ML20147C946
| ML20147C946 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/24/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147C950 | List: |
| References | |
| NUDOCS 8803030197 | |
| Download: ML20147C946 (33) | |
Text
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UNITE 38TATES I
NUCLEAR REGULATORY COMMIS$10N e
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KANSAS GAS & ELECTRIC COMPANY KAhSAS CITY POWER AND LIGHT C0hPANY KANSAS ELECTRIC _ POWER COOPERATIVE tINC.
M F CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendrent No.15 License No. NPF-42 1.
TheNuclearRegulatoryCoreission(theCommissien)hasfoundthat:
A.
The application for amendn4nt to the Wolf Creek Generating Station (the f acility) Facility Operating License No. NPF-42 filea by Kansas Gas and Electric Company acting for itself and Kansas City Power and Light Company and Kansas Electric Pcwcr Cooperative. Inc.. (licensees) dated March 2. 1987 as supplemented April 17 and October 30, 1987 ana January 8, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations ot' the Comission; C.
There is reasonable assurance:
(1) that the activities authorized by this anandment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in coapliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the concon 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 Coanission's regulations and all applicable requirecents have been satisfied.
8803030197 0B0224 PDR ADOCK 05000402 P
2-2.
Accordingly. Facility Operating License No. NPF-42 is amended as follows:
(A) Change the Technical Specifications as indicated in the attachment to this license amendment, and amend paragraph 2.C.(2) to read as follows:
(2)
Technical Specifications The Technical Specific 6tions contained in Appendix A as revised through Arrendment No.15. and the Environmental Protection Plan contained in Appendix 8. both of which are attached hereto, are hereby incorporated in the license.
KG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(B) Amend paragraph 2.C.(5)(b) to read as follows:
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(b) The itcensee may make changes to the approved fire protection i
program without prior approval of the Commission only if those i
changes would not adversely affect the ability to achieve and I
maintain safe shutdown in the event of a fire, l
(C) Deleteparagraph2.C.(5)(c).
3.
The license amendment is effective upon issuance and shall be irrplemented upon the licensee's completion of the necessary procedural changes. The licensee will notify the Commission in writing when the necessary procedural changes have been completed.
FOR THE NUCLEAR REGULATORY C0telSS10N w[ 6.
64 dW Jose A. Calvo. Director Project Directorate - IV Division of Reacter Projects - !!!.
IV. Y and Special Projects Office of huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications 04tc of Is wance: February 24, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.15 FACILITY OPERATING LICENSE N0. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages 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.
REMOVE PAGES INSERT PAGES VI VI VII VII XI XI XVII XVII 3/4 3-57 thru 3/4 3-57 (No changes, 3/4 3-76 thru 3-71 pages renumbered) 3/4 7-27 thru 3/4 7-36 3/4 7-37 3/4 7-27 (No changes, page renumbered) 3/4 7-38 3/4 7-28 (ho changes, page renumbered) 8 3/4 3-5 B 3/4 3-5 8 3/4 7-7 B 3/4 7-7 B 3/4 7-8 6-9 6-9 6-14 6-14 l
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o 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 FUNCTION 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 (Z) AS A FUNCTION OF CORE HEIGHT...
3/4 2-5 9
3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT0R.................................................
3/4 2-8 FIGURE 3.2-3 RCS TOTAL FLOW RATE VERSUS R - FOUR LOOPS IN 0PERATION.................................
3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATI0................................
3/4 2-11 3/4.2.5 DNB 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 l
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM l
INSTRUMENTATION....................................
3/4 3-14 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS......................
3/4 3-22 l
TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES.............
3/4 3-29
)
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........
3/4 3-34 l
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l WOLF CREEK - UNIT 1 V
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE r
INSTRUMENTATION (Continued) 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations................
3/4 3-39 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT 0PERATIONS................................
3/4 3-40 TABLE 4.3-3 RADIATION 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 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION............
3/4 3-51 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................
3/4 3-52 Accident Monitoring Instrumentation......................
3/4 3-53 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...
3/4 3-58 TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................
3/4 3-59 r
i WOLF CREEK - UNIT 1 VI Amendment No. 15
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE INSTRUMENTATION (Continued)
TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........
3/4 3-61 Radioactive Gaseous Effluent Monitoring Instrumentation.
3/4 3-63 TABLE 3.3-13 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION...................................
3/4 3-64 TABLE 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........
3/4 3-67 3/4.3.4 TURBINE OVERSPEED PR0TECTION.............................
