ML20141H937
| ML20141H937 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/23/1997 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141H941 | List: |
| References | |
| GL-91-08, GL-91-8, NPR-42-A-108, NUDOCS 9708040113 | |
| Download: ML20141H937 (18) | |
Text
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n.us4 3
UNITED STATES l
,j NUCLEAR REGULATORY COMMISSION R
WASHINGTON, D.C. 20066 4001 o
- ...+
WOLF CREEK NUCLEAR OE RATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the i
Wolf Creek Nuclear Operating Corporation (the Corporation), dated February 17. 1997, 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:
amended, the provisions of the Act and the rules and regulations of B.
The facility will operate in conformity with the application, as the Commission:
C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:
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.
9708040113 970723 PDR ADOCK 05000482 P
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I 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby j
amended to read as follows:
2.
Technical Soecifications
?
The Technical Specifications contained in Appendix A as revised through Amendment No.108, 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.
In addition, the license is amended to add paragraph 2.C.(15) to Facility Operating License No. NPF-42 as follows:*
(15) Additional Conditions The Additional Conditions contained in Appendix D. as revised through Amendment No.108, are hereby incorporated into this license. Wolf Creek Nuclear Operating Corporation shall operate the facility in accordance with the Additional Conditions.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
Implementation of the license amendment shall include the relocation of certain technical specifications requirements to the appropriate licensee-controlled document as described in the licensee s application dated February 17. 1997, and evaluated in the staff's safety evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
[.
ames C. Stone. Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachments:
1.
Changes to the Technical Specifications 2.
Pages 6 and 7 to License Appendix D 3.
AdditionaiConditions Date of Issuance:
July 23, 1997
- Pages 6 and 7 are attached, for convenience for the composite license to reflect this change.
2
ATTACHMENT TO LICENSE AMENDMENT NO. 108 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following Jages of the Appendix A Technical Specifications with the attached pages. T1e revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT IX IX 1-2 1-2 3/4 6-1 3/4 6-1 3/4 6-16 3/4 6-16 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-25 3/4 6-26 3/4 6-27 3/4 6-28 3/4 6-29 3/4 6 30 B 3/4 6-4 8 3/4 6-4
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5.2 ECCS SUBSYSTEMS - T.,, > 350 F.
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T.,, < 350 F...
3/4 5-7 3/4.5.4 ECCS SUBSYSTEMS - T,, s 200 F..................
3/4 5-9 3/4.5.5 REFUELING WATER STORAGE TANK.......
3/4 5-10 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity...
3/4 6-1 Containment Leakage.
DELETED Containment Air Locks.
3/4 6-4 Internal Pressure.
3/4 6-6 Air Temperature.
3/4 6-7 Containment Vessel Structural Integrity.
DELETED Containment Ventilation System.....
3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.........
3/4 6-13 Spray Additive System...
3/4 6-14 Containment Cooling System..
3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.
3/4 6-16 TABLE 3.6-1 DELETED l
3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers...
DELETED Hydrogen Control Systems..
3/4 6-31 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.
3/4 7-1 WOLF CREEK - UNIT 1 IX Amendment No. 89.108
y 4
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PXaE i
TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE l
STEAM LINE SAFETY VALVES DURING FOUR LOOP 0PERATION..........................................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 '
Auxiliary Feedwater System...............................
3/4 7-4 i
Condensate Storage Tank..................................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY f
SAMPLE AND ANALYSIS PR0 GRAM.........................
3/4 7-8 3
Main Steam Line Isolation Va1ves.........................
3/4 7-9
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Steam Generator Atmospheric Relief Valves...............
.3/4 7-9a l
i Main Feedwater System...................................
3/4 7-10 l
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
DELETED 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 l
1 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...........................
3/4 7-12 t
3/4.7.5 ULTIMATE HEAT SINK.......................................
3/4 7-13 i
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................
3/4 7-14 j
3/4.7.7 EMERGENCY EXHAUST SYSTEM.................................
3/4 7-17 3/4.7.8 SNUBBERS.................................................
DELETED l
TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL..................
DELETED l
FIGURE 4.7-1 SAMPLING PLAN 2) FOR SNUBBER FUNCTIONAL TEST.........
DELETED l
l 3/4.7.9 SEALED SOURCE CONTAMINATION..............................
DELETED l
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i WOLF CREEK - UNIT 1 X
Amendment No. 44,89
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1 4
1.O DEFINITIONS The defined terms of this section appear in capitali:ed type and are applicable j
throughout these Technical Specifications.
j ACTION 1
1.1 ACTION shall be that part of a Technical 5 pacification which prescribes i
remedial measures required under designated conditions.
