ML17158A818

Proposed Tech Specs,Relocating Fire Protection Program from TS to Another Controlled Document Following Guidance of GL 88-12

ML17158A818
Person / Time
Site:	Susquehanna
Issue date:	08/11/1995
From:	PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17158A817	List: ML17158A816 ML17158A818
References
GL-88-12, NUDOCS 9508150098
Download: ML17158A818 (81)

Text

ATlACHMENT1 TO PLA-4352 Page 2 of 58 INDEX LIMITIHG CONDITIONS FOR OPERATION AHD SURVEILLANCE RE UIREMEHTS SECTION 3/4. 3 INSTRUMENTATION PAGE 3/4.3.1 REACTOR PROTECTION SYSTEM IHSTRUMEHTATION............

3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.........

3/4 3-9 3/4. 3. 3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.........

3/4 3-27 3/4. 3. 5 REACTOR CORE ISOLATION COOLIHG SYSTEM ACTUATION INSTRUMENTATION...................

3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION..

3/4. 3. 7 MONITORING INSTRUMENTATION Radfatfon Honktorfng Instr~ntatfon.......

Seismic Monitorfng Instruaentatfon.........

Meteorologfcal Monitoring Instr~ntatkon..

Remote Shutdmm Monftorfng Instruaentatfon.

Accfdent Monitoring Inst~ntatfon........

Source Range Monitors......................

Travorsfng In-Core Probe System............

Chlorine Detection System..................

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3/4. 3. 4 RECIRCULATION PUMP TRIP ACTUATION IHSTRUMEHTATION AWS Reef rculation Pump Trfp System Instrumentation..

End-oi'-Cycle Recirculation Pump Trip System nstrumentation......................................

3/4 3-36 3/4 3-40 3/4. 3-46 3/4 3-51 3/4 3-57 3/4 3-61 3/4 3-64 3/4 3-67 3/4 3-70 3/4 3-74 3/4 3-75 3/4 3-76 Radioactive Liquid Effluent Monitoring InSitlNntatfOnoo

~ o ~ o..ooo.o.oooo

~ oooo.ooo

~ oo ~ ooooooo Radioactive Gaseous Effluent Monitoring Instrueentatfon......'................................

Loose-Part Oetectfon Systee..........................

3/4 3-81 3/4 3-86 3/4 3-93 3/4.3.8 TURSINE OVERSPEED PROTECTION SYSTEM...................

3/4 3-94 3/4.3. 9 FEEDWATER/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..............................

3/4 3-95 SUSquEHANNA - UNIT 1

'ss508i 500'P8 9'508i i PDR ADOCK 05000787 P

PDR

ATTACHMENT 1 TO PLAQ352 Page 3 of 58 LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE RE UIREMENTS SECTION 3/4.7 PLANT SYSTEMS 3/4. 7. I SERVICE MATER SYSTFMS Residual Heat Removal Service Mater System.......,...

Emergency Service Mater System.......................

Ultimate Heat Sink..........

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3/4.7.2 CONTROL ROOM EMERGENCY OUTSIOE AIR SUPPLY SYSTEM.....

PAGE 3/4 7-l 3/4 7-2 3/4 7-4 3/4 7-5 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...............

3/4?-8 3/4. 7. 4 SNU88ERS 3/4. 7. 5 SEALEO SOURCE CONTAMINATION..........................

3 6

FiRE SUPPRESSION SYSTEMS Fi pression Mater System.....................

Spray and Spr er Systems.............

COZ Systems

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Hal on Systems t

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Fire Hose ions ~ ~ ~ 014 ~ ~ ~ 0 ~ ~ ~ ~ t ~ ~ ~

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Fire Hydrants and Hydrant Hose Houses...........

.7.7 FIRE RATED ASSE%LIES..................

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3/4?-ZO 3/4 7-14 3/4 7-16 3/4 7-19 3/4 7"21 3/4 7-22 3/4 7-23 4 7-25 3/4-7-2 3/4.7.8 MAIN TURBINE BYPASS SYSTEM...........................

3/4 7~ ~~

3(4.'7 4-Mfpt~g

>Iw.v.q -- 5 le~

SUSQUEHANNA - UNIT 1 Amendment No. 3".

ATTACHMENT 1 TO PLA-4352 Page 4 of 58 BASKS SECTIOM ENOEX PAGE INSTRUMENTATION (Continued) 3/4. 3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...........

Seismic Monitoring Instrumentation.............

Meteorological Monitor ing Instrumentation......

Remote Shutdown Monitoring Instrumentation.....

Accident Monitoring Instrumentation............

Source Range Monitors..

Traversing In-Core Probe System................

Chlorine Detection System.

'I 8 3/4 3-4 8 3/4 3-4 8 3/4 3-5 8 3/4 3-5 8 3/4 3-5 8 3/4 3"5 8 3/4 3-5 8 3/4 3-5 3/4. 3. 8 3/4.3.9 Radioactive Liquid Effluent Instrumentation..

Radioactive Gaseous Effluent Instrumentation.

Loose-Part Detection System..................

TURBINE OVERSPEED PROTECTION SYSTEM..........

FEEDMATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.................................

8'3/4 3-6 8 3/4 3-6 8 3/4 3-6 8 3/4 3-7 8 3/4 3-7 3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 3/4.4. 2 3/4.4. 3 3/4.4. 4 3/4.4. 5 3/4.4. 6 3/4.4. 7 3/4.4. 8 3/4.4. 9 RECIRCULATION SYSTEM....

SAFETY/RELIEF VALVES............................

REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems........

Operational Leakage..............

CHEMISTRY o

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SPECIFIC ACTIVITY...............................

PRESSURE/TEMPERATURE LlMITS......

MAIN STEAM LINE ISOLATION VALVES.

STRUCTURAL INTEGRITY.............

RESIDUAL HEAT REMOVAL.......;....

8 3/4 4-1 8 3/4 4-2 8 3/4 4-2 8 3/4 4-2 8 3/4 4-2 8 3/4 4-3 8 3/4 4-4 8 3/4 4-5 8 3/4 4-5 8 3/4 4-5 SUSQUEHANNA - UNIT 1 xiii Amendment No.

BASES.

INOEX ATTACHMENT 1 TO PLA4352 Page 5 of 58 SECTION 3/4 7 PLANT SYSTEMS PAGE 3/4.7. l SERViCE WATER SYSTEMS.........

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY OUTSIOE AIR SUPPLY.......

8 3/4 7-l 3/4.7.3 'EACTOR CORE ISOLATION COOLING SYSTEM...........

8 3/4 7-l 3/4.7.4 SNUBBERS...

3/4. 7. 5 3/4. 7. 6 3/4. 7. 7 SEALEO SOURCE CONTAMINATION.

lXLETED 8 3/4 7-2 8 3/4 7-3 8 3/4 7-3 8 3/4 7-4 3/4.7.8 MAIN TURBINE BYPASS SYSTEM......................

8 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8. 1, 3/4. 8. 2 and 3/4. 8. 3 A. C.

SOURCES,

0. C.

SOURCES and ONSITK POWER OISTRIBUTION SYSTEMS...........

8 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE OEVICES.....;...

8 3/4 8-3 3/4.9 REFUELING OPERATIONS

'3/4.9. 1 REACTOR HOOK SWITCH................

3/4.9. 2 INSTRUMENTATION.........................

3/h.9. 3 CONTROL ROG POSITION............................

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3/h.9. 5 CON/NICATIONS..................................

8 3/4 9-1 8 3/4 9-1 8 3/4 9-1 8 3/4 9-1 8 3/4 9-1

. 3/4.9o6

.'- 3j'4.9.7 REFUELING PLATFORM.....................

8 3/4 9-2 CRANK TRAVEL-SPENT FUEL STORAGE OOLo

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P 3/4.9.8 and 3/4.9.9 MATER LEVEL -

REACTOR VESSEL and MATER LEVEL - SPENT FUEL STORAGE POOL.......

3/4.9.10 CONTROL ROD REMOVAL.............................

8 3/4 9-2 8 3/4 9-2 8 3/4 9-2 3/4.9.$ 1 RESIDUAL HEAT REHOVAL ANO COOLANT CIRCULATION... '

3/4 9-2 SUSQUEHANNA - UNIT 1 rv

LIST OF TABLES Continued INOEX ATTACHMENT t TO PLAP352 Page 6 of 58 TABLE

4. 3. 7.4-1

3. 3. 7. 5-1

4. 3. 7. 5-1 REMOTE SHUTGOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ACCIOENT MONITORING INSTRUMENTATION ACCIOEHT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMEHTS..

PAGE 3/4 3-69 3/4 3-71 3/4 3-73

3. 3. 7. 10-1

4. 3. 7. 10-1

3. 3. 7. 11-1 4, 3. 7. 11-1

3. 3. 9-1

3. 3. 9-2 RAOIOACTIVE LIQUIO EFFLUEHT MONITORING INSTRUMENTATION.

RAOIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION...................................

RAOIOACTIVE GASEOUS EFFLUEHT MONITORING INSTRUMENTATIOH SURVEILLANCE REQUIREMENTS..........

FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATIOH INSTRUMENTATION.......

FEEOWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMEHTATION SETPOINTS.........................

3/4 3-82 3/4 3-34 3/4 3-87 3/4 3-90 3/4 3-96 3/4 3-97

4. 3. 9. 1-1 3.4. 3. 2-1

3. 4. 4-1 4.4. 5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AHO ANALYSIS PROGRAM n

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3/4 4-15 FEEGWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS.....

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~. '/4 3-98 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES...

3/4 4-9 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS............

3/4 4-12 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHORAWAL SCHEOULE...................

3/4 4-20

3. 6. 3-1

3. 6. 5. 2-1 SECONOARY.CONTAINMEHT'ENTILATION SYSTEM AUTOMATIC ISOLATION OAMPERS..................................

3/4 6-33 PRIMARY CONTAIHMEHT ISOLATION VALVES...............

3/4 6-19 SUSQUEHANNA - UNIT 1 xxiv Annndsnnt No.

32

IHSTRUMEHTATrOH FIRE OETECTIOH IHSTRUHEHTATIOH LIMITIHG CONDITION FOR OPERATION ATTACHMENTf TO PLA-4352 Page 7 of 58 tection zone shown in Table 3.3.7.9-1 shall be OPERABLE.

APPLI BILITY:

Whenever equipment protected by the fire detection instru nt is requi o to be OPERABLE.

ACTION:

With the number o

PERABLE fire detection instruments less an the Minimum Instruments OPERABLE quirement of Table 3.3.7.9-1:

a.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, e

lish a fire watch patr to inspect the zone(s) with the inoperabl instrument(s) at le t once per hour, unless the instrument(s) is loca d fnside an i ccessible

zone, then inspect the area surrounding th inaccassi e zone at least once per hour.

b.

The provisions of Specfffcat 3..0.3 are not applicable.

SURVEILLANCE RE UIRBfEHTS

4. 3. 7. 9.1 Each of the ve required fire detection truants which are accessible dur'fng u operation shel.l be demonstrated 0

LE at least once per 6 eonths by p forsance of a'HANNEL FUNCTIONAL TEST.

re detectors which are not access e during unit operation shall be deaonstrate PERABLE by the performance a CHANEL FUNCTIONAL TEST during each COLD SHUT exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> less performed fn the previous 6 months.

4.3..9.2 Th>> supervised cfrcufts supervision associated wfth the. detec res of each of the above required fire detection fnstruaents shall be demonstrated OPERABLE at 1east once per 6 months.

SUSQUEHANNA - UNIT 1 3/4 3-77 Amendment Ho.

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I FIRE OE. ECTION INSTRUHEHTATION ATTACHMENT 1 TO PLAP352 Page 8 of 58 i RUHENT LOCATION INSTRUHENTS OPERABLE FIRE ZONE ROOH OR AREA HEAT ELF/.

