Text

Amend 42 to License NPF-42,revising Tech Specs Per Generic Ltr 89-01
	ML20070D315
Person / Time
Site:	Wolf Creek
Issue date:	02/19/1991
From:	Dick G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20070D318	List: ML20070D315; ML20070D344;
References
	GL-89-01, GL-89-1, NUDOCS 9102280200
	Download: ML20070D315 (46)
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UNITED STATES

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WOLF CREEK NUCLEAR OPERATING f,'*!PORATION WOLF CREEK GENERATING STATION DOCKET NO. 50 482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. NPF-42 1.

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

A.

The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation),

cated August 24, 1990, complies with the standards and requirefrents of the Ats c Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance:

(.i) that tha activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wiil be conducted in compliance with the Commission's regulations; D.

The issuance of this license 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.

l 9102280200 910219 DR ADOCK 050 2

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2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of facility Operating License No. NPF-42 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

42, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.

The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of date of issuance to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

' 1 Jul jL b / %c d

}

George F. Dick, Jr., Acting Director Project Directorate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Techrical Specifications Date of Issuance:

February 19, 1991 3

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ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical $pecificat-ions by removing the pages identified below and inserting the enclosed pages.

The revised pagst are identified by amendment number and contain marginal lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

I REMOVE INSERT I

I VI VI VII VII XIII XIII XIV XIV XVIII XVIII XXI XXI XXII XXII 1-4 1-4 1-5 1-5 3/4 3-58 3/4 3-58 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 3-63 3/4 3-63 3/4 3-64 3/4 3-65 3/4 3-66 3/4 3-67 3/4 3-68 3/4 3-69 3/4 3-70 3/4 3-71 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-6 3/4 11-7 3/4 11-8

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l REMOVE INSERT 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11 12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-16 3/4 11-17 3/4 11-18 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 3/4 12-12 3/4 12-13 3/4 12-14 B 3/4 3-6 B 3/4 3-6 8 3/4 3-7 B 3/4 11-1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-2 B 3/4 11-3 B 3/4 11-4 B 3/4 11-5 B 3/4 11-6 B 3/4 12-1 B 3/4 12-1 B 3/4 12 --

6-17 6-17 6-18 6-18 6-18a 6-19 6-19 6-20 6-20 6-21 6-21 6-22 6-22 6-23 6-23 6-24 6-24 6-25 6-25

g DEFINITIONS SECTION PAGE 1.0 -DEFINITIONS 1.1 ACTION....................

1-1 1.2 ACTUATION LOGIC TEST...

1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST...

1-1 1.4 AXIAL FLUX DIFFERENCE 1-1 1.5 CHANNEL CALIBRATION.

1-1

1. 6 CHANNEL CHECK..

1-1 1.7 CONTAINMENT INTEGRITY...

1-2 1.8 CONTROLLED LEAKAGE.......

1-2 1.9 CORE ALTERATION......

1-2 1.10 DOSE EQUIVALENT I-131....

1-2 1.11 5-AVERAGE DISINTEGRATION ENERGY......

1-2 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME.....................

1-3 1.13 FREQUENCY NOTATION.

1-3 1.14 IDENTIFIED LEAKAGE...

1-3 1.15 MASTER RELAY TEST.

1-3 1.16 MEMBER (S) 0F THE PUBLIC..

1-3 1.17 0FFSITE DOSE CALCULATION MANUAL.............................

1-4 1.18 OPERABLE - OPERABILITY..

1-4 1.19 OPERATIONAL MODE - MODE.......

1-4 1.20 PHYSICS TESTS............................................

1-4 1.21 PRESSURE BOUNDARY LEAKAGE....................................

1-4 1.22 PROCESS CONTROL PR0 GRAM......................................

1-4 1.23 PURGE - PURGING.........

1-4 1.24 QUADRANT POWER TILT RATI0....................................

1-5 1.25 RATED THERMAL POWER.........................................

1-5 1.26 REACTOR TRIP SYSTEM RESPONSE TIME.,.........................

1-5 1.27 REPORTABLE EVENT.........

1-5 1.28 SHUTDOWN MARGIN..............................................

1-5 1,29 SITE B0VNDARY................................................

1-5 1.30 SLAVE RELAY TEST.............................................

1-5 1.31 DELETED..........

1-5 WOLF CREEK - UNIT 1 I

Amendment No. 42 1

1

DEFINITIONS SECTION PAGE DEFINITIONS (Continued) 1.32 SOURCE CHECK.................................................

1-6 1.33 STAGGERED TEST BASIS.........................................

1-6 1.34 THERMAL POWER.........

1-6 1.35 TRIP ACTUATING DEVICE OPERATIONAL TEST.......................

1-6 1.36 UNIDENTIFIED LEAKAGE.......................................

1-6 1.37 UNRESTRICTED AREA........

1-6 1.38 VENTILATION EXHAUST TREATMENT SYSTEM....

1-6 1.39 VENTING...........

1-7 1.40 WASTE GAS H3 LOUP SYSTEM.

1-7 TABLE 1.1 FREQUENCY NOTATION.......