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ACTUATION LOGIC TEST 1
1.2 An ACTUATION LOGIC TEST shall be the application of various simulated input combinations in conjunction with each possible interlock logic state and verification of the required logic output.
The ACTUATION LOGIC TEST shall j
include a continuity check, as a minimum, of output devices.
4
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ANAt.0G CHANNEL OPERATIONAL TEST i
i 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated j
signal into the channel as close to the sensor as practicable to verify DPERASILITY of alare, interlock and/or trip functions.
The ANALOG CHANNEL l
OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip Setpoints such that the Setpoints are within the required i
j range and accuracy.
AXIAL FLUX DIFFERENCE 2.4 AXIAL FLUX OIFFERENCE shall be the difference in normalized flux signals l
between the top and bottom halves of a two section excore neutron detector.
4 CHANNEL cal.1BRATION
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j 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the l
channel such that it responds within the required range and accuracy to known j
values of input.
The CHANNEL CALIBRATION shall encompass the. entire channel including the sensors and alars, interlock and/or trip functions and may be performed by any. series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK I
i 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior i
during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
{'
WOLF CREEK - UNIT 1 1-1 i
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DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when; a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system. or 2)
Closed by manual valves, blind flanges or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.
b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE and e.
The containment leakage rates determined by Specification 4.6.1.1.c are within limits.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow from the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
CORE OPERATING LIMITS REPORT J
1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specificatica 6.9.1.9.
Plant operation within these operating limits is addressed in indwidual Specifications.
i WOLF CREEK - UNIT 1 1-2 Amendment No. 61.89.97.108
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5.
s 3/416 CONTAINMENT SYSTEMS l
3/4.6.1 PRIMARY CONTAINMENT i
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l.
CONTAINMENT INTEGRITY
[
LIMITING CONDITION FOR OPERATION f
3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
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APPLICABILITY: MODES 1, 2, 3, and 4.
i ACTION:
t Without primary CONTAINMENT INTEGRITY. restore CONTAINMENT INTEGRITY within i
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD l
t SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l SURVEILLANCE REQUIREMENTS l
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
l i'
i a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE' containment automatic l
isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by j
Specification 3.6.3:
1 b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3:
t j
c.
By performing containment leakage rate testing in'accordance with the Containment Leakage Rate Testing Program of Specification l
6.8.4.i; and i
i d.
By verifying containment structural integrity in accordance with the Containment Tendon Surveillance Program of Specification 6.8.5.c.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
WOLF CREEK - UNIT 1 3/4 6-1 Amendment No. 89-97,108 (Next page is 3/4 6-4) l
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION r
3.6.T.37actrtantainment air lock shall-be OPERABLE with both doors closed except when the air lock is being used for normal transit and exits through the containment, then at least one air lock door shall be closed.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
P a.
With one containment air lock door inoperable:
~
~
1.
Maintain at least the OPERABLE air 1ock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door
- closed, 2.
Operation may then continue until performance of the next required overall. air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and 4.
The provisions of Specification 3.0.4 are not applicable.
b.
With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air iock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
WOLF CREEK - UNIT 1 3/4 6-4 Amendment No. 97
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_ CONTAINMENT SYSTEMS f
CONTAINMENT COOLING SYSTEM j
LIMITING CONDITION FOR OPERATION 3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE j
with two fan systems to each group.
l APPLICABILITY: MODES 1, 2, 3, and 4.
j ACTION:
a.
With one group of the above required containment cooling fans inoperable and both Containment Spray Systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 7 days or 4
be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD j
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With two groups of the above required containment cooling fans inoperable and both Containment Spray Systems OPERABLE, restore at least one group of cooling-fans to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> e
or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD i
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore both above required j
groups of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in l
COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With one group of the above required containment cooling fans inoperable and one Containment Spray System inoperable, restore the l
inoperable Containment Spray System 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of ini-tial loss or be in at least HOT STANDSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, i
i SURVEILLANCE REQUIREMENTS
_4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERAB'LE:
l a.
At least once per 33 days by:
l l
- 1) Starting each non-operating fan group from the control room, and verifying that each fan group operates for at least 15 minutes.