3/4 3-71 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration..............................
3/4 4-1 j
Hot Standby..............................................
3/4 4-2 l
Hot Shutdown.............................................
3/4 4-3 Cold Shutdown - Loops Filled.............................
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 INSPECTION.........................
3/4 4-16 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION.......................
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 i
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l Amendment No. 15 WOLF CREEK - UNIT 1 VII 1.
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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 e
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 THERMAL 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 PR0 GRAM....................................
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 16 EFPY...........................
3/4 4-30 FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE UP TO 16 EFPY...........................
3/4 4-31 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITPDRAWAL 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 4-36 3/4.4.10 STRUCTURAL INTEGRITY.....................................
3/4 4-37 3/4.4.11 RE ACT OR COO LANT SY ST E M V E NTS.............................
3/4 4-38 3/4.5 EMERGENCY CORE COOLING SYSTEMS g
3/4.5.1 ACCUMULATORS.............................................
3/4 5-1 WOLF CREEK - UNIT 1 VIII
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE PLANT SYSTEMS (Continued)
I 3/4.7.10 DELETED TABLE 3.7-3 DELETED 3/4.7.11 DELETED 3/4.7.12 AREA TEMPERATURE M0NITORING..............................
3/4 7-27 TABLE 3.7-4 AREA TEMPERATURE M0NITORING...........................
3/4 7-28 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating................................................
3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................
3/4 8-7 Shutdown.................................................
3/4 8-8 3/4.8.2 D.C. SOURCES 0perating................................................
3/4 8-9 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.....................
3/4 8-11 Shutdown.................................................
3/4 8-12 3/4.8.3 ONSITE POWER DISTRIBUTION I
0perating................................................
3/4 8-13 Shutdown.................................................
3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices.....................................
3/4 8-16 TABLE 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES......................
3/4 8-18 l
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WOLF CREEK - UNIT 1 XI Amendment No.15
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................
3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................
3/4 9-2 3/4.9.3 DECAY TIME...............................................
3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.,.....................
3/4 9-4 3/4.9.5 COMMUNICATIONS...........................................
3/4 9-5 3/4.9.6 REFUELING MACHINE........................................
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY...............
3/4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.........................................
3/4 9-9 Low Water Level..........................................
3/4 9-10 3/4.9.9 CONTAINMENT VENTILATION SYSTEM...........................
3/4 9-11 3/4.9.10 WATER LEVEL - REACTOR VESSEL Fuel Assemblies..........................................
3/4 9-12 Control Rods................
3/4 9-13 3/4.9.11 WAT ER LEVE L - STO RAGE POO L.......,......................
3/4 9-14 3/4.9.12 SPENT FUE L ASSEMB LY STORAGE.............................
3/4 9-15 FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2........................................
3/4 9-16 3/4.9.13 EMERGENCY EXHAUST SYSTEM.................................
3/4 9-17 i
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WOLF CREEK - UNIT 1 XII l
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BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.............................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........
B 3/4 7-3 t
3/4.7.3 COMPONENT COOLING WATER SYSTEM............................
B 3/4 7-3 I
3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...........................
B 3/4 7-3 l.
3/4.7.5 U LT I MAT E H E AT S I N K........................................
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 SNUBBERS..................................................
B 3/4 7-5 l
l 3/4.7.9 SEALED SOURCE CONTAMINATION...............................
B 3/4 7-6 1
3/4.7.10 DELETED 3/4.7.11 DELETED 3/4.7.12 AREA TEMPERATURE M0NITORING...............................
B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION...............................
E 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES...................
B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................
B 3/4 9-1 l
3/4.9.2 INSTRUMENTATION...........................................
B 3/4 9-1 i
1 3/4.9.3 DECAY TIME................................................
B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................
B 3/4 9-1 WOLF CRECK - UNIT 1 XVII Amendment No.15 l
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BASES SECTION PAGE REFUELING OPERATIONS (Continued) 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 COOLANT CIRCULATION.............
B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM............................
B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P00L............................................
B 3/4 9-3 3/4.9.12 SPENT FUEL ASSEMBLY ST0 RAGE...............................
B 3/4 9-3 3/4.9.13 EMERGENCY EXHAUST SYSTEM..................................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, 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 L00PS.....................................
B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM -
SHUTD0WN.....................
B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................................
B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTES.................................
B 3/4 11-5 3/4.11.4 TOTAL 00SE...............................................