1-6 TABLE 1.2 OPERATIONAL MODES.....

1-9 1

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WOLF CREEK - UNIT 1 II

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...........................

3/4 2-1 FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUN 2 TION OF RATED THERMAL P0WER................................

3/4 2-3 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R.............................

3/4 2-4 FIGURE 3.2-2 K(Z)-NORMALIZED F (2) AS A FUNCTION OF CORE HEIGHT...

3/4 2-5 q

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR...

3/4 2-8 FIGURE 3.2-3 RCS TOTAL FLOW RATE VERSUS R - FOUR LOOPS IN OPERATION....

3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO............

3/4 2-11 3/4.2.5 DNE PARAMETERS.

3/4 2-14 TABLE 3.2-1 DNB PARAMETERS..

3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1-REACTOR TRIP SYSTEM INSTRUMENTATION....................

3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION...................

3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES....

3/4 3-7 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................................

3/4 3-9

- 3/4,3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............

3/4 3-13 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.....................................

3/4 3-14 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS......................

3/4 3-22 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPGNSE TIMES.............

3/4 3-29 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION' SYSTEM INSTRUMENTATION SURVEILLANCE REQUIRE'4ENTS...........

3/4 3-34 WOLF CREEK - UNIT 1 V

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LIMITING CONDITIONS FOR-OPERA 110N AND SURVEILLANCE REQUIREMENTS SECTION FAGE INSTRUMENTATION (Continued) 3/4.3.3 MONITORING INSTRUMENTATION i:

Radiation Monitoring for Plant Operations.................

3/4 3-39 L

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION F OR P L ANT OPE RAT I ONS.........................

3/4 3-4 0 TABLE-4.3-3 RADI ATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.

3/4 3-42 Movable Incore Detectors...

3/4 3-43 Seismic Instrumentation..

3/4 3-44 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION.

3/4 3-45 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...................

3/4 3-46 Meteorological Instrumentation.-...

. 3/4 3-47 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.,

3/4 3-48 TABLE 4,3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-49 Remote Shutdown Instrumentation..........................

3/4 3-50 TABLE 3.3 -REMUTE SHUTOOWN MONITORING INCTRUMENTAT10N...........

3/4 3-51 TABLE 4.3-6 REMOTE-SHUTDOWN MONITORING INSTRUMENTATION l-SURVEILLANCE' REQUIREMENTS........................, 3/4 3-52 l

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

. 3/4 3-53 L

TABLE 3'3-10 ACCIDENT MONITORING INSTRUMENTATION.

. 3/4 3-54 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................

3/4 3-55 Chlorine Detection Systems.....................,..........

3/4 3-56 Loose-Part Detection System......

3/4 3-57 Radioactive Liquid Effluent Monitoring Instrumentation DELETED TABLE 3.3-12

-RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED l

l WOLF CREEK - UNIT 1 VI Amendment No. IB. 42

_. _ _ _. _ _ _.. _ _. _. _. _ = _ _. _

i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE INSTRUMENTATION (Continu(1)

TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Radioactive Gaseous Ef fluent Monitoring Instrumentation DELETED Explosive Gas Monitoring Instrumantation...............

3/4 3-58 TABLE 3.3-33 EXPLOSIVE GAS MONITORING INSIRUMENTATION............

3/4 3-59 TABLE 4.3-9' EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.....

3/4 3-63 3/4.3.4 TURBINE OVERSPEED PROTECTION...

3/4 3-63 3/4.4 REACTOP COOLANT SYSTEM 3/4.4.1 REACTOR C0OLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation....

3/4 4-3 Hot Standby.

3/4 4-2 Hot Shutdown.

3/4 4-3 Cold Shutdown - Loops f illed...

3/4 4-5 Cold Shutdown - Loops Not Filled.....

3/4 4-6 3/4.4.2 SAFETY VALVES

-Shutdown.

. 3/4 4-7 Operating..

3/4 4-8 3/4.4.3 PRESSURIZER.......................................

3/4 4-9 3/4.4.4 RELIEF VALVES...

3/4 4-10

.3/4.4,5 STEAM GENERATORS.........................................

3/4 4-11 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECT 10N........................

3/4 4-16 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECT 10N......................

3/4 4-17 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...............................

3/4 4-18 Operational Leakage.......................................

3/4 4-19 WOLF CREEK - UNIT 1 Vil Amendment No. IB, 42 i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

-PAGE TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES...................

3/4 4-21 3/4.4.7 CHEMISTRY................................................

3/4 4-22 TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS...............

3/4 4-23 TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY SURVEILLANCE REQUIREMENTS......................................

3/4 4-24 3/4.4.8 SPECIFIC ACTIVITY.......

3/4 4-25 FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERKAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY >

1 pCi/ GRAM DOSE EQUIVALENT I-131.................

3/4 4-27 TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...............................

3/4 4-28 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System......

3/4 4-29 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 7 EFPY............................

3/4 4-30 FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE UP TO 7 EFPY...

.3/4 4-31 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITH0RAWAL SCHEDULE.....................

