ML17278B188

Proposed Tech Specs Re Deletion of Fire Protection Requirements

ML17278B188
Person / Time
Site:	Columbia
Issue date:	02/10/1987
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17278B187	List: GO2-87-046, Application for Amend to License NPF-21,modifying License Condition 2.C.(14) to Incorporate Std Fire Protection License Condition & Remove Fire Protection Tech Specs,Per Generic Ltr 86-10.Fee Paid ML17278B188
References
TAC-64655, NUDOCS 8702190386
Download: ML17278B188 (54)

Text

{{#Wiki_filter:ATTACHMENT This amendment request consists of the following Technical Specification pages: V1 1X X111 XV XX111 XX1V 3/4 3-79-thru 3/4 3-82 3/4 7-18 thru 3/4 7-29 B 3/4 3-6 B 3/4 7-3 B 3/4 7-4 6-12 6-13 6-14 870219038b 870210 PDR ADOCK 05000397 P PDR

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0 O. CONTROLLED COPY INDEX LIMITIHG CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4. 3 INSTRUMENTATION PAGE'/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATIOH........... 3/4 3-10 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIOH. 3/4 3"25 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMEHTATION ATWS Recirculation Pump Trip System Instrumentation.. 3/4 3-37 3/4.3.5 End-of-Cycle Recirculation Pump Trip System Instrumentation...... REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.... 3/4"3-41 3/4 3"47 3/4. 3. 6 CONTROL ROD BLOCK INSTRUMENTATIOH.........;........... 3/4 3"52 3/4. 3-7 MONITORING INSTRUMENTATION ~ Radiation Monitoring Instrumentation. wSeismic Monitoring Instrumentation.................... g.Meteorological Monitoring Instrumentation............ 9 Remote Shutdown Monitoring Instrumentation........... 4 Accident Monitoring Instrumentation..... (,Source Range Monitors.... gTr aversing In-Core Probe System. q Chlorine Detection System........- ~ ~ ~< Loose-Part Detection System. << Radioactiye Liquid Effluent Monitoring Instrumentation....--.. ~Madioactive Gaseous Effluent Monitoring Instrumentation.... ~..-.. ~ 3/4. 3. 8 TURBINE OVERSPEED PROTECTION SYSTEM. 3/4 3-58 3/4 3"61 3/4 3"64 3/4 3-67 3/4 3-7O 3/4 3-76 3/4 3"77 3/4 3"78 3/4 3-83 3/4 3-84 3/4 3-89 3/4 3"96 3/4. 3. 9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.......................... ~.... -.. -. 3/4 3-98 3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION.......... - -... 3/4 3"102 WASHINGTON NUCLEAR - UNIT 2 Vi Amendment Ho. 16

INOEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4. 7 PLANT SYSTEMS 3/4.7. 1 SERVICE MATER SYSTEMS Standby Service Mater System............ High Pressure Core Spray Service Mater System......... U1timate Heat Sink..................... PAGE 3/4 7-1 3/4 7"3 3/4 7"4 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM... ~.......... 3/4 7-5 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM................. 3/4 7"8 I 3/4.7. 4 NUBBERSr ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ S 3/4 7-10 3/4.7.5 SEALED SOURCE CON TION........................... 3/4 7"16 .~o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4.7.8 AREA TEMPERATURE MONITORING........................... 3/4 7-30 3.4.7r9 MAIN TURBINE BYPASS SYSTEM-3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8. 1 A. C. SOURCES A. C. Sources - Operating.. A.C. Sources - Shutdown. 3/4. 8. 2

0. C.

SOURCES 3/4 7-32 3/4 8"1 ~ ~ ~ ~ ~ ~ ~ ~ ~ r r 3/4 8 '10 O.C. Sources - Operating..... ~ ~ r ~ ~ ~ ~ ~ ~ ~ D. C. Sources " Shutdown.............................. I 3/4 8-11 3/4 8-15 WASHINGTON NUCLEAR - UNIT 2 \\

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il e BASES SECTION INSTRUMEHTATIOH (Continued) 3/4.3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....'.... Seismic Monitoring Instrumentation.......... Meteorological Monitoring Instrumentation... Remote Shutdown Monitoring Instrumentation.. Accident Monitoring Instrumentation......... Source Range Monitors........................... Traversing In-Core Probe System......... Ch1orine Detection System....................... Loose-Part Detection System............... Radioactive Liquid Effluent Monitoring Instrumentation........... Radioactive Gaseous Effluent Monitoring Instrumentation........................... 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM....... 3/4.3.9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION................. 3/4. 3. 10 NEUTRON FLUX MONITORING INSTRUMENTATION... 3/4.4 REACTOR COOLANT SYSTEM PAGE 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 8 3/4 3-6 8 3/4 3-6 8 3/4 3"7 8 3/4 3"7 8 3/4 3-7 B 3/4 3"7 >e.LE,TG 3/4. 4; 1 3/4. 4. 2 SAFETY/RELIEF VALVES............................. 8 3/4 4-1 RECIRCULATION SYSTEM............................ 8 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4. 4. 4 Leakage Detection Systems............,.......... Operational Leakage......,,...,. CHEMISTRY................... 8 3/4 4"2 8 3/4 4-2 B 3/4 4"2 3/4. 4. 5 SPECIFIC ACTIVITY. B 3/4 4-3 3/4.4.6 PRESSURE/TEMPERATURE LIMITS........ 8 3/4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES B 3/4 4-5 WASHINGTON'UCLEAR - UNIT 2 ~ ~ ~ X111 Amendment Ho. 16