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- 2) Verifying that each valve (manual, power-operated, or automatic) l in the cooling water flow path serving the containment coolers j
that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months by verifying that on a Safety Injection l
test signal, the fans start in slow speed or, if operating, shift to slow speed and the cooling water flow rate increases to at least i
2000 gpm to each cooler group.
l WOLF CREEK - UNIT 1 3/4 6-15 Amendment No. 38, 50 i
CONTAINMENT SYSTEMS
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3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION l
3.6.3 Each containment isolation valve shall be OPERABLE *.
l APPLICABILITY:
MODES 1, 2. 3. and 4 ACTION:
With one or more containment isolation valve (s) inoperable, maintain at least l
one isolation valve OPERABLE in each affected penetration that is open and:
a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position or c.
Isolate each affected enetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manua valve or blind flange, or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
e.
The provisions of Specification 3.0.4 do not apply.
SURVEILLANCE REQUIREMENTS 4.6.3.1 Each power-operated or automatic containment isolation valve shall be l
demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time.
- Locked or sealed-closed valves may be opened on an intermittent basis i
under administrative control.
WOLF CREEK - UNIT 1 3/4 6-16 Amendment No. &h89.108 l
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each power-operated or automatic containment isolation valve shall be l
1 demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by-l a.
Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position:
b.
Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position: and c.
Verifying that on a Containment Purge Isolation test signal, each i
purge supply and exhaust isolation valve actuates to its isolation j
4 position.
j 4.6.3.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
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1 WOLF CREEK - UNIT 1 3/4 6-17 '
Amendment No. 108 (Next page is 3/4 6-31)
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CONTAINMENT SYSTEMS HYDROGEN CONTROL SYSTEMS 4
LIMITING CONDITION FOR OPERATION 3,6.4.2 A Hydrogen Control System shall be OPERABLE with two independent Hydrogen Recombiner Systems.
j
&'PLICABILITY: MODES 1 and 2 L
AC[lQH:
l With one of the two independent Hydrogen Recombiner Systems inoperable, restore the inoperable Hydrogen Recombiner System to OPERABLE status within i
30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i l
SURVEILLANCE REOUIREMENTS
{
'4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE:
a.
At least once per 6 months by verifying, during a Hydrogen Recombiner System functional test, that the heater air temperatu e increases to greater than or equal to 1150*F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; an(
b.
At least once per 18 months by:
1)
Performing a CHANNEL CALIBRATION of all hydrogen recombiner system instrumentation and control circuits, 2)
Verifying through a visual examination that there is no evidence of abnormal conditions within the hydrogen recombiner system enclosure (i.e., loose wiring or structural connections, deposits of foreign materials, etc.), and 3)
Verifying the integrity of all heater elec'trical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be gr' eater than or equal to 10,000 ohms.
WOLF CREEK - UNIT 1 3/4 6-31 Amendment No. 89 l
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l CONTAINMENT SYSTEMS BASES l
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS f
3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or steam line break. The pressure reduction and resultant lower j
containment leakage rate are consistent with the assumptions used in the j
safety analyses.
l The Containment Spray System and the Coritainment Cooling System are redundant to each other in providing post-accident cooling of the containment atmosphere. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable Spray System to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
j 3/4.6.2.2 SPRAY ADDITIVE SYSTEM.
The OPERABILITY of the Spray Additive System ensures that sufficient NaOH
.is added to the containment spray in the event of a LOCA. The limits on NaOH volume and concentration ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained solution i
volume limit includes an allowance for solution not usable because of tank discharge line location or other physical characteristics.
The educator flow test of 52 gpm with RWST water is equivalent to'40 gpm NaOH solution. These i
assumptions are consistent with the iodine removal efficiency assumed in the safety analyses.
}/4,6.2.3 CONTAINMENT CCOLING SYSTEM The OPERABILITY of the Containment Cooling System ensures that: (1) the containment air temperature will be maintained within limits during normal operation, and (2) adequate heat removal capacity is available when operated in conjunction with the Containment Spray Systems during post-LOCA conditions.
The required design cooling water flow to the Containment Cooling System is verified by the surveillance testing requirements of Specification 4.6.2.3(b) which is perfomed at 18 month intervals.. The testing requirements of Specification 4.6.2.3(a), performed at 31 day intervals, ensure that the fan units and the cooling water flow paths (supply and return) from the Essential Service Water System headers are OPERABLE.