TOTAL HIN.

IONIZATION TOTAL HIN PHO KL RIC T

AL HIN.

a.

Cant 0-240 0 240 0-25E 0 2SH 0 26H 0 27C 0 27E 0-27E 0-2N 0 28L 0 28H 0 28N 0 28I 0-RSJ 0 286 0-28F 0-8%

0 28C 0-2N 0-28T re 1 u< 1 dh n L~

Relay Rooe PQCC Laser Cab e

Spread1 Re.

Lever Cable Spreads ny Re.

Control Re.

(Under Flr. Unkt Control Rooe (Under Flr. Unit 2)>>

Control Rooe Control Re.

(Above Clg}~

Upper Cabl e Spreading Re.

Upper Cable Spreading Re.

Upper Relay Rooe PIC Sattary Rooe Sattary Rooe Sattary Rooe Sattary Rooe Sattary Rooe Sattary Sattary Sa

%No has Sattary Rooe--

Sattary Rooe 698'1" 4

2 698 -1" 54 27 4

2 30 714'.0" 25 Q

714'-0<<

20 10 d

3 729'"

NA 8

4 28 W1>>

4 754'<<

m'-o NA.

771'M Nl m'm 771'M NA m'm m'W NA m'W>>

NA

'm'-0",

NA 771'-0" 771'-0<< -

NA m'-o" 771'"

NA 14 S

3 2

2 1

28 30 IS NA 1

1 1

1 NA 1

NA 1

NA 1

NA 1

1 NA 1

NA 1

1 NA 1

1 NA L

1 NA 1

1 NA 1

1 729'1>>

NA NA 1S 8

75'"

NA ID 5

729'-1>>

NA NA 9

5 NA NA NA NA l

NA NA NA NA NA NA

'A NA SUSQUEHANNA UNIT 1 3/4 3 78 Aeendeent No. 36

0

ATlACHMENT 1 TO PLAC352 Page 9 of 58 IHS UMENT LOCATIOH TABLE 3. 3.7.9-1 (Continued)

FIRE DETECTION INSTRUMENTATION INSTRUMENTS OPERABLE PHOTC-FIRE ZONE OOM OR AREA HEAT ELEY.

TOTAL MIN.

ON IZAT.O TOTAL M'ri.

'v. iC O 'L vl 0-22k 0-268 0-ZGC 0-268 0-ZGF 0-ZGG 0-ZGJ 0-26M 0-ZGN 0-ZGP 0-ZGR 0-265 0-2GT 0-26V 0-2?F 0-2?G 0-27H 0-ZBA 0-288 0-28H 0-ZBP 0-28R 0-298 0-'30A 0-25B 0-25C 0-25D 0-ZBQ 0-26 Fi er Area South Cabie Chase Center ble Chase North Cab Chase Vest bule Shift Office Vestibule E:

Soffit Cantral Room Saffit Control Room Soffit Soffit

~ South Cable Chase Center Cable Chase North Cable Chase South Cable Chase Center Cable Chase North Cable Chase Equipment Roam Equipment Race Repair Shop South Cable ase North Cabl Chase H4V Equi ment Room HVAC uipment Raam Sou Cable Chase C

ter Cable. Chase orth Cable Chase Cente~ Cable Chase Operational Support Center 687'8" 729'-L" 729'1'i

?29'-L" 729'-V 729'L'i 729'1" 729'1" 729'-1" 729

-1'29 I

II.

72

-1" 9 I ALII 729 -1".

754I ~

II 754'-1" 754 I ~Lll 771 I pll T?1'-0" 771'-04 771'-0" 771'-0" 783'-0'e 806 i Pll 714'-0" 714'-0" 714 I ~PII 771'-0"

'29 I << Lll NA iVA NA iVA iVA iVA NA NA iVA NA NA HA NA N

NA HA NA NA NA NA HA 1

1 1

1 1

1 1

1 1

1 1

NA NA NA NA HA 1

1 1

1 NA NA NA NA 1

1 1

1 1

1 1

1 NA NA

~1 1

1 1

1 4

2 2

NA iVA NA HA NA NA 4

4 2

NA NA 0

20 HA HA HA NA 1

6 1

L 1

1 1

2 L

1 2

HA NA NA NA NA NA 2

2 1

HA NA 5

10 HA NA HA

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1 VA NA NA NA NA NA NA NA NA iVA NA NA iVA NA NA NA NA iVA NA NA NA NA NA

,VA VA VA NA NA VA iVA NA NA NA HA iVA NA iVA HA iVA iVA VA iVA

>VA NA iVA SUSQUEHANNA - UNIT 1 3/4 3-78A Amencmen- '('. -"

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DeLETED 3/4. 7. 6 ATTACHMENTf TO PLAA352 Page f2 of 58 a.

Two OPERABLE fire suppression

pumps, one electric mdtor driven and one diesel driven, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression

header, b.

At ast two separate water

supplies, each with a minim contained volume f 300,000 gallons, and C.

Two OPERAS flow paths capable of taking sucti from any two of the following:

(1) Unit 1 cooling tower basi

, (2) Unit 2 cooling tower basin, (3) arified water storage k, and transferring the water through distri t,ion piping with RABLE sectfonalizing control or isolation valves to e yard hydr curb valves, the last valve ahead of the water flow a rts dev'n each sprinkler or hose standoioe and the last valve ahead of eluge valve on each deluge or spray system required to be OPERAS r Specfffcatfons

3. T.6.2, 3.7.6.5, and 3.7.6.6.

APPLICABILITY: At all tfNes.

ACTION:

Wth one re p~ and/or one of the above requf water supplies inoper le, restore the inoperable equfpeent to OPE LE status wfthi 7

s or provide an alternate backup puiap or supply.

e provisions Speci ffcatfon 3.0.3 are not applfcabl ~.

fifth the fire suppression water systaa otherwise inoperable establish a backup ftre suppression water systaa within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SUSQUEHNNA - UNIT 1 3/4 7-16 Aeendaent Ho.

7B

ATTACHMENT 1 TO PLA4352 Page 13 of 58 SURVE LLANC"- qewUtqcggqTS.

4.

.6. 1. 1 The fire suppression water system shall be Cemonstratad 3P~RA6(.:-:

At least once per 7 days by verifying the minimum contained wa r

supply volume.

b.

C.

least, once per 31 days by starting the electric motor iven ',ire su ression pump and operating it for at least 15 minute on reer ul ation flow.

At leas once per 31 days by verifying that each va e, manual,

."c~e.

operated r automatic, in the flow path is in its orrect :os :ion.

d.

At least on per 12 months by performance of system",ush.

At least once p

12 months by cycling each astable valve in the flow path throug at least one complete le of full travel.

At least once per I

months by perform' a system func.'anal

as

which includes simula d automatic a

uation of the system:nrougnou:

its operating

sequence, nd:

l.

Verifying that each a

ma c valve in the flow path ac:uatas to its correct position, 2.

Verifying that each f e

s pression pump develops at leas 2500 gpm at 'a syst ead o

125 psig, 3.

Cycling each val in thi flow th that is not tastable during plant operation through at least e complete cycle of full

travel, and 4.

Verifying at each fire suppression p

starts sequentially to main n the fire suppression water stem pressure greater than or equal to 85 psig.

At least nce per 3 years by performing a flow te of the system in accord ce with Chapter 5, Section ll of the Fire P

tection Handbook, 14th dition, published by the National Fire Protect n Association.

4.7. 6.1. 2 e diesel driven fire suppression pump shall be demons ated QPERABL=:

t least once per 31 days by:

Verifying the fuel storage tank contains at least 250 ga Ions of fue.I.

2.

Starting the diesel driven pump from ambient conditions and operating for greater than or equal to 30 minutes on recirculation flow.

SUS/UEHANNA - UNIT 1 3/

-17 Amendment No.

0 0

ATlACHMENT1 TO PLA4352 Page 14 of 58 SURVEILLANCE REQUIREMENTS Continued)

At least once per 92 days by verifying that a sample of die 1 fuel from the fuel storage tank, obtained in accordance with A

-0270-7=.,

is within the acceptable limits specified in Table 'f STN-397=.-77 en checked for viscosity, water and sediment.

At le st once per 18 months by subjecting the die 1 :o an

.'nspec:ion in acco dance with procedures prepared in conju

ion with i:s manufac.u r's recommendations for the class service.

4. 7.6.1.3 The diesel d 'ven fire pump diesel stat g 24-volt battarj "ank and charger snail be demo trated OPERASLE:

a.

At, least once per'7 ays by verifyi that:

1.

The electrolyte lev of ch pilot cell is above the plates, 2.

The pilot cell specifi ravity, correc.ed to 77'F, is greater than or equal to 1.

3.

The overall bat ry voltage i reater than or equal to 24 vol:s.

b.

At least once per 92 days by verifying at the specific gravity is appropriate fo continued service of the ttery.

c At least o

er per 18 months by verifying tha 1.

ce11 and battery racks show no visual in cation of physical ge or abnormal deterioration, and Terminal connections are clean, tight, free of corr ion and coated with anti-corrosion material.

SUS)UEHANNA -. UNIT 1

~ra Amendment No.

0

ATTACHMENTf TO PLAP352 Page 15 of 58 SPRAY ANQ SPRINKLER SYSTEMS L

ITIHG CQHOITION FOR OPERATION 3.7.6.2 e followfng spray and sprinkler systems shall be OPERAS c

d.

e.,

RC Pump Roow, Unit 1 HPCI Room, Unit 1 Upper C

~ Spreading Rooa, Unit 1 Lower Cable readfng Rooe, Unft 1 Ofesel Qenerat A Room f.

Of ese1 Generator Room g.

Gfesel Generator C

R h.

Ofesel Generator 0 Rooa i.

Ffre lanes 1-3A and 1-3B j.

Fire lone 1-4A k.

Fire lone 1-6A 1.

Ffre lone 1-28 i.

Fire Zone 0-298 n.

Fire lone 0-3 o.

Ofesel Gene tor E Building, Ffr'e Zone 0-41E APPLICABILITY: 1 never equitant protected by the spray or sprf nkler

~

RRRRIR ACTION:

ao Nth one or sore of the above required spray andlor sprink r systems fnoperahl ~, 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 watch th baCkup ffre SuppreeafOn equfpeent far thOSe areaS fn whiCh dant systees or codponents could be dmtged; for other areas, establf an hourly f'fre watch patrol.

SUSQUEHANNA' UNIT 1 Awendment No.

ATIACHMENT1 TO PLAC352 Page 16 of 58 RVKD ~>NC-

.PggU1 ggycqyg 4.7.6.

Kach of the above required spray and sprfnkler systems shall be dtmonstra d OPERAB1.E:

a.

At st once per 31 days by verifying that, each valve, m

ual, power crated or automatic, fn the flow path fs fn fts orrec:

.position.

b.

At least once r 12 months by cycling each tes le va1ve in the flow path throug at least one complete cycle f full,travel.

c.

At least once per LS nths:

1.

Sy performing a sys functfo test which includes simulated automatic actuation of

taa, and:

a)

Verffyfng that the tfc valves in the flow path ac~ate to their correct p

itions on a test signal, and b)

Cycling ta valve fn the flow th that fs not tastabl ~

during p t operation through at east one complete cycl ~

of ful travel.

2.

Sy a v ual fnsyection of the dry pfpe spray sprinkler he to verffy their integrfty, and 3.

a vfsua1 fnspectfon of each de1uge nozzle's spray a to ver{+ that the spray pattern fs not obstructed.

At least ona per 3 years by parform{ng-an afr or water flow test through each open head spray and sprfnkler header and verffyfng tach open head spray and sprinkler nozzle fs unobstructed.