3/4 4-32 Pressurizer......................................

3/4 4-33 Overpressure Protection Systems..........................

3/4 4-34 FIGURE-3.4-4 MAXIMUM ALLOWED PORV SETPOINT FOR THE COLD OVERPRESSURE MITIGATION SYSTEM...............

3/4 4-35 3/4.4.10 STRUCTURAL INTEGRITY.....................................

3/4 4-37 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................

3/4 4-38

-3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.......

3/4 5-1 WOLF CREEK - UNIT 1 VIII Amendment No. 40

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SFCTION PAGE 3/4.30 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOWN MARGIN...........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS....

3/4 10-2 3/4.10.3 PHYSICS TESTS....

3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS..

3/4 10 4 3/4.10.5 POSITION INDIC ATION SYSTEM - SHUTDOWN..............

3/4 10-5 3/4.31 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EffLUEh75 Concentration OELETED TABLE 4.))-1 RADIDACTIVE L20'J10 WASTE SAMPLING AND ANALYSIS PROGRAM DELETED Dose OELETED Liquid Radwaste Treatment System DELETED Liquid Holdup Tanks.

3/4 11-1 3/4.11.2 GASEOUS b

EN15 Dose Rate DELETED TABLE 4.11-2 RADI0 ACTIVE GASEOUS W/pTE SAMPLING AND ANALYSIS PROGRAM DELETED Dose-Noble Gases DELETED Dose-Iodine-131 and 133, Tritium and Radioactive Material in Particulate Form DELETED Gaseous Rada'aste Treatment System DELETED Explosive Gas Mixture.....................................

3/4 11-2 Gas Storage Tanks........................

3/4 11-3 l

WOLF CREEK - UNIT 1 XIII Amendment No. 42

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LIMITING CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS SECTION PAGE 3/4.11.3 SOLID RADIDACTIVE WASTES DELETED 3/4.11.4 TOTAL DOSE DELETED 3/4.12 RADIOLOGICAL ENVIRONMENT AL MONITORING 3/4 12-1 3/4.12.1 MON!10 RING PRDGRAM DELETED TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DELETED TABLE 3.12-2 REPORTING LEVELS FOR RADIDACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES DELETED TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS DELETED 3/4.12.2 LAND USE CENSUS DELETED 3/4.12.3 INTERLABDRATOR1 COMPAR150h PROGRAM DELETED l

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l WOLF CREEK - UNIT 1 XIV Amendment No. 42 l

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+

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BASES'-

SECTION PACE 3/4.7-' PLANT 5YSTEMS 3/4.7.1' 1URBINE CYCLE..........,........

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRES $URE/ TEMPERATURE LIMITATION..........

B 3/4 7-3 3/4.- 7. 3 COMPONENT COOLING WATER SYSTEM-B 3/4 7-3 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...

B 3/4 7-3 3/4.7.5 ULTlfmTE HEAT SINK, B 3/4 7-3 3/4.7 6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...

B 3/4 7-4 3/4.7.7 EMERGENCY EXHAUST SYSTEM.,

B 3/4 7-4 3/4.7.8 SNUEDERS B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION...

B 3/4 7-6 1

L3/4.7.10 D[LElED 3/4.7.11 DELETED 3/4.7.12' AREALTEMPERATURE MONITORING............................

B 3/4 7-7 3/4.8 ELECTRICAL F0WER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. 00VRCES, and ONSITE POWER DISTRIBUTION,...

B 3/4 8-1

- 3/4.8.4

-ELECTRICAL EQUIPMENT. PROTECTION DEVICES...............

B 3/4 8-3 3 /4. 9 REFUELING OPERATIONS 3/4.9.11 BORON CONCENTRATION......................................

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

B 3/4 9-1 3/4.9.3

-DECAY TIME.....

B 3/4 9-1 3/4.9.4 CONT AINMENT BUI LDING PENETRATIONS......................

B 3/4 9-1

~3/4.9.5 COMMUNICATIONS...........................................

B 3/4 9-1 WOLF CREEK - UNIT 1 XVil Amendment No, 15

=-.-.- --.-.

BASES SECTION

_ PAG _E REFUELING OPERATIONS (Cont ~.nued) 3/4.9.6 REFUELING MACHINE..............................

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

B 3/4 9 2 3/4.9.8 RESIDUAL HEAT REMOVAL AND C00LAN1 CIRCULAfl0N...

B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM.

B 3/4 9-2 3/4.9.10 ind 3/4,9.11 WATER LEVEL REACTOR VESSEL and STORAGE POOL.

B 3/4 9 3 3/4.9.12 SPENT FUEL ASSEMBLY STORAGE............................

B 3/4 9-3 3/4.9..s EMERGENCY EXHAUST SYSTEM.,

B 3/4 9 3 3/4.10 SPECI AL TEST ExCEPT10:15 3/4.10.1 SHUTDOWN MARGIN.....

B 3/4 10-1 3/4.10.2 GROUP HEIGH 1, INSERTION, AND POWER DISTRIBUTION LIMITS..