~ ~ ~ ~ 'a ~ I r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ I I I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I I ~

INDEX LIST OF TABLES Continued) TABLE 3.3.7.5-1 4.3.7.5"1 ACCIDENT MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUllENTATIOH SURVEILLANCE REQUIREMENTS PAGE 3/4 3-71 3/4 3-74 Tel.ETP

3. 3. 7. 11-1 4.3.7.11-1

3. 3. 7. 12-1

4. 3. 7. 12-1

3. 3. 9"1

3. 3. 9"2

4. 3. 9. 1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION..

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............ RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.... RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............ FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION. FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS................ 3/4 3-85 3/4 3-87 3/4 3"90 3/4 3-93 3/4 3-99 3/4 3-100 3/4 3"101

3. 4. 3. 2-1

3. 4. 3. 2"2

3. 4. 4-1 4.4.5-1 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS....................

3/4 4-11 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS.............. 3/4 4-14 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM 3/4 4-17 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES..... 3/4 4-11 WASHINGTON NUCLEAR - UNIT 2 XXl1 i r r l . rg'I, Er

INDEX LIST OF TABLES (Continued TABLE

4. 4. 6. 1. 3-1 3 ~ 6. 3-1

3. 6. 5. 2-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM"-

WITHDRAWAL SCHEDULE PRIMARY CONTAINMENT ISOLATION VALVES 1, SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES PAGE 3/4 4-22 3/4 6-21 3/4 6-39 3.7 '-1 4.8. 1. l. 2-1 4.8. 2.1-1 3.8.4. 2-1 3.8.4.3-1

4. 11"1 4.11-2

3. 12-1 3.12"2

4. 12-1

'REA TEMPERATURE MONITORING DIESEL GENERATOR TEST SCHEDULE BATTERY SURVEILLANCE RE(UIREMENTS....... PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES... MOTOR"OPERATED VALVES THERMAL OVERLOAD PROTECTION RADIOACTIVE LI(UID WASTE SAMPLING AND ANALYSIS PROGRAM RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.;.. t REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES...... DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 3/4 7-31 3/4 8-9 3/4 8-14 3/4 8-23 3/4 8-26 3/4 11-2 3/4 11-9 3/4 12-3 3/4 12-9 3/4 12-10 WASHINGTON NUCLEAR " UNIT 2 Xxiv Amendment No. 28

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATiON 3.3. 7. 9 As a minimum, the fire detection instrumentation for each ire detection zone shown in Table 3.3.7.9-1 shall be OPERABLE. APPLICABILITY: Whenever equipment protected by the fir dete ion instrument is required to be OPERABLE. ACTION: b. With the number of OPERABLE fire dete n truments in one or more zones: 1. Less than, but more than on hal , the Total Number of Instruments shown in Table 3. 1 for Function A, restore the inoperable Function tr ent(s) to OPERABLE status within l4 days ithin 1 hour sh a fire watch patrol to inspect the zone ith the e a e instrument(s) at least once per hour. 2. One less than Tota mber of Instruments shown in Table 3.3.7.9-Fu ion B, or one-half or less of the Total Number of Instr own in Table 3.3.7.9-1 for Function A, or with any two o e adjacent instruments inoperable, within 1 hour establish a ~ watch patrol to inspect the zone(s) with the inoperable i r (s) at least once per hour. The provisions of S cifications 3.0.3 and 3.0.4 are not appiicahie. SURVEILLANCE REOUIREME S

4. 3. 7. 9. 1 Each of e above required fire detection instruments which are accessible during nit operation shall be demonstrated OPERABLE at least once per 6 months by rformance of a CHANNEL FUNCTIONAL TEST.

Fire detectors which are not accessi e during unit operation shall be demonstrated OPERABLE by the performance o a CHANNEL FUNCTIONAL TEST during each COLO SHUTDOWN exceeding 24 hours unl s.performed in the previous 6 months.

4. 3. 7. 9. 2 i he NFPA Standard 720 supervised circuits supervision associated with the etector alarms of each of the above required fire detection ins ru ts shall be demonstrated OPERABLE at least once per 6 months.