Ql$gUEHAliA NIT 1 3

20

ATTACHMENT 1 TO PLA<352 Page 17 of 58

2 LIMITING CONQITIONS a.

C.

d.

e.f.

g h.l.

J.

k.

Control Room Under Floor, Control Room Under Floor>

wer Relay Room, Unit 1>

Up er Relay Room, Unit 1 Sou Cable Chase Cente Cable Chase North ble Chase Room C-4 1 Sorrit Control R

a Soffft; Unit Control Roo Soffft, Unit Room C-412 S fit 3.7..3 The following low pressure CO2 systems shall be OPERABLE:

Unit 1 Unit 2 APPLICABILITY: Whenever qufpment protected by t ACTION:

CO2 systems is requf red o

a.

b.

With one or more of t e above req red 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 /> establish a cont uous f re watch with backup fire suppres-sion equipment for those rea in which redundant systems or com-ponents could be damaged; other areas, establish an hour1y fire watch patrol.

The provfsfons of Specff catfo 3.0.3 are not applicable.

SURVEILLANCE RE UIRBIENTS

4. 7. 6. 3; 1 Each of the abov required low press CO2 systerss shall be demon-strated OPERABLE at leas once per 31 days by ver yfng that each valve, manual power operated, or au tfc, in the flow path is f its correct position.

4. 7. 6.3.2 Each of above required low pressure CO2 systerss shall be dersonstrated OPERAS a.

At lea once per 7 days by verifying the CO2 s

rage tank level o

be g

ater than 2K'nd pressure to be greater th 270 psig, and b.

At east once per 1S months by:

Verifying the systee valves and associated ventil tion dampers and ffre door release mechanisms actuate manually a d automa-tically, upon receipt of a simulated actuation signa and 2.

Flow froo each accessfble nozzle by performance of i " ff Test."

Accessible noziles.

SUSQUEHANNA - UNIT 1

~31 Amendment No.

ATTACHMENT 1 TO PLAC352 Page 18 of 58 L

ITING CONOITION FOR OPERATION 3.7.6.4 e Halon systems in the following panel modules shall be OPERAB with the st age tanks having at least 95'f full charge weight and 9

of full charge p essure:

1U700 1U701 1U702 1U703 1U706 1U730 1U731 1U732 APPLICABILITY:

Whenev equipment protected by the Halon sy ems is required PEW E.

ACTION:

a.

With one or more of t above required H

on 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 continuous fi e watch with backup fire suppression equipment for those areas n which redundant systems or components could be damage for ot r areas, establish an hourly fire watch patrol.

b.

The provisions of Specificati 0.3 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 7.6.4 Each of the above req red Halon systems s ll be demonstrated OPERABLE.

a.

At least once p r 31 days by verifying that.eac valve, manual, power operate or automatic, in the flow path is its correct position.

b.

At leas once per 6 months by verifying Halon storage nk weight and pr ssure.

c.

At east once per 18 months by:

1.

Performance of a flow test through accessible headers and nozzles to assure no blockage.

2.

Performance of a functional test of the general alarm circuit and associated alana and interlock devices.

SUS(UEHANNA - UNIT 1 3

-22 Amendment No.

82

ATTACHMENT 1 TO PLA-4352

- Page 19 of 58 LIMITING CONOITION FOR OPERATION 3.7.6.

The fire hose stations shown in Table 3.7.6.5-1 shall be OPE LE.

APPLICABI TY:

Whenever equipment in the areas protected by the fi e hose stations is required to be OPERABLE ACTION:

a.

lith on or more of the fire hose stations shown

'n Table 3.7.5.5-1 inoperab1 route an additional fire hose of eq 1 or greater diame~er to the unp tec.ed area(s) froo an OPERABL'E h

e station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inope le fire hose is the primary ans of ffre suppression; otherwise, rou the additional hose withi 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

The provisions of eciffcation 3.0.3 not applicable.

SURVEILLANCE RE UIREHENTS 4.7.6.5 Each of the fire hose statf s

own in Tabl ~ 3.7.6.5-1 shall be deaonstrated OPERABLE:

a.

At least once per 31 days a

sual inspection of the fire hose stations accessible durf g plant ration to assure all required equfpeent is at th>> s ion.

At least once per 1

eonths by:

1.

Visual fns fon of the ffre hose a

tfons not accessible during plant ope tfon to assure all required ufpaent fi at the station.

Rmovf the hose for inspection and re-r king for all fire hose stat ons, and 3.

spectfng all gaskets and replacfng any degr gaskets in couplfngs for all fire hose statfons.

least once per 3 years by:

1.

Ptrtfally opening each hose statfon valve to verify val OPERAIILITY and no flee blockage.

2.

Cohductfng a hose hydrostatic test at a pressure of 150 psig r

at least 50 psfg above the aaxfma fire cain operating pressu whichever is greater.

SUSQUEHANNA - UNIT 1 Aeendaent No.

76

ATTACHMENT 1 TO PLA4352

- Page 20 of 58

~

~

FIRE HOSE STATIONS a,

C.

T IOUS ntro) Structure El.

697'-0" El 6o 7 I ~OII El 4'0" E'..

71 '-0" El.

729 -0" El.

729'- "

El.

754'-0 El.

754'04 El 77L'-Ou El.

771'-0" Reactor Sufldfng El.

645'-0" El.

645'-0" El.

646'-0" Ei 645'-0" El.

645'-0" El 645'-0" El.

El.

El.

El.

El.

El.

El.

El.

El.

El.

El.

El.

El.

Kl.

El.

El.

El.

Kl.

El.

Kl.

Kl.

El.

670'-0" 670'-0" 670'0" 683'-0" 683'-0" 683< -0 719'-I" 719"I" 719'I" 7191 ~IN 7I9'-I" 749 1 ~]N 749'1" 749 I ~]N 749 1 <>

779'-Ii 779'-I" 779'>>

779'>>

779'~1>>

N'S'"

El.

El 1.

El.

El.

656 "6" 656'-6" 676'-6" 676'"

708)-0 708'-0" El.

-1>>

Ofese Generator E Bufldfng COLLNN L-26 L-32 L-26 L-31 L-25. 9 L-32. I L-26 L-32 L-26 L-31 R 29 P-20. 6 U 22 R-37. 4 U 30.5 R 30 0 27.5 Q 29

% 22

.5 Q-

.6 Q-27.

$-27. 5 Q-20. 6 T-20.6 T-23. 5 S-27. 5 5-27.5 Q-20. 6 T-20. 6 P 25.5 5-26.5 Q 22 U 20.6 T-23. 3 P 25.3 V-26.3 Q-20. 6 Near North Stafrwe11 Hear South Staf noel 1 Near North Staf~ll Near South Stafnve1 1

Near North Staf~ll Near South Stafnal1 HOSE RACX NURSE IH -171 R 171 HR 162 2HR-162 IHR-a58 2HR-158 1HR-136 2HR-136 IHR-125 2HR-125 IHR-271 IHR-272 IHR-273 2HR-271 2HR-272 2HR-273 IHR-261 IHR-262 IHR 263 IHR-251 IHR-252 IHR-253 IHR-241 IHR-242 IHR-243 IHR 244 IHR-245 IHR-231 IHR-231 IHR 232 IHR 233 IHR 221 IHR-222 IHR-223 IHR-224 IHR-211 IHR 201 IHR 202 IHR 203 OH -Sil OHR-I2 OHR-OHR-8 OHR 831 OHR-832 SUSQUEHANNA - UNIT I Aaendment No. ~l

$8 16 88'

ATTACHMENTf TO PLA-4352 Page 21 of 58 IHITING CONOITION FOR OPERATION 3.7.6.

Yard fire hydrants 1FH122 and 1FH104 and associated hydrant se houses shal 1

be PERABLE.

APPLICABILI Whenever equipment in the areas protected by the ard fire hydrants is re uired to be'OPERABLE.

ACTION:

a.

fifth yard e hydrants IFHI22 and/or IFH104 d/or associated

hydrant, hose houses i

perable, route sufficient ad tional lengths of fire hose of equal o

greater dfaaeter located n ad)acent OPERABLE hydrant hose house(s) to rovide service to the protected area(s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

The provisions of Spec ffcation 3.

3 are not applicable.

SURVEILLANCE RE UIR&ENTS 4.7.6.6 Yard fire hydrants IFHI22 and IFH and associated hydrant hose houses shall be deaonstrated OPERABLE:

At least onc>> per days by. vfsual fn houses to assure 1 required equi poent fon of the hydrant hose at the hose houses.

c At least once er 6 months, during March, fl or Hay and during Septeeber,.

r or Noveeber, by visually f ectfng the yard fire hydrants verifying that the hydrant barrels re dry and that the hydr an are not daeeged.

At 1 t once per 12 aonths by:

Conductfng hose hydrostatic tests at a pressure of 0 psig or at least 50 pafg above the aaxfaa fire aafn oper atfn

pressure, whfchever fs greater.

2.

Replecaaent of all degraded gaskets in couplfngs.

3.

Perforafng a.flow check of-each'ydrant.

SUS)UEHANNA - UNIT I 3/

5 Amendment No.. B

ATTACHMENTf TO PLA-4352 Page 220f58 3/4.7.7 FIRE RATED ASSEHSLIES INITING CONOITION fOR OPERATION 3.7.7 1 fire r atad assemblies, including walls, floor/ceilings, ble tray enclosure and other fire barriers separating safety related fire reas ar separating rtions of redundant systams important to safe shut n within a fire area, an all sealing devices in ffre rated asseably pene rations, including fire oors, fire windows, ffre daapers, cable and iping penetration seals and venti 1 ian seals snail be OPERABLE.

APPLICABILITY: At a 1 times.

ACTION:

With one or more the above ~uf ffre rated assamb1ies and/or sealing devices ino rable, within our establish a continuous fire awatch on at leas one sfde of he affected assembly and/or sealing device or veri the OPE ILITY of fire detectors an at least ane side'f the in crab ffre assembly and/or sealing cevfca and establish an hour'ly fi tch patrol.

The provisions of Speciff tfo 3.0.3 are not applicable.

SURVEILLANCE RE UIREHENTS 4.7.7.l Each of the abo requfred fire rated ass lfes and sealing devices shall be verfffed OPE LE at least once per. IS month by performing a visual inspection of:

a.

The ey sed surfaces of each ffre rated assembly.

b.

Eac fire wfndow, fire damper, and assocfatad hardwa c.

t least IO percent of each type of sealed penetration.

If apparent cha~s fn appearance or abnormal degradatfons are found, visual fnspectfon of an addftfonal IO percent of each type of seal

<catt'ation shall be sade.

This inspectfon process shall can nue untf) a IO percent saapl ~ wfth no apparent changes fn appearanc or abnormal degradatfon fs found.

Samples shall be selected such th t each penetration wfll be inspected every IS years.

SUSQUEHANNA - UNIT I 3

3 Amendment No.

78

ATTACHMENT 1 TO PLA4352 Page 23 of 58 SU

'LINC REOU>RE.'4ENTS Cant nues) 4.7.7. 2 Each of.,

above required fire doars shaH be v

d QPcASt a.

Verifying the p

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ion of each closed door at least once per Veri ying that. doors ~ith a

atic hole-coen and release mec.-.anisms are free of abstructions lea ance per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Verifying the po 'on of each locked c ed re daar at '.east cnc per 7 days.

Verif g the QPERABlLITY of the, ire door supervis>

svstem "y p

arming a

CHANNEL FUNCTIONAL TEST at least ance per days.

Inspecting the automatic hold-open, release and c!asing meehan~

and latches at least ance per 6 months.

SUSQUEHANNA - UNIT 1 Amendment No. "S

ATTACHMENT 1 TO PLA-4352 Page 24 af 58 INSTRUMENTATION 8ASES 3/4. 3. 7. g warnin ility is available for the prampt detection of fires.

