ML20035A013

Proposed Tech Specs Re Plant Fire Protection

ML20035A013
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/16/1993
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20035A010	List: ML20035A009 ML20035A011 ML20035A013
References
NUDOCS 9303230235
Download: ML20035A013 (26)

Text

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LCA 231 Attcchment II INDEX Pags 1 of 23 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION Page 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference................... 3/4 2-1 i

3/4.2.2. Heat Flux Hot Channel Factor............... 3/4 2-3

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3/4.2.3 Nuclear Enthalpy Rise Hot Channel. Factor......... 3/4 2-7 j

3/4.2.4 Quadrant Power Tilt Ratio................. 3/4 2-11 3/4 2-14 3/4.2.5 DNB Parameters.....

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION............ 3/43-1 3/4.3.2 ENGINEERED SAFETY' FEATURE ACTUATION SYSTEM INSTRUMENTATION..................... 3/4 3-13 j

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation........... 3/4 3-33 f

i Movable Incore Detectors................. 3/4 3'-37 Seismic Instrumentation.................. 3/4 3-38 l

Meteorological Instrumentation.............. 3/4 3-41 I

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Remote Shutdown Instrumentation..............- 3/4 3 t hlorine Detection Systems................. 3/4 3-47.

i Delete

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l Decouple Switches..................... 3/4 3-50 l

Accident Monitoring Instrumentation............ 3/4 3-51' i

Radioactive Liquid Effluent Instrumentation........- 3/4 3-54 l

Radioactive Gaseous-Process and Effluent Monitoring Instrumentation................ 3/4 3-59.-

l l

S0 Detection Systems................... 3/4 3-68 j

2 l

3/4.4 REACTOR-COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS................... 3/44 l l

TRO.1AN-UNIT 1 IV Amendment No. 48, IE. 75, 95, 795, 327. 172 I Se+ + -?O,7""1-L i

9303230235 930316 PDR ADOCK 05000344 P

PDR j

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LCA 231-Attechment II Page 2 of 23-E t

INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS

!1i SECTION PAGE i

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......

3/4 7-12..

j i

3/4.7.3 COMPONENT COOLING WATER SYSTEM........................ 3/4 7-13

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3/4.7.4 SERVI CE WATER SYSTEM.................................. 3/4 7-15 i

t 3/4.7.5 ULTIMATE HEAT SINK.................................... 3/4 7-17 3/4.7.6 CONTROL ROOM EMERGENCY YENTILATION SYSTEM............. 3/4 7-18

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3/4.7.7 SEALED SOURCE CONTAMINATION........................... 3/4 7-21 s

r-3/4.7.

e v e...re, m. m. m e c. c. e ne.aur--ue

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' Fir: S;PP r::; f =n 2 t r 5y;;;......................... 3/

• 7 22 35)-

(,>eteteafsPr<r.a,crSy:t=;.....................................3/7-:7 tt -

l f F4 r0 H::: S t:t i:n:.................................... 3/ ' 7- 0 El'#

3/,*.7.9(".""..".'.".".~.'^..".".'."..."'.,.."...'.'"...............................'.,",',.".ES/

a s

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3/4.7.10 SNUBBERS............................................. 3/4 7-32 l,)\\

s 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS........

3/4 7-38 l l Obs -

j i

3/4.8 ELECTRICAL POWER SYSTEMS r

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3/4.8.1 A.C. SOURCES

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Operating.............................................

3/4 8-1 S h u td o wn.............................................. 3/ 4 8-5 i

. i, 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS l

i A.C. Distribution - Operating.........................

3/4 8-6 i

A. C. Di s tribution - Shutdown.......................... 3/4 8-7 D.C. Distribution - Operating.........................

3/4'8-8 D.C.- Di stribution - Shutdown.......................... 3/4 8-10 3/4.8.3 UNDERVOLTAGE PROTECTION 4.16 kV Emergency Bus Undervoltage Protection.........

3/4 8 1

-l i.!

TROJAN - UNIT 1 VII Amendment No. 18, 37, #7, 30. 57,102

m. m uy :. = b -

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LCA 231 Attochment II

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Page 3 of 23 INDEX i

F.

