Text

Amend 67 to License NPF-21,revising License Condition 2.C.14 to Incorporate Std Condition for Fire Protection Set Forth in Generic Ltr 86-10
	ML17285A492
Person / Time
Site:	Columbia
Issue date:	05/25/1989
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17285A493	List: ML17285A492;
References
	GL-86-10, NUDOCS 8906020306
	Download: ML17285A492 (32)
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UNITED STATES t

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.

~ 2 AMENDMENT TO FACILITY.OPERATING LICENSE Amendment, t)o.. 67,

License No.

NPF-21 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Washington Public Power Supply System (the licensee),

dated February 10, 1987 and supplement dated March 31, 1989 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the Operating License and the Technical Specifications are amended as indicated below and in the attachment to this license amendment.

Paragraph 2.C.(14) of Facility Operating License No. NPF-21 is hereby amended to read as follows:

8906020 05000397 06 890525 pDR ADQCK PDQ P

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(14) Fire Protection Program (Generic Letter 86-10)

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in Section 9.5.1 and Appendix F of the Final Safety Analysis Report (FSAR) for the facility thru Amendment ¹39 and as described in subsequent letters to the staff through November 30, 1988, referenced in the May 22, 1989 safety evaluation and in other pertinent sections of the FSAR referenced in either Section 9.5.1 or Appendix F and as approved in the Safety Evaluation Report issued in March 1982 (NUREG 0892) and in Supple-ments 3, issued in May 1983, and 4, issued in December

1983, and in safety evaluations issued with letters dated November ll, 1987 and May 22, 1989 subject to the following provision:

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

3.

Paragraph 2.C.(2) ot Facility Operating License No.

NPF-21 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

67

, and the Environ-mental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the faci lity in accordance with the Technical Specifications and the Environmental Protection Plan.

4.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications George

. Knighton, Director Project Directorate V

Division of Reactor Projects III, IV, V and Special Projects Date of Issuance:

May 25, 1989

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ENCLOSURE TO-LICENSE-AMENDMENT NO.. 67 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Also to be replaced are the following overleaf pages.

AMENDMENT PAGE vi 1X Xi11 xvxxiii XX1V 3/4 3-79 through 3/4 3-82 3/4 7-18 through 3/4 7-20 3/4 7-21 through 3/47-32*

8 3/4 3-6 8 3/4 7-4 8 3/4 7-5*

6-2 6-3 OVERLEAF.PAGE v

X xiv xvi 3/4 7-17 8 3/4 3-5 8 3/4 7-3 6-1 6-4

Remove these pages (there is no replacement).

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INDEX LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE RE UIREMENTS SECTION

. 3/4. 3 INSTRUMENTATION PAGE 3/4.3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............

3/4 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 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION..

3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION..

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..

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/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION....................

3/4. 3. 4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATMS,Recirculation Pump Trip System Instrumentation..

End-of-Cycle Recirculation Pump Trip System Instrumentation...............

3/4 3-37 3/4 3-41 3/4 3-47 3/4 3-52 3/4 3-58 3/4 3-61 3/4 3-64 3/4 3-67 3/4 3-70 3/4 3-76 3/4 3-77 3/4 3-83 3/4 3-84 3/4 3"89 3/4 3"96 3/4 3"98 MASHINGTON NUCLEAR - UNIT 2 vi Amendment No. 67

0 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION Control Rod Maximum Scram 'Insertion Times.....'

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3/4.0 APPLICABILITY.............................................

3/4.1 REACTIVITY CONTROL SYSTEHS 3/4.1. 1 SHUTDOWN MARGIN........................................

3/4.1. 2 REACTIVITYANOMALIES...................................

3/4.1. 3 CONTROL RODS Control Rod Operability................................

PAGE 3/4 0-1 3/4 1"1 3/4 1-2 3/4 1-3 SKI-S I

Four Control Rod Group Scram Insertion Times...........

3/4 1-8 Control Rod Scram Accumulators...........:.............

3/4 1-9 Control Rod Drive Coupling............

Control Rod Position Indication.................

Control Rod Drive Housing Support......................

3/4. 1.4 CONTROL ROD PROGRAM CONTROLS

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Rod Worth Minim>zer...................................

Rod Sequence Control System............................

Rod Block Monitor......................................

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM..........................