WASHINGTON NUCLEAR UNIT 2 3/4 3-79

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TABLE 3. 3. 7. 9-1 FERE DETECTION ENSTRUMENTATION INSTRUMENT LOCATION REACTOR BUILDING EI EV 422'-3" CRO PUMP ROOM AUX COND. PUMP Roots REACTOR BUILDING ELEV 441'-0" RAILROAD AIRt.OCK REACTOR BUILDING ELEV 444'-0" TOTAL NUMBER" OF INSTRUMENTS ID SD TO UD 5 (x/y) (x/y) (x/y) (x/y) /y) 4/0 2/O 4/0 RHR-2A PUMP RM R2 RHR"28 PUMP RM R1 RHR-2C PUMP RM R4 RCIC PUl'1P RM R3 LPCS PUMP RM R5 HPCS PUMP RM R6 REACTOR BUILDING ELEV ~ MCC gOOM GENERAL AREA REACTOR. BUELDING ELEV GENERAL AREA REACTOR BUILDING ELEV tlCC ROOM OIV. 2 GENERAL AREA RHR VALVE ROOM REACTOR BUILDING ELEV 3/0 3/Q 3/0 3/0 471'-O" 4 ~ 501'"0" ( 522(-0'( 1/0 ~+ 28/0 ~ 1/0 54S'-O" FUc'OOL HT. EXCHGR ROOM A Atfo PUMP ROOM GEttiRAL AREA RHR HT. EXCHGR B ROOM REACTOR BUILDING ELEV 57 -0" HYDROGEN RECOMBINER Co Rt1 OIV. 2 RHR HT

EXCHGP, RM lA RHR HT.

EXCHGR RM 1 GENERAL FLOOR ARE, P. ACTOR BUILDIt< cLEV 606'-10.5" CENTRAL FLOOR RcA RAG!'4'ANTE Co ROL BUELDENG LFV 467'" ELEC; PIC EQUI Pf 1ENT Root! No. 1 Sk'.:"J" AR RGOti NO. ,.ICAL cEQUIPf>cElJT root! tiO. 2 =;.Y ROOt! NO. 2 '~TOM (JUCLEnR - ~N.'T 2 1/O 29/0 1/0 2/0 1/O. 1/0 25/0 2/0 c/0 3: 0 3/0 2/G 6/0

4p,"~ 4

INSTRUMENT LOCATION TABLE 3.3.7.9-1 (Continued) FIRE DETECTION INSTRUMENTATION TOTAL HUMBER" OF INSTRUMENTS ID SD TD (x/y) U SMO /y) (x/y) CABLE SPREADIHG ROOM 0/36 RADWASTE AND CONTROL BUILDING ELEV 501'-0" 12/0 1/~@ 8/0 11/ + 0/0 6/0 F/0 4/0 S/04~ S/0 5/0 8/0 0/5 CABLE CHASE CONTROL ROOM CONTROL ROOM U679 U680 U681 U682 U683 U684 U685 U686 U687 uses U689 U690 U800 U840 U891 U892 US93 U894 RADWASTE AND (CEILING) (PGCC) 0/9 0/14 0/9 0/8 0/8 0/8 0/8 0/8 0/8 0/8 0/8 0/8 0/6 0/6 0/8 0/10 0/9 0/9 8/0 9/0 8/0 COHTRO BUILDING ELEV 525'"0" RADWASTE CONTROL BUILDING ELEV 467'-0" (Continued) SWITCHGEAR ROOM NO. 2 3/0 REMOTE SHUTDOWN ROOM 1/0 CORRIDOR C-205 5/0 RADWASTE AND CONTROL BUILDING ELEV 484'-0" CABLE CHASE UNIT A " AIR 'CO TIOHING ROOM UNIT B - AIR C DITIONING ROOtl STAtlGBY SERV E WATER PUMP HOUSE 1A PUMP HOUSE I ELeCTRICA VAULT STANDBY ERVICE WATER PUMP HOUSE 1B PUt':P .USE EL=".-.iCAL VAULT 0/6 5/0 5/0 1/0 1/0 1/0 1/0 2/1 2/1 rin ~'. ' Otk t'tUC LEAR UNIT 2 3/4 3-8" '--"r~-"n "c o

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I ss r e" TABLE 3.3.7.9-1 (Continued) FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION TURBINE GENERATOR CORRIDOR ELEV 4a1'-0" TG-1 CORRIDOR DIESEL GENERATOR BUILDING ELEV 441'-0" T AL NUMBER" OF STRUMENTS ID SD TO UO SMD (x/y) (x/y ~(x y) ~x/y) ~x/y) 6/18 1A DIESEL GENERATOR ROOM 1A DIESEL OAY TANK ROOM 1A DIESEL OIL TANK PUMP ROOM 1B DIESEL GENERATOR ROOM lB DIESEl. DAY TANK ROOM 1B DIESEL OIL TANK PUMP ROOM HPCS DIESEL GEHERATOR ROOM HPCS DIESEL DAY TANK ROOM HPCS DIESEL OIL TANK PUMP ROOM 2/0 2/0 /0 t 4/0 0/4 1/1 1/1 4/0 0/4 1/1 1/1 4/0 0/4 1/1 1/1 TABL NOTATION IO - Ionization Detector SD - Sm e Detects D - Thermal Detector UD' Ultraviolet (Flame) Oetecto SMD - DucWIonization Detector "(x/y): x is number of Functi A (ear~arning fire detection and notification only) nstrumg~ y is number of Fun on B QBlgbtion of fire suppression sys .ems and early warni and a@~cation) instruments ~+ Jl gl m r s WASHINGTON NUCLEAR - UNIT 2 3/4 3-82

