 3/4 4-21 l

BYRON - UNITS 1 & 2 VII I

I-.- . _ - _ _ _ . m., _

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE

.10 FIRE SUPPRESSIO'N SYSTEMS l

re Suppression Water Supply System.................... 7-30 Water ................................ ......... 3/4 7-33 CO 2 Systems........ ............ .................... 3/4 7-35 Halon Systems............ . ......................... 3/4 7-36 Fire Hose Station .................... .............. 3/4 7-37 TABLE 3.7-Sa FIR STATIONS (UNIT 1).................., ...... 3/4 7-38 TABLE 3. FIRE HOSE STATIONS (UNIT 2).......................... 4 7-42

.7.11 FIRE RATED ACKFMRLTES.................................... 3/4 7 '

3/4.7.12 AREA TEMPERATURE MONITORING.............................. 3/4 7-3 7 3 0 TABLE 3.7-6 AREA TEMPERATURE MONITORING........................... 3/47,$$"31 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating............... ................................' 3/4 8-1 TABLE 4.8-1 OIESEL GENERATOR TEST SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-8 Shutdown................................................. 3/4 8-9 3/4.8.2 0.C. SOURCES j 0perating................................................

3/4 8-10 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . 3/4 8-12 Shutdown.................................................. 3/4 8-13 3/4.8.3 ONSITE POWER DISTRIBUTION Operating................................................ 3/4 8-14 Shutdown................................................. 3/4 8-16 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective 0evices..................................... 3/4 8-17 TABLE 3.8-la CONTAINMENT PENETRATION CON 00CTOR OVERCURREN T PROTECTIVE DEVICES (UNIT 1). . . . . . . . . . . . . 3/4 8-19 TABLE 3.8-lb CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES (UNIT 2)............. 3/4 8-29 BYRON - UNITS 1 & 2 XI

~

I L

~

BASES SECTION PAGE 3/4.0 APPLICABILITY............................................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.......................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS.......................................... B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................ B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AX I A L F LUX 0 I FFERENC E. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR....... B 3/4 2-2 FIGURE B 3/4.2-1 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL P0WER.................................. B 3/4 2-3 3/4.2.4 QUADRANT POWER TILT RATI0................................. B 3/4 2-5 3/4.2.5 DNB PARAMETERS............................................ B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................- B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION.............................. B3/43./fo 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION. . . . . . . . . . . . . B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................. B 3/4 4-2 3/4.4.3 PRESSURIZER............................................... B 3/4 4-2 3/4.4.4 RELIEF VALVES............................................. B 3/4 4-2 4

BYRON - UNITS 1 & 2 XV

1 BASES SECTION PAGE l 1

3/4.7 PLANT SYSTDiS 3/4.7.1 TURBINE CYCLE............................................. B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........... B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................ B 3/4 7-3 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM............................ B 3/4 7-3 3/4.7.5 U LTIMATE H EAT S IN K. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.6 CONTROL ROOH VENTI LATION SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM ................................................. R 3/4 7-5 3/4.7.8 SNUBBERS.................................................. B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION............................... B 3/4 7-6

,,, , ,. ____ _..________. _ . - - - . , ,, , as _,

.,..w rinc averncaatun aia cna.................................. . . . , < -

,,, , ,, e,.. ..--- .__-.._._ .

. . ,, , news

,,,... _ ..m mnicu nasanoutca .................................... . , , , ,

3/4.7.12 AREA TEMPERATURE MONITORING............................... . B 3/4 7 d" 1 3/4.8 ELECTR: CAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER DISTRIBUTION............................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE'0EVICES................... B 3/4 8-3 3/4.9 REFUEL'ING OPERATIONS t

l 1

3/4.9.1 BORON CONCENTRATION....................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

B 3/4 9-1 3/4.9.3 OECAY TIME................................................ B 3/4 9-1 ,

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................ B 3/4 9-1 t

BYRON - UNITS 1 & 2 XVII l _

INSTRUMENTATION

~

FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentatio for each fire detection zone shown in Table 3.3-11a for Unit 1 (Table 3.3-11b f r Unit 2) shall be OPERABLE.

APPLICAEILITY: Whenever equipment protected by th fire detection instrument is required to be OPERABLE.

ACTION: ,

a. With any, but not more than one- if the total in any fire zone, fire detection instruments show in Table 3.3-11 inoperable, restore the inoperable instrument (s) OPERABLE status within 14 days or witnin the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> estab sh a fire watch patrol to inspect the zone (s) with the inoper le instrument (s) at least once per hour, unless the 'nstrume (s) is located inside the containment, then inspect tai ent zone 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 men air temperature at least once per hour at the locatio sted Specification 4.6.1.5.

b. With mor one- alf of the fire detection instruments in any fire zo.1e sho Tab 3.3-11 inoperable or with any fire suppression instr ent she in Table 3.3-11, inoperable, or with any two or mo a /ent re detection instruments shown in Table 3.3-11 fr ratle, w' hin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect tf ne(s) ith the inoperable instrument (s) at least once per u unie the instrument (s) is located inside the containment, ti en ins et that containment zone 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 nitor .he containment air temperature at least once per hour at e lo tions listed in Specification 4.6.1.5.

I

c. The rovisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLA, E REQUIREMENTS l

4.3.3 .1 Each of the above required fire detection instruments which are act sible during plant operation shall be demonstrated OPERABLE at least once pe 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST. Fire d ectors which are not accessible during plant operation shall be demonstrated ERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL 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 /> unless performed in the previous 6 months.

BYRON - UNITS 1 & 2 3/4 3-56

INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) 4.3.3.7.2 The NFPA Standard 720 supervised circuits supervisio associated with the detector alarms of each of the above required fire d ction instruments shall be demonstrated OPERABLE at least once per months.

v 9

h BYRON - UNITS 1 1 2 3/4 3-57

TA8LE 3.3-11a FIRE DETECTION INSTRUMENTS (UNIT 1)

INSTRUMENT LOCATION INSTRUMENT TYPE

• TOTAL NU R OF INSTRUMENTS Heat Flame Smoke

1. Containment *** I Zone 11 Elev 426 Suppression 1 Zone 12 Elev 426 Suppression **

Zone 2 Elev 401 Detection 2 Zone 3 Elev 401 Detection 2 Zone 4 Elev 401 Detection 2 Zone 5 Elev 401 Detection 2 Zone 6 Elev 426 Detection 6 Zone 76 Elev 426 Detection , 13 Zone 7 Elev 414 Detection 7 Zone 24 Elev 414 Detectio 16

2. Control Room Zone 29 Elev 383 tion 4 Zone 68 Elev 451 / ectiun 3 Q

Zone 69 Elev 451 taction 12 Zone 75 Elev 451 etection 20 i

Zone 68 Elev 451 (Unit Detection 3

3. Switchgear Rooms '%gf l

Zone 66 Elev 451 Zone 77 Elev 426 h/

Y Detection Detection 10 21 Zone 78 Elev 426 Detection 19

4. Upper Cable Spreadin Room 1 Zone 41 Elev 463 Detection 4 Zone 42 Elev 463 Detection 4

Zone 43 Elev 46 Detection 8 Zone 44 Elev 4 Detection '

8 Zone 45.Elev 3 Detection 10 Zone 46 Elev 63 Detection 10 Zone 47 El 463 Detection 5 Zone 48 E v 463 -

Detection 5 Lower C le Spreading Room

! Zone Elev 439 Detection 23 i Zone O Elev 439 Detection 23 Zo 51 Elev 439 Detection 13 Z e 52 Elev 439 Detection 13 ne 53 Elev 439 Detection 9 one 54 Elev 439 Detection 9 l Zone 55 Elev 439 Detection 6 Zone 56 Elev 439 Detection 6

. Remote Shutdown Panel Zone 13 Elev 383 Detection ,

7 SYRON - UNITS 1 & 2 3/4 3-58 i

i

- - - . - - . ,--.,--. ,_.-. - - - - . - - , . . . - . - . , , - - . , . , . . . . - - - - , - - . , . . , . _ , ., ,.---n--,, - - - , - - - .

y TABLE 3.3-11a (Continued) l FIRE DETECTION INSTRUMENTS l

(UNIT 1) '

