ML17278A691

Proposed Tech Specs Deleting Chlorine Detection Sys Due to Permanent Change Removing Chlorine Gas Storage from Immediate Site Area

ML17278A691
Person / Time
Site:	Columbia
Issue date:	04/08/1986
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17278A690	List: ML17278A689 ML17278A691
References
TAC-61222, NUDOCS 8604150320
Download: ML17278A691 (8)

Text

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION PAGE'/4 3/4. 3 INSTRUMENTATION 3/4. 3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3-1 3/4. 3. 2 ISOLATION ACTUATION INSTRUMENTATION. 3/4 3-10 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION .. 3/4 3"25 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION S..

ATMS Recirculation Pump Trip System Instrumentat ion.. 3/4 3-37 End-of-Cycle Recirculation Pump Trip System Instrumentation.. 3/4'3"41 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION INSTRUMENTATION.... 3/4 3-47 3/4. 3. 6 CONTROL ROD BLOCK INSTRUMENTATION..........,.... 3/4 3"52 3/4. 3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.;... 3/4 3"58 Seismic Monitoring Instrumentation..;-.... ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-61

., Meteorological Monitoring Instrumentation............ 3/4 3"64 Remote Shutdown Monitoring Instrumentation........... 3/4 3-67 Accident Monitoring Instrumentation...... 3/4 3-70 P

Source Range Monitors. 3/4 3-76 Traversing In-Core Probe Sy'tem 3/4 3-77 Fire Detection Instrumentation. 3/4 3-79 Loose-Part Detection System. 3/4 3"83 Radioactive Liquid Effluent Monitoring 0 o'p)A Instrumentation...................... 3/4 3"84 Radioactive Gaseous Effluent Monitoring

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<A Instrumentation.. 3/4 3-89 IO OX 3/4. 3. 8 TURBINE OVERSPEED PROTECTION SYSTEM. 3/4 3-96 CUO HQ OA LDLL 3/4.3.9 FEEDMATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION... 3/4 3"98 Oo:

QQ RG.O.

3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION............... 3/4 3-102 WASHINGTON NUCLEAR - UNIT 2 Vl Amendment No. 16

BASES SECTION PAGE INSTRUMENTATION (Continued) 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............ 8 3/4 3-4 Seismic Monitoring Instrumentation.............. 3/4 3"4 Meteorological Monitoring Instrumentation....... 8 3/4 3-5 Remote Shutdown Monitoring Instrumentation...... 3/4 3-5 Accident Monitoring Instrumentation............. 8 3/4 3"5 Source Range Monitors........................... 8 3/4 3"5 Traversing In-Core Probe System................. 8 3/4 3"5 Fire Detection Instrumentation.................. 8 3/4 3"6 Loose-Part Detection System..... 8 3/4 3."6 Radioactive Liquid Effluent Monitoring Instrumentation... 8 3/4 3-6 Radi oacti ve Gaseous Effluent Monitoring Instrumentation................ 8 3/4 3-7 3/4. 3. 8 TURBINE OVERSPEED PROTECTION SYSTEM............. 8 3/4 3"7 3/4. 3. 9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATIOH IHSTRUMENTATIOH...... 8 3/4 3"7 3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION......... 8 3/4 3"7 3/4.4 REACTOR COOLANT SYSTEM 3/4. 4. 1 RECIRCULATION SYSTEM......... 8 3/4 4-1 3/4. 4. 2 SAFETY/RELIEF VALVES...........,........,,....... 8 3/4 4"1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...... 8 3/4 4"2 Operational Leakage . 8 3/4 4"2 3/4. 4. 4 CHEMISTRY..... 8 3/4 4-2 3/4. 4. 5 SPECIFIC ACTIVITY. 8 3/4 4-3 3/4. 4. 6 PRESSURE/TEMPERATURE LIMITS..................... 8 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 8 3/4 4"5 WASHINGTON NUCLEAR - UNIT 2 X111 Amendment Ho. 16

STRUHENTATION CHL INE DETECTION SYSTEM LIHITI CONDITION FOR OPERATION 3.3.7.8 Two independent chlorine detection system subsystems shall e OPERABLE" wit their alarm/trip setpoints adjusted to actuate at a hlorine concentration o less than or equal to 5 ppm within 10 seconds.

APPLICABILITY: Al OPERATIONAL CONDITIONS.

ACTION:

'a ~ Mith one chlor e detection subsystem inoper le, restore the inoperable detec ion subsystem to OPERABLE atus within 7 days or, within the next 6 ours, initiate and mai ain operation of at least one control room em rgency filtration s tern train in the isolation mode of operation.