I 't 1'I y4

PLANT SYSTEMS 3/4.7.6 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 The fire suppression water system shall be OP BLE with: a. At least two of the three OPERABLE fire a capacity of 2000 gpm pumping from the 2500 gpm diesel-driven pump pumping fro tank, with their discharge aligned to s ression

pumps, each with rculating water basin, or one the secondary water supply e fire suppression header.

ACTION: b. Two separate fire water supplies, h a minimum contained volume of 300,000 gallons in the recirculat' water pump house inlet basin and 280,000 gallons in the seco ry w ter supply tank. c. An OPERABLE flow path capable f t suction from the circulating. water pump house inlet basi nd econdary water supply tank and transferring the water thr gh di ibution piping with OPERABLE sectionalizing control or. solation valves to the yard hydrant curb

valves, the last valve ead he water flow alarm device on each sprinkler or hose stan ipe the last valve ahead of the deluge valve on each deluge sgr~system required to be OPERABLE per Speciflcatlene 3.7., Q

.4, and 3.7.6.3. APPLICABILITY: At all time a. With two 2000 p ps or the 2500 gpm pump and/or one water supply inoperable, star at least two 2000 gpm pumps and the 2500 gpm pump and t fire water supplies to OPERABLE status within 7 days or provid an alternate backup pump or supply. The provisions of Specific ions 3.0.3 and 3.0.4 are hot applicable. b. With t fire suppression water system otherwise inoperable, esta 'h a backup fire suppression water system within 24 hours. Q SURVEILLAN RE UIREMENTS 4.7.6. 1 The fire suppression water system shall be demonstrated OPERABLE: a. At least once per 7 days by verifying the minimum contained water supply volume. b. At least once per 31 days on a STAGGERED TEST BASIS by starting each electric motor driven fire suppression pump and operating it for at least 15 minutes on recirculation flow. c. At, least once per 31 days'y verifying that each valve (manual, power

operated, or automatic) in the flow path is in its correct position.

WASHINGTON NUCLEAR " UNIT 2 3/4 7-18

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued) d. At least once per 6 months by performance of a sys flush. e. At least once per 12 months by cycling each tes le valve in the flow path through at least one complete cycle full travel. At least once per 18 months by performing ystem functional test which includes simulated automatic actuat n of the system throughout its operating

sequence, and:

1. Verifying that each automatic va e in the flow path actuates to its correct position, 2. 3. 4. Verifying that each circulat' water basin supplied fire sup-pression p develops at ast 2000 gpm at a system head of 250 feet that the sec dary water supplied unit develops at least 2500 at a sys head of 325 feet, Cycling each e in he flow path that is not testable during plant operatio gh at least one complete cycle of full travel, and Verifying that ch suppression pump starts (seq entuia11y) to maintain th fire pression water system pressure greater than or equal o 95 psig. g.

4. 7. 6. 1. 2 At least once p

3 years by rming a flow test of the system in accordance wi Chapter 5, Sect 1 of the Fire Protection

Handbook, 14th Edition ublished by the hat~i 1 Fire Protection Association.

Both dies -driven fire suppression pumps shall be demonstrated OPERA8LE At lea once per 31 days by: 1. erifying the fuel storage tanks contain at least 150 gallons of fuel. Starting the diesel-driven pump from ambient conditions and operating for greater than or equal to 30 minutes on recirculation flow. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-0270-75, is within the acceptable limits specified in Table 1 of ASTM 0975-77 when checked for viscosity, water, and sediment. At least once per 18 months, during shutdown, by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service. MASHINGTON NUCLEAR - UNIT 2 3/4 7"19

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5 PLANT SYSTEMS SURVEILLANCE REOUIREMENTS Continued ,I I'.7.6.1.3 Each diesel-driven fire pump starting 24-volt ttery bank and charger shall be demonstrated OPERABLE: a. At least once per 7 days by verifying that: 1. The electrolyte level of each cell. above the plates', 2. The cell specific gravity, corr ed to 774F and full electrolyte level, is greater an or equal to 1. 20O, 3. The overall battery voltage s greater than or equal to 24 volts. b. At least once per 92 days by ify . hat the specific gravity is appropriate for continued se ic'e he battery. C. At least once per 18 mont by v , fying that: 1. The batteries and physical damage 2. Battery-to-ba er free of corr io att acks show no visual indication of a al deterioration, and terminal connections are clean, tight, coated with anti-corrosion material. WASHINGTON NUCLEAR - UNIT 2 3/4 7-20

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'PLANT SYSTEMS SPRAY ANO SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.2 The following pre-action and deluge spray'and s er systems shall be QPERABLE: a. Radwaste Building: l. 2. 3 ~ Cable spreading room, elev. 484', syst 065. Cable chase and corridor, elev. 441' 525', system ~66. Control Bldg. emergency charcoal fi

ers, elev.