B 3/4 11-5 3/4.12 RADIOACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.......................................
B 3/4 12-1 3/4.12.2 LAND USE CENSUS..........................................
B 3/4 12-1 3/4.12.3 iNTERLABORATORY COMPARISON PR0 GRAM.......................
B 3/4 12-2 WOLF CREEK - UNIT 1 XVIII i
INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.9 The Loose-Part Detection System shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACITON:
a.
With one or more Loose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
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 by performance of:
a.
A CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint at least once per 31 days, and c.
A CHANNEL CALIBRATION at least once per 18 months.
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WOLF CREEK - UNIT 1 3/4 3-57 Amendment No.15
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INSTRUMENTATION i
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
\\
LIMITING CONDITION FOR OPERATION j
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3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The Alarm /
Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL i
(ODCM).
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l APPLICABILITY:
At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the i
channel inoperable.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7, why this inoperability was not corrected within the time specified.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequen-cies shown in Table 4.3-8.
WOLF CREEK - UNIT 1 3/4 3-58 Amendment No.15
TABLE 3.3-12 g
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION r-MINIMUM E
CHANNELS E
INSTRUMENT OPERABLE ACTION
[
1.
Radioactivity Monitors Providing Alarm and z
Automatic Termination of Release
[
a.
Liquid Radwaste Discharge Monitor (HB-RE-18) 1 31 b.
Steam Generator Blowdown Discharge Monitor (BM-RE-52) 1 32 c.
Turbine Building Drain Monitor (LE-RE-59) 1 32 d.
Secondary Liquid Waste System Monitor (HF-RE-45) 1 33 2.
Flow Rate Measurement Devices a.
Liquid Radwaste Discharge Line
(
y
- 1) Waste Monitor Tank A Discharge Line 1
34
- 2) Waste Monitor Tank B Discharge Line 1
34 b.
Steam Generator Blowdown Discharge Line 1
34 c.
Secondary Liquid Waste System Discharge Line 1
34 h"
2 a~
TABLE 3.3-12 (Continued)
ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for principle gamma emitters and I-131 at a lower limit of detection as specified in Table 4.11-1:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.
WOLF CREEK - UNIT 1 3/4 3-60 Amendment No. 15 l
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TABLE 4.3-8 g
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS G
ANALOG E
CHANNEL El CHANNEL SOURCE CHANNEL OPERATIONAL
'[
INSTRUMENT CHECK CHECK CALIBRATION TEST E
1.
Radioactivity Monitors Providing i
il Alarm and Automatic Termination e.
of Release 1
1 a.
Liquid Radwaste Discharge Monitor D
P R(2)
Q(1) 1 (HB-RE-18) b.
Steam Generator Blowdown Discharge D
M R(2)
Q(1)
Monitor (BM-RE-52) u, c.
Turbine Building Drain Monitor 3
(LE-RE-59)
D M
R(2)
Q(1) u, l
in d.
Secondary Liquid Waste System D
P R(2)
Q(1)
Monitor (HF-RE-45) 2.
Flow Rate Measurement Devices a.
Liquid Radwaste Discharge Line D(3)
N.A.
R N.A.
b.
Steam Generator Blowdown Discharge Line 0(3)
N.A.
R N.A.
c.
Secondary Liquid Waste System D(3)
N.A.
R N.A.
$[
Discharge Line E
B n
TABLE 4.3-8 (Continued)
TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions exists:
a.
Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or b.
Circuit failure (alarm only), or c.
Instrument indicates a downscale failure (alarm only), or d.
Instrument controls not set in operate mode (alarm only).
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source.
For subsequent CHANNEL CALIBRATION, NBS trace-able standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source standard traceable to NBS.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
WOLF CREEK - UNIT 1 3/4 3-62 Amendment No.15
(
INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous effluent 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 3.11.2.1 and 3.11.2.5 are not exceeded.
The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY:
As shown in Table 3.3-13.
ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.
b.
With less than tne minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3.3-13.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Specifica-tion 6.9.1.7, why this inoperability was not corrected within the time specified.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequen-cies shown in Table 4.3-9.
WOLF CREEK - UNIT 1 3/4 3-63 Amendment No.15
'T TABLE 3.3-13 g
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION q
n MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 7
1.
WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System e*
a.
Hydrogen Monitor 1/recombiner 44 b.
Oxygen Monitor 2/recombiner 42 2.
Unit Vent System Noble Gas Activity Monitor - Providing 1
a.