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BASES SECTION PAGE l

h b

3/4.7 PLANT SYSTEMS t

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 i

3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

B 3/4 '7-4 3/4.7.4 SERVICE WATER SYSTEM......................................

B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK........................................

B 3/4 7-4 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM...........................

B 3/4 7-5 3/4.7.7 SEALED SOURCE CONTAMINATION..

B 3/4 7-5 3/4.7.8 FI"E SL'"""EE.r!0N SYC......t

..c.n n......................

! 3/' 7-h h 3/4.7.*. "".'....'....".".".#*'"""

• ' ', ' '. ' ' ^

3/4.7.10 SNUBBERS..................................................

B 3/4 7-6 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION B0LTS............

B 3/4 7-8 s.

3/4.8 ELECTRICAL POWER SYSTEMS l

3/4.8.1 A.C.

SOURCES..............................................

B 3/4 B-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS.........................

B 3/4 8-1 1

3/4.9 REFUELING OPERATIONS 3/4. 9.1 BORON CONCENTRATION.......................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

B 3/4 9-l' 3/4.9.3 DECAY TIME..............................,.................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILOING PENETRATIONS.........................

B 3/4 9-1 3/4.9.5 Com0NICATIONS............................................

B 3/4 9-1 t

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TROJAN-UNIT 1 XIII Amendment No. IE, 77, #7, 192, 187 v

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LCA 231 INSTRUMENTATION Attachment II Page 4 of 23 FIRE PROTECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire protection instrumentation for each fire detection zone shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTION:

With one or more of the fire detection instrument (s) shown in Table 3.3-10 inoperable:

a.

Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour unless the instrument (s) is located inside the Containment, then inspect the Containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1 or 10 CFR 50.72, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

_. c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEitlANCE REQUTREMENTS 4.3.3.7.1 Each of the above required smoke detection instruments shall be l

demonstrated OPERABLE at least once per 6 months by performance of a ll' CHANNEL FUNCTIONAL TEST. Smoke detectors which are not accessible during plant operation shall be oemonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless l

performed in the previous 6 months.

4.3.3.7.2 One or more of the thermal detection instruments from each fire I

detector zone shall be tested at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Different detectors shall be selected for each subsequent test such that within five years, each detector shall have been tested.

l 4.3.3.7.3 The NFPA Code 72D Class B supervised circuits supervision lI associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERAELE at least once per 6 months.

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Intentionally Deleted LI TROJAN-UNIT 1 3/4 3-48 Amendment No. 48, EG,y,189 j

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LCA.231 Att chment I Pegs 5 of 23 Table 3.3-10 FIRE DETECTION INSTRUMENTS

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f INSTRUMENT LOCATION MINIMUM INSTRUMENTS ORERABLE*

Smoke Thereal l

1.

Control Room a.

KIIU 6-#1, Zone 1 4

[

b.

KZIU 6-#1, Zone 2 4

c.

KZIU 6-#1, Zone 3 1

d.

KZIU 6-#1, Zone 4 1

-l 2.

Cable Spreading Room j

a.

KZIU 6-#2, Zone 1 2

b.

KZIU 6-f2, Zone 2 2

(

c.

KZIU 6-#2, Zone 3 2

i d.

KZIU 6-#2, Zone 4

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2 3.

Electrical Penetration Area l

a.

KZIU 6-#5, Ione 1 2

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b.

KZIU 6-f5, Zone 4 1

4.

Switchgear Room f

a.

Train A Elevation 69 ft (1) KZIU 6-#7, Zone 1 5

(2) KZIU 6-#7, Zone 2-5 5

i r

b

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TROJAN-UNIT I 3/4 3-49 Amendment No. M, 9, M 189 1

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LCA 231 Attachment II Page 6 of 23 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE \\

Smske Thermal b.

Train B Elevation 61 ft I

1 KZIU 6-f6, Zone 3 5

c.

Train A Elevation 65 ft KZIU 6-f6, Zone 4 2.

f 5.

Station Battery Rooms a.

Train A Elevation 65 ft KZIU 6-f6, Zone 2 1

)

b.