525'., system ~WMA-DV-54A and WMA-OV-54B. Control

Room, Elev. 501',

automa c sprieklers office areas only b. Diesel Generator Building: 1. ..DG room 1 d day tank roo elev. 441', system 879. 2. OG 1A day pump room, ev. 441', system ~80. 3. DG room 1B a ay tank r m, elev. 441', system 081. 4.'G 1B day tan p roo elev. 441', system 082. 5. HPCS DG room a t k room, elev. 441', system 083. 6. HPCS OG day tank oom, elev. 441', system 484..

c. 'eactor Building:

1. Standby gas tre ent system charcoal filters, elev. 572', system OSGT-DIV -1, OSGT V-lA-2, 8SGT-DIV"1A-3, ~SGT-DIV-1B-1 8SGT-OIV-1 and ~SGT-DIV-18-3. s 2. Sump vent f ter system chare filters, elev. 572', system ~R -DV-2A and KOREA-DV-ZB. APPLICABILITY: Whenev equipment protected by the spray and/or sprinkler systems is required t be OPERABLE. ACTION: a. With o or more of the above required spray and/or sprinkler systems inope ble, within 1 hour establish a continuous sire watch with bac fire suporession equipment for those areas in which redundant sy ems or components could be damaged; for other

areas, establish a

hourly fire watch patrol. ihe provis',ons. of Specification 3.0.3 and 3.0.4 are not applicable. 3/ rs ~ sr 7'a IC IJIIICII 1 slJ ~

I

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS 4.7.6.2 Each of the above required spray and sprinkler syst shall be demonstr ated OPERABLE: a. At least once per 31 days by verifying that ea valve (manual, power" operated or automatic) in the flow path is i.-'s correct position. b. C. At least once per 12 months by cycling eac testable valve in the flow path through at least one complete cle of full travel. At least once per 18 months: l. By performing a system functio 1 test which includes simulated automatic actuation of the s

tern, and:

b) Cycling each val v in the during plant op ation t of full travel a) Verifying that the a matic valves in the flow path actuate to their correct po tions o detector test signal, and path that is not testable h at least one complete cycle 2. 3. By a visual insp tion o dry pipe spray and sprinkler headers to verify their ntegri~ nd By a visual specti each deluge nozzle's spray area to veri fy that he sp atter n is not obstructed. d. At least once er 3 by performing an air flow test through each open head sp y an snkler header and verifying each open head spray and s inkle zzle is unobstructed. WASHINGTON NUCLEAR - UNIT 2 3/4 7-22

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PLANT SYSTEMS HALON SYSTEMS LIMITING CONOITION FOR OPERATION

3. 7. 6. 3 The 18 Halon systems in the PGCC units in the c trol room shall be OPERABLE with the storage tanks having at lea 95Ã of full charge weight and 90Ã of full charge pressure.

APPLICABILITY: Whenever equipment protected by th alon systems is required to be OPERABLE. ACTION: a. With one or more of the above req ed Halon systems inoperable, within 1 hour establish a contin us fire watch with backup fir'e suppression e 'pment for those reas in which redundant systems or components co e damaged; f other areas, establish an hourly fire watch pat b. The provisions of ifi ions 3. 0. 3 and 3.0. 4 are not applicable. SURVEILLANCE REOUIREMENTS

4. 7. 6. 3 Each of the above r

uired on systems shall be demonstrated OPERABLE: a. At least once r 31 days by v ing that each valve (manual, power-operat, or automatic) in flow path is in its correct position. b. At least ce per 6 months by verifying Halon storage tank quantity and pres re. c. At lea once per 18 months by: l. erifying the system, including associated ventilation system fire dampers and fire door release mechanisms,

actuates, manually and automatically, upon receipt of 'a simulated actuation signal, and Performance of a flow test through accessible headers and nozzles to assure no blockage.

At least once per, 36 months by verifying Halon storage tank weight. WASHINGTON NUCLEAR " UNIT 2 3/4 7"23