3/4. 2 POWER DISTRIBUTION LIMITS 3/4 1"11 3/4 1-13 3/4 1-15 3/4 1-16 3/4 1-17 3/4 1-18 3/4 1-19 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.............

3/4 2-1 3/4 2.2 PRM SETPOINTSo

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A 3/4 2-5 3/4.2.3 MINIMUM CRITICAL POWER RATIO......"-"".-.--.........

3/4 2-6 3/4.2.4 LINEAR HEAT GENERATION RATE................. -..........

3/4 2-9 3/4.2.5 (RESERVED FOR FFTR) 3/4. 2. 6 POWER/FLOW INSTABILITY.................................

3/4 2-11 3/4.2.7 NEUTRON FLUX NOISE MONITORING.................;........

3/4 2-13 WASHINGTON NUCLEAR - UNIT 2 Amendment No. 62

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4.7 PLANT SYSTEMS 3/4.7. 1 SERVICE WATER SYSTEMS Standby Service Water System..............

High Pressure Core Spray Service Water System.

Ultimate Heat Sink.

PAGE 3/4 7"1 3/4 7-3 3/4 7"4 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM.

3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM....

3/4.7.4 SNUBBERS 3/4 7-5

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~ 3/4 7 8 3/4 7-10 3/4. 7. 5 SEALED SOURCE CONTAMINATION........................... 3/4 7-16 3/4.7.8 AREA TEMPERATURE MONITORING...........................

3/4 7-30 3.4.7.9 MAIN TURBINE BYPASS SYSTEM.....

3/4.8 ELECTRICAL POWER SYSTEMS 3/4 7-32 3/4.8. 1 A.C.

SOURCES A.C. Sources A.C. Sources 3/4.8.2 D.C.

SOURCES D. C.

Sources D. C.

Sources

- Operating.

- Shutdown..

- Operating.........

hutdown...............................

S 3/4 8-1 3/4 8-10 3/4 8-11 3/4 8-15 WASHINGTON NUCLEAR - UNIT 2 1X Amendment No. 67

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 0

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I SECTION ELECTRICAL POWER SYSTEMS (Continued) 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Distribution - Operating.

Distribution - Shutdown...................

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES PAGE 3/4 8"16 3/4 8-18 A.C. Circuits Inside Primary Containment..............

3/4 Primary Containment Penetration Conductor Overcurrent Protective Devices..

. 3/4 8-20 8-21 Motor-Operated Valve Thermal Overload Protection..

Reactor Protection System Power Supply Monitoring.

3/4. 9 REFUELING OPERATIONS 3/4 8"25 3/4 8-29 3/4. 9. 1 REACTOR MODE SWITCH.

3/4 9-1 3/4.9.2 INSTRUMENTATION.

3/4.9.3 CONTROL ROD POSITION.

3/4 9-3 3/4 9-5 3/4.9.4 DECAY TIME...........

3/4 9-6 3/4. 9. 5 COMMUNICATIONS

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3/4.9.7 CRANE TRAVEL -

SPENT FUEL STORAGE POOL 3/4. 9. 8 WATER LEVEL " REACTOR VESSEL..........

3/4 9"8 3/4 9-9 3/4 9"11 3/4.9.9 WATER LEVEL -

SPENT FUEL STORAGE POOL...............

. 3/4 9-12 3/4.9. 10 CONTROL ROD REMOVAL Single Control Rod Removal.......

Multiple Control Rod Removal.

3/4.9. 11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.................

Low Water Level.

3/4 9-13 3/4 9-15

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3/4 9-17

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3/4 9-18 WASHINGTON NUCLEAR - UNIT 2

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g INDEX BASES SECTION INSTRUMENTATION (Continued) 3/4.3. 7 MONITORING INSTRUMENTATION Radi ati on Monitoring Instrumentati on..........

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

Meteorological Monitoring Instrumentation.....

Remote Shutdown Monitoring Instrumentation....

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

Source Range Monitors..

Traversing In-Core Probe System..

Loose-Part Detection System..

Radioactive Liquid Effluent Monitoring Instrumentation........

Radioactive Gaseous Effluent Monitoring Instrumentation.................

PAGE B 3/4 3-4 B 3/4 3 4 B 3/4 3-5 B 3/4 3-5 B 3/4 3-5 B 3/4.3 5

B 3/4 3-5 B 3/4 3-6 B 3/4 3-6 B 3/4 3-7 3/4.3.8 3/4.3.9 FEEDMATER SYSTEH/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.......................