B 3/4 10-1 3/4.10.3 PHYSICS TESTS.

B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS......

B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.................

B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 -LIQUID EFFLUENTS...........

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................

B 3/4 11-1 3/4.11.3 DELETED 3/4.11.4 DELETED 3/4.12 RADI0 ACTIVE ENVIRONMENTAL MONITORING B 3/4 12-1 3/4.12.1-DELETED 3/4.12.2 DELETED 3/4.12.3 DELETED WOLF CREEK - UNIT 1 XVIII Amendment No. 42

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1 ADMINISTRATIVE CONTR0t 5:

l SECTION PAGE 6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (N5RC)

Function.

6-9 Composition!..

6-10 Alternates......

6-10 Consultants.

6-10 Meeting frequency..

.6-10 Quorum.................

6-10 Review.

6-11 j

i Audits.

6-11 Records...

6-12 6.6 REPORTABLE EVENT ACTION.,

6-13 6.- 7 SAFETY LIMIT VIOLATION.

6-13 i

6.8 PROCEDURES AND PROGRAMS...

6-13 6.9 REPORTING REOUIREMENTS 6,9,1 ROUTlNE REPORTS......

6-18 Startup Report.,

6-19 Annual Reports.

6-19 Annual Radiological Environmental 0perating Report.,,.........

6-20 Semiannual Radioactive Effluent Release Report...........

6-20 i

Monthly Operati ng Report........

6-20 Radial Peaking Factor Limit Report............................

6-21 6.9.2 SPECIAL REPORTS...........

6-21 6.10 RECORD RETENT10N..............................................

6-21 i

i WOLF CREEK - UNIT 1 XXI Amendment No. 42 l

L..

4 ADMINISTRATIVE CONTROLS SECTION-

_PAGE 6.11 RADIATION PROTECTION PR0 GRAM...,,.................................

6-23

'6.12 HIGH RADIATION AREA...............................................

6-23 6.13 PROCESS CONTROL PROGRAM (PCP)........................

6-24 6.14 0FFSITE 005E CALCULA110N MANUAL (0DCM)....

6-24 6.15 DELETED WOLF CREEK - UNIT 1 XXII Amendment No. 42

DEFINITIONS ENGINEERED SAFETY FEATURES RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety f unction (i.e., the v'alves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequenct loading delays where applicable.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall corr (spond to the intervols defined in lable 1.1.

IDENTIFIED LEAKAGE 1.24 IDENTIFIED LEAKAGE sha'l be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sun:p or collecting tank, or b.

Learage into the containment stmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to the Si.conaary Coolant System.

MASTER RELAY TEST I

1.15 A MASTER RELAY TEST shall be the energilation of each master relay and verification of OPERABILITY of each relay.

The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

ME;;BER(5) 0F THE PUBLIC 1.16 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.

This category does not include employecs of the licensee, its contractors, or vendors, Also excluded frnm this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recreational, occupational, cr other purposes not associated with the plant.

WOLF CREEK - UNIT 1 1-3

DEFINITIONS OFFSITE DOSE CALCULATION MANUAL l

L 17 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program, The 00CM shall also contain (1) the Radioac-tive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should b(

included in the Annual Radiological Environmental Operating and Semiannual Radio-active Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.

OPERABLE - OPERABILITY 1.16 A system, subs 3 stem, train, component or desice shall be OPERABLE or i

l have OPERABILITY when it is Capable of performing its specified function (s),

ar:d when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perfort its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusist combination of core reactivity condition, powet level, and average reactor coolant temperature specified in Table 1.2 PHYSICS TESTS 1.20 PHYSICS TESTS shall be those tests performed to measure the fundamental i

l nuclear characteristics of the core end related instrumentation: (1) described in Chapter 14.0 of the FSAR, or (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radiocctive wastes based on demonstrated processing of actual or simulated wet sclid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

PURGE - PURGING 1.23 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

l WOLF CREEK - UNIT 1 1-4 Amendment No. 42

DEFINITIONS QUADRANT POWER Till RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper exccre detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is. greater.

With one excore detectr inoperable, the remaining three detectors shall be used for computing the avs. age.

RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from 4

when the mon tored parameter exceeds its Trip 5etpoint at the channel sensor until loss of stationary gripper coil voltage, R!bORTABLE EVEN1 1.27 A REPORT AELE EVENT shall be any of those Conditions specified in Section E0.73 to 10 CFR fart 50.

SHUTDOWN MARCIN 1.28 5HUTDOWN MARGIN shall be the instantaneous amount nf reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDAR) 1.29 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor-leased, nor otherwise controlled by the licensee.