Train B Elevation 65 ft i

KZIU 6-#6, Zone 1 1.

6.

Containment a.

KZIU 6-f5, Zone 2 1

~

b KZIU 6-f5, Zone 3 1

c.

KZIU 6-fl9, Zone 3 2

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7.

Auxiliary Feedwater Pump Rooms i

b.

KZIU 6-f16, Zone 2

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2 a.

KZIU 6-f16, Zone 1 1

i i

c.

KZIU 6-#16, Zone 3 1

i 8.

Residual Heat Removal and Safety Injection Pump Rooms a.

KZIU 6-113, Zone 1 2

b.

KZIU 6-#13, Zone 2 4

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9.

Service Water Pump Area t

a.

KZIU 6-#8, Zone 1 1

l b.

KZIU 6-f8, Zone 2 1

c.

KZIU 6-f8, Zone 3 1

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VW TROJAN-UNIT 1 3/4 3-49a Amendment No. 48, M, G,

92, 189

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LCA 231 Attachment'II Page 7 of 23 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

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10. Service Water Booster Pump Area I

a.

XIIU 6-19, Zone 1 1

b.

KZIU 6-#9, Zone 4 4

11. Centrifugal Charging Pump Rooms a.

KZIU 6-f14, Zone 2 1

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b.

KZIU 6-#14, Zone 3 1

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12. Emergency Diesel Generator Rooms a.

KZIU 6-#15, Zone 1 3

2

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b.

KZIU 6-#15, Zone 2

13. Component Cooling Water Pump Area b.

KZIU 6-#9, Zone 3 2

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a.

KZIU 6-f9, Zone 2 l'

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..,.b.

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• The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment J

leakage Rate Tests.

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Intentionally Deleted i

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TROJAN-UNIT 1 3/4 3-49b Amendment No. 48, GG, 69, G3,189

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LCA 231

, 1 Page 8 of 23 LANT SYda d5 3/t.7.8 FIRE SUPPRESSION SYSTES.S FIRE SUPPRESSION WATER SYdied LIMITING CONDITION FOR OPERATION 3.7.8.1 The fire suppressicn water system shall be OPERABLE with:

One 2000 gpm fire pu=c capable cf being pcwered by an OPERAELE a.

ciesel engine, b.

One 2000 gpm meter-d-iven fire pump capable cf being pcwered by an GPERAELE pcwer supply, and 4

An CPERABLE ficw path capable cf taking suction fr::m the c.

Coluccia River and transferring the water thrcush distri-butien piping with CPERAELE secticnalizing centrol er isolatica valves to the yard hydrant curb valves and the

. first valve ahead cf the watar ficw alarm device en each sprinkler / spray / deluge er hese standpipe riser required to be OPERABLE per Specificatiens 3.7.8.2 and 3.7.3.3.

APPLICABILITY: At all times.

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ACTION:

4 With cne pump inepe able, res:cre the inceerable equipment to CPERAELE status within 7 days cc, in lieu of any other

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report required by Specification 5.5.1 cr 10 CFR 50.72, l/97\\

prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 30 days cutlining the plans and precedures to be used to provide for the icss of redundancy in this system. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

h b.

With the fire suppressien water system ctherwise incperable:

1.

Establish a backup fire suppressien water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 2.

Sub=it a Special Repcrt in ac:crdance with Specificatica 6.9.2:

a) By telephcne within 24 hcurs, b) Confir=ed by talegraph, mailgram er facsimile t ansmissien no later than the first werking day follcwing the eve:t, and 4

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Intentionally Deleted TROJAN-UNIT 1

/4 7-23 Amend ent No. JE MJ' 97 Ge*+ e20,IM' C

LCA 231 i

Attachment II f-Page 9 of 23

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PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) c)

In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7. 8. L 1 The fire suppression water system shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by starting each a.

pump and operating it for at least 15 minutes.

b.

At least once per 31 days by verifying that each valve (manual,

~ power operated or automatic) in the flow path is in its correct -

position.

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

c.

d.

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

\\ _. i' At least once per 18 months by performing a system functional test e.

which includes simulated automatic actuation of the system throughout its operating sequence, and:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a test signal, 2.