B 3/4 3-7 TURBINE OVERSPEED PROTECTION SYSTEM.............

B 3/4 3-7 3/4, 4. 4 3/4.4. 5 CHEMISTRYo

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

3/4.4. 6 PRESSURE/TEMPERATURE LIMITS...................

3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 RECIRCULATION SYSTEM......... ~..................

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

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems....

Operational Leakage...

B 3/4 4-1 B 3/4 4-1 8 3/4 4-la B 3/4 4-2 B 3/4 4-2 B 3/4 4-3 B 3/4 4"4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................

B 3/4 4-5 WASHINGTON NUCLEAR - UNIT 2 Amendment No. 6

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BASES INDEX SECTION 3/4.5 EMERGENCY CORE COOLING SYSTEMS PAGE 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN..........

B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER......

3/4.6 CONTAINMENT SYSTEMS 3/4.6. 1 PRIMARY CONTAINMENT Primary Containment Integrity.

Primary Containment Leakage..

Primary Containment Air Locks......

MSIV Leakage Control System..................

Primary Containment Structural Integrity.....

Drywell and Suppression Chamber Internal ressure.

P Drywell Average Air Temperature..............

Drywell and Suppression Chamber Purge System.

B 3/4 5-2 B 3/4 6-1 B 3/4 6-1 B 3/4 6-1 8 3/4 6-1 B 3/4 6-2 B 3/4 6-2 8 3/4 6-2 B 3/4 6-2 3/4.6. 2 DEPRESSURIZATION SYSTEMS B 3/4 6-3 3/4. 6. 3 PRIMARY CONTAINMENT ISOLATION VALVES.............

B 3/4 6-4 3/4.6.4 VACUUM RELIEF 3/4.6.5 SECONDARY CONTAINMENT.

B 3/4 6-4 8 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL...........

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7. 1 SERVICE WATER SYSTEMS............................

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM.........

B 3/4 7"1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM............

B 3/4 7-1 3/4.7.4 SNUBBERS..

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INDEX BASES SECTION PLANT SYSTEMS (Continued)

PAGE 3/4.7.5 SEALED SOURCE CONTAMINATION.

B 3/4 7-3 3/4.7.8 AREA TEMPERATURE MONITORING.....................

B 3/4 7-4 3/4.7.9 MAIN TURBINE BYPASS SYSTEM........

3/4.8 ELECTRICAL POWER SYSTEMS 3/4. 8. 1,.3/4. 8. 2, and 3/4.8.3 '.C.

SOURCES, D.C.

SOURCES, and ONSITE POWER DISTRIBUTION SYSTEMS....

B 3/4 7-4 B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.........

B 3/4 8-3 3/4. 9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.................

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

3/4. 9. 3 CONTROL ROD POSITION...............

3/4. 9. 4 DECAY TIME 3/4. 9. 5 COMMUNICATIONS.....

3/4. 9. 6 REFUELING PLATFORM..............................

B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL..........

B 3/4 9-2 3/4. 9. 8 and 3/4. 9. 9 WATER LEVEL -

REACTOR VESSEL and WATER LEVEL -

SPENT FUEL STORAGE POOL.......

3/4. 9. 10 CONTROL ROD REMOVAL.........

B 3/4 9-2 B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...

B 3/4 9-2 WASHINGTON NUCLEAR - UNIT 2 XV Amendment No. 67

BASES INDEX SECTION 3/4.10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 PRIMARY CONTAINMENT INTEGRITY.

3/4. 10. 2 ROD SEQUENCE CONTROL SYSTEM.

PAGE B 3/4 10-1 B 3/4 10-1 3/4. 10.3 SHUTDOWN MARGIN DEMONSTRATIONS..................

B 3/4 10-1 3/4. 10. 4 RECIRCULATION LOOPS B 3/4 10-1 3/4. 10. 5 OXYGEN CONCENTRATION........................

8 3/4 10-1 3/4. 10. 6 TRAINING STARTUPS 3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID EFFLUENTS 3/4. 11.2 GASEOUS EFFLUENTS 3/4. 11.3 SOLID RADWASTE SYSTEM..

3/4. 11. 4 TOTAL DOSE 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM..