INSTRUMENT LOCATION INSTRUMENT TYPE

• TOT NUMBER OF INSTRUMENTS l H t Flame Smoke

6. Station Battery Room Zone 67 Elev 451 Detection 13

7. Diesel Gener~a tor Room Zone 37 Elev 401 Suppression 6 Zone 38 Elev 401 Suppression 6 Zone 71 Elev 401 Detection 1 Zone 72 Elev 401 Detectio - 1

8. Diesel Fuel Storage Zone 39 Elev 401 Supp ssion 1 Zone 40 Elev 401 Su: ression 1 Zone 27 Elev 383 S pression 3 Zone 28 Elev 383 uppression 3 Zone 10 Elev 383 Detection 6

9. Safety Related Pumps Zone 41 Elev 383 Zone 42 Elev 383 h Suppression Suppression 2

1

, Zone 16 Elev 3 Detection 2 Zone 18 Elev 3 Detection 10 Zone 19 Elev 364 Detection 3 i Zone 20 Elev 346 Detection -

3 Zone 21 Elev 346 Detection 3 l Zone 52 RSH Suppression S l Zone 11 Elev 33 (Unit 2) Detection 23

10. Fuel Storage Zone 39 Ele 401 Detection 26 Zone 38 El 426 Detection 3

11. Auxilia Building Zone 7 Elev 451 Detection 11 Zone 7 Elev 364 Detection 37 Zon. 40 Elev 364 Detection 7 Zo 11 Elev 383 Detection 37 ne 8 Elev 401 -

Detection 36 one 23 Elev 426 Detection 6 Zone 25 Elev 467 Detection 7 Zone 64 Elev 401 Detection 5 Zone 65 Elev 401 Detection 5 Zone 14 Elev 401 Detection 4 Zone 15 Elev 401 Detection 4 BYRON - UNITS 3 & 2 3/4 3-59 .

I TABLE 3.3-11a (Continued)

FIRE DETECTION INSTRUMENTS q (UNIT 1)

INSTRUMENT LOCATION INSTRUMENT TYPES TOTAL N BER OF INSTRUMENTS

11. Auxiliary Building (continued)

Zone 17 Elev 346 (Unit 2) Detection 32 Zone 40 Elev 346 (Unit 2) Detection 12 Zone 12 Elev 459 (Unit 2) Detection 11 Zone 22 Elev 467 (Unit 2) Detection 18 Zone 62 Elev 451 (Unit 2) Detection 11 Zone 61 Elev 439 (Unit 2) Detectio 7 Zone 75 Elev 426 (Unit 2) Detect' 33

12. Miscellaneous Zone 26 Elev 864 Det i 12 i

A E NOTATIONS

- *A single detector in a zone mar d " Detection" will alarm in the Main Control Room. A single detector in a one marked " Suppression" will initiate suppression s

and alarm in the Main Contro Room. .

~

ation temperature switches. Upon receipt of a Hi-Hi

• • These are Containment Ven temperature, suppression ust be manually initiated. These switches are not-720 supervised.

• • • The fire detection i truments located within the containment are not required to be OPERABLE during e performance of Type A containment leakage rate tests.

BYRON - UNITS 1 & 2 3/4 3-60

TABLE 3.3-11b FIRE DETECTION INSTRUMENTS (UNIT 2)

INSTRUMENT LOCATION INSTRUMENT TYPE

• TOTA NUMBER OF INSTRUMENTS He[ Flame Smoke

1. Containment ***

Zone 11 Elev 426 Suppression 1 **

Zone 12 Elev 426 Suppression 1 **

Zone 2 Elev 401 Detection .

2 Zone 3 Elev 401 Detection 2 Zone 4 Elev 401 Detection 2 ,

Zone 5 Elev 401 Detection 2 Zone 6 Elev 426 Detection , 6 Zone 76 Elev 426 Detection 9 Zone 7 Elev 414 Detectio 6 Zone 24 Elev 414 Detecti n 10

2. Control Rcom Zone 29 Elev 383 (Unit 1) De ction 4 Zone 68 Elev 451 0 action 3 Zone 69 Elev 451 etection 14 Detection 20 Zone6875Elev451(Unit Zone Elev 451 (Unit ')

1)h(/

Detection 3 s 3. Switchgear Rooms -

Zone 66 Elev 451 Detection 6 Zone 77 Elev 426 Detection 9 Zone 78 Elev 426 Detection 9

4. Upper Cable Spreadi Room Zone 41 Elev 4E3 Detection 4 Zone 42 Elev 463 Detection 4 Zone 43 Elev 46 Detection 8 Zone 44.Elev 4< Detection 8 Zone 45 Elev 3 Detection 9 j Zone 46 Elev 463 Detection 9 Zone 47 El Detection 463 5 Zone 48 E v 463 Detection 5 Lower ble Spreading Room Zone 9 Elev 439 Detection 8 Zon 50 Elev 439 Detection 8 Zo 51 Elev 439 Detection 19

~~

Z e 52 Elev 439 Detection 19 one 53 Elev 439 Detection 11 Zone 54 Elev 439 Detection 11 Zone 55 Elev 439 Detection 6 Zone 56 Elev 439 Detection 6

5. Remote Shutdown Panel Zone 13 Elev 383 (Unit 1) Detection 7 BYRON - UNITS 1 & 2 3/4 3-61

TABLE 3.3-11b (Continued)

FIRE DETECTION INSTRUMENTS (UNIT 2) .

INSTRUMENT LOCATION INSTRUMENT TYPE

• TOTAL NU R OF INSTRUMENTS Heat Flame Smoka ,

6. Station Battery Room Zone 67 El'ev 451 Detection '6

7. Diesel Generator Room Zone 37 Elev 401 Suppression 4 Zone 38 Elev 401 Suppression 4 Zone 71 Elev 401 -

Detection 1 Zone 72 Elev 401 Detection -

1

8. Diesel Fuel Storage Zone 39 Elev 401 Suppre ion 1 Zone 40 Elev 401 Suppr ssion 1 Zone 27 Elev 383 Sup ession 3 Zone 28 Elev 383 u aression 3 Zone 10 Elev 383 taction 6

9. Safety Related Pumps Zone 41 Elev 383 Y Suppression 2

.- Zone 42 Elev 383 Suppression 1 -

t. Zone 16 Elev 364 Detection 2 Zone 18 Elev 364 Detection 3 Zone 19 Elev 364 Detection 2 Zone 20 Elev 346 Detection 3 Zone 21 Elev 346 Detection 3 Zone 52 RSH (Unit ) Suppression 8 Zone 11 Elev 330 Detection 23

10. Fuel Storage Zone 39 Ele 401 (Unit 1) Detection 29 Zone 38 E v 426 (Unit 1) Detection 3

11. Auxili y Building Zone 7 Elev 346 Detection 32 Zon 40 Elev 346 Detection -

12 Z e 22 Elev 467 Detection 18 one 62 Elev 451 Detection 11 Zona 14 Elev 401 Detection 4 Zone 15 Elev 401 Detection 4 Zene 64 Elev 401 Detection 3 Zoae 65 Elev 401 Detection 3 Zone 61 Eiev 439 Detection 7 Zone 70 Elev 451 Detection 11 i

BYRON - UNITS 1 & 2 3/4 3-62

TABLE 3.3-11b (Continued)

FIRE DETECTION INSTRUMENTS (UNIT 2) l INSTRUMENT LOCATION INSTRUMENT TYPE

• TOTAL JMBER OF INSTRUMENTS Heat [ Flame Smoke

11. Auxiliary Building (continued)

Ione 75 Elev 426 Detection 33 Zone 25 Elev 467 Detection 7 Zone 17 Elev 364 (Unit 1) Detection 37 Zone 40 Elev 364 (Unit 1) Detection 7 Zone 11 Elev 383 (Unit 1) Detection 37 Zone 8 Elev 401- (Unit 1) Detection 36 '

Zone 23 Elev 426 (Unit 1) Detection 6 Zone 12 Elev 459 Detectio -

11

12. Miscellaneous Zone 26 Elev 864 (Unit 1) ction 12 h) '

\7 TABLE NOTATIONS

• A single detector ihpon marked " Detection" will alarm in the Main Control Room. A single detecWr ' a zone marked " Suppression" will initiate suppression

( and alarm in the Main Co trol Room.