Verifying that each pump develops at least 2000 gpm at a system head of 125 psig, 3.

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 4.

Verifying that each high pressure pump starts (sequentially) to-maintain the fire suppression water system pressure > 100 psig.

Intentionally Deleted M

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i TRO.IAN-UNIT 1 3/4 7-24 A=endment No. IE,185

1, :0 2 L

LCA 231 y

Attcchment II i

Pege 10 of 23

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PLANT SYSTEMS r

SURVEILLANCE REOUIREMENTS (Continued) f.

At least once per 3 years by performing a flow test of the system in accordance with' Chapter 5, Section 11 of 1

the Fire Protection Handbook,14th Edition, published by the National Fire Protection Association.

4.7.8.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1.

The fuel storage tank contains at least 200 gallons of fuel, and 2.

The diesel starts from ambient conditions and operates for at least 20 minutes.

b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tant, obtained in accord-i ante with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM 0975-78 when checked for water, viscosity and sediment.

f I

c.

At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in f

conjunction with its manufacturer's reconenendations for

^

g the class of service.

4.h.8.1.3 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:

s a.

At least once per 31 days by verifying that:

)

1.

The electrolyte level of each battery is above the plates, and 2.

The overall battery voltage is >24 volts.

Intentionally Deleted TROJAN-UNIT 1 3/4 7-25 Amendment No. 77, 27, AD, 110 mm 3,1901 C i

LCA 231 Attaciunent 11 Page 11 of 23 PLANT SYSTEw.S SURVEILLANCE REOUIREMERTS (Continued) b.

At least once per 31 days by verifying that the charging current d

is appropriate for continued service of the battery.

c.

At least once per 18 months by verifying that:

1.

The batteries, ceil plates and battery racks show no visual

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indication of physical damage or abnomal deterioration, and

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2.

The battery-to-battery and teminal connections are clean, tight, free of corrosion and coated with anit-corrosion material.

Intentionally Deleted N

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i TROJAN-UNIT 1 3/4 7-25 Amendment N,o,.Jg 92 v

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LCA 231 1 Page 12 of 23 LANT SYSTEMS

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SPRAY, SPRINKLER, AND/0R DELUGE SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.8.2 The following spray, sprinkler, and/or deluge systems shall be

't OPERABLE:

a.

Emergency diesel generator rooms, b.

Auxiliary feedwater pump room, c.

Electrical penetration areas, d.

Diesel fire pu=p room, e.

Cable spreading room,

(

f.

Service water booster pump area, and g.

Component cooling water pump area.

J APPLICABILITY:

Whenever equipment in the spray, sprinkler, and/or deluge proteccea areas is required to be OPERABLE.

ACTION:

With one or more of the above required spray, sprinkler, and/or

. _. /

a.

deluge systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days I

or, in lieu of any other report required by Specification 6.6.1 or 10 CFR 50.72, prepare and submit a Speclal Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specificatiens 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.3.2 Each of the above required spray, sprinkler, and/or deluge systems shall be demonstrated OPERABLE:

At least once per 12 months by cycling each testable valve in the a.

t y

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

b.

At least once per 18 ronths:

1.

By performing system functional tests (including simulated automatic actuation of the system) to:

a)

Verify that the automatic valves in the flow path actuate to their correct positions on a test signal, and 1

Intentien liv.. leted TROJAN-UNIT 1 Amendment No. IS, 50, M e 97 21 :2, :,' L

LCA 231 Attachment Il Page 13 of 23

/ plAhT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) b)

Cycle each valve in the flow path that is not ld testable during plant operation through at least one complete cycle of full travel.

2.

By-inspection of the spray headers to verify their integrity, and i

3.

By inspection of each nozzle to verify no blockage.

At least once per 3 years by performing an air flow test through c.

each open head spray / sprinkler header and verifying each open L

head spray / sprinkler nozzle is uncbstructed.

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4 Intentionally Deleted I

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TROJAN-UNIT 1 3/4 7-28 Amendment No. JB, 92

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LCA 231 Attachm2nt 11 Page 14 of 23 r.