SLAVE RELAY TEST 1

1.30 A SLAVE RELAY TEST shall be the energization of et slave relay and verification of OPERABILITY of each relay.

The SLAVE RL 1: TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

WOLF CREEK - UNIT 1 1-5 Amendment No. 42 I

OEFINITIONS SOURCE CHECK 1.32 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

l STAGGERED TEST BASIS 1.33 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains, or other designaied components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.34 THERMAL POWER shall be the total core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.35 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip' Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shc:1 include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE 1.36 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.37 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, com-mercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.38 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or partic-ulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Features (ESF) Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

WOLF CREEK - UNIT 1 1-6

_ _ _ _ _ - _.~. _

1 9

l INSTRUMENTATION LOOSE-PART DETECTION SiSTEM LIMITING CONDITION'FOR OPERATION l

3.3.3.9 TheLoose-ParkDetectionSystemshallbeOPERABLE, APPLICABILITY:

MODES 1 and 2.

ACITON:

i a.

With one or more Loose-Part Detection System channels inoperable for more than 30 day 5, prepare and submit a Special Report to the Commission pursuant to specification 6.9.2 within the next 10 days outlining the carse of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

l b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each channel of the Loose-Part Detection System shall be demonstrated OPERABLE tj performance of:

a.

A CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint l

at least once per 31 days, and c.

A CHANNEL CALIBRATION at least once per 18 months.

i L

l WOLF CREEK - UNIT 1 3/4 3 Amendment No. 15-l

e INSTRUMENTATION l

EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.5 are not exceeded.

APPllCABILITY:

As shown in Table 3.3-13.

ACTION:

a.

With an explosive gas monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With less tnan the minimum number of explosive gas monitoring instru-mentation channels OPERABLE, take the ACTION show i in Table 3.3-13.

Restore the inoperable instrumentation to 0FTlad;7 status within 30 days, and, if unsuccessful, prepare and subret a,pecial Report to the Commission pursuant to Specification 6.'.2 te axplain why this inoperability was not corrected in a timely 7.2hne:.

c.

The provisions of Specification 3.0,3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRA110N and ANALOG CHANNEL OPERATIONAL TEST at the f requencies shown in Table 4.3-9.

(

WOLF CREEK - UNI' 1 3/4 3-58 Amendment No. IE, 42 l

k TABLE 3.3-13

+

EXPLOSIVE GAS MONITORING INSTRtiMENTATION G

c)

MINIMUM CHANNELS 2

INSTRUMENT OPERABLE APPLICABILITY ACTION l.

x e

1.

(Not Used)

C5 i

2.

WASTE GAS HOLDUP SYSTEM Explosive Gas

~

Monitoring System f

a.

Hydrogen Honitor 1/Recombiner 4a b.

Oxyge : !1oniter 2/Recembiner 42 i

l i

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a#

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TABLE 3.3-13 (Continued)

- During WASTE GAS HOLDUP SYSTEM operation.

ACTION STATEMENTS ACTION 38 - (Not Used)

ACTION 39 - (Not Used)

ACTION 40 - (Not Used)

ACTION 41 - (Not Used)

ACTION 42 - With the Outlet Oxygen Monitor channel inoperable, operation of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Vith both oxygen channels or both the inlet oxygen ana inlet hydrogen channeis inoperable, suspend oxygen supply to the recombiner, I,ddition of waste gas to the system may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations, ACTION 43 - (Not Used)

ACTION 44 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner, WOLF CREEK - UNIT 1 3/4 3-60 Amendment No,15, 42

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WOLF CREEK - Jili 1 3/4 3-61 Amendment No.

IB, 42

TADt t 4.3 9 (Continued)

T ABtr NOT ATIONS

" During WASTE GA5 HOLOUP SYSTEM operation.

(1) (Not Used)

(2) (Not Used)

(3) (Not Used)

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a non,inel:

One volun.c percent hydrogen, balance nitrogen and a.

b.

Four vobime percent hydrogen, balance nitrogen.

(B) The CHANNEL CAllBRATION shall include the use of standard gas samples containing a honinal:

One volume percent oxygen, balance nitrogen, anc a.

b.

Four volume percent oxygen, balance nitrogen.

(Cf The CHANNEL CAllDRATION shall include the use of standard gas samples containing a nominal:

a.

10 ppn, by volutu oxygen, balance ni.* ogen, and b.

60 ppm by volun oxygen, balance nitrogen.

WOLF CREEK - UNIT 1 3/4 3-62 Amendnent No. ZE, 42

I i

INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTfCTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY:

MDDES 1, 2,* and 3.*

ACTION:

a.

With one stop valve or one governor valve per high pressure turbine steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoper*

alle, restert the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or close at least one valve in the affected steam lines or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the above rtquired Turbine Overspeed Protection System otherwise inoptrable, within 0 hours0 days 0 hours 0 weeks 0 months isolate the turbine from the steam supply.

SURVEILLAN;f REQUIREMfhT5 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4. 3. 4. 2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a.

At least once per 7 days by cycling each of the following valves through at least one complete cycle from the running position:

1) four high pressure turbine stop valves, 2)

Six low pressure turbine reheat stop valves, and 3)

Six low pressure turbine reheat intercept valves, b.

At least once per 31 days by cyclir.g each of the four high pressure main turbine governor valves through at least one complete cycle from the running position; c.

At least once per 31 days by direct observation of the movement of each of the above valvos througi, one complete cycle from the running position; l

d.

At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems; and e.