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PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.6.4 The fire hose stations shown in Table 3.7.6.4-1 sh 1 be OPERABLE. APPLICABILITY: Whenever equipment in the areas protect by the fire hose stations is required to be OPERABLE. ACTION: b. With one or more of the fire hose stati s shown in Table 3.7.6.4-1 inoperable, provide'ated wye(s) on t nearest OPERABLE hose station(s). One outlet of the wye s 1 be connected to the standard length of hose provided fo the hose station. The second outlet of the wye shall be connec d to a length of hose sufficient to provide coverage for the area nprotected by the inoperable hose station. Where it can be trated that the physical routing of the fire hose woul r in a recognizable hazard to operating technicians, plan qu ent, or the hose itself, the fire - hose shall be stored in a at the outlet of the OPERABLE hose station. Signs shall be above the gated wye(s) to identify the proper hose to use. h ove ACTION shall be accomplished within 1 hour if the i e le fire hose is the primary means of fire suppression; ot 'oute the additional hose within 24 hours. The provisions of ications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE RE UIREMENT 4.7.6.4 Each of the ire hose stations shown in Table 3.7.6.4-1 shall be demonstrated OPERAB a. At leas once per 31 days by a visual inspection of the fire hose statio accessible during plant operation to assure all required equi ent is at the station. b. At east once per 18 months by: Visual inspection'of the fire hose stations not accessible during plant operation to assure all required equipment is at 'the station. 2. Removing the hose for inspection and reracking, and 3. Inspecting all gaskets and replacing any degraded gaskets in the couplings. At least once per 3 years by: 1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage. 2. Conducting a hose hydrostatic test, at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater. WASHINGTON NUCLEAR " UNIT 2 3/4 7"24

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q ~ 2 I ~ > TABLE 3.7.6.4-1 FIRE HOSE STATIONS LOCATION ELEVATION SE RACK ENTIFICATION 427'-0>> 446'-0>> 476'-0>> 5062 0>> 527I-O'I 553'-0>> 577'- 0 II I 0>> 76I 0>> 506'"0>> 5271<<0>> 553'-0>> 577 I 0 II 612'-0>> 446'"0>> 472'-0>> 492'-0>> 512'-0>> 530'-0>> r 446'-0>> 072'0" 492'-00 A@2'-0" ~'-0>> 446'-0>> 446'0>> 530'-0>> 1. Reactor Bldg. Standpipe RB-1 2. Reactor Bldg. Standpipe RB-1 3. Reactor Bldg. Standpipe RB-1 4. Reactor Bldg. Standpipe RB-1 5. Reactor Bldg. Standpipe RB-1 6. Reactor Bldg. Standpipe RB-1 7. Reactor Bldg. Standpipe RB-1 8. Reactor Bldg. Standpipe RB-1 9. Reactor Bldg. Standpipe RB-2 10. Reactor Bldg. Standpipe RB-2 ll. Reactor Bldg. Standp e RB-2 12. Reactor Bldg. Stan RB"2 13. Reactor Bldg. Stand RB"2 14. Reactor Bldg. Standpat -2 15. Reactor Bldg. Standpip 2 16. Reactor Bldg. Standpipe 17. Railroad Car Air Lock 18. Radwaste Bldg. Standpipe RW 19. Radwaste Bldg. Standpipe RW 20. Radwaste Bldg. Standpipe -1~~ 21. Radwaste Bldg. Standpipe B-l ~ 22. Turbine Generator OG Bl . Corrido 23. Radwaste Bldg. Stair A 3 24. Radwaste Bldg. In Cor dor 25. Radwaste Bldg. In C ridor 26. Radwaste Control m Corridor 27. Oiesel Generator dg. In Corridor 28. Diesel Generato Bldg. 29. Radwaste Bldg. RB"HS-11 RB-HS-12 RB"HS"13 RB-HS-14 RB-HS-15 RB"HS-16 RB-HS"17 RB-HS"18 RB-HS-21 RB"HS-22 RB-HS"23 RB-HS-24 RB-HS"25 RB-HS-26 RB-HS-27 RB-HS-28 RB-HS"29 RWB"HS-13 RWB"HS"14 RWB"HS-15 RWB-HS-16 RWB-HS-25 RWB-HS-26 RWB-HS-28 RWB-HS-29 RWB-HS-31 OG"HS-41 OG"HS-40 RWB-HS-33 WASHINGTON NUCLEAR - UNIT 2 3/4 7-25

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PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES LIMITING CONDITION FOR OPERATION 3.7.6.5 The yard fire hydrants and associated hydrant hos houses shown in Table 3.7.6.5-1 shall be OPERABLE. APPLICABILITY: Whenever equipment in the areas prote ed by the yard fire hydrants is required to be OPERABLE. ACTION: b. With one or more of the yard fire hy ants or associated hydrant hose houses shown in Table 3. 7. 6. 5-1 ino rable, within 1 hour have sufficient additional lengths of / inch diameter hose located in an adjacent OPERABLE hydrant hos h to provide service to the unprotected area(s) if the ino fire hydrant or associated hydrant hose house is the pri r ns of fire suppression;. otherwise provide the additi al se within 24 hours. The provisions of Specifi

3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7. 6. 5 Each of the yard in Table 3.7.6.5-1 shall ydrants and associated hydrant hose houses shown 'nstrated OPERABLE: 'a 0 b. C. At least on per 31 days by visual inspection of the hydrant hose house to a ure all required equipment is at the hose house. At leas once per 6 months, during March, April or May and during Septem r, October, or November, by visually inspecting each yard fire hydr and verifying that the hydrant barrel is dry and that the hyd nt is not damaged. least once per 12 months by: 1. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater. 2. Replacement of all degraded gaskets in couplings. 3. Performing a flow check of each hydrant. WASHINGTON NUCLEAR - UNIT 2 3/4 7"26