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PLANT SYSTEMS FIRE HOSE STATICHS LIMITING CONDITIONS FOR OPERATICN 3.7.8.3 7he fire hose stations shown in Table 3.7-4 shall be OPERABLE.

APPLICABILITY: Whenever ecuipment in the areas protected by the fire nose scations is recuired to be OPERABLE.

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7-4 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an CPERABLE hose station wihin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1 g

or 10 CFR 50.72, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and plans and schedule for restoring the station to OPERABLE status.

b.

7he provisions of Specifications 3.0.3 and 3.0.4 are not i

applicable.

SURYEILLANCE REOUIR !ENTS n

4.7.8.3 Each of the fire hose stations shown in Table 3.7-4 shall be demonstrated OPEP.ABLE:

a.

At least once per 31 days by visual inspection of the station to assure all required ecuipment is at the station. Fire hose stations which are not accessible during plant operation shall be inspected 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 perfomed in the previous 31 days.

b.

At least once per 18 months by:

1.

Removing the hose for insoection and re-racking, and 2.

Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c.

At least once per 3 years by:

1.

Partially opening each hose station valve to i

verify valve OPERABILITT and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure

)

available at that hose station.

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g Intentionally Delete TROJAN-UNIT 1 1 /4 7-2 Amendment No. 7E, 50, #3 97 ee::t u 20, n :'

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LCA 231 Attachment II Page 15 of 23 TABLE 3.7-4 FIRE HOSE STAU CNS LOCAUCN ELEYAD ON" HOSE STAU CN r

1.

Auxiliary Building 5 ft MS-34 i

2.

Auxiliary Building 25 ft.

5 33 3.

Auxiliary hilding 45 ft.

5 13, 33 4.

Auxiliary Building 63 ft.

5 29 5.

Auxiliary Butiding 77 ft Ms-28

5. Thrrbine Building 45 ft.

N3-3, 5 I

7.

Turtine Building 89 ft MS-27 l

8.

Turbine Batiding S3 ft.

5 15 3.

Controi auf1 din, s3 ft.

nC.:

10. Control Building 77 ft.

us-tg

11. Cantairment 45 ft 4 a,h1

-l C

12. Cantainment 93 ft Cx5-sta,b1 M

ff

13. Containment 93 ft CX5-C[a,b]

4

[al From Deafnerali:ed Water Systam

[b] I W d Durfng COLD SHUTDOWN f

A Intentionally Deleted l

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l ra m N-UNIT 1-3/4 7-se amendmentno.gg,'ss m.=u:u,un 0 b

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LCA 231

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Attachspnt 11 i

Page 16 of 23 LANT SYS T.MS s

r3/a.7.9 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION l.7.9 3

All 3-hour penetraten fire barriers prctecting safety related areas shall be func:1cnal.

AFPLICABILITY: At all times.

ACTION:

With one er :cre cf the above required penetratica fire a.

barriers nenfunctional in areas with a ecdustible leasing greater than 1 lb/sq ft equivalent weed, provide either a continucus fire watch en at least one side cf the affected penetration within I hour or verify the OPEPABILITI cf fire deteccrs en at least one side cf the nonfuncticnal fire barrier and establish an hourly fire watch patrol. Restcre the ncnfunctional fire barrier penetratien(s) to func:1cnal status within 7 days cc, in 11eu cf any c:her repert recuired by Specification 6.6.1 cr 10 CFR 50.72, prepare and submit a

\\/97\\

A Special Report to the Comission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the nonfunctional penetrations and plans and

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schedule for restoring the fire barrier penetration (s) to functional status.

b.

The previsions cf Specifications 3.0.3 anc 3.0.4 are no:

applicable.

i SURVEILLANCE REOUIREMENTS 4.7.9 Each cf the abeve re j

) verified to be functienal: quired penetratica fire barriers shall be

~

At least ence per 18 =cnths, by a visual inspectica.

~

a.

b.

Pricr to returning a penetraticn fire barrier to ftncticnal i

status following repairs er :aintenance by perfer_ance of a visual inspecticn of the affected penetra:1cn fire harrier (s).