At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion; i

Not applicable in MODE 2 or 3 with all main steam line isolation valves and associated bypass valves in the the closed position and all other steam flow paths to the turbine isolated.

WOLF CREEK - UNIT I 3/4 3-63 Amendment No. 15, 42

i j

l j

3/4.11_ RADIDACTIVE [FFLUfNTS j

3/4.11.1 LIQUID EFFLUENT!

LIQUID HOLDUP TANKS i

L]MITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the f ol-lowing unprotected outdoot tants shall be limited to less than or equal to 100 i

Curies, excluding tritium and dissolved or entrained noble gases.

a.

Reactor Mateup Water Storage Tank, b.

Refueling Weter Storage Tank, c.

Condensate Storage Tant, and d.

Outside ten;porary tarks, *xcluding demineralizer vessels and lir,ers being used te solid'fy radioactive wastcs.

A0 PLICA 01LITY:

At all tine.

ACTION:

I a.

With the quantity of radioactive material in any of ttA above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tant contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.3. 7.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determi-M to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank.

1 i

1 WOLF CREEK - UNIT 1 3/4 11-1 Amendment No. 42

O RAD 10ACT!V[ EFFLUENT 5 3/4.13.2 GASEOUS EfrLUEN15 EXPLOSIVE GA5 MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 34 tiy volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABillTY:

At all tirres.

ACTION:

a.

With the concentration of oxygen in the WASTE GAS HOLDUP SY51Et.'

greater than 31 by volume but less than or equal to 4% try volun e, reduce the oxygen concentratior to the above limits within 4E hours, b.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSilt.'

greater than 41 by volun,e and the hydrogen concentration greater than 4% by volurre, immediately suspend all additions of waste gases to the system and reduce the concentration of oxvgen to less than or equal to 4% by volume, then take AC110N a. abo.e.

c.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUF l

SYSTEM shall be determined to be within the above limits by continuously monitorin0 the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11, i

l l

l WOLF CREEK - UNIT 1 3/4 11-2 Amendment No. 42

-.m. _ _ _

m._

l

)

1 3

1 RADIDACTIVE EFFLUEN15 j

1 GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 2.5 x 106 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABillTY:

At all times.

ACTION.

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the tant contents to within the. limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Rellase Report, pursuant to Specification 0.9.1.7.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVtlLLANCE REOUlREMENTS 4

4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days when radioactive materials are being added and within 7 days following any 3

addition of radioactive material to the tank.

1 1

4 t

WOLF CREEK - UNIT 1 3/4 11-3 Amendment No. 42

)

I t

INTENTIONALLY BLANK SECTION 3/4.12 DELETED IN ITS ENTIRETY WO;.F CREEK - UNIT 1 3/4 12-1 Amendment No. 42

)'

/

i.

!N5TRUMLNTAl10N BASES l

i 3/4.3.3.4 METEOROLOG1 cal INSTRUMENTAT10N The OPERABILITY of the rteteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive l

materials to the atmosphere.

This capability is requhed to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Progran.5," February 1972.

3/4.3,3.b RFMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the Remote Shutdown System ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room and that a fire will not. preclude achieving safe shutdtsn.

The Remote Shutdown System transfer switches, power circuits, and control circuits are independent of areas whert a fire could damage systens normally used to shut down the reactor.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 3 and 19 and Appendix R of 10 CfR 1

Part 50.

3/4.3.3.6 ACCIDENT M3N!TORING INSTRUMENTAT10N The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent 2

withtherecommendationsofRegulator) Guide 1.97, Revision 2," Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and following an Accident," December 1980 and NUREG 0737, " Clarification of TMI Action Plan Requirernents," November 1980.

3/4.3.3.7 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 1

protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95. " Protection of Nuclear Power Plant Control Room i.

Operators _Against an Accidental Chlorine Release," Revision 1. January 1977.

3/4.3.3.8 DELETED i-WOLF CREEK - UNIT 1 B 3/4 3-5 Amendment No. 15 l

j y

i i

INSTRUMENTATION BASE $

3/4.3.3.9 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant 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-Water-Cooled Reactors," May 1981.

3/4.3.3.30 DELETED 1

3/4.3.3.12 DELETED 3/4. 3. 4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed pro-tection instrumentation and the turbine speed control valves are OPERABL[ end will protect the turbine from ex:essive overspeed.

Although the orientation of the turbine is such that the number of potentially damaging missiles which could impact and damage safety-related components, equipment, or structures is minimal, protection from excessive turbine overspeed is required.

l l

l WOLF CREEK - UNIT 1 B 3/4 3-6 Amendment No. 25, 42

l J

j 4

l l

3/4.11 RAD 10ACT]VI EFFLUEN1.

BASES 3/4.11.1 LIQUID EFFLUENTS l

3/4.11.1.1 DFLETED 3/4.11.1.2 DELETED 3/4.11.1.3 DELETED 3/4.12.1.4 LIOUIE HDtD& TANL5 The tants listed in this specification include all those outdoor radwaste tanks that are not surrounded b, liners, dikes, or walls capable of holding the tank contents and th6t do not have tant overflows and surrounding area drains connected to the Liquid Radwa>te Treatment System.