• • These are Containment entilation temperature switches. Upon receipt of a Hi-Hi temperature, suppres on must be manually initiated. These switches are not 720 supervised.

i;

• • • The fire detectio instruments located within the containment are not required to be OPERABLE duri g the performance of Type A containment leakage rate tests.

8YRON - UNITS 1 & 2 3/4 3-63

. ~ - . - - ., -

PLANT SYSTEMS 3/4.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10.1 The Fire Suppression Water Supply System shal be OPERABLE with:

a. Two fire suppression pumps with their dis arge aligned to the fire suppression header, and

b. An OPERABLE flow path capable of taki suction from the flume and transferring the water through distr' ution pipirig with OPERABLE sectionalizing control or isolatic valves to:

1) The yard hydrant isolation alves (for hydrants near buildings containing safety-related quipment),

2) The last valve a f each hose standpipe as required by Specification ~,

3). .The last val a of the deluge valve (on the diesel generator f 1 storage room foam system and manual contain-ment charcoal er deluge systems)., or 2

4) Flow a fal s (on sprinkler systems) as required by Specif on .7.10.2.

APPLICABILITY: A ti s.

ACTION:

a. With one p p and/or one water supply inoperable, restore the i inoperabl equipment to OPERABLE status within 7 days or provide an alternat backup pump or supply. The provisions of Specifica-tions 3 .3 and 3.0.4 are not applicable.

b. With he Fire Suppression Water Supply System otherwise inoperable l est lish a backup Fire Suppression Water Supply System within 24 ours.

l SURVEIL CE REQUIREMENTS 4.7 0.1.1 The Fire Suppression Water Supply System shall be demonstrated l OF ABLE:

l a. At least once per 7 days by verifying the contained water supply l volume, 1

BYRON - UNITS 1 & 2 3/4 7-30

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 31 days by starting the electric otor-driven pump

/

and operating it for at least 15 minutes on recir lation flow,

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

d. At least once per 6 months by performance f a system ring header flush,

e. At least once per 12 months by cyclin each testable valve in the flow path through at least one comp te cycle of-full travel, '

f. At least once per 18 months by p formi.ng a system functional test which includes simulated automa c actuation of the system throughout its operating sequence, and:

1) Verifying that each fi pumo develops a discharge of 150% of rated capacit at 6 of rated pressure (3750 gpm 2 10% gpm at 107 2 1 , nd recording measured performance at minimum a ads.

2) Cycling c va e in the flow path that is not testable during plant o tio through at least one complete cycle of full trav d

3) Ve ng at each fire suppression pump starts (sequentially) nt n the fire suppression water system pressure greater or qual to 125 psig.

g. At least o ce per 3 years by performing a flow test of the system in accordan with Chapter 8, Section 16 of the Fire Protection Handbook, 15th Ed' ion, published by the National Fire Protection Association. ,

4.7.10.1.2 Th fire pump diesel engine shall be demonstrated OPERABLE:

a. A least once per 31 days by verifying:

) The fuel storage tank contains at least 325 gallons of fuel, and

2) The diesel starts from ambient conditions and operates >for at

! east 30 minutes on recirculation flow.

F BYRON - UNITS 1 & 2 3/4 7-31

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) /

b. At least once per 92 days by verifying that a drain sample o diesel fuel from the fuel oil day-tank, obtained in accordance with AS 04057-1981, is within the acceptable limits specified in Table , of ASTM 0975-1977 whenchockedforviscosity, water,andsedimgpi;and

c. At least once per 18 months, during shutdown, by su ecting the diesel to an inspection in accordance with procedu s prepared in conjunction with its manufacturer's recommendati s for the class of service.

4.7.10.1.3 The fire pump diesel starting 24-volt bat ry bank shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying at:

1) The electrolyte level of each ttery is above the plates, and

2) The overall batte tage s greater than or equal to 24 Volts.

b. At least once per kys verifying that the specific gravity is appropriate for nued ervice of the battery, and

c. At least on bv#18 ths, by verifying that:

1) The ies cell plates, and battery racks show no visual ind "on o physical damage or abnormal deterioration, and

2) The batte -to-battery and terminal connections are clean, tight, f ee of corrosion, and coated with anticorrosion material.

l t I 4

1 BYRON - UNITS 1 & 2 3/4 7-32

PLANT SYSTEMS WATER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.10.2 The Water Systems including the Foam Systems in the die 1 generator fuel oil storage tank room, the Sprinkler Systems in the Auxili Building, and the Containment Charcoal Filter Manual Deluge System shall e OPERA 8LE.

AJPLICABILITY: Whenever equipment protected by the above " stems is required to be OPERABLE.

ACTION:

a. With one or more of the above required sy ems inoperable, within

' 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire wate with backup fire suppression equipment for those areas in which red dant systems or components could be damaged; for other areas, e ablish an hourly fire watch patrol.

b. The provisions of Specifications .0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS [12

-~,

4.7.10.2.1 The above require F stem shall be demonstrated OPERABLE:

a. At least once perg3 a , by verifying that each valve (manual, power-operated j oMu matic.) in the flow path is in its correct position, p

b. At least on er months, by cycling each testable valve in the flow path throJ at least one complete cycle of full travel, i

c. At least once er 18 months:

1) By pe arming a system functional test which includes simulated

{

t actu fon of the system, and:

a Verifying a " Fire Trouble" alarm is received when the isolation valve is closed, and b) Verifying a " Fire" alarm is received on actuation of the alarm switch.

2) By a visual inspection of the dry pipe deluge headers to verify their integrity, and

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

l

,d. At least once per 3 years by performing an air flow test through l

each open deluge nozzle and verifying each nozzle is unobstructed.

BYRON - UNITS 1 & 2 3/4 7-33

(

PLANT SYSTEMS ,

WATER SYSTEMS j

, SURVEILLANCE REQUIREMENTS (Continued) j/

1 4.7.10.2.2 The required Sprinkler System shall be demonstr ed OPERABLE:

a. At Feast once per 92 days:

1) By discharging water out of the inspec rs test connections and verifying a " Fire" alarm.

b. At least once per 12 months:

1) By a visual inspection of the s inkler header to verify integrity and that the head s ay pattern is not obstructed.

2) By verifying water flow the ugh the 2-inch test drain at the riser.

4.7.10.2.3 The required Manua System shall be demonstrated OPERABLE:

a. At least once per An s:

1) By cycling i lation valve and verifying the " Fire Trouble" alarm.

2) By 1 e deluge valve.

3) By a visu inspection of the deluge header to verify integrity and tha the spray heads are not obstructed.

BYRON - UNITS 1 & 2 3/4 7-34 ,

n PLANT SYSTEMS CO2 SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.10.3 The following CO2 Systems shall be OPERABLE:

a. Diesel generator rooms and day tank rooms,

b. Lower cable spreading room,

c. Auxiliary feedwater diesel room and day t k room,

d. Diesel-driven Essential Service Water / SW) make-up pumps and day tank rooms, and

e. Cable tunnel room.

APPLICA81LITY: Whenever equipment d by the CO2 systems is required to be OPERA 8LE:

• ACTION:

a. With one or more a ve required CO2 systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> es h continuous fire watch with backup fire suppression equ f r those areas (Lower Caole. Spreading Room) in which red sy ems or components could be damaged; for other areas, estab jan urly fi'rs watch patrol. ~

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

SURVEILLANCE REQUIREMENTS 4.7.10.3.1 Each of th above required CO 2 Systems shall be demonstrated OPERABLE at least on per 31 days by verifying that each valve (manual, power operated or automat ) in the flow path is in its correct position. ,

4.7.10.3.2 Each the above required.CO 2 Systems shall be demonstrated OPERABLE:

j a. At ast once per 7 days by verifying the plant CO2 storage tank 1 el to be greater than 96% (9.6 tons) and river screen house CO 2 orage tank level to be greater than 50% (1 ton), and pressure of oth to be greater than 275 and less than 357 psig, and b At least once per 18 months by verifying:

1) The system, includin'g associated ventilation system fire dampers, actuates both automatically upon receipt of a simulated actuation signal, and manually, and

2) Flow f. nom each nozzle during a " Puff Test."

t BYRON - UNITS 1 & 2 3/4 7-35

PLANT SYSTEMS

~

HALON SYSTEMS LIMITING CONDITION FOR OPERATION z

3.7.10.4 The Halon Systems in tihe upper cable spreadin room shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the on System is required to be OPERABLE.