3/4. 12. 2 LAND USE CENSUS 3/4. 12. 3 INTERLABORATORY COMPARISON PROGRAM.

B '3/4 10-'1 B 3/4 11-1 B 3/4 11-2 B 3/4 11"5 B 3/4 11-6 B 3/4 12-1 B 3/4 12-1 B 3/4 12-2 MASHINGTON NUCLEAR - UNIT 2 XV)

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INDEX LIST OF TABLES {Cont1nued)

TABLE 3.3.7. 5-1

4. 3.7. 5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........

3/4 3-74 PAGE ACCIDENT MONITORING INSTRUMENTATION.................

3/4 3-71

3. 3. 7. 11-1

4. 3. 7. 11-1

3. 3.7. 12-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION...

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....

3/4 3-S5 3/4 3-87 3/4 3-90 4.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............

3/4 3-93

3. 3. 9-1

3. 3. 9-2 4.3. 9. 1-1 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 3-99 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 4-3.1 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 XX111 Amendment No.

5 INDEX LIST OF TABLES (Continued)

TABLE 4.4. 6. l. 3-1

3. 6. 3-1

3. 6. 5. 2-1 3.7. 8-1

4. 8. 1. 1. 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 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE PRIMARY CONTAINMENT ISOLATION VALVES..............

SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES AREA TEMPERATURE MONITORING..

DIESEL GENERATOR TEST SCHEDULE BATTERY SURVEILLANCE REQUIREMENTS PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES..

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION.....

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM.......

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....

REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES.........................

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE NALYSIS

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A PAGE 3/4 4"22 3/4 6-21 3/4 6-39 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. 6T

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This page intentionally 1 eft blank MASHINGTON NUCLEAR - UNIT 2 3/4 3"80 Amendment No. 67

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67

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months.

Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

C.

Startu sources and fission detectors - Each sealed startup source and fission detector shall be tested within 3l days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.5.3

~Re orts A report shall be prepared and submitted to the Commission.'n an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.

WASHINGTON NUCLEAR - UNIT 2 3/4 7-17

PLANT SYSTEMS 3/4.7.8 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 3.7.8 The temperature of each area shown in Table 3.7.8-1 shall be maintained within the limits indicated in Table 3.7.8-1.

APPLICABILITY:

Whenever the equipment in an affected area is required to be

~BL ACTION:

With one or more areas exceeding the temperature limit(s) shown in Table 3.7.8-1:

a.

For more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , in lieu of any report required by Specification 6.9. 1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days providing a record of the amount by which and the cumulative time the temperature in the affected area exceeded its limit and an analysis to demonstrate the continued OPERABILITY of the affected equipment.

b.

By more than 30 F, in addition to the Special Report required above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area to within its temperature limit or declare the equipment in the affected area inoperable.

SURVEILLANCE RE UIREMENTS 4.7.8 The temperature in each of the areas shown in Table 3.7.8-1 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

WASHINGTON NUCLEAR " UNIT 2 3/4 7"18 Amendment No.67

AREA TABLE 3.7.8-1 AREA TEMPERATURE MONITORING TEMPERATURE LIMIT F

a.

Control Room b.

Auxiliary Electric Equip.

Rooms c.

Primary Containment (Drywell) d.

HPCS, LPCS,

RHR, RCIC Rooms e.

Primary Containment Beneath Reactor Pressure Vessel f.

Switchgear Rooms

< 104

< 150

< 165

< 104 WASHINGTON NUCLEAR - UNIT 2 3/4 7"19 Amendment No.

67

PLANT SYSTEMS 3/4.7.9 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9 The main turbine bypass system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITION 1 when THERMAL POWER is greater than

~q2EE T

RATER THERMAL POWER.

ACTION:" With the main turbine bypass system inoperable, restore the system to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or reduce THERMAL POWER to less than 25K of RATED THERMAL POHER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS 4.7.9 The main turbine bypass system shall be demonstrated OPERABLE at least once per:

a.

7 days by cycling each turbine bypass valve through at least one complete cycle of full travel, and b.

18 months by:

1.

Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.

2.

Performing a

CHANNEL CALIBRATION of the main turbine bypass system actuation instrumentation.

3.

Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to 300 milliseconds to a valve position equivalent to SO% of rated bypass flow.