Restricting the cuantity of radioactive material contained in the specifiec tan 6s provides assurance that in the event of an uncontrolled release of the tanks ' cnr. tents, the r(sulting concentrations would be less than the limits of 10 CFR Part 2D, Appencix B, lable II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.2 GASEOUS EFFLUENTS 3/4.1L 2.1 DELETED 3/4.11.2.2 DELETED 3/4.11.2.3 DELETED 3/4.11.2.4 DELETED 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen.

Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.

These automatic control features include isolation of the source of hydrogen and/or oxygen.

Maintaining the concentration of hydrogen and oxygen below their flammability l

limits provides assurance that the releases of radioactive materials will be I

controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part $0.

WOLF CREEK - UNIT I B 3/4 11-1 Amendment No. 42

D e

RADIOACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem.

This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leal or Failure," in NUREG-0800, July 1981.

3/4.11.3 DELETED 3/4.11.4 OtLFTED WOLF CREEK - UNIT 1 B 3/4 11-2 Amendment No. 42 l

t I

3/4.12 RADIOLOGICAL ENVIRONMENTAL MON!10 RING BASES l

3/4.12.1 DELETED 3/4.12.2 del [TfD c

3/4.12.3 DflEllD l

WOLF CREEK - UNil 1 0 3/4 12-1 Amendment No. 42

.. ~ -

4 s

@MINISTRAllVi CONIROL5 PROCEDURE S AND PROGRAMS (Continued) e.

Radioactive E f fluent Controls Program A program shall be provided conf orming with 10 CF R 50.36a f or the control of radioactive effluents and for maintaining the doses to MEMBERS Of lHE PUBLIC frort radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implerient ed by operating procedures, and (3) shall include remedial acticns to t>e taken whenever the program limits are exceeded.

The progran, shall include the following elements:

1)

Limitations on the operability of radioactive liquid ami gaseDut monitoring instrumentation including surveillance tests and I

setrcint deterroindtion in accordance with methodology in the

ODCM, 2)

Limitations on the concentrations of radioactive material releated in liouid effluents to UNRESTR]CTED AREAS conforming to 10 CIR Part A, Appendim 0, Table II, Column 2, 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CfR 20.106 and with the inethodology anc parameters in the ODCM, 4)

Limitat ions on the annual and quarterly doses or dose cornmitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid offluents released to UNRESTRICTED AREAS conforming to Appendix 1 l

to 10 CF R Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive eff'4ents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50, 7)

Limitations of the dose rate resulting from radioactive material released in gaseous ef fluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B Table 11, Column 1, WOLF CREEA - UNIT 1 6-17 Amendtnent No. 42

O O

ADMINISTRATIVi_ CONTROL 5 PROCEDURES AND PROGRAMS (Continued, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CfR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER Of THE PUBLIC from lodine-131 Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released it 'reas beyond the SITE BOUNDARY conforming to Apptndii 1 to 10 C; iart 50, 10)

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190, f.

Radiological Environmental Monit:

ing Program A progra" shall bt provided to monitor the radiation and radionuclidet in the environs of the plant.

The program shall provide (1) repre-sentative reasurements of radioactivity in the highest potential exposure path ays, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendia I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and the modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in an Interlaboratory Comparison Program to ensure that independent cFecks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.9 REPORT]NG REQUIREMENTS ROUTINE REPORTS

6. 9.1 In addition to the applicable reporting requirements of Title 10, Code of federal Regulations, the following reports shall be submitted to the Regional Administrator of the NRC Regional Office unless otherwise noted.

WOLF CREEK UNIT 1 6-18 Amendment No. 42

4 ADMINI$TRATlvE CONTROLS STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following:

(1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6. 9.1. 2 The Startup Report shall address each of the tests identified in the Final Safety Analysis Report FSAR and shall include a description of the measurtd values of the op rating conditions or characteristics obtained duting the test prografn and a cortpatisoi of these values with design predictions and specifications.

Any corrective ACTIONS that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in licenso conditions based on other commitrtents shall be includeo in this report.

6.9.1.3 Stsrtu; Reports shall be submitted within:

(1) 90 days following cocpletion of the Startup Test Program, (2) 90 days following resumption of commencement of commercial power operation, or (3) 9 months following initial criticality, whichevet is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program,

?'id resumption or commencement of commercial operation) supplementary reports stall be submitted at least esery 3 months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual Reports covering the activities of the Unit as described below for the previous calendar year shall be submitted prior to March I of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6. 9.1. 5 Reports required on an annual basis shall include:

a.

Tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLO, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions; and

This tabulation supplements the requirements of S20.407 of 10 CFR part 20.

l WOLF CREEK UNIT 1 6-19 Amendment No. 42

\\

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) b.

Documentation of all challenges to the PORVs or safety valves.

c.

The results of specific activity analysis in which the primary coolant esceeded the limits of Specification 3.4.8.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded.