ACTION:

a. With one or more of the above requir Halon systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuou fire watch with backup fire suppression equipment for those ar s in which redundant systems or components could be damaged; for her areas, establish an hourly fire watch patrol.

b. The provisions of Sp ati s 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS , 4.7.10.4 Each of the ab qu ed Halon Systems shall be demonstrated OPERABLE:

a. At leas er days, by verifying that each solenoid valve in the ath ' in its correct position,

b. At least once r 6 months by verifying Halon storage cylinder weight to be at leas 95% of full charge weight and pressure to be at least.

90% of full harge pressure, and

c. At least ce per 18 months by:

1) Ve fying the system, including associated ventilation dampers, tuates automatically, upon receipt of a simulated actuation ignal, and 2 Perfonnance of a flow test through headers and nozzles to assura no blockage.

8YROH - UNITS 1 & 2 3/4 7-36

f' PLANT SYSTEMS FIRE HOSE STATIONS ,

LIMITING CONDITION FOR OPERATION I

3.7.10.5 The fire hose stations given in Table 3.7-5a for Uni 1 (Table 3.7-5b for Unit 2) shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected y the fire hose stations is requireo to be OPERABLE.

ACTION:

a. With one or more of the fire hose statio given in Table 3.7-5 inoperable, provide gated wye (s) on th nearest OPERABLE hose

, station (s). One o-utlet of the wye sh be connected to the stan-dard length of hose provided for the osa station. The second outlet of the wye shall be connect to a length of hose sufficient to provide coverage for the area ft unprotected by the inoperable hose station. Where it'can be onstrated that the physical routing of the fire hose would suit a recognizable hazard to operating personnel, plant equi o the hose itself, the fire hose shall be stored in a a the outlet of the operable hose station.

Signs shall be mou d bo the gated wye (s) to identify the proper hose to use. The ea ion 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 se is the primary means of fire suppression; otherwise rou ad tional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. The provisi n Sp ifications 3.0.3 and 3.0.4 are not applica.ble.

SURVEILLANCE REOUIREM 4.7.10.5 Each of the fi hose stations given in Table 3.7-5 shall be demonstrated OPERABLE:

a. At least on a per 31 days, by a visual inspection of the fire hose stations cessible during plant operations to assure all required equipmen is at the station,

b. At' lea once per 18 months, by:

1) isual inspection of the stations not accessible during plant operations to assure all required equipment is at the station, 2 Removir;g the hose for inspection and re-racking, and

) Inspecting all gaskets and replacing an'y degraded gaskets in the couplings.

At least once per 3 years, by:

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

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

BYRON - UNITS 1 & 2 3/4 7-37

i I

( TABLE 3.7-Sa j (Unit 1)

= FIRE U0SE STATIONS i

LOCATION ELEVATION HOSE RACK REEL ANGLE VALVE

[ Aux. Roof h

m.

L-10:

L-26:

South wa North wall U-1 of safety valve penthouse - 481 of safety valve penthouse 481 1

2 0FP331 0FP338 Aux. Bldg.

[

t m 5-18: By dumb waiter 480 233 0FP458 S-15: By U-1 prefilters (near s rs) 471 176 0FP329 S-21: By U-2 prefilters (near sta 471 177 0FP334 j Q-17: Wall by elevator in upper cable ro 244* OFP469 j Q-19: Wall by stairs in upper cable room 4 252* OFP477 i

L-11

Outside Southeast corner of upper cable spreading room A-1 467 240 0FP465 R

• L-14: By the southeast door of UCSR C-1 467 2418 0FP466 M-13: By the northwest corner of UCSR A-1 467 242* OFP467

) 7 Q-13: In the northwest corner of UCSR B-1 467 243* OFP468

! Ir$ P-18: Northwest corner of UCSR C-1 467 5* OFP470 H-18: North wall of UCSR C-1 467 2 0FP471 M-18: South wall of UCSR C-2 467 247* OFP472

! L-25: Outside northeast corner of UCSR A-2 467 248 0FP473

/ L-22: In the northeast corner of UCSR C-2 467 -

249* FP474 1

M-23: In the southwest corner of UCSR A-2 467 250* 475 t P-20: West wall of UCSR C-2 467 251* OFP Q-23: In the southwest corner of UCSR 8-2 467 253* OFP47 S-21: By U-2 VA Filters (U-2 side) 464 232 OFP457 S-15: By U-1 VA Filters (U-1 side) 464 234 0FP459 S-21: By VA Filters (U-2 side) 456 231 0FP456 S-15: By VA Filters (U-1 side) 456 235 0FP460 Q-24: Radwaste drimuning Station 387 110 0FP375 L-10: By Control room refrig. units 387 106 0FP385 L-12: By blowdown after filters 387 107 0FP384 S-19: By 2A RilR heat exchanger room 387 112 0FP378

• Fire hoses that do not supply the primary means of fire suppression.

TABLE 3.7-Sa (Continued)

(Unit 1) 1 g FIRE HOSE STATIONS l 8 z LOCATION ELEVATION HOSE RACK REEL ANGLE VALVE

[ Aux. Bldg. (Con ed) -

h in M-26:

M-18:

Radwaste By Aux. Feedw trol panel r motor driven pump 1A 387 387 109 108 0FP377 0FP383 s N-23: By remote shut anel U-1 387 111 0FP376 e- Q-15: By 480V MCC 132X3 387 113 0FP382 to V-18: By letdown heat exchang 387 114 0FP379 P-7: West wall 6.9 kV switchgear om 455 20 0FP324 L-11: In UC HVAC Hm OA of LCSR C-1 5 22 0FP332 L-25: By OBVC HVAC room 27 0FP335

, M-8: South wall of battery room 4 279 0FP638 l M-26: South wall of battery room 451 280 0FP639 M-18: North wall U-1 A8 by door 4 238* OFP463 L-7: East wall LCSR A-1 443 207* OFP330 -

w M-10: In the southeast corner of LCSR B-1 443 208* OFP327 -

D P-10: In the southwest corner of LCSR B-1 443 209* OFP325 u M-13: South wall of LCSR C-1 443 10* OFP326 i <1 P-13: West wall of LCSR D-1 443

• OFP328 l

M-18: South wall of LCSR U-2 by door 443 239 0FP464 L-29: East wall LCSR A-2 443 212* OFP336 M-26: Northeast corner of LCSR B-2 443 213* FP337

! P-26: Northwest corner of LCSR B-2 443 214* 40 M-23: North wall of LCSR C-2 443 215* OFP P-21: East wall _of LCSR 0-2 443 216* OFP333 S-21: By cabinet 2RY01EC (elec. pen. area) 431 229 0FP454 l S-24: By U-2 cont. shield wall (elec pen. area) 431 230 . OFP455 l S-15: By Pzr htr. transformer (elec pen. area) 431 236 0FP461 5-12: By U-1 cont. shield wall (elec pen. area) 431 237 0FP462 i M-18: Rad chem offices 430 57 0FP323 l Q-10: Back of Div. Il swgr roor 430 283 0FP640

{ P-ll: Outside Laundry Room 430 52 0FP313 Q-19: By U-2 VCI valve aisle 430 54 0FP342 P-24: By radwaste evaporator 430 55 0FP343 V-17: By east door to decon/ change area 430 58 0FP319 V-17: By west door to decon/ change area 430 61 0FP320 j

• Fire hoses that do rot supply the primary means of fire suppression.

i l TABLE 3.7-Sa (Continued) i (Unit 1) .

g FIRE HOSE STATIONS

n E LOCATIO .