Mith both chlorine dete ion subsy ems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain ope tion o at least one control room emer-gency filtration system tra'n i the isolation mode of operation.

C. The provisions of Specifica o 3.0.4 are not applicable.

I SURVEILLANCE REOUIREhlENTS 4.3.7.8 Each of the abov required chlorine detect n system subsystems shall be demonstrated OPERABL by performance of

a. CHANNEL C CK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.. CHANNE FUNCTIONAL TEST at least once per 31 days, and

c. CH <EL CALIBRATION at least once per 18 months.

"The ormal or emergency power source may be inoperable in OPERATIONAL CO ITION 4 or 5.

MASHINGTON NUCLEAR - UNiT 2 3/4 3-78

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PLANT SYSTEMS SURVEILLANCE REOUIREMEHTS Continued "la Co At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painti.ng, fire, or chemical release in any ventilation zone cormunicating with the train by:

1. Verifying that the train satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05 and uses the test procedure guidance in Regulatory

'ositions C.5. a, C.5.c, and C.5. d of Regulatory Guide 1. 2, Revision 2, March 1978 when operating at a flow rate of 1000 cfm + lOX.

2. Verifying within 31 days after removal that a laboratory analysis of. a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory- Guide 1.52, Revision 2, March 1978, meets the laboratory tes'ting criteria of R ulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, g h 1978, for a methyl iodide penetration of less than 1.0"; aalu

3. Yerifying a tras w rate of 1000 cfm + 10 during train operation when test 'n accordance with ANSI H510-1980.

d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of c a 1 adsorber operation by verifying

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within 31 days after remova sentative carbon sample obtai

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laboratory analysis of a repre-accordance with Regulatory Positon C.6.b of Regulatory Gui 52, Revision 2, March 1978, meets the laboratory testing crit of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision arch 1978, for a methyl iodide. penetration of less than l. 0 .

e. At least once per 18 months by:

l. Yerifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches water gauge while operating the train at a flow rate of 1000 cfm + 10 .

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NSHIHGTON NUCLEAR - UNIT 2 3/4 7"6

'PLANT SYSTEMS SURVEILLANCE REOUIREMENTS Continued)

Verifying that on each of the below pressurization mode actuation test signals, the train automatically switches to the pressurization mode of operation and the control room is maintained at a positive pressure of 1/8 inch water gauge relative to the outside atmosphere during train operation at a flow rate less than or equal to 1000 cfm:

a) Drywell pressure-high, b) -Reactor vessel water level-low, and c) Reactor Suilding exhaust plenum-high radiation.

Verifying that the heaters dissipate 5.0 + 0.5 kW when tested in accordance with ANSI sV510-1980.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter 'bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05X in accordance with ANSI N510=1980 whi le operating the train at a flow rate of 1000 cfm + 10'~.

After each complete or<par. ial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration~an+ bypass leakage testing acceptance, criteria of less than 0.05K~'i'ccordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the train at'a flow rate of 1000 cfrii<+~10~.

'plASHINQTON iVUCLEAR

- UiVIT 2 3/4 7-7

INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4. 3. 7. 3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required 'o evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Regulatory Guide 1.23, "Qnsite Meteorological Programs," February, l972.

3/4.3.7.4 REMOTE SHUTDOWN MONITORING IHSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of Appendix A to 10 CFR Part 50.

3/4. 3. 7. 5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an 'accident. This capability is consistent with the recommendations of Regulatory.-Guide 1.97, "Instrumentation fo: Light Water Cooled Nuclear Power Plants to 'As'sess Plant Conditions During and Following an Accident," December 1975,and NUREG-0737, "Clarification c" TMI Action Plan Requirements," November+1980.

3/4.3.7.6 SOURCE RANGE MONITORS+w The source range monitors provide the operator with information o'he status of .the neutron level,"in'>the core at very low power levels during startup and shutdown. At these power~levels, reactivity additions shall not be made without this flux level information available to the operator. When the inter-mediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.

3/4.3.7.7 TRAVERSING IH"CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.

4. 3. 7. 8 CHLORINE DETECTION SYSTEM The ILITY of the chlorine detection system ensures that an acc chlorine release w detected promptly and the necessary r ie actions will be automatically init> to provide protection f ntrol room person-nel. Upon detection of a high conce ion o rine, the control, room emergency ventilation system will au a laced in the isolation mode of operation to provide the red protection. Tne ion systems required by this speci ficati e consistent with the recommendations o u Iatorv otection of Nuclear Power Plant Control Room Operators a ccidental Chlorine Release," February 1975.

WASHINGTON NUCLEAR

- UNIT 2 B 3/4 3-5

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