(2) Results of the last isotopic analysis for radiciodine perfortred prior to exceeding the limit, results of analysis while limit was exceeded and resvits of one analysis after the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radiciodire concentrations; (3) Clean up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time fer the duration of the specific activity I

above the steady-state level; and (b) The tirce duration when th(

specific activity of the primary coolant exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the 00CM and (2) Sections IV.8.2, IV.8.3, and IV.C of Appendix 1 to 10 CFR Part 50.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section 1u.9.1 of Appendix 1 to 10 CFR Part 50.

MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D C.

20555, with a copy to the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.

WOLF CREEK UNIT 1 6-20 Amendment No. 42

l e

ADMINISTRATIVI CONTROLS RADIAL PEAK]NG FACTOR LIMIT REPORT

6. 9.1. 9 The F,y limits.for RATED THERMAL POWER (F

) shall be pravided to the NRC Regional Adrrinistretor with a copy to Director of Nuclear Reactor Regulation, Attention:

Chief, Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555 for all core planes containing Bant "D" control rods and all unroddea core planet and the plot of predicted (f

.Ppp)) vs Arial Core q

Height with the limit envelope at least 60 days prior to each cycle initial criticality unless otherwise approved by the Commission by letter.

ln addition, in the event that the limit should change requiring a new submittal or an amended submittal to the Pealing factor limit Report, it shall be submitted 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter.

Any information needed to support f

will be by request from the NRC and need not be included in this report.

SPECIAL REPOR15 6.9.2 Special reports snn11 be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

6.10 RECORD RETENTION in addition to the applicable record retention requirements of Title 10. Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least 5 years:

a.

Recoros and logs of unit operation covering time interval at each power level; b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety; c.

All REPORTABLE EVENTS; d.

Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e.

Records of changes made to the procedures required by Specification 6.8.1; f.

Records of radioactive shipments; g.

Records of sealed source and fission detector leak tests and results; and h.

Records of annual physical inventory of all sealed source material of record.

WOLF CREEK UNIT 1 6-21 Amendment No. 42

e ADMIN 15TRA11VE CONTROLS RECORD RETENTION (Continued) 6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the final Sefety Analysis Report; b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories; c.

Records of radiation exposure for all individuals entering radiation control areas; d.

Records of gaseous and liquid radioactive material released to the environt; e.

Records of transient or operational cycles for those Unit components identified in lable 5.7-1; f.

Records of reactor tests and experiments; g.

Records of training and qualification for current members of the Unit Staff; h.

Records of in-service inspections performed pursuant to these Technical Specifications; i.

Records of Quality Assurance activities required by the QA Manual; j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.b9; L.

Records of meetings of the PSRC and the NSRC; 1,

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; m.

Records of secondary water sampling and water quality; and Records of analysis required by the Radiological Environmental n.

Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were followed.

I o.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

WOLF CREEK UNIT 1 6-22 Amendment No. 42

e ADMINISTRAT]VE CONTROL 5 i

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.1? H]GH RAD}Al]ON AR[A 6.12.1 Pursuant to Paragr aph 20.203(c)(b) of 10 CFR Part 20, in lieu of the

" control device" or " alarm signal" required by Paragraph 20,203(c)(2), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mk/h et 45 cm (18 in.) from the radia-tion source ci f r om any surf ace which the r adiation penetrates shall be barri-caded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 n.R/h, provided they are otherwise f ollowing plant radiation protec-tion procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area, or D.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and persq nel have been made knowledgeable of then, or c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Site Health Physicist in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.)

from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor / Supervising Operator on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable $tay -time for individuals in that area.

In lieu of the stay time specification of the RWP, direct or remote (such as closed-circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

WOLF CREEK UNIT 1 6-23 Amendment No. 42

e t

ADMINISTRATIVE CONTROL 5 HIGH RADIATION ARIA (Continued) for individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure c6n be reasonably constructed around the individual area, that individual area sht.11 be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 0.10.2.0, lhis documentation shall contain; 1)

Sufficient information to support the change together with tia appropriate analyses at evaluations justifying the change (s) and 2)

A determination that the chance will maintain the overell conformance of the solidified waste product to existing requirements of federal, State, or other applicable regulations.

s b.

Shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager.

6.14 0FFSITE DO5E CALCULATION MANUAL (ODCM)

Changes to the ODCM; a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.0, This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the level of radicactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations, b.

Shall become effective after review and acceptance by the PSRC and the approvol of the Plant Manager, WOLF CREEK UNIT 1 6-24 Amendment No. 42

7 0

6 O

ADMINISTEATIVE CONTROL 5 0Ff slTE 005E CALCUl ATION MANUAL (ODCM) (Continued) c.

Shell t>e sutimitted to the Commission in the form of a complete, legitale copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of th-report in which any change to the ODCM was made, fach t

change shail tre identifitd tiy markings in the margin of the afftcted peges, clearly indicating the area of the page that was changt c, and shall indicate the date (e.g., nionth/ year) the change was implenented.

i I

l WOLF CREEK UNIT 1 6-25 Amendment No. 42

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ML20070D315

Text

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