ELEVATION HOSE RACK REEL ANGLE VALVE -

Aux. Bldg. inued)

Io 5-15: By Pzr. tr. transformer (elec pen. areal 419 174 0FP322 d Q-10: By electr I penetration area 419 205 0FP321 x L-11: By waste oil nk room 405 90 0FP315 e- P-18: By elevator 405 91 0FP318 m P-23: By spent resin pump 405 92 0FP349 Q-II: By laundry tanks 405 93 0FP314 S-21: East of U-2 hydrogen rec iner 405 94 0FP348 V-21: West of U-2 hydrogen recomb -

05 95 0FP345 V-15: West of U-l hydrogen'recombiner panel trol [M  % OFP316 5-15: East of U-1 hydrogen recombiner 40 97 0FP317 N-ll: By the recycle holdup Lanks 130 0FP373 R

M-13: By the U-l stairs 3 131 0FP374 '

P-13: By panel IPL84J8 368 132 0FP369 7 L-20: By the U-2 stairs 368 133 0FP355 8 P-21: By the blowdown condenser 368 134 0FP356 L-25: By the PW M/U pumps 368 5 ,

OFP361 N-25: By chemical drain tank 368 13 0FP357 S-18: By panel IPL86J 368 138 0FP362 Q-ll: By Aux. Bldg. floor drain tanks 368 139

• OFP368 U-15: By U-l spray add tank 368 140 372 V-18: By U-2 cent. chg. pump room 368 141 0FP3 P-11: By recycle evaporator feed pumps 350 151 0FP381 M-13: By U-l stairs 350 152 OFP370 N-23: By gas decay tanks 350 154 OFP352 Q-19: By "B" Aux. Bldg. Equip. drain tank 350 155 0FP365 Q-17: By "A" Aux. Bldg. Equip. drain tank 350 156 0FP371 Q-13: By collection sump pumps 350 157 0FP380 S-18: Between moderating heat exchangers 350 158 0FP354 V-18: Between BR. chiller units 350 161 0FP353 W-15: By CS pump 1A 350 163 0FP367 L- 19: By 08 recycle evap. room 350 153 0FP363

t TABLE 3.7-Sa (Continued)

(Unit 1) n; FIRE HOSE STATIONS 8

z LOCATION ELEVATION HOSE RACK REEL ANGLE VALVE

^

Aux. Bldg. (Continue

[

55 M-13: By leak detection 334 165 0FP448 L! P-18: By elevator pit 334 166 0FP449 to P-18: By 18 SX pump room - 334 167 0FP351 e- M-23: By 18 SX pump room 334 168 0FP350 fuel Hand. Bldg.

Z-15: South of decon. area 0 170 OfP389 X-21: Narth of spent fuel pool 171 0FP386 Z-15: By 480V MCC 134X6 0 172 0FP388 AA-19: Outside FC pump room 4 , 173 0FP387 Cont. #1 R-17: By reactor head assembly area 430 62 IFP163

}{ R-2: By accumulator tank IC 430 63 -

IFP154 u

E R-7: By equipment hatch 430 64 IFP160 R-12: By charcoal filter IA 430 65 IfP157 R-17: By south stairs 403 98 P164 ,

R-2: By RCFC IC 403 99 1 5 R-7: By pressurizer (outside missile shield) 403 100 IFP1 R-12: By panel IPL69J 403 101 1FP158 R-12: By PRT 381 143 IFP159 R-17: By south stairs 381 144 1FP162 R-2: By RCFC IC 381 145 IFP156 R-7: By panel IPL52J 381 . 146 1FP155 .

Turbine Bldg.

K-14: By the control room -

451 16 1FP194 L-6: Outside IB D/G room 405 87 IFP183 K-10: Outside 1A D/G room 405 281 IFP275 L-7: Basement of Turbine Bldg. 361 129 IFP184 L-7: Outside Div. 12 SWGR 430 47 1FP181 L-10: Outside Div. 11 SWGR 430 51 IFP182 L-5: Outside non-ESF SWGR 455 18 IFP180 L-10: Outsiele battery room 455 21 IFP179

TABLE 3.7-Sb (Unit 2) c; FIRE h0SE STATIONS LOCATIO ,

ELEVATION HOSE RACK REEL ANGLE VALVE

[ Aux. Roof 55 L-10: South wall of safety valve penthouse 481 1 0FP331 v! L-26: North wall U-2 safety valve penthouse 481 2 0FP338 w

e. Aux. Blog.

$~18: By dumb waiter 480 233 0FP458 S-15: By U-1 prefilters (near stair 471 176 0FP329 S-21: By U-2 prefilters (near stairs) 471 177 0FP334 Q-17: Wall by elevator in upper cable room 9 244* OFP469 Q-19: Wall by stairs in upper cable room 69 252* OFP477 L-ll: Outside Southeast corner of upper cable spreading room A-1

• 240 0FP465

u. L-14: By the southeast door of UCSR C-1 46

• OFP466 30 M-13: By the nortuwest corner of UCSR A-1 467

• OFP467

~4 Q-13: In the northwest corner of UCSR B-1 467 3* OFP46a A

P-18: Northwest corner of UCSR C-1 467 5* OFP470 M-13: North wall of UCSR C-1 467 24 0FP471 H-18: South wall of UCSR C-2 467 247* OFP472 L-25: Outside northeast corner of UCSR A-2 467 248 0FP473 L-22: In the northeast corner of UCSR C-2 467 249* OFP474 M-23: In the southwest corner of UCSR A-2 467 250" 0FP475 P-20: West wall of UCSR C-2 467 251* P476 Q-23: In the southwest corner of UCSR B-2 467 253* 0 78 S-21: By U-2 VA Filters (U-2 side) 464 232 . OFP45 S-IS: By U-l VA Filters (U-l side) 464 234 0FP459 5-21: By VA Filters (U-2 side) 456 231 0FP456 5-15: By VA Filters (U-1 side) 456 235 0FP460 Q-24: Radwaste Drumming Station 387 110 0FP375 L-10: By control room refrig. units 387 106 0FP385 L-12: By blowdown after filters 387 107 0FP384 S-19: By 2A RilR lleat Exchanger Room 387 112 OfP378

• fire hoses that do not supply the primary means of fire suppression.

.. ~ _ _ - .-- . _ .

TABLE 3.7-5b (Continued)

(Unit 2) co FIRE il0SE STATIONS 5

@ LOCA ELEVATION HOSE RACK REEL ANGLE VALVE C

Aux. Bi b nLinued) 2 M-26: Radwaste ntrol Panel 387 109 0FP377 d M-18: By Aux. Fee ter motor driven pump 1A 387 108 0FP383 g N-23: Dy remote shut panel U-1 387 111 0FP376

e. Q-15: By 480V MCC 132X3 387 113 0FP382 m V-18: By letdown heat excha r 387 114 0FP379 P-29: West wall 6.9kV SWGR Re 455 29 0FP339 L-11: In UC llVAC Rn OA of LCSR C-1 455 22 0FP332 L-25: By OSVC HVAC Room 455 27 0FP335 M-8: South wall of battery room 451 279 0FP638 M-26: South wall of battery room p1 283 0FP639 M-18: North wall U-1 A8 by door 4 238* OFP463 L-7: East wall LCSR A-1 443 207" 0FP330 1:' M-10: In the southeast corner of LCSR B-1 08* OFP327

• • P-10: In the southeast corner of LCSR B-1 443 2098 0FP325 Y M-13: South wall of LCSR C-1 443 210* OFP326 O P-13: West wall of LCSR D-1 443 211* OFP328 M-18: South wall of LCSR U-2 A8 By Door 443 2 . OFP464 L-29: East wall LCSR A-2 443 212* OFP336 M-26: In Northeast corner of LCSR B-2 443 213* OFP337 P-26: In Northwest corner of LCSR B-2 443 214* OFP340 M-23: North wall of LCSR C-2 443 215* OFP341 P-21: East wall of LCSR D-2 443 216* P333 5-21: By cabinet 2RYOlEC (elec. pen. area) 431 229 . OFP S-24: By U-2 cont. shield wall (elec pen. area) 431 230 0FP45 5-15: By Pzr htr. transformer (elec pen area) 431 236 0FP461 5-12: By U-1 cont shield wall (elec pen area) 431 237 0FP462 M-18: Rad Chen Of fices ,

430 57 0FP323 P-11: Outside Laundry Room 430 52 0FP313 Q-19: By U-2 VCT valve aisle 430 54 0FP342 P-24: By radwaste evaporator 430 55 0FP343 V-17: By east door to decon/ change area 430 58 0FP319 V-17: By west door to decon/ change area 430 61 0FP320

^ Fire hoses that do not supply the primary means of fire suppression.