T 'pa-bility is requs n order to detect and locate fires in th r ly stages.

Prompt detectian of f~

'll reduce the potential f age to safety-relataa equipment and is an integral e

in the facility fire pratec.ian pragrcUQ.

In the event that a

on of the fire detec 'nstrumentation is inoperable, inc the frequency of fire watch patro the affected areas is requi provide detection capability until the inaperable umentasion tared ta OPERABILITY.

3/4.3.7.10 RADIOACTIVE LI UIO EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentatian is provided to monito~

and cantral, as applicable, the releases of radioactfve materials in li.quid effluents during actual or potential releases of liqufd effluents.

The alarm/

trip setpoints far these instruments shall be calculated in accordance with the procedures in the OOCN to ensure that the alarm/trip will accur prior to exceedfng the limits of 10 CFR Part 20.

The OPERABILITY.'nd use af thfs fnstrumentatfan is cansfstent wfth the requirements of General Design Criterfa 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4. 3.7. 11 RADIOACTIVE GASES EFFLUENT INSTRlNENTATION The radfoactfve gaseous eff1uent fnstrumentatfan fs provided to monitor and control, as applfcable, the releases of radioactive materials in gaseous effluents during actual or potentfal releases of gaseous effluents..

The alarm/

trip setpoints for these fnstruaents shall be calculated in accordance with the procedures fn the DOCÃ to ensure that the alarm/trip will occu" prior to exceeding the lfmfts af 10 CFR Part K.

This fnstruaentatfan also includes provisions for monitoring (and controlling) the concentrations of potentially explasfve gas mfxtures fn the waste gas holdup system.

The OPERABILITY and use of this fnst~ntatfon fs consistent with the requirements of General Oesfgn Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.12 LOOSE PART DETECTION SYSTEM The OPERABILITY af the loose-part detection systaa ensures 'that sufficient capebflfty fs avaflable to detect loose metallfc parts in the primary system and avofd or mitigate damage to primary system components.

The allowable aut-of-service times and survef 1 lance requf reaents are consistent wfth the recomenda-tions of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Kater-Cooled Reactors,"

Nay 1981.

SUSQUEHANNA - UNIT 1 B 3/4 3 6

ATlACHMENTf TO PLA4352

-Page 25 of-58 BASKS 3/4 7.4 SHUBBERS (Continued)

The service life of a snubber is evaluated via manufacturer input and information through cansideratian of the snubber service conditions unct asso-ciated installation and maintenance records (newly installed snubber, seal

replaced, spring'eplaced, in high radi'ation area, in high temperature

area, etc...).

The requfrersent to monitor the snubber service life is included ta ensure that the snubbers periodically undergo a performance evaluation in view of their age and operatfng conditions.

These records will provide statistical bases for'uture consideration of snubber service life.

The requir enents for the riafntananca or'cords anci the snubber service life review are not intanaaa to affect plant operation.

3/4 7. 5 SKALEO S0URCK CQHTAHIHATIQH The lfmftatfans on resravable cantarafnatfon for sources required leak tasting, fncludfng alpha esfttars, is based on 10 CFR 70.3S(c) limfts for plutonium.

thfs liraitatfon will.ensure that leakage frora byproduct,

source, and special nuclear material sources will not exceed allowable fntaka values.

Sealed sources are classfffed fnta three graubS aCCardfng ta thefr use, with survefllance requirements c~nsurata wfth the prababflfty of damage ta a source in that group. 'hose sources whfch are fluently handled are required to be tasted rmrre often than thase wtrfch are not.

Sealed sources which are continuously errclased wfthfn a shielded mechanfsa, f.a., sealed sources within radfatfan manftarfng or boron measuring devices, are considered to be stared and need not be tested unless they are removed fram the scalded mechanfsrs.

trELaT837 3/4 7.6 ssfon capabflfty fs avaflable to canffne and extfngufsh ffris accurrf fn any foe af the facflfty where safety related equfpment is loca The fire suppres systae consists of the water

system, spray and/

prfnklers, CO~ systems, Hal taws and ffre hose statfans.

The co fve capability o~ fire suppressfon taws fs adequate to mfnfmf tantfal damage ta safety related equfpoent and major

~lament e facf1 fty ffre protection prog~

?5-She event that portfons ffre s sion systems are fnoperable, alternate bacfcup fire ffgh equfpment is requf be made availab)e fn the affected areas the fnoperWle equfpment is res to service.

Men the fnoperable ffghtfng equfpwent fs fntanded for usa as a

up means of fire supp orr ~ a longer pel'fod of time fs allowed to provide an a

ate means fire fighting than if the fnoperable equiparant fs the primary mes suppress fan.

SQSqQnfAINA - UHIT 1 8 3/4 7-3 Amendment Ho. 36

ATrACHMENT 1 TO pLA~352

~ page 26 o< 58 PLANT SYSTEHS BASKS The su llance redui~nts provide assurances that the min'pKRABIL..~

r equireaents of re suppression systems are met.

An a nca is made for censuring a sui'ficient vo of Halon in the Helen s

e tanks by verii'ying the might and pressure of the In the event the fire supp vater becoises inoperable, ismsediate corrective measures must

~n since this systea des the Iajor fire suppression capabil of the plant.

The ~uirtaent for a t

i'our hour report to ission provides for proept evaluation of the acc ility of the c.fve measures to provide adeouata fire suppression capability

'QB 3/4 7.7 i'ire daaage of a single fire

~xtinguisnaent.

cable trays iai tad.

involving The fire Oa re These design features einisl si ility one fir or to detection and etrations for conduitS, Windows, fire d4)ers, and 3/4 7.B HAIN TURBINE BYPASS SYSTBI The required OPERASILITY of th>> aain turbine bypass system fs consistent with the assertions of the ftahetar controller failure analysis in the cycle specific transient analysis.

SUSQUEHANNA UNIT 1 8 3/4 7-4

~ncIaept No.

64

'1

ADMINI TRATIV NTR AITACHMENT 1 TO PLA-4352 Pa e 27 of58 IC l

dl c;

A health physics technician shall be onsite when fuel is in the reactor.

d.

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

Ake-Fire-Brigade-shaI&oHnd Are rad=fo~t embers-shaMe-mainta4'-ed-ons~MII-times the~embe~f ollM Administrative procedures shall be developed and implemented to limitthe working hours of unit staff who perform safety-related functions; e.gds senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

1. A individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

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

3. A break of at least eight hours should be allowed between work periods, including shift turnover-time.

d

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

vtt!i. pcs(Jwf-h4dehc d

l l

i C

ldll ddd C l*dd C

l I ~

Cld M,

ld l

with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shill be reviewed monthly by the or his desiy'ice to assure that excessive hours have ot been assigned.

Routine deviation from the above guidelines is not authorized.

(It ce Prssi Jane'-lhvtew Ope.dshopts

'F g.

The Manager-Nuclear Operations shall hold a Senior Reactor Operator license.

C CC'll'~

l' 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.

, SUSQUEHANNA - UNITI 6-2 Amindmant No. 117

nn

ATTACHMENT 1 TO PLA-4352 Page 28 of 58 AOMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

a.

b.

C.

g.

h.

k.

Review of all administrative procedures and changes thereto.

Review of all proposed tests and experiments that affect nuclear safety.

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

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

Review of the safety evaluations. for procedures and changes thereto completed under the provisions of 10 CFR 50. 59.

Investigation of all violations of the Technica'I Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President-Nuclear Operations and to the Susquehanna Review Committee.

Review all REPORTABLE EVENTS.

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

Performance of special reviews, investigations or ana'lyses and reports thereon as requested by the Superintendent of Plant-Susquehanna or the Susquehanna Review Committee.

'Review of the Security Plan and shall submit recommended changes to the Susquehanna Review Committee.

Review of the Emergency Plan and shall submit recommended changes to the Susquehanna Review Committee.

Review of "every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the cor rective action to prevent recurrence to the Vice-President-Nuclear Operations and to the Chairman of the Susquehanna Review Committee.

Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE OOSE CALCULATION MANUAL, and radwaste treatment systems.

Review ~~ @~t p~pcseA c4aaqes %4m. t~c4~ical Regu~~eoh Iioqram en'hallso4~)q approvaL chagggs @~ S~g~e~~

g, ~ ~

SUS/UEHANNA - UNIT 1 6-9 Amendment No. 29

A MINI TR ATTACHMENT1 TO PLAR352 Page 29 of 58 6.7 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vice President-Nuclear Operations and the SRC

'shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety LimitViolation Report shall be prepared.

The report shall be reviewed by the PORC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety LimitViolation Report shall be submitted to the Commission, the SRC and the Vice President-Nuclear Operations within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

6.8.

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2. February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Ran implementation.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

Offsite Dose Calculation Manual implementation.

i.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Riigplatoq Guide.4.1,5~Feery 1979:

J ~

><<4nical R,ej~<mwle~g Pxogram i

g$~~~.

~~~ J 2

Each procedure of 6.8.1(a) through (g) above, and changes thereto, shall be reviewed in accordance with Specifications 6..1.6 or 6.5.3, as appropriate. and approved by the.Su indents-Ran~squehsnna prior to implementation and shall be review periodlca]ly as set forth in administrative procedures.

V<~ t~ W+ IJcdmv" Qqa~b~

Each procedure of 6.8.1, above, and changes thereto, that is established to implement those portions of the radiological effluent and environmental monitoring programs and those portions of the ODCM that are the responsibility of Nuclear Technology shall be approved by the Manager-Nuclear Technology.

SUSQUEHANNA - UNIT 1 6-15 Amendment No. 117

ATIACHMENT 1 TO PLA4352 Page 30 of 58 IM)EX LIMITING COHQITIONS FOR OPERATION AHO SURVEILLANCE RE UI SECTION 3/4. 3 IHSTRUHEHTATIOH 3/4. 3. 1 3/4. 3. 2 3/4, 3. 3 3/4. 3. 4 3/4. 3. 5 3/4.3.6 3'/4. 3. 7 REACTOR PROTECTION SYSTEH IHSTRUHEHTATIQH.........,..

ISOLATION ACTUATIQH INSTRUHEHTATION...............,,,

EHERGEHCY CORE COOLING SYSTEN ACTUATIOH IHSTRtNEHTATIOH..........,....,.

RECIRCULATION PtNP TRIP ACTUATIOH IHSTRIPKHTATIOH ASS Recfrculatfon Puap Trfp Systea Instruoentatfon..

End-of-Cycle Recfrculatfon Puep Trfp System Instruaentatfon..............,.......,...,...........

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION IHSTRtNENTATION....................,..............

CONTROL ROO BLOCK INSTRtNEHTATION.................

NONITORIHG IHSTRUNEHTATION Radfatfon Honftorfng Instr~ntatfon..............

Sefsafc Nonftorfng Inst~ntatfon................

Hetaorologfcal Monftorfng Inst~ntatfon.........

Reeote Shutdown Monftorfng lnst~ntatfon........

Accfdent Nonftorfng Inst~ntatfon...............

Source Range conf tors 1

~ ~ ~ ~ ~ ~

~

~

~ ~ ~ ~ ~

~ ~ ~

~ ~ ~ ~ ~ ~ ~

~

~ ~ ~'

Traversfng In-Core Probe Systaw...................

Ch1orfne Oetactfon Systea.........................

3/4 3-1 3/4 3-9 3/4 3-27 3/4 3-36 3/4 3-4Q 3/4 3-46 3/4 3-51 3/4 3-57 3/4 3-61 3/4 3-64 3/4 3"67 3/4 3-7O 3/4 3-74 3/4 3-75 3/4 3-76 Radfoactfve Lfqufd Effluent Honftorfng lnstMtntatf one

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~-"Nadfoactfve Gaseous Effluent Nonftorfng instvaeentatf one

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Loose-Part Oetectfon Systaw..................

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3/4 3-82 3/4 3-87 3/4 3-94 3/4.3. 8 3/4.3.9 TUNINE OVKRSPKEQ PROTECTION SYSTEM..........

FEEGlQTKR/NLIN TURSINE TRIP SYSTN ACTUATION INSTRtNTATION..........................

3/4 3-95 3/4 3-96 SUSQUEHANNA - UNIT 2

ATlACHMENT1 TO PLA4352 Page 31 of 58 LIMITING CONOITIONS FOR OPERATION ANO SURVEiLLANCE RE UIREMENTS SECTION 3/4. 7 PLANT SYSTEMS 3/4. 7. 1 SERVICE MATER SYSTEMS PAGE Reefdtial Heat Removal Semfce Mater Systea...........

3/4 7-1 Bsergancy Servfce Mate~ Systae.....................

UltfAte Heat Sf Ako ~ ~

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3/4 7-2 3/4 7-4 3/4.7.2 CONTROL ROOM EMERGENCY OUTSIOE AIR SUPPLY SYSTEM.....

3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...............,

3/4. 7.4 SNUBBERSo

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3/4.7.5 SEALEO SOURCE CONTAMINATION...............;..........

QcmwFQ 3l4.7. 6 3l4 7-8 3/4 7-10 3/4 7-16 Demean 3/4.7. 7

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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3/4.7.8 WLIN TNSINK BYPASS SYSTEM.. ~.. ~........ ~... ~...

~ ~."

3/4 7-30 SUSQUEHANNA - UNIT 2

BASES SECTION lNSTRUMEHTATIOH (Continued)

INDEX ATTACHMENT 1 TO PLAP352 Page 32 of 58 3/4, 3. 7 MONITORING IHSTRUMENTATlOH Radiation Hanktorfng Instrueentatkon..........,.

Sek silkc Monitor ing instr umentatk on..............

Meteorological Monitoring Instrulsentatfon.......

Renrote Shutdown Manitoring Instrurrrentatf on......

Accfdent Monftaring Instrumentation...........,.

Source Range Monitors...........................

Traversing In-Core Probe Systera...........,.....

Chlorine Detection Systera.......................

8 3/4 3-4 8 3/4 3-4 8 3/4 3-5 8 3/4 3-5 8 3/4 3-5 8 3/4 3-5 8 3/4 3-5 8 3/4 3-5

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Radioactive Lfqufd Ek'fluent Instrulentatfon.....

8 3/4 3-6 Radfoactfve Gaseous Effluent Instruaentatfan....

8 3/4 3-6 Loose-Part. Detection Systea.....................

8 3/4 3-6 3/4.3.8 TURBINE QVERSPEED PROTECTION SYSTEM.............

8 3/4 3-7 3/4. 3. 9 FEEOWTER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..................:..............

8 3/4 3-7 3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 RECIRCULATION SYSTEM.........................

3/4.4. 2 SAFETY/RELIEF VALVES...~....

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3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE

- Leakage Detection Systeas..............

8 3/4 4-1 J

83l442 I

8 3/4 4-2 T

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3/C4; 4 Operatfonal Leakage.............................

8 3/4 4-2 CHEMISTRY...........................,...........

8 3/4 4-2 3/4.4.7 MAIN STEAM LIHE ISOLATION VALVES..... ~ ~......."

~

8 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY.......... ~.. -..............

8 3/4 4-5 8 3/4 4-5 l

AIrendment Ho.

3/4.4. 9 RESIDUAL HEAT REMOVAL.......~........

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SUSQUEHANNA - UNIT 2 xiii 3/4.4.5 SPECIFIC ACTIVITY...............................

8 3/4 4-3 3/4.4. 6 PRESSURE/TEMPERATURE LIMITS........... ~.... ~...

~

8 3/4 4-4

BASES INOEX I

ATTACHMENT1 TP PLA~352'age 33 of 58 I

SECTION 3/4. 7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEHS..............

8 3/4 7-1 3/4.7.2 CONTROL ROON EMERGENCY OUTSIDE AIR SUPPLY.......

8 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEH...........

8 3/4 7-1 3/4o 7o 4 SNUBBERSo

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3/4.7.5 SEALED SOURCE CONTAHINATION................,,...

Dt~

3/4. 7. 6

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baLet.eD 3/4. 7. 7 8 3/4 7-2 8 3/4 7-3 3/4. 7.8 HAIN TURBINE BYPASS SYSTEH......................

8 3/4 7-4.

3/4.8 ELECTRICAL POWER SYSTEHS 3/4.8. 1, 3/4.8.2, and 3/4.8N3 A.C.

SOURCES, O.C.

SOURCES, and ONSITK ONER DISTRIBUTION SYSTEHS...........

8 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPHENT PROTECTIVE DEVICES.........

8 3/4 8-3 3/4. 9 REFUELING OPERATIONS 3/4.9. 1 REACTOR HOQE %ITCH.............................

3/4o 9o 2 INSTRUIENTATIONo~ ~ ~ ~ ~

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3/4.9. 3 CONTROL ROO POSITION............................

3/4.9. 4 DECAY TILo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 'o ~

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3/4o.

CQIOOIICATIONSo ~ ~

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A 3/4'EFUELING PLATFORH.... ~.........................

3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE Lo ~ ~

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POO 8 3/4 9-1 8 3/4 9-1 8 3/4 9-1.

8 3/4 9-1 8 3/4 9-1 8 3/4 9-2 8 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL -

REACTOR VESSKL and WATER LEVEL - SPENT FUEL STORAGE POOL.......

8 3/4 9-2 3/4.9. 10 CONTROL ROD REHOVAL...................

~. ~ ~ ~ ~ ~ ~

.'/4.9.

11 RKSIOUAL HEAT REHOVAL ANO COOLANT CIRCULATION...

8 3/4 9 2

8 3/4 9-2 SUS/UEHANNA - UNIT 2 XV

INDEX ATTACHMENT 1 TO PLA-4352 Page 34 of 58 LIST OF TABLES Continued TABLE PAGE

4. 3.4. 2. 1-1

3. 3. 5-1

3. 3. 5-2 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS........

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION...................................

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS...............,.........

3/4 3-45 3/4 3-47 3/4 3-49 4.3.5. 1-1 3.3. 6-.1 3.3.6-2 4.3.6-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRlNENTATION SURVEILLANCE REQUIREMENTS.....'...

CONTROL ROD BLOCK INSTRUMENTATION.....;...........

3/4 3-50 3/4 3-52 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS.......

3/4 3-54 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE 3.3. 7. 1-1 4.3.7. 1-1 3.3.7. 2-1 4.3.7. 2-1 REQUIREMENTS o

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RADIATION MONITORING INSTRUMENTATION..............

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........'.................

SEISMIC MONITORING INSTRUMENTATION................

SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................

3/4 3-55 3/4 3-58 3/4 3-60 3/4 3-62 3/4 3"63 3.3.7.3-1 4.3. 7. 3-1 3.3.7. 4-1 4.3.7. 4-1 3.3.7. 5-1 4.3.7. 5-1 METEOROLOGICAL NNITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................

RBSTE SHUTDOWN MONITORING INSTRUMENTATION......

. 49$TE SHUTMMN MONITORING INSTRUMENTATION LLANCE REQUIREMENTS;......................

ACCIDENT MONITORING INSTRUMENTATION.............

ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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3/4 3-66 3/4 3-68 3/4 3-69 3/4 3-71 3/4 3-73 METEOROLOGICAL NNITORING INSTRUMENTATION.........

3/4 3-65 3.3.7. 10-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION...................................

3/4 3-83 SUSQUEHANNA - UNIT 2 Aaendaent No. 3l

0

LIST OF TABLES Continued INOD I

ATTACHMENT 1 TO PLA-4352 Page 35 of.58 I

TABLE

4. 3. 7. 10-1 3.3. 7. 11-1 4.3.7. 11-1

3. 3. 9-1 3.3. 9-2 4.3. 9. 1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION..............................

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS..........

FEEDWATER/MAIN TURBINE TRIP SYSTEH ACTUATION INSTRUMENTATION.......................,...........

FEEDWATER/MAIN TURBINE TRIP SYSTEH ACTUATION INSTRUHENTATION SETPOINTS.........:...

FEEDWATER/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

PAGE 3/4 3-85 3/4 3-88 3/4 3-91 3/4 3-97 3/4 3"98 3/4 3-99 3.4.3. 2-1 3.4. 4-1 4.4. 5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAHPLE ANO ANALYSIS PROGRAM.............;.....................

3/4 4-15 REACTOR COOLANT SYSTEM PRESSURE ISOLATION 'VALVES...

3/4 4-9 REACTOR COOLANT SYSTEM CHEHISTRY LIHITS............

3/4 4-12 4.4.6. l.3-1 3.6. 3-1 3.6.5.2.-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAH-WITHDRAWAL SCHEDULE...............'.:...............

PRIMA)Y CONTAINMENT ISOLATION VALVES...............

~i SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAHPERS............................'......

3/4 4-19 3/4 6-19 3/4 6-35 4:8.l.l.2-1 DIESEL GENERATOR TEST SCHEDULE....................

3/4 8-7 4.8.1.1.2-2 UNIT 1 AND UNIT 2 DIESEL GENERATOR LOADING TIMERS..

3/4 8-8 4.8.2. 1-1 3.8.4.1-1

3. 8. 4. 2-1 BATTERY SURVEILLANCE REQUIREHENTS.................

PRIHARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.....-....-.

MOTOR OPERATED VALVES THERMAL OVERLOAD P ROTECTION

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3/4 8-15 3/4 8-26 3/4 8-31