40 Alarm (GT-RE-21) y b.
Iodine Sampler 1
43 s
y c.
Particulate Sampler 1
43 m
^
d.
Flow Rate N.A.
45 e.
Sampler Flow Rate Monitor 1
39 3.
Containment Purge System a.
Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (GT-RE-22,GT-RE-33) 1 41 E
b.
Iodine Sampler 1
43 R
A c.
Particulate Sampler 1
43 z
?
d.
Flow Rate N.A.
45 e.
Sampler Flow Rate Monitor 1
39
+"
TABLE 3.3-13 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION g
r-MINIMUM CHANNELS k
INSTRUMENT OPERABLE APPLICABILITY ACTION 4.
Radwaste Building Vent System E
a.
Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (GH-RE-10) 1 38, 40 ea 43 b.
Iodine Sampler 1
43 c.
Particulate Sampler 1
45 d.
Flow Rate N.A.
39 e.
Sampler Flow Rate Monitor 1
Y F
R 8n O.
}
TABLE 3.3-13 (Continued)
TABLE NOTATIONS
- At all times.
- During WASTE GAS HOLDUP SYSTEM operation.
ACTION STATEMENTS ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:
a.
At least two independent samples of the tank's contents are analyzed, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With both oxygen channels or both the inlet oxygen and inlet hydrogen channels inoperable, suspend oxygen supply to the recombiner.
Addition of waste gas to the system may contique provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.
ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sample equipment as required in Table 4.11-2.
ACTION 44 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirements, suspend oxygen supply to the recombiner.
ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements.
WOLF CREEK - UNIT 1 3/4 3-66 Amendment No.15
TABLE 4.3-9
-RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 6
i I
ANALOG n
A CHANNEL MODES FOR WHICH E
CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED f
C l
1.
WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System t
- a. Inlet Hydrogen Monitor D
N.A.
Q(4)
M I
- b. Outlet Hydrogen Monitor D
N.A.
Q(4)
M
- c. Inlet Oxygen Monitor D
N.A.
Q(5)
M
- d. Outlet Oxygen Monitor 0
N.A.
Q(6)
M 2.
Unit Vent System E
l
- a. Noble Gas Activity Monitor-D M
R(3)
Q(2)
T Providing Alarm (GT-RE-21) m
- b. Iodine Sampier W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate N.A.
N.A.
R(7)
N.A.
l
- e. Sampler Flow Rate Monitor D
N.A.
R Q
3.
Containment Purge System
- a. Noble Gas Activity Monitor -
p Providing Alarm and Automatic Termination of Release k
(GT-RE-22,GT-RE-33)
D P
R(3)
Q(1) 5
- b. Iodine Sampler W
N.A.
N.A.
N.A.
2 l
P
- c. Particulate Sampler W
N.A.
N.A.
N.A.
C
- d. F1ow Rate N.A.
N.A.
R(7)
N.A.
- e. Sampler Flow Rate Monitor D
N.A.
R N.A.
(p TABLE 4.3-9 (Continued)
!?
RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTP.UMENTATION SURVEILLANCE REQUIREMENTS ANALOG e,
N?
CHANNEL MODES FOR WHICH g;
CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED
~
C sg 4.
Radwaste Building Vent System
- a. Noble Gas Activity Monitor -
D, P M, P R(3)
Q(1)
Providing Alarm and Automatic Termination of Release (GH-RE-10)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate N.A.
N.A.
R(7)
N.A.
}g 4>
- e. Sampler Flow Rate Monitor D
N.A.
R N.A.
3I a
8 n
-n-,
v
4 TABLE 4.3-9 (Continued)
TABLE NOTATIONS
- At all times.
- During WASTE GAS HOLOUP SYSTEM operation.
i (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation as appropriate occur if any of the following conditions exists:
a.
Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or b.
Circuit failure (alarm only), or c.
Instrument indicates a downscale failure (alarm only) or l
1 d.
Instrument controls not set in operate mode (alarm only).
(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any one or combination of the following conditions exists:
l a.
Instrument indicates measured levels above the Alarm Setpoint b.
Circuit failure c.
Instrument indicatar a downscale failure d.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source.
For subsequent CHANNEL CALIBRATION, NBS traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source traceable to NBS.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
One volume percent hydrogen, balance nitrogen, and b.
Four volume percent hydrogen, balance nitrogen.