TABLE 3.7-5b (Continued)

(Unit 2)

e. FIRE HOSE STATIONS 5 '

E LOCATION ELEVATION HOSE RACK KEEL ANGLE VALVE

[ Aux. Side. (Con )

5 V-19: By West Door Decon Pad & Storage 430 59 0FP344 d Q-26: Back of Div. 21 Boom 430 2&E OFP641 S-21: By U-2 Pzr. HTR. Tr oreer (elec. pen. area) 419 175 0FP347 Q-26: By U-2 Elect. Penetrat Area 419

[ 206 0FP346 L-11: By weste oil tank room 405 90 0FP315 P-18: By elevator 405 91 0FP318 P-23: By spent resin pumps 405 92 0FP349 Q-11: By laundry tanks i

5 93 0FP314 S-21: East of U-2 hydrogen recombiner 94 0FP348 V-21: West of U-2 hydrogen recambiner 95 0FP345 V-15: West of U-1 hydrogen recombiner control w panel 5 96 0FP316 1 S-15: East of U-1 lr,4. :;:.7 receabiner 40 0FP317 7 N-11: By the recycle holdup tanks 368 0FP373 2 M-13: By the U-1 stirs l 368 1 0FP374 P-13: By panel IPL84J8 368 0FP369 L-20: By the'U-2 stairs 368 13 0FP355 P-21: By the blotd.wn condenser 368 134 0FP356

• L-25: By the PW M/U pumps 368 135 0FP361 W-25: By chemical orain tank 368 136 0FP357 S-18: By panel IPL86J 368 138 0FP362 Q-11: By Aux. 81dg. floor drain tanks 368 139- 368 Q-25: By spent resin flushing pump 368 137 0FP U-21: By U-2 spray add tank 368 142 0FP358 y V-18: By U-2 cent. chg. pump room 368 141 0FP366 3 P-11: By recytle evaporator feed pumps 350 151 0FP381 g M-13: By U-1 stairs 350 152 0FP370 '

. M-23: By gas decay tanks 350 154 0FP352 5 Q-19: By "8" Aux. 81dg. Equip. drain tank 350 155 0FP365 Q-17: By "A" Aux. 81dg. Equip. drain tank 350 156 0FP371 m

}

TABLE 3.7-5b (Continued)

(Ur.it 2) co FIRE il0SE STATIONS ,

Y

@ LOCATION ELEVATI0tl HOSE RACK REEL ANGLE VALVE Aux. Bldg. (Contin k S-18: Between moderati , heat exchangers 350 158 0FP354 O V-18: Between BR chiller ts 350 151 0FP353

" By U-2 collect' ion sump p 350 0FP364 Q-21: s 159

• W-21: By CS Pump 2A 350 164 0FP359 i L-19: By 08 Recycle Evap Rs 350 153 0FP363 M-13: By leak detection sump 334 165 0FP448 P-18: By elevator pit 4 166 0FP449

, P-18: By 18 SX pump room .

167 0FP351 M-23: By IB SX pump room 168 0FP350 Fuel Hand. Bldg.

R Z-15: South of decon. area 430 170 0FP389

• • X-21: North of spent fuel pool 430 171 0FP386

7 Z-15: By 480V MCC 134X6 405 72 0FP388 g AA-19: Outside FC pump room 405 1 0FP387 Cont. - #2 R-26: By personnel hatch 430 66 .

2FP163 R-31: By west stairs 430 67 2FP154 R-37: By reactor head assembly area 430 68 FP160 R-42: By charcoal filter 2A 430 69 .157 R-26: By pressurizer (outside missile shield) 403 102 2FP 4 R-31: By west stairs 403 103 2FP15 R-37: By north stairs 403 104 2FP161 R-42: Outside missile barrier by Loop 0 MS pipe 403 105 2FP158 R-26: By panel 2PL52J 381 147 2FP165 R-31: By west stairs 381 148 2FP156 R-37: By north stairs 381 149 2FP162 R-42: By PRT . 381 150 2FP159

s T.ABLE 3.7-5b (Continued)

(Unit 2) co FIRE HOSE STATIONS -

5 E LOCATION ELEVATION HOSE RACK REEL ANGLE VALVE Turbine Bldg. ntinued) 5'i L-30: Outside Unit non-ESF swgr 455 14 2FP232 d L-24: In IM shop 455 15 2FP237 e-o L-26: Outside Unit 2 bat room 455 28 2FP233

e. L-29: Outside Div. 22 swgr 430 42 2FP231 m L-26: Outside Div. 21 swgr 430 56 2FP230 L-29: Outside 28 D/G room 405 82 2FP229 K-28: Outside 2A D/G room 405 282 2FP275 l-29: By 2C cond/cond booster pump 364 124 2FP228 3; .

• e f

_-- .-- J

PLANT SYSTEMS 3/4.7.11 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 4

3.7.11 All fire rated assemblies (walls, floor / ceilings, cabl tray enclosures and other fire barriers) separating safety-related fire areas r separating portions of redundant systems important to safe shutdcwn wit in a fire area and all sealing devices in fire-rated assembly penetrations (fi e doors, fire windows, fire dampers, cable, piping and ventilation duct enetration seals) shall be OPERABLE.

APPLICA8ILITY

At all times.

ACTION:

1 a. With one or more of the above required re rated assemblies and/or i sealing devices inoperable, within 1 ur either establish a contin-uous fire watch on at least e side f the affected assembly, or verify the OPERABILITY of '

ete ors on at least one side of the inoperable assembly and h n hourly fire watch patrol.

b. The provisions of Spec fi t'on 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS g/

4.7.11.1 At least once p ikjont the above required fire barrier penetra-i tions and penetration se Yevi s shall be verified OPERABLE by:

a. Performing i pection of:

1) The expo sur aces of each fire rated assembly,

2) Each fire wi ow/ fire damper and associated hardware.

3) At least 1 of each type of sealed penetration. If apparent changes ip/ appearance or abnormal degradations are found, a visual i pection of an additional 10% of each type of sealed penetr ton shall be made. This inspection process shall con-tinue ntil a 10% sample with no apparent changes in appear-ance r abnormal degradation is found. Samples shall be selected su that each penetration seal will be inspected ev'ery 15 years,

b. Perfo ing a functional test of at least 10% of the fire dampers. If

= any nconforming dampers are found, an additional 10% will be func-

! tio 11y tested. This process will continue until an acceptable j s le is found.

i 4.7.11.2 ach of the above required fire doors shall be verified OPERABLE by inspecti the release and closing mechanism and latches at least once per 6 month and by verifying:

The OPERA 8ILITY of the Fire Door Supervision System for each electri-cally supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days,

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

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

I BYRON - UNITS 1 & 2 3/4 7-47 ,

INSTRUMENTATION

, BASES SEISMIC INSTRUMENTATION (Continued) i The response spectrum analyzer computes the response spectrum of the event for two sensor locations, compares"it to the design response spectra of the plant, and indicates whether the event exceeded the operating basis earthquake criteria or the safe shutdown earthquake criteria.

This instrumentation is consistent with the recommendations of Regulatory Guide 1.12. " Instrumentation for Earthquake," April 1974. .

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERA 8ILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential < radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

! 3/4.3/3.5 REMOTE SHUT 00WN INSTRUMENTATION ,

The OPERA 8ILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the' facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.