3. 11.l. 1-1 SUSQUEHANNA HAXIHUH PERHISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASFD FROH THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE................

3/4 11-2

- UNIT 2 xxvi Amendment No.

r ATlACHMENT 1 TO'age 36 of 58 FIR%

ATION ION INSTRtNKNTATION 3/4:? gA Dct m.CO tectfon zone shown fn Table 3.3.7.9-1 shall be QPERASLE.

APPLI ILITY: &enever equfpeent protected by the ffre detactfon fn ru t is raqu d to be OPERAILE.

ACTION:

fifth the nueber of ERASLE ffre detectfon fnst~nts 1

s thin the Nfnfl~

?nstr~nts OPERASLE ufreeent of Table 3. 3. 7. 9-1:

a.

Wfthfn 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, es lfsh a ffre watch trol to fnspect the zone(>)

wfth the fnoperabl ~

straint(s) a east once per hour, unless the fnst~nt(s) fs Iocat fnsfde fnaccessfble

zone, then fnspect the area our roundfng the ac sfble zone at least once per heur.

b.

The provfsfons of Specff tfo

.0.3 are-not applfcable.

SURVEILLANCE RE IRENENTS 4.3.7.9.1 Each of th above requfred ffre detectfon taunts whfch are accessfble durfng t operatfon shall be deaonstrated 0

LE at least once per 6 oonths by rforeance of a CHANNEL FUNCTIONAL TEST.

detectors

~nfch are not acces le durfng unft operatfon shall'e deeonstrated ERASLE by the perforaanc of a CHQOtEL FUNCTIONAL TEST durfng each COLD excsedf ng 24 hou less perforeed fn the prevfous 6 eonths.

4..9.2 The supervfsed cfrcufts supervfsfon assocfated wfth the 4etect ares of each of the above ~fred ffre detectfon.fnstnuents shell be SUSQUEHANNA - UNIT 2 3/4 3-77 Agenchent No.

<3 4PR y,'4~

ATTACHMENT 1 TO PLA-4352 Page 37 of 58 TABLE 3'.7.9-1 FIRE ZONE NSTRUMENT LOCATION OM OR AREA FIRE OETECTION INSTRUMENTATION INSTRUMEHTS OPERABLE PHOTO-HEAT IONIZATION ELECTR C

ELEV.

TOTAL MIH.

TOTAL MIN.

TOTA MIN.

a.

Control Bu'ldin 0-22A 0-240 0-24G 0-24G 0-25A 0-258 0-25C 0-250,

-25E 0-26B 0-26C 0-260 0-26F 0-26G 0-26H 0-26H 0-26H 0-26H 0-26I Filter rea Lower Rel Room Lo~er Relay oom PGCC Lower Cable Spreading Rm.

South Cable Chase Center Cable Chase North Cable Chase Lower Cable Spreading Rm.

South Cable Chase Center Cable Chase North Cable Chase Vestibule Shift Office Control Rm.

(Under Flr. Unit 1 Control Room (Under Flr.

Un 2)~

Control=;4gea Control-'.4L" Above Clg) ~

Oper ati Support Center 687'-8" 698'1" 698'1" 698'1'I 714'-0" 20 10 714'-0" 1

1 714'-0" 1

1 14'0" 1

6 3

NA NA NA' NA NA NA 714 0"

729'-1 729'-1'I 729'- "

72

-1" 29 I~]ll 2

13 A

NA NA NA HA NA NA NA 6

3 1

1 1

1 1

1 1

1 1

1 729'-1" NA HA 18 9

729'14 NA NA 729'1" NA HA 729'-1" NA HA 729'-1" NA HA 5

8 10 5

9 1

1 NA NA 11 6

4 2

4 2

4 2

4 54 27 30 15 KA NA

.NA NA NA NA NA NA NA NA NA NA NA NA NA

NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 0-26J 0-26M, 0-26N 0-26P

-26R USgUEHANNA - UNIT 2 Vesti le Sof it ntrol Room Soffit Control Room Soffit Sorfit South Cable Chase 729'1" NA NA 729'1" NA NA 729 '1" NA HA 729 '1" NA NA 729'1" NA NA 729'1" 1

1 3

78 1

1 4

2 2

1 2

1 4

2 NA NA NA NA NA NA NA NA NA NA HA NA Amendment No.

50

I ATTACHMENT 1 TO PLA<352 Page 38 of 58

'HSTRUMEHT LOCATION TABLE 3.3 7.9-1 (Cont fnued)

F IRE OETECTION INSTRUMEHTATION INSTRUMENTS OPERABLE FIRE OHE a.

C 0-26 0-26V 0-27A 0-27A 0-27B 0-27C 0-27E 0-27F 0-27G 0-27H 0-28A 0-288 0-28C 0-280 0-28E 0-28F 0-28G 0-28H 0-28I 0-0-2 0-28L 0-28M 0-28H 0-28 0"

-28R ROOM OR AREA ontrol Bufldfn (Continued)

Center Cable Chase North Cable Chase pper Relay Room PG Uppe Cable Spr'e fng Rm.

Upper Cab e

Spreadin Rm.

Upper Relay R

m South Cable Chas Center Cable Chase North Cable Chase Equipment Roea Equipment Room Battery Roore Battery Roora Battery Rooe Battery Rooe Battery R

Repair S

Battery ooe Batte Rooe Bat ery Rooe 8 ttery Rooe Battery Rooe Battery Rooe South Cable Chase Center'able Chase North Cable Chase 729'-1" 729'-1" 754 i 754I-1" 1

1 L

1 2

1 55 2

A NA NA NA 2

1 30 15 NA NA NA VA HA iVA NA IVA 753'-0" 24 12 5

3 NA iVA 753'-0" 754'-1" 754'-

754 I Lll 7

I ~ill 71'-0" 7

I ~Oil I

771 0"

771'-0 771'0" 77ZI~OII 771'-0" 771 OII 771'-0" 77Z'-ON 771i Ou 771'"

77Zi Ou 771 I ~OH 771'-Ou 771'-0" 771'-0" 5

13 4

2 L

1 1

1 1

1 NA MA NA NA NA NA NA NA A

HA N

NA HA NA HA NA NA NA HA NA NA 1

1 1

MA MA NA HA MA NA 1

1 1

8 4

2 1

NA NA NA NA NA NA 4

2 4

2 1

1 1

1 1

.1 L

1 1

1 2

1 1

1 1

1 1

I 1

1 1

1 NA NA NA NA Hh NA NA NA NA NA HA NA NA NA HA iVA NA NA NA NA, NA NA NA HA

,NA NA NA NA NA NA NA NA HA NA NA NA NA NA NA NA NA NA NA NA NA NA NA HEAT IOHIZAT OH TOTAL IH.

TOTA'I ELEV.

TOTAL MIH.

SUSQUEHANNA - UNIT 2 3/

-9 Amendment iVo.

I ATTACHMENT 1 TO PLA4352

, Page 39 of,58 FIRE ZONE STNNENT LOCATION OR AREA TABLE 3.3.7.9-1 (Contfnued)

FIRE OETECTION INSTRtNENTATION INSTRtNENTS OPERABLE HOTO-HEAT IONIZATION ELECTRIC ELEV.

TOTAL IIIM.

TOTAL NIII.

TOTAL I IN.

a.

Control B

ldf (Contfnued) 0-28T Battery ooe 0-29B HtV Equf nt Rooa 0-30A HVAC Equfpea t Rooo

~RE II 2-1B Core Spray Puep R

2-IA Core Spray Puap Rooa 2-IE RHR Puap Roce 2-IF RHR Puap Rooe

-10 RCIC Puap Rooe IC HPCI Puep Rooe 2-IG Suap Rooa 2-2B Core Spray Puep Rooe 2-4C Swftchgear Rooa 2-40 Swftchgear Rooe 2-4A Contafneent Access A

a 2-5F Load Center Rooe 2-5G Load Center Rooe 2-2A.

Access Area Reaote Shutdown P

1 Rooe 2-3A Access A

2 3B Access A

2-3C Access rea 2-48 Pfpe enetratfon Rooa 2-4G Na n Steaa Pfpfng 2-5A uel Pool Puaps and Heat Exchangers 2-5B Valve Access Area 5C RlCLI Backwash Tank 771'-0" 783'-0" 806'-0" 645I-0 645I-0>>

645'-0" 0>>

64 I >>ON 645 I >>

N 645'- "

67

-0" I >>ON 719'-0>>

719'>>

749'-I>>

749'>>

670'-0" NA NA NA NA NA I

2' NA NA NA NA NA NA NA NA NA NA NA NA N

683'-0>>

683'>>

683'>>

719'-I" 719'-1>>

749'1>>

NA NA 761'10" NA NA 749'>>

N NA I

I I

5 20 10 6

3 8

NA NA NA N

NA NA NA NA 2

I Il 6

2 I

2 I

26 I3 2

I 2

I 3

4 14 7

NA NA I

I NA NA 21 11 N

NA I

I NA NA NA NA I3 7

8 5

3 7

4 N

NA NA N

NA NA 3

2 NA NA NA NA N

NA NA NA NA NA 13 7

NA NA 4

2

. 7 2

I 2

I

ATTACHMENT 1 TO PLA<3 Page 40 of 58 INSTRUMENT LOCATION FIRE OETECTIOH INSTRUMENTATION INSTRUMENTS OPERABLE FIRE ZONE ROOM OR AREA b.

React Buf 1 df n Contf nued TO-HEAT IONIZATION CTRIC ELEV.

TOTAL MIN.

TOTAL MIN.

OTAL MIN.

2-50 2-5E 2-5H 2-6A 2-6B 2-6C 2-6E 2 6D 0-6G 2-7A IItC Puaps 4 Heat Exc ngers Penetrat on Roce Instr~nt epafr Rools Access Area Load Center R

Electrfc Equfperent Rooe Hatch and Laydown A HLV Equfpeent Rooe Surge Tank Vault HN Fan and Fflter Rooaa Refuel fng Floor 749'-1" 749 I 1>>

7491 <<]>>

779I~]>>

779 I <<]>>

779 I ~]>>

779I-1 779'-1" 799' 24 12 8

-1 HA NA HA HA 2

1 10 5

4 2

2 1

2 1

6 2

1 14 7

NA NA

]0 5

2 1

NA HA HA NA.'A NA HA HA HA HA NA NA 59 30 0-51 Puap Rooa 0-52 Puap Rooa d.

Ofesel Gene r'

ldf 685I 6" NA NA 6LII-6" HA 6

3 6

3 INFRA RED (FLAME)

OTAL MIH.

0-4]A 0 4]C Qfese ator Rooes V

and Ofese Generator Rooes and D esel Generator Rooas and Dfesel Generator Roose and 660'-0" 677'-0" 660'-0" 677I-0>>

660'-0" 677I-0>>

660'-0" 677'-0" 22 11 22 11 23 12 22 11 2

1 2

1 2

1 15 B

t accessfble.

0

ATTACHMENT t TO PLA-4352 Page 41 of 58 INSTRUHE ATION FIRE OETECTION INSTRNENTATION INSTRUMENTS OPERABLE FIRE 20NE RNN OR AREA Ofesel Generator E Bufldfn H

L KIN.

INFRA-RED (FLAKE)

IONIZATION TOTAL HlH.

TOTAL MIN.

0-41E Ofesel Generato oeas and and eS6 -6" 1

1 e75'-S" NA 708'-0" NA NA NA NA 3

4 18 9

3 2

NA NA SUSQUEHANNA - UNIT 2 Amendment No.

32

ATTACHMENT 1 TO PLA l352 Page 42 of 58 PLANT SYSTBlS

'OWLET'E3) 3/4. 7. 6 a.

Two OPERABLE fire suppression

pumps, one electric motor driven and one diesel driven, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression

header, b.

At least two separate water supplies, each with a minimum con ined olume of 300,000 gallons, and c.

Two PERABLE flow paths capable of taking suction from a two of the llowing:

(1) Unit 1 cooling tower basin, (2) Uni 2 cooling tower b sin, (3) clarified water storage

tank, and tr nsferring the water th ugh distribution piping with OPERABLE sec onalizing control or isolati valves to the yard hydrant curb valv

, the last valve ahead of the ater flow alarm device on each spr'nkler or hose standpipe and the last v lve ahead of the deluge valve o

each deluge or spray system required o be OPERABLE per Specifica ons 3.7.6.2, 3.7.6.5, and 3.7.6.6.

APPLICABILITY: At all times.

ACTION:

a.,Nth one fire pump and/or on of he above required water supplies inoperable, restore the inope le equipment to OPERABLE status within 7 days or, provide an altern a

ackup pump or supply.

The provisions of Specification 3.0.3 are t ap icable.

l b.

Wth the fire suppressi water sys otherwise inoperable establish a backup fire suppress on water system ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE UIRENENTS

4. 7. 6. 1.1 The fire supp ssion water systee shall be d nstrated OPERABLE:

At least o

e per 7 days by verifying the minimum ontained water supply vo use.

At le

t. once per 31 days by starting the electric moto driven fire sup ession pump and operating it for at least 15 minutes on r

irculation flow.

C.

At least once per 31 days by verifying that each valve, manual po~er operated or automatic, in the flow path is in its correct posit n.

d.

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

ATTACHMENT 1 TO PLAP352 Page 43 of 58 e4 g.

4.7.6.L.

a.

Co At least once per L2 aronths by cycling each testabl ~ valve fn the flow paCh through at least one coaplete cycle of full travel.

At least once per'S aenths by performfnq a systesr functfonal whfch fncludes sfaulated autaeat)c actuatfon of the systea t raugnout ts operating

sequence, and:

L.

Ver'ffy)ng that each autosat)c valve fn the flow pa actuates

)ts correct pos) t)on, 2.

Ve fyfnq thaC each f)re suppression pursp dave ops at least 2500 at a systaa head of L25 psig, 3.

Cyclfng ach valve fn th>> flow path that f 'not testable during plant ope ation through at least one corn ete cycle of full

travel, an 4.

Ver)fy)ng tha each f)re suppressio peip starts sequent)ally ta eafntafn the f)r4 suppression r systers pressure greater than or equal to 5 ps)g.

At least once per 3 yea by perfo

)ng a flow test of the system in accordance with Chapter 5, ectfo IL of the Pfre Protection

Handbook, L4th Edftfon, publfshed..by e

N tfonal Fire Protectfon Association.

2 The d)esel drfven ffre suppr

)an pump shall be desonstrated OPERASLE:

At least once per 31 days L.

Verffy)ng the fuel rage tan canta)ns at least 250 gallons of fuel.

2.

Start)ng the df sel drfven pusrp f aabfent conditions and operatfng for ater Chan or equal 30 afnutes on reef rculatf flow.

At least once r 92 days. by ver)fyfng that a asple of dfesel fuel ffOa the fuel storage tank, obtained in accorda e w)th ASTM-0270-75, 5+Hthfn acceptable l)rs)ts specified