WOLF CREEK - UNIT 1 3/4 3-69 Amendment No. 15
TABLE 4.3-9 (Continued)
TABLE NOTATIONS (Continued)
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
One volume percent oxygen, balance nitrogen, and b.
Four volume percent oxygen, balance nitrogen.
(6) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
10 ppm by volume oxygen, balance nitrogen, and b.
80 ppm by volume oxygen, balance nitrogen.
(7)
If flow rate is determined by exhaust fan status and fan performance I
curves, the following surveillance operations shall be performed at least once per 18 months:
a.
The specific vent flows by direct measurement, or l
l b.
The differer.tial pressure across the cxhaust fan and vent flow established by the fan's "flow-AP" curve, or c.
The fan motor horsepower measured and vent flow established by the l
fan's "flow-horsepewer" curve.
l WOLF CREEK - UNIT 1 3/4 3-70 Amendment No.15
INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
APPLICABIt.ITY:
MODES 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-able, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS
- 4..'. 4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required Turbine Overspeed Protsetion System shall oe 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 cycling 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 valves through one complete cycle from the running
(
position; 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 i
the above valves and performing a visual and surface inspection of l
valve seats, disks and stems and varifying no unacceptable flaws or corrosion.
l l
- Not applicable in MODE 2 or 3 with all main steam line isolation valves and I
associated bypass valves in the the closed position and all other steam flow paths to the turbine isolated.
WOLF CREEK - UNIT 1 3/4 3-71 Amendment No.15
PLANT SYSTEMS 3/4.7.12 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 3.7.12 The temperature limit of each area given in Table 3.7-4 shall not be exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or by more than 30*F.
APPLICABILITY: Whenever the equipment in an affected area is required to be OPERABLE.
ACTION:
a.
With one or more areas exceeding the temperature limit (s) shown in Table 3.7-4 for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that provides a record of the cumulative time and the amount by which the temperature in the affected area (s) exceeded the limit (s) and an analysis to demonstrate the continued OPERABILITY of the affected equipment.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
Witn one or more areas exceeding the temperature limit (s) shown in Table 3.7-4 by more than 30*F, prepare and submit a Special Report as required by ACTION a. above, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either restore the area (s) to within the temperature limit (s) or declare the equipment in the affected area (s) inoperable.
SURVEILLANCE REQUIREMENTS 4.7.12 The temperat'.are in each of the areas shown in Table 3.7-4 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
WOLF CREEK - UNIT 1 3/4 7-27 Amendment No. 15
TABLE 3.7-4 AREA TEMPERATURE MONITORING MAXIMUM TEMPERATURE AREA LIMIT (*F) 1.
ESW Pump Room A 119 2.
ESW Pump Room B 119 3.
Auxiliary Feedwater Pump Room A 119 4.
Auxiliary Feedwater Pump Room B 119 5.
Turbine Driven Auxiliary Feedwater Pump Room 147 6.
ESF Switchgear Room I 87 7.
ESF Switchgear Room II 87 8.
RHR Pump Room A 119 9.
RHR Pump Room B 119 10.
CTMT Spray Pump Room A 119 11.
CTMT Spray Pemp Room B 119
[
12.
Safety Injection Pump Room A 119 l
13.
Safety Injection Pump Room B 119 14.
Centrifugal Charging Pump Roosa A 119 15.
Centrifugal Charging Pump Room B 119 16.
Electrical Penetration Room A 101 17.
Electrical Penetration Room B 101 18.
Component Cooling Water Room A 119 19.
Component Cooling Water Room B 119 20.
Diesel Generator Room A 119 21.
Diesel Generator Room B 119 I
22.
Control Room 84 WOLF CREEK - UNIT 1 3/4 7-28 Amendment No.15 i
INSTRUMENTATION BASES 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological 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 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 and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUT 00WN INSTRUMENTATION The OPERABILITY of the Remote Shutdown System ensures that suffielent capability is available to permit r,hutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room and that a fire will not preclude achieving safe shutdown.
The Remote Shutdown System transfer switches, power circuits, and control circuits are independent of areas where a fire could damage systems 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 Part 50.
3/4.3.3.6__AC_CIDENT MCNITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures th&t sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recomendations of Regulatory 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 Requirements," 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 protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," Revision 1, January 1977.
3/4 1 3.8 DELETED WOLF CREEK - UNIT 1 B 3/4 3-5 Amendment No.15
INSTRUMENTATION BASES 3/4.3.3.9 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY cf 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.
3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The Alarm /
Trip Setpoints for these instruments shall be calculated and adusted 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.