The Containment Cooling System and the Containment Spray System are redundant to each other in providing post accident cooling of the containment atmosphere. As a result of this redundancy in cooling capability, the allowable out-of-service time requirements for the Containment Cooling System
,have been appropriately adjusted. However, the allowable out-of-service time WOLF CREEK - UNIT 1 B 3/4 6-3 Amendment No. 60,89.
l
T CONTAINMENT SYSTEMS BASES CONTAINMENT COOLING SYSTEM (Continued) l requirements for the Containment Spray System have been maintained consistent with that assigned other inoperable ESF equipment since the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere.
3/4.6.3 CONTAINMENT ISOLATION VALVES l
I The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of
.i GDC54 thru 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
1 The opening of locked or sealed-closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:
(1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls. (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
3/4.6 4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associated with: (1) zirconium-water reactions.
(2) radiolytic decomposition of water, and (3) corrosion of metals within containment.
Operation of the Emergency Exhaust System with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. These Hydrogen Control Systems are consistent with the recommendations of Regulatory Guide 1.7. " Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident."
Revision 2. November 1978.
Adequate mixing of the containment atmos)here following a LOCA is ensured by natural circulation without reliance on a lydrogen mixing systems.
This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit.
WOLF CREEK - UNIT 1 B 3/4 6-4 Amendment No. 89.108
_=
i (11) Steam Generator Tube Ruoture (Section 15.4.4. SSER #5)
Prior to restart following the first refueling outage, the Operating Corporation shall submit for NRC review and approval an analysis which demonstrates that the steam generator single-tube rupture (SGTR) analysis presented in the FSAR is the most severe case with respect to the release of fission products and calculated doses.
Consistent with the analytical assumptions, the licensee shall propose all necessary changes to Appendix A to this license.
(12) LOCA Reanalysis (Section 15.3.7. SSER #5)
Prior to restart following the first refueling outage, the Operating Corporation shall submit for NRC review and approval a reanalysis for the worst large break LOCA using an approved ECCS evaluation i
model.
(13) Generic Letter 83-28 The Operating Corporation shall submit responses to and implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in their February 29, 1984 and February 6, 1985 letters.
(14) Surveillance of Hafnium Control Rods (Section 4.2.3.1(10). SER and SSER #2)
The Operating Corporation shall perform a visual inspection of a sample of hafnium control rods during one of the first five refueling outages.
A summary of the results of these inspections i
i shall be submitted to the NRC.
(15) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No.
, are hereby incorporated into this license.
Wolf Creek Nuclear Operating Corporation shall operate the facility in accordance with the Additional Conditions.
D.
Exemptions from certain requirements of Appendix J to 10 CFR Part 50, and from a portion of the requirements of General Design Criterion 4 of Appendix A to 10 CFR Part 50, are described in the Safety Evaluation Report. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
Amendment No. 4.108
7-l E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made Jursuant to provisions of the Miscellaneous Amendments and Search lequirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21. are entitled:
"Wol f Creek Generating Station Physical Security Plan." with revisions submitted through August-2, 1988: " Wolf Creek Generating Station Security Training and Qualification Plan." with revisions submitted through August 2, 1988: and " Wolf Creek Generating Station Safeguards Contingency Plan."
with-revisions submitted through August 2. 1988.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
Except as otherwise provided in the Technical. Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to
'the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b). (c) and (e).
G.
The licensees shall have and maintain financial protection of such ty)e and in such amounts as the Commission shall require in accordance witi Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
This license is effective as of the date of issuance and shall expire at Midnight on March 11. 2025.
FOR THE NUCLEAR REGULA10RY COMMISSION
" Original Signed By" Harold R. Denton. Director Office.of Nuclear. Reactor Regulation 1
Attachments / Appendices:
- 1. - Deleted
- 2. - Operating Staff Experience Requirements
- 3. - NUREG-0737. Supplement 1.
Requirements 4.
Appendix _A - Technical Specifications (NUREG-1136) 5.
Ap)endix B - Environmental 3rotection Plan 6.
Appendix-C - Antitrust Conditions 7.
Appendix D - Additional Conditions i
Date of Issuance:
June 4. 1985 Amendment No. 88, 108
i APPENDIX 0 ADDITIONAL CONDITIONS i
FACILITY OPERATING LICENSE NO. NPF-42 Wolf Creek Nuclear 0)erating Corporation shall comply with the following conditions on the scledules noted below:
Amendment Implementation Number Additional Condition Date 108 The licensee is authorized to relocate The amendment shall certain technical specification be implemented 30 requirements to licensee-controlled days from the date documents.
Implementation of this of issuance.
amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated February 17, 1997, and evaluated in the staf f's safety evaluation dated July 23,1997, i
l Amendment No.108 l
l l
.