)n Tabl 1 of ASTM-0975"77 Net chec f'r v)scosfty, water and sedfaent.

At 1 once pei IS canthi by sub)ectfng the dfesel an fnspectfon fn a rdance with procedures prepared fn con)unct)on w th its aan acturer's recomendatfans far the class of service.

S QUEHANNA - UNIT 2 3/4

-L9

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~

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~

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~

~

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ATTACHMENT 1 TO PLA-4352 Page 45 of 58 PRAY ANO SPRINKLER SYSTEMS LIMIT CONOITION FOR OPERATION 3.7.6.2 The ollowing spray and sprinkler systems shall be OPERABL:

a.

b.

C.

d.

k.

~.

n.

RCIC P

Rooe, Unit 2 HPCI Pump ooe, Unit 2 Upper Cable reading Roow, Unit 2 Lower Cable Spr ding Room, Unit 2 Diesel Generator A

ooe Diesel Generator B Ro Diesel Generator C Rooa Diesel Generator 0 Rooa

~Fire Zone 2-3B Fire Zones 2-4A and 2-4B Fire Zone 2-5A Ffre Zone 0-29B Fire Zone 0-30A Diesel Generato E Building, Fire Zone 0-41E APPLICABILITY:

Whene r equfpoent protected by the spray a d/or sprinkler systems is required be OPERABLE.

ACTION:

a.

b.

N one or sore of the above required spray and/or sprink r systens erable, 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 watch th backup ffre suppression equfpaent for those areas in which red dant systoes or components could be daaaged; for othe~ areas, establi an haply fire watch patrol.

The~fsfons of Specf ffcatfon 3.0.3 are not applicable.

SUSQUEHANNA - UNIT 2 3

- 1 Amendment No.

43

ATTACHMENT 1 TO PLA-4352 Page 46 of 58 SUR ILLANCE RE 1

NTS 4.7.6.2 ch of the above requfred spray and sprfnkler systeas shall be dejsonstrata OPERABLE:

1 a.

At lea t once per 31 days by verffyfng that each valve,

nual, power ated or autoeatfc, fn the flow path fs fn f correct posftfon.

b.

At least once p

12 eonths by cyclfng each tes le valve fn the flow path through t least one coeplete cycle f full travel.

C.

At least once per XS nths:

1.

By perforafng a syst functfon test whfch fncludes sfaulated autoaatfc actuatfon of e

s ea, and:

a)

Verffyfng that the tfc valves fn the flow path actuate to thefr rrect sftfons on a test sfgnal, and b)

Cyclfng each alve fn the fl th that fs not testable durfng pla operatfon through a

least one collate cycle of full avel.

2.

By a vfs fnspectfon of the dry pfpe spra and sprfnkler header to'verffy thefr fntegrfty, and 3.

By vfsual fnspectfon of each deluge nozzle's spr area to rffy that the spray pattern fs not obstructed.

least once per 3 years by perforafng an afr or water flow t

through each open head spray and sprfnkler header and ver ffyfng ch open head spray and sprfnkler nozzle fs unobstructed.

SUS/UEHANNA - NIT 2 3/

1 ATTACHMENT 1 TO PLAR352 Page 47 of 58 LI TING CONITION FOR OPERATION 3.7.6.

The following low pressure COs systeas shall be OPERABLE:

a.

ontrol Rooa Under Floor, Unit 1 b.

C trol Rooe Under Floor, Unit 2 c.

L r Relay,Rooa, Unit Zt d.

Uppe Relay Rooo, Unit A e.

South able Chase f.

Center ble Chase g.

North Cab e Chase h.

Rooe C-412 offit Rooa C-414 S ffft 5.

Control Rooa ffit, Unit I k.

Control Rooe So it, Unit 2 APPLICABILITY: Nenever eq pment protected by the COs systeas is required to mKKE.

ACTION:

a.

b.

Nth one or sore of the ove required s systeas 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 contin us fire wa h with backup fire suppres-sion equfpwrent for those ar as fn wh ch redundant systems or coa-ponents could be dawaged; fo othe

areas, establish an hourly fire watch patrol.

The provisions of Speci ficatfo 0.3 are not applicable.

SURVEILLANCE RE UIREHENTS 4.7.6.3.1 Each of the above requ d low pressu COs systeas shall be demon-strated OPERABLE at least once p r 31 days by veri fng that each valve, manual, power operated, or autowatfc, the flow path fs fn ts correct position.

4. 7.6.3.2 Each of the abov required low pressure COs steas shall be deaanstrated OPERABLE:

a.

b.

At l~t o per 7 days by verifying the COs stor e tank level to be r

an 25X and pressure to be greater than 70 psfg, and I

At Tikt'once per 1B eonths by:

1.

erifyfng the systea valves and associated ventilatfo dampers ale fire door release aeehanfsws actuate wanually and toma-tfcally, upon receipt of a sfaulated actuation signal, a d 2.

Flow f~ each accessible nozzle by perforeance of a "Puff Test."

OAcc ssfble nozzles.

SUSQUEHANNA - UNIT 2 3/4 3

Amendment No.

43

ATTACHMENT 1 TO PLAR352 Page 48 of 58 LON SYSTEMS LI TING CQOITION FOR OPERATION 3.7.6.

The Halon systeas in the following panel modules shall be OPE LE with th storage tanks having at least 9RL of full charge weight and of full cha e pressure:

00 2U701 2U702 2U703 2U704 2U705 2U7 2U730 2U731 2U732 APPLICABILITY:

enever equfpaent protected by the Halon sys eas is required KlWESKE.

ACTION:

a.

Nth one or of the above required Halon systeas inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> e tablfsh a continuous fire tch with backup fire suppression equi nt for those areas in ich redundant systetis or coeponents could daaaged; for other as, establish an hourly ffre watch patrol.

b.

The provisions of Spec ication 3.0 are not applfcabl ~.

SURVEILLANCE RE IREITS 4.7.6.4 Each of the above required H

o systeas shall be deaonstrated OPERABLE.

a.

At least once per 31 s by verffy ng that each valve, sanual, power operated or au tfc, in the ow path is fn fts correct position.

b.

At least once,per aonths by verifying ion storage tank wefght

~

and pressure.

c.

At least once r 1B eonths by:

2.

e of a flow test through accessfb headers and es to assure no blockage.

~,3 rforaance of a functfonal te4t of the general lars circuit associated alarm and fnterlock devfcer.

SUSQUEHANNA - UNIT 2 3/4 24 Amendment No.

43

ATIACHMENT1 TO PLAQ352 Page 49 of 58 RE HOSE STATIONS LIMIT CONOITION FOR OPERATION 3.7.6.5 e fire hose stations shown in Table 3.7.6.5-1 shall bc OPERAB APPLICABILI

~

whenever equipment in the areas protected by the fire ose ERAS E.

ACTION:

a.

b.

With one o

sore of the fire hose stations shown in able 3.7.6.5-1 inoperable, ute an additional fire hose of equal or greater diameter to the unprot ted area(s) floe an OPERABLE hose tation within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoper le fire hose is the priaary sean of fire suppression; otherwise, route the additional hose within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The provisions of ification 3.0.3 are n

applicable.

SURVEILLANCE RE IREMENTS 4.7.6.5 Each of the fire hose stat ns shown n Table 3.7.6.5-1 shall be dewonstrated OPERABLE:

a.

At least once per 31 days by.a stations accessible during pl a equipaent is at the station.

b.

At least once per 1B cont by:

sual inspection of the fire hose operation to assure all required C.

l.

Visual, inspection f the fire hose tations not accessible during plant operation assure all requi equipaent is at the station.

I 2.

Reaoving the se for inspection and racking for all fire hose

stations, a

3.

Inspect) all gaskets and replacing any de aded gaskets in the co ings for all fire hose stations.

At~

nce per 3 years by:

I.

P ially opening each hose station valve to veri valve ERABILITY and no flow blockage.

2 Conducting a hose hydrostatic test at a pressure of 150 sig or at least 50 psig above the saxi'ire main operating p

ssure, whichever is greater.

SUS)UEHANNA - UNIT 2 3/

25 Amendment No.

43

ATTACHMENT 1 TO'PLA4352 Page 50 of 58 LO TIONS FIRE HOSE STATIONS COLUMM HOSE RACK NUMBER a.

ant E

El.

El.

El.

El.

El.

El.

El.

El.

El.

rol Structure 697'-0" 697'-0" 14'-0" 7

I <<PII 729 -P" 729I~

It 754 '0 754 I ~OII 77] I ~Oil 0 II L-26 L-32 L-26 L-31 L-25. 9 L-32.I L-26 L-32 L-26 L-31 1HR-171 2HR-17 1HR-2 2HR 62 1

-158 R-158

. 1HR-136 ZHR-136 1HR-125 2HR-125 ing r E Bu)ld)ng EL.

EL.

EL.

EL.

EL.

E.

Reactor Build El.

645'-0" El.

645'-0" El.

645'-0" El.

670'-0" El.

670'-0" El.

670'-0" El 683I-0 El.

683'-0" El 683'-Ow El.

719'-1" El.

719'1" El.

719'l" El.

719'-1" El ~

719'-1" El.

749'-1" El.

749'-1" EI.

749'-1" EL.

779'-1" EL.

779'-1" EL.

779'-1"

'L.

'79'".

EL. 779',

EL.

81S'.

EL.

818I 1 0)esel Gew 656'56 6

'6" 6'6" 708'0" 708'0" R-37. 4 U-30. 5 R-30 Q-36

'-30.3 5-29

-36 Qa Y-2 Q-36 5-.36 Q-T

-30. 5

$-36 Q-30. 5 T-29 Q-36 S 34.5 Q 31.$

0-29 T-33 R-33 U-33.

Near North Sta)nrell Near South Stairwell Near North Sta)~ll Near South Stairwell Near North Stafnvell Near South Stairwell 2HR-271 2HR-272 2HR 273 2HR-261 2HR-262 2HR-263 2HR-251 2HR-252 2HR-253 2HR-241 2HR 242 2HR-243 2HR-244 2HR-245 2HR-231 2HR-232 2HR-233 2HR-221 2HR-222 2HR-223 2HR-224 2HR-211 2HR-201 2HR-202 OH 811 OHR-OHR-8 OHR 822 OHR 831 OHR-832

~ ~ AO

~ 4

ATTACHMENT 1 TO PLA4352 Page 51 of 58 ARD FIRE HYORANTS ANO HYDRANT HOSE HOUSES LIMNI NG CONOITION FOR OPERATION

3. 7. 6. 6 Yard ffre hydrants 1FHM2 and 1FH104 and associated hydrant hos houses shall be ERABLE.

APPLICABILI Whenever equipeent in the areas protected by the ya fire

>>ERI8iK.

ACTION:

a.

With yard ire hydrants 1FH122 and/or 1FH104 and/o as soci ated hydr ant hose houses noperabl e, route sufficient addi tfo 1 lengths of fire hose of equal or greater dfaaeter located in ad acent OPERABLE hydrant hose house(s) provide service to the unpro cted area(s) wfthf n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

The provisions of cfffcatf on 3. 0. 3 are not appl f cable.

SURVEILUSCE RE IRENENTS 4.7.6.6 Yard fire hydrants 1Fi622 an 1FH and associated hydrant hose houses shall be deaonstrated OPERABLE:

At least once per 31 days by i al inspection of the hydrant hose houses to assure all requi equ nt fs at the hose houses b.

C.

At least once pet 6 eon s, durfng rch, Aprfl or Nay and during Septeaber, October or

velaber, by vf ally inspecting the yard fire hydrants and verifyf that the hydrant arrels are dry and that the hydrants are not At 1 east once pe 12 eonths by:

1.

Conductf hose hydrostatic tests at a p sure of 150 ps kg or

.Lt,. 1 50 psf g above the aaxf aa ffre aa operating pressure, ar Ia greater.

2.

aceaent of all degraded gaskets fn coupl fng 3.

erforaf ng a flow check of each hydrant.

SUSQUEHANNA - UNIT 2 27 Amendment No.

43

PLANT SYSTEMS GeL~D 3/4. 7. 7 ATTACHMENTf TO PLA-4352

- Page 52 of 58 3.7.7 All fire rated asseablfes, including walls, floor/ceilings, cable tra nclosures and other fire barriers separating safety related fire areas or s

arating portions of redundant systeas important to safe shutdown withi a

fir

area, and all sealing devices fn fire rated asseably penetrations, incl fng fire doors, fire windows, fire dajspers, cable and piping pen tratfon seals d ventilation seals shall be OPERABLE.

APPLICA8IL TY:

At all tfats.

'CTION:

a.