Intentionally Deleted

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ncJAN-UNIT I 3/4 7-n Ameneent no. n, n,Jp, g7

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LCA 231

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Attachment II Page 17 of 23 5,

INSTRUMENTATION BASE 5 3/4.3.3.6 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personnel and is consistant with the reconnendations of Regulatory Guide 1.95 " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.

The recirculatica mode of operation is defined as stopping the control room I

nomal ventilation system and maintaining the emergency control room ventilation system in a lineup capable of responding to a safety infection signal. This does not preclude operating the C3-1 fans with the outside air makeup campers closed and/or performing the other required actions in the event of an actual chlorine release.

The compensatory actions necessary when providing periodic air exchanges for saintaining Control Room air quality per the footnote of Specification 3.3.3.6 shall include:

(1) restricting Control Roodi access to essential personnel to limit carbon dicxide, (2) suspending onsite activities which could generate chlorine gas, including receipt of chlorine shipments or chlorine producing materials, and (3) establishing continuous communica+'on between the Control Rcom and personnel observing the railroad craffic on the tracks both east and west of the Plant. The personnel must alert the Control Room in.

sufficient time to allow outside air damars to be closed whenever a train _ approaches and passes by the Plant.

3/4.3.3.7 T MIM 2 9 9CM

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w OIERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumen-tation is restored to OPERABILITY.

TROJAN-UNIT 1 B 3/4 3-3 Amendment No. 18, 56,IEK l

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LCA 231 Attachment II Page 18 of 23 PLANT SYSTEMS EASES (Continued) plutonium. Leakage of sources excluded from the requirements of this specification represent less than one maximum permissible body burden for total body irra e source material is inhaled or ingested.

3/4.7.8 T: % 2 Pr"::CION N U E"!

E The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, sprinklers and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made avcilable in the affected areas until the inoperable equipment is restored to service.

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1 TPA1AN-UNIT 1 B 3/4 7-Sa Amendment No. IE, 25, I12,184

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3. e_ n_ e n 7

LCA 231

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PLANT SYSTEMS BASES In the event the fire suppression water system becomes inoperable, imediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Comission provf fes for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppres-l sion capability for the continued protection of the nuclear plant.

3/4.7.9

~I " '"' I Z D I

The functional integrity of the penetration fire barriers ensures that.

fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detec-tion and extinguishment.

The penetration fire barriers (doors, walls, dampers, and seals) are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, the combustible leading of the safety-related areas dictates the type of temporary protection to be provided. The combustible loadings for each room in the "e

plant are listed in Table 3-1 of PGE-1012, Trojan Nuclear Plant Fire Protec-

/

tion Review. Where combustible loadings are considered low (less than or equal to 1 lb/sq ft equivalent wood), credit is allowed for installed detec-

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tion syste=s and installation of temporary fire barriers.

Either of these, in addition to an hourly fire patrol, give adequate assurance that a fire could not initiate and propagate through the nonfunctional penetration barrier.

Where combustible loadings are somewhat greater (greater than 1 lb/sq ft l

equivalent wood) either a temporary fire barrier is installed, an installed detection system is provided, and an hourly fire patrol is established, or a continuous fire watch is required.

For either case, the continuous fire watch or the fire watch patrol is uired to be maintained until the barrier is restored to functional status.

3/4.7.10 SNUBSERS All snubbers are required OPERABLE to ensure that the structural integ-rity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed

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on nonsafety-related systems and then only if their failure or failure of the

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system on which they are installed would have no adverse effect on any safety-related system, e

TROJAN - IJNIT 1 B 3/4 7-6 Amendment No. 78,f,102

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LCA 231 Attachment II

? age 20 of 23

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ADMINISTRATIVE CONTROLS h

6.2.2 FACILITY STAFF The Facility organization shall be subject to the following:

a.

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

The minimu= shift crew necessary for safe shutdown is five.

b.

At least one licensed Operator shall be in the control room when fuei is in the reactor.

At least two licensed Operators shall be present in the control room c.

during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor, All CORE ALTERATIONS after the initial fuel loading shall be e.

directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handlird who has no other concurrent responsibilities during this operation.

f.