1 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION 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 1.97, Revision 3, " Instrumentation

, for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During l and following an Accident," May 1983 and NUREG 0737, " Clarification of TMI

Action Plan Requirements," November 1980.

i

., ' 17 FIRE OtitcIION IN5iRUMtNIA11UM i

OPERABILITY of the ion instrumentatio at both adequate

! warning capability is available detection of fires and that ,

i Fire Suppression Systems, that ua tre detectors, will discharge extinguishing agents in e y manner. Prompt n and suppression of l fires will redue potential for damage to safety-relate ment and is an integr . ment in the overall facility fire protection progra , h3 zone de ions given in Table 3.3-11 are from electrical schematic diagram .

l BYRON - UNITS 1 & 2 8 3/4 3-5 >

INSTRUMENTATION ,

J BASES M TECTION INSTRUMENTATION (Continued)

Fire dete s that are used to actuate Fire Suppression S represent a more critically 1 ant component of a plant's fire ion program than detectors that are insta solely for early fir ing and notification.

Consequently, the minimum numb operabl e detectors must be greater.

The loss of detection capa

• for Suppression Systems, actuated by fire detectors represents nificant degrada f fire protection for any area. As a result, stablishment of a fire watch 1 must be initiated at an earlier s than would be warranted for the loss o - ctors that provide o arly fire warning. The establishment of frequent patrols in t facted areas is required to provide detection capability un the erable instrumentation is restored to OPERABILITY.

3/4.3.3.8 LOOSE-PART DETECTION SYSTEM ,

The OPERABILITY of the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant System components. The allowable out-of-service times and Surveillance Requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Drogram for the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION I

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 /

l Trip Setpoints for these instruments shall be calculated and adjusted in i 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 c' Appendix A to 10 CFR Part 50.

3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrnnentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents 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 alar.a/ trip will occur prior to exceeding the limits of 10 CFR Part 20.

BYRON - UNITS 1 ANO 2 8 3/4 3-6

PLANT SYSTEMS BASES 3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) 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. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation. monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

% 4.7.10 FIRE SUPPRESSION SYSTEMS OPERABILITY of the Fire Suppression Systems ensures that equate fire sup sion capability is available to confine and extingui fires occurring in ortion of the facility where safety-related uipment is located. The Fir pression System consists of the water stem, foam, spray, and/or sprink CO 2 , Halon, and fire hose statio . The collective capability of the Fire Su ession Systems is adequate t minimize potential damage to safety-related equi nt and is a major elem t in the facility Fire Protection Program.

In the event that portions of the Supp ssion Systems are inoperable, alternate backup fire-fignting equipment is ired to be made available in the affected areas until the inoperable equi is restored to service.

When the inoperable fire-fighting equipmery is in .ded for use as a backup means of fire suppression, a longer perjd of time 1 allowed to provide an i

alternate means of fire fighting tharff the inoperabl !quipment is the pri-mary means of fire suppression. 3 gpm pump capacity based on.NFPA 20, 1981 standards which call for 1 of rated capacity (2500 ) at 65% of dis-charge pres sure.

The Surveillance R irements provide assurance that the min m OPERABILITS requirements of the F e Suppression Systems are met. An allowance made for ensuring a suffic t volume of Halon in the Halon sto, rage tanks by v ifying either the wei or the level of the tanks. Level measurements are ma by i either a U.L or F.M. approved method.

I e event the Fire Suppression Water System becomes inoperable, imme ate corr ive measures must be taken since this system provides the major fire ,

s ression capability of the plant.

_t BYRON - UNITS 1 & 2 8 3/4 7-7 l

I

PLANT SYSTEMS BASES h FIRE RATED ASSEMBLIES.

The func integrity of the fire rated assemblies and barrier I penetrations ensure t fires will be confined or adequately ret from spreading to adjacent po ns of the facility. These design f uees minimize the possibility of a single rapidly involving several as of the facility prior to detection of and the ex uishing of the fir he fire barrier

! penetrations are a passive element . he facility e protection program and are subject to periodic inspections.

~

l Fire barrier penetrations, includi ab enetratio6 barriers, fire 2

doors and dampers are considered fu onal when observed condition is the

! same as the as-designed conditio For those fire b ier penetrations that are not in the as-designed c tion, an evaluation sha be performed to show that the modification ha t degraded the fire rating of fire barrier penetration.

1 l During pe ds of time when a barrier is not functional, either. '1) a continuous e watch is required to be maintained in the vicinity of t affecte arrier, or (2) the fire detectors on at least one side of the af ted barr must be verified OPERABLE and an hourly fire watch patrol establishe , ,

l l'the barrier is restored to functional status.

7 3/4.7.12 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment l will not be subjected to temperatures in excess of their environmental i qualification temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERA 8ILITY.

l t

c\fE lb b h-9 l dcick pay 3 3/*f 7-8 l

l l

i I

BYRON - UNITS 1 & 2 8 3/4 7-8

r ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Superintendent, Byron Station, shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence. "

6.1.2 The Shift Engineer (or during his absence from the control room, a designated individual) shall be responsible for the control room command

_ function. A management directive to this effect, signed by the Division Vice President and General Manager-Nuclear Stacions shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION

~

OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in M gure-6c2-1 M UNIT STAFF T4;;,

'n 3:1 ces C_ H M lS

,g.-nr-. -

6.2.2 The unit organization shall be as shown i Hgure-Gr2dand:

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

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room;

c. A Radiation Chemistry Technician,* qualified in radiation protection procedures, shall be on site when fuel is in the reactor;

d. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during

this operation;

e. Brigade of at least five members

• sha11 M -4rrtTTiief i onsite at a The Fire JLr.igedr-Mall not include the Shift}

l. Engineer, and t ghe%. m . . M -en of the minimum shift crew necess TUe shutdown of the unit ai.m Qonnel required her essential functions during a fire emergency, %

• TheRadiationChemistryTechnicianand-Hre-Brigede-compositikmaybeless than the minimum requirements for a period 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

fill the required positions.

. BYRON - UNITS 1 & 2 6-1

~ ~ ~ ~

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) - _ _ -

N

e. f. Administrativeprocsduresshallbedevelopedandtaplesinntedto limit the workin functions; e.g.,g ifcensed hours ofSenior unit staff who perform Operators, licensed safety related 0p,erators, health physics personnel, equipment operators, and key Qintenance personnel.

~

J.

The amount' of overtime worked by Unit staff members performing '

' safety-related functions shall be Ifmited in accordance with the '

NRC Policy Statement on working hours (Generic Letter No. 82-12).

6.2.3 ONSIfE NUCLEAR SAFETY GROUP (ONSG) .

FUNCTION .

i . -. . .

~

6.2.3.1 The 0NSG serves as an independent safety engineering gro'up and shall '

function to examine plant operating characteristics, NRC issuances, industry '

1dvisories, REPORTA8LE EVENTS and other sources of plant design and operating experience information, including plants of similar design, which any indicate

' areas for faproving plant safety. The 0NSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, opera-1 tier.. setivities or other means of taproving plant safety to the Manager of Nuclear Safety, and the Superintendent, Byron Station.

COMPOSITION j-

"- 6.2.3.2. The ONSG shall be composed of at least four, dedicated,' full-time engineers located on site.

RESPONSIBILITIES s

6.2.3.3 The 0NSG shall be responsible for mainta'ining surveillance of plant activitiss to provide indepen: font verification

• that these activities are performed correctly and that human errors are reduced as such as practical.

RECOR05 __

i 6.2.3.4 Records of activities performed by the 0NSG shall be prepared, main-l tained, and. forwarded each calendar month to the Nanager of Nuclear Safety, l and the Superintendent, Byron Station.

6.2.4 SHIFT TECHNICAL ADVISOR _ _ _ - . . _ _. .

The Station Control Roos Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal operating or accident conditions. During these conditions the SCRE or other on duty STA shall provide technical support to the

' Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safs operation of the unit.

• Not responsible for sign-off function. -

BYRUN - UNITS 1 & 2 6-2 Amendment flo.1 l

- , - , _,_,-.c , _ , , - - - , , - - - .- - - - - - , . - - - - - , , - . , , _ _ . . - , , . , _ . - - - - , - - - - - - - - - - . - - - , - - , .