WASHINGTON NUCLEAR - UNIT 2 3/4 7-20 Amendment No. 67

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 to 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, "Onsite Meteorological Programs,"

February, 1972.

3/4. 3. 7. 4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION 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 for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the 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 IN-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.

WASHINGTON NUCLEAR " UNIT 2 B 3/4 3-5 Amendment No. 36

INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Conti nued) 3/4.3.7.9 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.

The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Mater-Cooled Reactors,"

May 1981.

3/4.3.7.10 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is'rov'ided'o monitor'nd

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 Amendment No.

67

PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS (Continued) failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an assumed initiating event.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections performed before the original required time interval has elapsed, (nominal time less 25X) may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

The acceptance criteria are to be used in the visual inspection to deter-mine OPERABILITY of the snubbers.

For example, if a fluid port of. a hydraulic snubber is found to be uncover'ed, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.

To provide assurance of snubber functional reliability, one of two functional testing methods are used with the 'stated acceptance criteria:

1.

Functionally test 10K of a type of snubber with an additional 5X tested for each functional testing failure, or 2.

Functionally test a sample size and determine sample acceptance or continue testing using Figure 4.7-1.

MASHINGTON NUCLEAR - UNIT 2 B 3/4 7-3 Amendment No.

54

PLANT SYSTEMS BASES SNUBBERS (Continued)

Figure 4.7-1 was developed using "Wald's 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 is 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 fabrication 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 established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal

replaced, spring replaced, in high radiation area, in high temperature area, etc.).

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

These records will provide statis-tical bases for future consideration of snubber service life.

3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak

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

This limitation vill 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 requir ements commensurate with the probability of damage to a source in that group.

Those sources which are frequently handled are required to be tested more often than those which are not.

Sealed sources which are continuously enclosed within a shielded mechanism, i. e.,

sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

3/4. 7. 8 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.

Exposure to excessive temperatures may degrade equipment and can cause loss of its OPERABILITY.

3/4.7.9 MAIN TURBINE BYPASS SYSTEM The main turbine bypass system is required to be OPERABLE consistent with the assumptions of the feedwater controller failure analysis of the cycle specific analysis.

The main turbine bypass system provides pressure relief during the feedwater controller failure event so that the safety limit MCPR is not violated.

WASHINGTON NUCLEAR - UNIT 2 B 3/4 7"4 Amendment No.

67

6. 0 ADMINISTRATIVE CONTROLS

6. 1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Manager (or during his absence from the control room, a

designated individual) shall be responsible for the control room command func-tion.

A management directive to this effect, signed by the Director of Power Generation shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS

~.

~

Onsite and offsite organizat'ioris shall be established for unit op'eration and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions.

These requirements are documented in the MHP-2 FSAR and updated in accordance with 10 CFR 50.71.

b.

The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of 4he plant.

c.

The Assistant Managing Director for Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carry out health physics functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

e.

The organization responsible for the overall quality assurance functions shall report to the Supply System Managing Director.

6.2.2 UNIT STAFF a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; WASHINGTON NUCLEAR - UNIT 2 6-1 Amendment Ho. 63

AOMINISTRATIVE CONTROLS a

UNIT STAFF (continued) b.

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

In addition, while the unit is in OPERATIONAL CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room.

C.

d.

e.

A Health Physics Technician" shall be on site when fuel is in the reactor and at least one fully qualified chemistry technician shall be on site in OPERATIONAL CONDITION 1, 2, or 3; All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions

e. g., licensed Senior Operators, licensed Operators, health physi-

cists, chemistry technicians, auxiliary operators, and key maintenance personnel.

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

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shut-.,

down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:

1.

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

straight, excluding shift turnover time.

2.

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

period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work

periods, including shift turnover time.

he ealth Physics Technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected

absence, provided immediate action is taken to fill the required positions.

WASHINGTON NUCLEAR " UNIT 2 6-2 Amendment No.

67

h 7

ADMINISTRATIVE CONTROLS UNIT STAFF (continued) 4.

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

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

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

f.

The Operations Manager, Assistant Operations Manager, Shift Managers and Control Room Supervisors shall hold a senior reactor operator license.

The Reactor Operators shall hold either a senior reactor operator license or a reactor operator license.

WASHINGTON NUCLEAR " UNIT 2 e-3 Amendment No.

67

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63

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