A Fire Brigade of at least 5 members shall be saintained onsite at all times. The Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit or any.

personnel recuired for other essential functions during a fire emergency. Fire Brigade composition may be less 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 accommcdate unexpected absences of enduty members provided immediate action is taken to restore the Fire Brigade composition to within the minimum requirement of 5.

l g.

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

Key maintenance personnel of the unit staff are those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety related structures, systems or components, and who are personnel performing or immediately supervising the performance of such activities. ' This applies to key saintenance personnel whether on shift or not.

i Adequate shift coverage shall be maintained without routine heavy use of overtime. The baseline for determining overtime use will be l

a 40-hour work week when the plant is operating. However, in the event that unforeseen problems require substantial a ounts of i

TROJAN-UNIT 1 6-2 Ame ent No. y,f87

r LCA 231 Attachment II Page 21 of 2.3 ADMINI3TRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum i

cualifications of ANSI N18.1-1971 forcomparablepositions,exceptfor(1)the Radiation Protection Manager who shall meet or exceed the qualifications of i

Regulatory Guide 1.8, Rev. 2, April 1987 and (2) the Shift Technical Advisor i

who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design,' and response and analysis of the Plant for transients and accidents.

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6.3.2 The Operations Manager shall hold a Senior Reactor Operator License.

6.4 TRAINING

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6.4.1 A retraining and replacement training program for the facility staff shall be mair.tained under the direction of a General Manager and shall meet

l. I-or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

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[6.4.2 A training pro

!directionofaGenerafasfortheFireBrigadeshallbemaintainedunderthe Manager and shall aset or exceed the requirements of l

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hection 27 of the NFPA Code-1975, except for Fire Brigade training sessions i

ch shall be held at least quarterly.

6.5 REVIEW AND AUDIT g

6.5.1 PLANT REVIEW BOARD (PRB) j FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the Plant General I

Manager on all matters related to nuclear safety.

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TROJAN-UNIT 1-6-5 Amendment No. 18, II, #2, If, 148, Idf A r r t 25, '^^', ~, III, 187 155 16I 4

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LCA 231 Attachznent II Page 22 of 23 4.

ADMINISTRATIVE CONTROLS c.

Review of proposed tests or experiments which may involve an unreviewed safety question as defined in 10 CFR 50.59 or requires a change in Technical Specifications, d.

Review of proposed changes to Technical Specificatient or the Operating License.

Investigation of all violations of the Technical specifiestions e.

including the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence to the Vice President Nuclear and to the Chairman of the Trojan Nuclear Operations Board. The investigation shall include an assessment of the safety significance of each violation.

f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential safety hazards.

h.

Perfor=ance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Trojan Nuclear Operations Board.

i.

Review of the Plant Security Plan and implementing procedures.

j.

Review of the Emergency Plan and implementing procedures.

k Review of the Offsite Dose Calculation Manual.

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rotection P-an and liiiplemiinfing proce ae m.

Review of tne F re ALTTHORITY

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6.5.1.7 The Plant Review Board shall:

a.

Recomend to the Plant General Manager written approval or disapproval of items considered under 6.5.1.6(a) through (c) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety maestion. -

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President Nuclear and the Trojan Nuclear Operations Soard of disagreement between the PRB and the Plant General Manager; however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

TROJAN-UNIT 1 6-7 Amend:ent No. #2, if, is, 77, 72, IJK re=y r, "W, Iff,181

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IIA 231 Attachment II Page 23 of 23

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ADMINISTRATIVE CONTROLS 6.9.1.7.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions Ll or supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 The originals of Special Reports shall be submitted to the Document Control Desk with copies sent to the Regional Administrator, NRC Region V, and the Resident Inspector within the time period specified for each report. These

_ reports shall be submitted co'vering the activities identified below pursuant to

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the requirements of the applicable reference specification:

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

a.

b.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

l c.

Failed or inoperable safety valve, Specifications 3.4.2 and 3.4.3.1.

d.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

Sealed Source Leakage in excess of limits, Specification 4.7.7.1.3.

a.

f.