Nth o or aore of the above required fire rat assemblies and/or sealing evices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> estab ish a continuous fire watc on at least one side of the affect asseably and/or sealing dev e or verify the OPERABILITY of fre detectors on at least one si of the inoperable fire ass ly and/or sealing device and establish hourly fire watch patro b.

The provisions of fffcatfon 3.0.3 re not applfcabl ~.

SURVEILLANCE RE IREHBITS 4.7.7.1 Each of the above required shall be verified OPERABLE at least inspection of:

a.

The exposed surfaces each fire ated asseably.

rated asseablfes and sealing devices per 18 aonths by perforafng a visual b.

Each fire windage, re deeper, and as ocfated hardware'.

c.

At least 1 of ach type of sealed pene tfon. If apparent changes fn appearanc>>

r abnormal degradatfons are found, a visual inspection of aa addftf 1 3$ of each type of sealed tratfon shall be made.

fon process shall continue until ICE seaple with no s fn appearance or abnoraal deg dation is found.

sha11 be selected such that..each penetra on will be every 15 years.

SUS/UEHANNA - UNIT 2

&~%8 Amendmen t No.

43 sl

g1

ATTACHMENT 1 TO PLA Page 53 of 58 SURVEI E

IRENENTS Cont) nued 4.7.7.2 Each of t bove required fire doors shall er3f1ed OPERABLE by:

a.

b.

C.

d.

Verifying the pos

)on of each closed re door at least ance per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Verifying that doors with a t$ c hold-open and release aechan$ ses are free of abstructfons 1 ~

onc>> per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Ver)fyfng the pos on of each locked sed ffre door at~ least ance per 7 days.

Ver)fy the OPERABILITY of the f$re door superv on systee by per ra$ ng a CHANNEL FUNCTIONAL TEST at least once pe 31 days.

Inspect)ng the autoeat$ c hold-open, release and closing ecch se and latches at least once per 6 aonths.

ATTACHMENT 1 TO PLA-4352 Page 54.of 58 IN BASH 3/4. 3. 7. 9 warn ability is available for the p~t detection of fires.

Tg a-bility fs fn order to detect and locate fires fn their y stages.

Proept detection o

wf11 reduce the potential for ge ta safety-related

~qufpeent and is an integra nt in the ov acflfty fire protection program%

In the event that a

of the fire de fnstrumentatfon is inoperable, incre e frequency of ffre watch patro the affected areas is requi pravfd>> detection capability until the inoperable ntati an i

red to OPERABILITY.

3/4. 3:7. 10 RAOIOACTIYE LI UIO EFFLUENT INSTRUNENTATION The radioactive liquid effluent fnstrusentatfan fs provided to eanftar and control, as applicable, the releases of radioactive aaterfals in liquid effluents during actual or potentfal releases of lfqufd effluents.

The alarm/

trip setpofnts for these fnstrmants shall be calculated fn accordance with the procedures in the OOCN to ensure that the alarm/trip will occur prior to exceeding the 1fofts of 10 CFR Part ZO.

The OPERABILITY and use of this fnst~ntatfon fs consfstent with the requf~nts of General Oesign Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.11 RAOIOACTIVE GASEOUS EFFLUBIT INSTRUMENTATION The radfaactive gaseous effluent fnstruaentatfon is provfded to monitor and control, as applicable, the releases of radfoactfve aaterials in gaseous effluents during actual or potentfal releases of gaseous effluents.. The alarts/

trfp setpofnts for these fnst~nts shall be calculated in accordance with the procedures fn the OOCN to ensure that the alarms/trip will occur prior to exceeding the lfafts of. 10 CFR Part 20.

This fnstnaentatfon also includes provisions for aeftorfng (and controllfng) the concentrations of potentially explosfve gas afxtures fn the waste gas holdup systea.

The OPERABILITY and use of this fns~~ntatfon fs consfstent wfth the requfreaents of General Oesfgn C

rfa 50, 53 and 64 of Appendfx A to 10 CFR Part 50.

3/4 3 7 E PART OETECTION SYSTEN The Q'ERNILITY of the loose-part detection systea ensures that sufffcfent capabflfty fs available to detect loose aetallfc parts fn the prfaary systea and avoid or eftfgate daaage to prfoag systoa coeponents.

The allowabl ~ aut-af-

'service tfmos and surveillance requfreoents are consistent with the recaaeenda-tfons of Regulatory Gufde 1.133, "Loose-Part Oetectfon Prograa for the Prfmary Systea of Light~ter-Cooled Reactors,"

Nay 1ML SVQUEHAtSA - UNIT 2 B 3/4 3 6

I ATTACHMENT 1 TO PLA4352 Page 55 of 58 PLANT SYSTEMS BASES 9ELFrBX) 3/4 7.6 uppressfon capabilfty is available to conffne and axtfngufsh fires occurring fn ny portion of the facility where safety related equfpeent is located.

e fire ressfon systea consists of the water systee, spray and/or spri

ers, CO sys

, Halon systaas and ffre hose stat1ons.

The collectfve o~

1itiy tna fina suppnassion systaas is adaquata to ~iniaiz otantial dosage to safe related equi peent and is a Na)or eleaent in t facility fire protection progr In the event that rtfons of the fire suppressi systems are inoperable, alternate backup fire ffgh g equfpaent fs requf to be made available in the affected areas unt11 the operable equipoe is restored to service.

When the inoperable fire ffghtfng equ nt is in for use as a backup Neans of fire suppression, a longer perio f t fs allowed to provide an alternate means of fire ffghtfng than if the fno able equfpeent fs the prfwary means of fire suppression.

The surveillance requf ts provide assu as that the efnfaa OPERABILITY requfreaents o

he fire suppression sy are met.

An allowance is sade for ensuring a

ffcfent vole<a of Halon fn.

Halon storage tanks by verifying the wef and pressure of the tanks.

In the ev the fire suppression water systee becoees in, able, fesedfate corrective asures est be taken s1nce this systea provides the r fire suppress n capability of the plant.

The requfreaent for a twenty-fo hour repo to the Coaefssfon provides for proapt evaluation of the acceptabf of e corrective eeasures to provide adequate ffre suppression capabflfty he continued protection of the nuclear plant.

3/4.7. 7 fire lfafted.

These design features afnfwfze th y

of a sfng1 fnvolv n one fire are etectfon and extfngufs

'he fire barriers netrat1ons for conduits, cable tr~Qt pfpf ows, fire diapers, an are per1odf ted to verify the1r OPERABIt.ITY 3/4.7aB MAIN TURBIliE BYPASS SYSTEM The required OPERABIt.ITY of the cain turbine bypass systea fs consistent with the assuaptfons of the feedwater controller failure analysis fn the cycle I

specific transient analysis.

SUSgUEHAHNA - UHIT 2 B 3/4 7-4 Amendaent Ho.

31

J

ADMINISTRATIVE CONTROLS ATlACHMENT1 TO PLA<352 Page 56 of 58 UNIT STAFF (Continued) c.

A health physics technician" shall be onsite when fuel is in the reacto'r.

d.

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

mu4dew a

e Admini s trative procedures shall be developed and implemented to limi:

the working hours of unit staff who perform safety-related functions; e.g.,

senior reactor ooerators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

1.

A individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />

straight, excluding shift turnover time.

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour

period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.

3.

A break of at least eight hours should be allowed between work

periods, including shift turnover time.

4.

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

pe, 'PC~S:.ge F- ++~~~ +~+~~

Any deviation from the above guidelines shall be authorized by the or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be ev>ewe mon y

y e

ehanna or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

The Supervisor of Operations shall hold a Senior Reactor Operator License.

Amendment No.:.

'OV I 6 1988 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.

SUS(UEHANNA - UNIT 2 6-2

I ATTACHMENT 1 TO PLAR352 Page 57 of 58 ADMINISTRATIVECONTROLS RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

a.

b.

Co d.

e.

go h.

k.

Review of all administrative procedures and changes thereto.

Review of all proposed tests and experiments that affect nut;)ear safety.

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

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

Review of the safety evaluations for procedures and changes thereto completed under the provisions of 10 CFR 50.59.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports cove~ing evaluation and recommendations to prevent recurrence to the Vice President-Nuclear Operations and to the Susquehanna Review Committee.

Review all REPORTABLE EVENTS.

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

Performance of special reviews, investigations or analyses and reports thereon as requested by the Superintendent of Plant-Susquehanna or the. Susquehanna Review Committee.

Review of the Security Plan and shall submit recommended changes to the Susquehanna Revie~ Committee.

Review of the Emergency Plan and shall submit recommended changes to the Susquehanna Review Committee.

Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the <or

, rective action to prevent recurrence to the Vice-President-Nuclear Operations and to the Chairman of the Susquehanna Revie~ Committee.

Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

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cba<qes 44 ShgW<<ncL SUSQUEHANNA - UNIT 2 6-9

ATTACHMENTI TO PLA~352 Pa e5 6.7 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vice President-Nuclear Operations and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety LimitViolation Report shall be prepared.

The report shall be reviewed by the PORC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety LimitViolation Report shall be submitted to the Commission, the SRC and the Vice President-Nuclear Operations within 1'4 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 6.8.1 Written procedures shall be established.

implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Ran implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

Offsite Oose Calculation Manual implementation.

i.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979..

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~~/ J 6.8.2 Each procedure of 6.8.1(a) through (g) above, and changes thereto, shall be reviewed in accordance with Specifications 6.5.1.6 or 6.5.3, as appropriate, and approved by the d

revie periodically as set forth in administrative procedures.

theo Prve ann@-A~ti~r Opar~kons Each groped ore of 6.8.1. above. and changes thereto, that is established to impiement those portions of the radiological eNuent and environmental monitoring programs andi those portions of the OOCM that are the responsibility of Nuclear Technology shall be approved by the Manager-Nuclear Technology.

SUSQUEHANNA - UNIT 2 6-15 Amendment No. 86

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