3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITCRING INSTRUNENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the reieases of radioactive materials in gaseous t
effluents during actual or potential releases of gaseous effluents.
The Alarm / Trip Setpoints for these instruments shall be adjusted to values calculated in accordance with tha 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 instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS H0 LOUP SYSTEM.
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 sensitivity of any noble gas activity monitor used to show compli-ance with the gaseous effluent release requirements of Specification 3.11.2.2 shall be such that concentrations as low as 1 x 10 8 pCi/cc are measurable.
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 valvet are OPERABLE and will protect the turbine from excessive overspeed.
Although the orientation i
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.
WOLF CREEK - UNIT 1 B 3/4 3-6 Amendment No. 15
PLANT SYSTEMS BASES SEALED SOURCE CONTAMINATION (Continued)
Sealed sources are classified into three groups according to their use, with Surveillance Requirements 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 or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.10 DELETED 3/4.7.11 OELETED i
3/4.7.12 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 a loss of its OPERABILITY.
The temperature limits include an allowance for instrument error of 13*F.
WOLF CREEK - UNIT 1 B 3/4 7-7 Amendment No. 15
ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) k.
Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL and the Radwaste Treatment Systems, and 1.
Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Plant Manager and to the Nuclear Safety Review Committee.
m.
Review of the Fire Protection Program and shall submit recommended changes to the Nuclear Safety Review Committee.
6.5.1.7 The PSRC shall:
a.
Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6a. through d. and m. above, l
b.
Render determinations in writing with regard tc whether or not each item considered under Specification 6.5.1.6a. through e. above constitutes an unreviewed safety question, and c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President Nuclear Operations and the Nuclear Safety Review Committee of dis-agreement between the PSRC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.
I RECORDS 6.5.1.8 The PSRC shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activities performed under the responsibility provisions of these Technical Specifications.
Copies shall be provided to the Vice President Nuclear Operations and the Nuclear Safety Review Commntee.
6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)
FUNCTION 6.5.2.1 The NSRC shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, d.
Metallurgy, i
e.
Instrumentation and control, f.
Radiological safety, WOLF CREEK UNIT 1 6-9 Amendment No. 4, 15
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
Process Control Program implementation; e.
f.
ODCM implementation; and g.
Quality Assurance Program implementation for effluent and environ-mental monitoring.
h.
Fire Protection Program implementation.
l Major Procedures, supported by appropriate Minor Procedures (such as checkoff lists, operating instructions, data sheets, alarm responses, etc.), shall be provided for the above activities.* A Major Procedure is a procedure which con-trols safety related activities, and establishes one or more basic controls, overall responsibilities, authority assignments or administrative and opera-tional ground rules at the Wolf Creek plant.
Major Procedures are written to meet the requirements of ANSI N18.7-1976/ANS 3.2 and generally are supported by Minor Procedures which provide delineation of details such as fur valve lineups, calibration procedures, operating instructions, data sheets, alarm responses, and other procedures identified as "supporting." Major Procedures require sig-nature approval in all cases by the Plant Manager or a Call Superintendent in his absence. A Minor Procedure is a procedure which controls safety-related activitiesinsupportofaMajorProcedure.
It addresses a specific topic or sub-topic established by its parent' Major Procedure, expanding on it by pro-viding working level instructions.
Minor Procedures are not permitted to con-tradict requirements contained in their governing Major Procedure.
Minor Procedures require signature approval by the Plant Manager, or a Call Super-intendent in his absence, only at Revision '0.'
6.8.2 Approval of Procedures a.
All Major Procedures of the categories listed in Specification 6.8.1 and modifications to the intent thereof shall be reviewed by the PSRC and approved by the Plant Manager prior to implementation and reviewed periodically as set forth in Administrative Procedures.
b.
Minor Procedures (checkoff lists, operating instructions, data sheets, alarm responses, chemistry and analytical procedures, technical instructions, special and routine maintenance procedures, laboratory manuals, etc.) shall, prior to initial use, be approved by the PSRC or a Subcommittee thereof.
c.
Corporate Emergency Plan implementing procedures shall be reviewed by appropriate corporate and plant personnel and approved by the Presi-dent and Chief Executive Officer as set forth in General Procedures.
- With the exception of Corporate Emergency Plan implementing procedures.
4 Corporate Emergency Plan implementing procedures shall be provided but shall not be designated as major or minor procedures.
WOLF CREEK UNIT 1 6-14 Amendment No.4,15
_