S t Analysis, Specification 4.3.3.3.2.

rir: 0: teeth n !n:tru :.t:ti:n, Sp:ci'!::ti:n 2.2.2.'. U

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n e t pp)essica Systems, Cpecificetica; 0.7.0.1, 0.7.0.2, and 0.7.0.0. gv (Xe}etep %

h.

1.

Accident Monitoring Instrumentation, Specification 3.3.3.9.

f.

Control Butiding Modification Connection Bolts, Specifications 3.7.11 and 4.7.11.2.

k.

Overpressure Protection System, Specification 3.4.9.3.

1.

Reactor Coolant Loop, Specification 3.4.1.4.

_ _ r % 2 = i =, :p =if m t = :.7.:. v m.

Instrumentation Decouple Switches, Specification 3.3.3.8.

n.

Containment Structural Integrity, Specification 4.6.1.6.4.

o.

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TROJAN-UNIT 1 6-17 Amandment No. JK, 76, 78, gg, II, 57, 255, IK2,157, 272, I75,187 augu:: 253 1002 U

LCA 231l Attachment III Page 1 of 3 2. (cont.)

C. (cont.)

(6) Spent Tuel Pool Modification Since spent fuel is now being stored in the spent fuel i pool, upon cc=.encement of work on either the existing racks or the new racks in the spent fuel pool in conjunction with replacement of the existing racks with new racks:

l (a) the water in the spent fuel pool shall contain at least 2000 ppm boron and shall be maintained at this -

boron concentration until completion of the ract replacement; and (b) spent fuel stored in the spent fuel pool must have a

decayed at least 60 days from the time it was last removed from the reactor.

During the time that boron is required in the spent l

fuel pool, it shall be verified to meet the concen-tration requirement by chemical analysis at least 3 times per 7 days, with a maximum time interval between samples of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

L Priortofinalconversionto'themodifiedrackdesign,[

fuel may be stored, as needed, in either the new storage racks described in Technical C

Specification $.6.1.2 cr in the existing storage racks 88 l

(or both). The existing racks are designed and shall be maintained with a nominal 13.3-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a K,gg of less than or equal to 0.95 with the storage pool filled with unborated water, including a conservative allowance.for uncertainties as described in section 3.1.2 of Topical Report PCE-1013.

(7) Quality Assurance Except for the installation of the hangers, restraints and snubbers identified in item A.1 of Enclosure 1 to this license, which may be completed in accordance with the Quality Assuran:s Program for Construction, all activities to which a Quality Assurance Program is applicable shall, after the date of issue of this l

t licenne, be conducted in accordance with the Nuclear

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Quality Assurance Program.

M1 (8) The licensee may proceed with and is required to i

INSERT A complete the modifications identified in l

Amendment No. 23, 34

88. 110 Date of Issuance:

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LCA 231 Attechment III Page 2 of 3

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2. (cont.)

C. (cont.)

Paragraphs 3.1.1 through 3.1.18 of the NRC's Fire Protection Safety Evaluation Report on the Trojan Nuclear Plant dated March 22, 1978. These modifications shall be completed by the end of the second refueling outage of the Trojan facility and prior to return to operation for Cycle 3.

In 2

addition, the licensee shall submit the additional information identified in Table 3.2 of this safety Evaluation Report in accordance with the schedule contained therein. In the event these dates for submittal cannot be met, the licensee ahn11 submit a report explaining the circumstances, together with a revised schedule.

(9) Priman chield4ne Nedifientien The licensee is authorized to modify the primary shielding design as described in PGE letter dated 2

April 22, 1977, as supplemented and amended by letters dated September 22 and 23. 1977 December 22. 1977 January 4 and 24, 1978.

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March 20. and April 4, 1978.

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1 (10) (This paragraph intentionally deleted.)

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(11) (This paragraph intentionally deleted.)

lM (12) (This paragraph inter.tionally deleted.)

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(13) (This paragraph intentionally deleted.)

Areendment No. 43, 39. H. Gir. M6. 188 i.

Date of Issuance: f

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LCA 231 Attachment III Page 3 of 3 i

INSERT A 1

The licensee shall and maintain in effect all provisions of the approved fire j

protection program as described in PGE-1012. " Trojan Nuclear Plant Fire Protection Plan" subject to the following provision:

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

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