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TABLE 3. 7. 6. 5-1 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES LOCATION 1. South side of Diesel Generator Bldg. 2. Southeast corner of Diesel Generator Bldg. 3. West side of Radwaste Bldg. 4. South side of Radwaste Bldg. 5. Northwest of Standby Service Mater Pump H se lA 6. North side of Standby Service Water Pu House 1B 7. Mest side of Radwa and Turbine Ge rator Bldg. HY ANT NUMBER HT"1A HT-1B HT-1G HT"1H HT"1M HT-lN HT-1R @4 WASHINGTON NUCLEAR - UNIT 2 3/4 7-27

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~ s 4 I, p I PLANT SYSTEMS 3/4. 7. 7 FIRE-RATED ASSEMBLIES 4 LIMITING CONDITION FOR OPERATION 3.'7.7 All fire-rated assemblies, including walls, f or/ceilings, cable tray enclosures and other fire barriers, separating safe related fire areas or separating portions of redundant systems important o safe shutdown within a fire area, and all sealing devices in fire-rated sembly penetrations, includ-ing fire doors, fire windows, fire dampers, cab, piping and ventilation duct penetration seals and ventilations seals, shal be OPERABLE. APPLICABILITY: At all times. ACTION: b. With one or more of the abo requ fire-rated assemblies and/or sealing devices inoperabl with'our establish a continuous fire watch on at least o side o he affected assembly(s) and/or sealing device(s) or ve>> fy t OPERABILITY of fire detectors on at least one side of 4 in le assembly(s) and/or sealing deviceis) and establ'n+ ly fire watch patrol. The provisions of ecitlQNy iona 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE RE UIREMEN 4.7. 7. 1 Each of t above required fire"rated assemblies and penetration sealing devices s 1 be verified OPERABLE at least once per 18 months by performing a vis 1 inspection of: b. The posed surfaces of each fire-rated assembly. E fire window, fire damper, and associated hardware. C. t least 10K of each, type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10K of each type of sealed penetration shall be made. This inspection process shall continue until a 10 sample with no apparent changes in appearance or abnormal degrada-tion is found. Samples shall be selected such that each penetration seal will be inspected at least once per 15 years. WASHINGTON NUCLEAR - UNIT 2 3/4 7-28

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7..7.2 Each of the above required fire doors sha11 be verif d OPERABLE by inspecting the automatic hold-open, release and closing mec nism and latches at least once per 6 months, and by verifying: a. The OPERABILITY of the fire door supervision stem for each electrical supervised fire door by performi a CHANNEL FUNCTIONAL TEST at 1east once per 31 days. b. That each lacked-closed fire door is c ed at least once per 7 days. c d. That doors with automatic hold-open d release mechanisms are free of obstructions at least once per hours and performing a functional test of these mechanis at least'nce per 18 months. That each unio~ fire door w'aut electrical supervision is closed at least per 24 rs. WASHINGTON NUCLEAR - UNIT 2 3/4 7-29

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~ ' ~C ~ ~ ~ -I e INSTRUMENTATION BASES MONITORIHG INSTRUMENTATION (Continued) 3/4. 3. 7. 9 FIRE DETECTION INSTRUMENTATION ILITY of the detection instrumentation ensures that both ad e warning cap 'ty is available for prompt detection of fires and t fire suppression sys , that are actuated by fire detectors, will arge extinguishing agen a timely manner. Prompt detection a uppression of fires will reduce the tial for damage to safety-re d equipment and is an integral element in the all facility fire pr ion program. Fire detectors that are used t tuat re suppression systems represent a more critically important component o lant's fire protection program than detectors that are installed solel ear e warning and notification. Consequently, the minimum numbe OPERABLE fire ectors must be greater. The loss of detect'apability for fire su pression

tems, actuated by fire detectors, esents a significant deg ion of fir otection for any area..

As a ult,. the establishment of a~ i watch patrol m be initiated a earlier stage than would be anted for the loss of tectors that pr e only early fire warning. The ~lishment of frequent fir pat in the affected areas 'is required rovide detection capability u 1 t inoperable instrumentation is resto OPERABILITY. 3/4. 3. 7. 10 LOOSE" PART DETECTION SYS The OPERABILITY of the loosest detection system ensures that sufficient capability is available to dete~%Qpose metallic parts in the primary system and avoid or mitigate damage to >mary system components. The allowable out"of-service 4imes and 'survePance requirements are consistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981. 3/4. 3. 7. 11 RADIOACTIVE LI UID EFFLUEHT MONITORING INSTRUMENTATIOH The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The. OPERABILITY and use of this instrumentation is 'consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS. WASHINGTON NUCLEAR - UNIT 2 B 3/4 3-6,

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PLANT SYSTEMS BASES SNUBBBNS (Continued) 3. Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation. Figure

4. 7-1 was developed using "Wald' Sequential Probability Ratio Plan" as described in "guality Control and Industrial Statistics" by Acheson J.