ADNINISTRATIVE CONTROLS ONSITE (Continued)

3) Review of all proposed changes to the Technical Specifications;

4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;

5) Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the 1 Division Vice President and General Manager - Nuclear Stations ,

and to the Supervisor of the Offsite Review and Investigative l Function;

6) Review of all REPORTABLE EVENTS;

7) Performance of special reviews and investigations and reports thereon as requested by the Supervisor of the Offsite Review

. and Investigitive Function;

8) Review of the Station Security Plan and implementing procedures and submittal of recommended changes to the Division Vice President and General Manager - Nuclear Stations;

9) Review of the Emergency Plan and station implementing procedur,es

, and submittal of recommended changes to the Division Vice l President and General Manager - Nuclear Stations;

10) Review of Unit operations to detect potential hazards to nuclear safety;

11) Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the cortective action to prevent recurrence and the forwarding of these reports to the Division Vice President and General Manager - Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function; -ande -

12) Review of changes to the PROCESS CONTROL PROGRAM, the 0FFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems;and r 3) Review of the Fire Prowchon Proyom and implementing indrochons

c. Authority and submWol of n commended c.hanges to* oppswe geview ond Inves h3 otive FuncNon .

The Technical Staff Supervisor is responsible to the Station Superintendent and shall make recommendations in a timely manner in -

all areas of review, investigation, and quality control phases of plant maintenance, operation, and administrative procedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulat.fons, and procedures when in his opinion sur.h action is necessary. The Station Superintendent shall follow such recommendations or select a course BYRON - UNITS 1 & 2 6-13 .%endment No. 2

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

b. The emergency operating procedures required to implement the' require-ments of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Sec-tion 7.1 of Generic Letter No. 82-33;

c. Plant Security Plan implementation,

d. Radiological Emergency Response Plan implementation,

e. PROCESS CONTROL PROGRAM implementation,

f. OFFSITE DOSE CALCULATION MANUAL implementation, and "

g. Quality Assurance Program implementation for eff1'uent and environ-mental monitoring, and

b. Ecc Protecficw Pr opom irnplemenb1 hon.

6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.8.3 Temporary changes to procedures of Specification 6.8.1 above, may be made provided:

a. The intent of the original procedure is not altered;

b. The change is approved by two members of the plant rr.anagement staff, at least one of whom holds a Senior Operator license on the Unit affected; and

c. The change is documented,' reviewed by the Onsite Review and Investi-gative Function, and approved by the Station Superintendant within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a. Reactor Coolant SgJFCes Outside Containment A program'to reduce leakage from those portions of systems outside I

containment that could contain highly radioactive fluids during a l serious transient or accident to as low as practical levels. The l systems include the recirculation portion of the Containment Spray i - System, Safety Infection System, Chemical and Volume Control System, and RiiR System. The program shall include the following:

1) Preventive maintenance and periodic visual inspection recuirements, -

and

2) Integrated leak test requirements for each system at refueling cycle intervals or less.

BYRON - UNITS 1 & 2 6-16

F- - T 4

ATTACHMENT 3 FIRE PROTECTION REPORT CHANGE

, 3 4.0 Fire Protection Program The fire protection program at Byron and Braidwood is implemented through station administrative procedures BAP/BwAP 1100-1, respectively.

These procedures establish administrative procedures BAP/BwAP 1100-2 through BAP/BwAP 1100-19, which specifically address all aspects of the fire protection program, ranging from establishing and training of the fire brigade, to surveillance and testing of fire protection systems, and remedial actions for systems or equipment out of service.

The following fire protection features will be subjected to periodic tests and inspections:

a. Fire alarm and detection systems.

b. Wet pipe sprinkler systems.

c. Deluge systems

d. IIalon 1301 system

e. Cart.on dioxide system

f. Foam application system

g. Fire pumps

h. Fire barriers (walls, fire doors, penetration seals, fire dampers, etc.)

1. Manual suppression (fire hoses, extinguishers, hydrants)

Equipment out of service including fire suppression, detection, and barriers will be controlled through the administrative program and appropriate remedial actions taken. The program requires all impairments to the fire protection system be identified and appropriate notification given to the Fire Marshall for evaluation. Based on the condition,

! engineering analysis may be required to determine the extent of the fire hazard to safe plant operatfora. As conditions warrant remedial actions would include compensatory measures to ensure an equivalent 3

level of fire protection in addition to timely efforts to effect repairs

{ and restore the equipment to service.

All procedures will be tracked by the General Surveillance Program which is summarized and implemented by administrative procedures BAP/BwAP 1400-1. This program is a computerized scheduling mechanism designed to prompt the performance and satisfactory execution of all procedures entered into the system.

The fire protection program is covered by the Commonwealth Edison

, Company Quality Assurance Program. Fire protection activities are thus subject to audit under the applicable portions of the Q.A. program to ensure proper implementation and compliance with commitments.

)

ATTACHMENT 4 FIRE PROTECTION REPORT CHANGE The. proposed amendment involves two changes that must be evaluated for no significant hazards considerations. These changos include:

1. Revision of License Condition 2.C(6) to the standard License Condition presented in Generic Letter 86-10.

2. Removal of the Fire Protection Technical Specifications and the addition of Fire Protection program requirements to the Administrative Control Section 6 of the Technical Specifications.

10CFR50.92 states that a proposed amendment will involve a no significant hazards consideration if the proposed amendment does 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.

The discussion below addresses each of these three criteria and demonstrates that the proposed amendment involves a no significant hazards consideration.

The proposed revision to the License Condition is in accordance with the guidance provided in Generic Letter 86-10 for l

Commonwealth Edison requesting the removal of the Byron Station Fire Protection Technical Specifications. The proposed License Condition l is virtually the same as the existing License Condition with minimal changes. The revision is proposed to be consistent with the NRC goal of standardizing the Fire Protection Program License Conditions to ensure uniform enforcement of fire protection requirements. The change requested is to the license condition which providos the guidelines for maintaining and making changes to the Station's Fire Protection Program and is not a change affecting the design or function of a particular feature of the fire protection system.

Since the License Condition wording is virtually the same, the 1

i

1 change does not involve a significant increase in the probability or consequences of an accident previously evaluated. It does not create the possibility of a new or different kind of accident from those previously evaluated. It also doesn't involve a significant reduction in the margin of safety since the license condition still requires that a 10CFR50.59 evaluation for identification of unreviewed safety questions be performed for each proposed change.

With the proposed license condition, as with the existing license condition, each change to the fire protection program will be evaluated for its impact on the fire hazards analysis and the margin of safety.

The second revision requests the removal of the Fire Protection Technical Specifications and the addition of certain i administrative control requirements. Removing the Fire Protection Technical Specifications does not increase the probability or consequences of an accident previously evaluated; the accident evaluated being the postulated fire in the fire hazard analysis documented in the Fire Protection Report. Removing these Technical Specifications does not alter the results of the fire hazards analysis. The Technical Specifications provide requirements for

fire protection of equipment important to the safe shutdown of the 1 plant. The proposed change does not remove or degrade Byron Station's requirement for maintaining an adequate level of fire protection. The fire protection requirements to demonstrate 1 operability or take remedial actions as required will be maintained through Byron Station's administrative program. So a level of fire i protection consistent with that currently existing will remain unchanged.

A new or different kind of accident from those previously evaluated is not created. The proposed change only involves a transfer of the controlling mechanisms for the fire protection requirements from the Technical Specifications to Byron Station's 2 administrative program. The Fire Protection Program License Condition 2.C(6) and the proposed changes to Technical Specification

' Administrative Control Section 6.0 requires that for any proposed 4 changes to the Fire Protection Program requirements, a 10CFR50.59 evaluation be performed. In addition, an onsite review involving personnel from different cognizant functional areas will also be required to review any proposed changes for acceptability. This demonstrates adequate control for evaluation of proposed changes to the Fire Protection Program. Therefore, individual changes will continue to be evaluated for their impact on the fire hazards analysis.

Again this proposed change is administrative in nature and does not involve a particular change to the fire hazards analysis previously documented. Therefore, it does not involve a reduction in the margin of safety. Each individual change will continue to be evaluated separately for their impact on the margin of safety. The

!. proposed revision will ensure that adequate review of proposed changes to the Fire Protection program continues to be performed.

\

Therefore, since the proposed license amendment satisfies the criteria specified in 10CFR50.92. Commonwealth Edison has determined that a no significant hazards consideration exists for this item and requests its approval in accordance with the provisions of 10CFR50.91(a)(4).

2051K 9

O