Duncan. Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption 's presented and,,if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the com-pletion of their fabr ication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions. The service life of a snubber is establ hed via manufacturer input and information through consideration of the s r service conditions and associated installation and maintenance ds (newly installed snubbers, seal

replaced, spring 'replaced, in high ation area, in high temperature area, etc.)..

The requirement to moni e snubber service life is included to ensure that the snubbers periodi undergo a performance evaluation in view of their age.and operating co ons. These records will provide statis-tical bases for future consider 'f snubber service life. 3/4.7.5 SEALED SOURCE CONTA ON ee ',V The lihitations on r le contamination for"sources requiring leak

testing, including alpha ers, is based on 10 CFR 70.39(c) limits for plutonium..

This limitatio will ensure that leakage from byproduct,

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

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a 'ource'in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously'enclosed within a shielded mechanism, i. e., sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are.removed from the shielded mechanism. IRE SUPPRESSION SYSTEMS The OPERABILI re suppression systems ensures t W 'fire suppression capability ss to confine a >sh fires ~ occurring in any portion of the facil> related equipment is located.'he fire suppression syst ater system, spray and/or sprinkler systems ms, Halon systems, a 'ose stations. The collective c 'fthe fire suppression systems is a to minimi a damage to safety"related equipment and is a major e facility fire protection program. u I'h e. e ,L WASHINGTON NUCLEAR - UNIT 2 B 3/4 7-3

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I < ~ ee n e" 'e I ~ GGPV A"."Y:=U ("on-inoen) I ~ Proposed tes s or experiments which involve an unreviewec safe y oues-ion as defined in 10 CFP. 50.59; d. Proposed chanoes to Technical Specifications or this'Operating License; e. Violations of codes, regulations,

orders, Technical Specifications, license requirements, or of internal proceoures or instructions having nuclear safety significance; Significan operating abnormalities or deviations from normal and expected performance of'nit equipmen. that affec nuclear safety; g.

All REPORTABLE EVENTS; h. All recoanized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affect nuclear safety; and Reports and meeting minutes of the POC.

j. Audit reports and summary reports of audits. AUDITS 5.3.2.S Audits of uni ac ivities shall be performed under the cognizance o he CNSRB. These audi s.shall encompass: a. The conformance of unit operation to provisions contained within the Technical Specifica.ions and applicable license conditions at lees once per 12 months; b. The performance, training and qualifications of the entire unit staff at least ance per 12 months; c. The results of actions taken to correct deficiencies occurring in unit equipment, s ructures, sys ems, or method of operation that affect nuclear safety, at least once per 6 months; d. The performance of ac.ivities required by he Operational guality Assurance Program ta m et the criteria of Appendix B, 10 CFR Par 50, at least once per 24 months; I ~ a. The Emergency Plan and implementing procedures at. least once per ~M months per 10'CFR 50.54(t). The Security Plan and implemen ing.procedures at least once per 12 months. WASHINGTON NUCLEAR - UNIT 2 6-12 Attend;ant No-5

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I 4 s im ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 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 tel'ephone as soon as possible and in all cases within 1 hour. The Assistant Managing Director for Operations and the CNSRB shall be notified. b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POC. 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 Limit Violation Report shall be submitted to the Commission, the

CNSRB, and the Assistant Managing Director for Operations.

d. Critical operation of the unit shall not be resumed until authorized by the Commission. 6.8 PROCEDURES AND PROGRAMS 'i 6.8. 1 Written procedures shall be covering the activities referenced established 'lemented, bel ow: and maintained a. The a'pplicable procedures recom d in Appendix A of'Regulatory Guide 1.33, Revision 2, Febru r 78. b. The applicable procedures r+ed to implement the requir ements of NUREG-0737. c. Refueling operations. d. Survei'fiance and test vities of safety-related equipment. e. Security Plan implementation. f. Emergency. Plan implementation. h. PROCESS CONTROL PROGRAM implementation. i. OFFSITE DOSE CALCULATION MANUAL implementation. j. gua1ity Assurance Program for effluent and environmental monitoring. k. Health Physics/Chemistry Support Program. m 6.8.2 Each procedure of Specification. 6.8. 1a. through j., and changes

thereto, shall be reviewed by the POC and shall be approved by the Plant Manager prior to implementation and reviewed periodicall'y as set forth in administrative procedures.

In addit.'on, the review and approval of the implementing orocedures supporting i em k. in Specification 6.8. 1 will be coordinated by the Director of Support Services. who will provide review and approval control. The MNP-2 Health Ph; sics/Chemistry Support Program procedure will be reviewed by ~OC and.app> oved -.he Plant Manager. 4:.' 'r r' iIle 'TON smsUCLEAR UNIT 2 6-14 Amendsment No. 6

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