ML20073R458
| ML20073R458 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/31/1991 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073R460 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9106070224 | |
| Download: ML20073R458 (17) | |
Text
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NUCLEAR REGULATORY COMMISSION 3-
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g, s s WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 44 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),
dated March 5, 1991, 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; 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 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 "ot 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.
9106070224 910531 PDR ADOCK 05000402 P
PDR-
. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment end 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. 44, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,, @p George F. Dick, Acting Director Project Directorate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 31, 1991 l
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i ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. 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 INSED.T X
X XI XI 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-30 B
e
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,----.-.,.n,----,-,,---..,m-a.-.,- -, - - -, < --. -,,,, -
v-----.
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5.2 ECCS SUBSYSTEMS - T
> 350 F.............................
3/4 5-3 avg 3/4.5.3 ECCS SUBSYSTEh5 - T 350'F..........................
3/4 5-7 avg 3/4.5.4 ECCS SUBSYSTEMS - T 200'F.............................
3/4 5-9 avg 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........................................
3/4 6-2 Containment Air Locks......................................
3/4 6-4 Internal Pressure..........................................
3/4 6-6 Air Temperature............................................
3/4 6-7 Containment Vessel Structural Integrity....................
3/4 6-8 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 CONTAINMENT ISOLATION VALVES............................
3/4 6-18 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers.........................................
3/4 6-31 Hydrogen Control Systems...................................
3/4 6-32 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves........................................
3/4 7-1 f
WOLF CREEK - UNIT 1 IX
L LIMITfNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH 3ETPOINT WITH INOPERABLE 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 Auxi l i a ry Feedwate r Sys t em..................................
3/4 7-4 Condensate Stor ge Tank.....................................
3/4 7-6 Specific Activity...........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM............................
3/4 7-8 Main Steam Line Isolation Va1ves............................
3/4 7 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.............
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM..............................
3/4 7-11 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM.......................
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK..........................................
3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...................
3/4 7-14 3/4.7.7 EMERGENCY EXHAUST SYSTEM....................................
3/4 7-17 3/4.7.8
-SNUBBERS....................................................
3/4 7-19 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL.......................
3/4 7-24 FIGURE 4.7-1 SAMPLING PLAN 2) FOR SNUBBER FUNCTIONAL TEST............
3/4 7-26 l
3/4.7.9 SEALED SOURCE CONTAMINATION.................................
3/4 7-27 WOLF CREEK - UNIT 1 X
Amendment No. 44
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LIMITING CONDITIONS FOR OPERATION AND-SURVEILLANCE REQUIREMENTS SECTION PAGE
-PLANT SYSTEMS (Continued) 3/4.7.10 DELETED TABLE 3.7-3 DELETED 3/4.7.11 DELETED 3/4.7.12' AREA TEMPERATURE MONITORING..............................
3/4 7-29 TABLE 3.7-4' AREA TEMPERATURE MONITORING...........................
3/4 7-30 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 8ATTERY SURVEILLANCE REQUIREMENTS.....................
3/4 8-11 Shutdown.................................................
3/4 8-12 3/4.8.3 051 SITE POWER DISTRIBUTION
-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 WOLF CREEK - UNIT 1
_XI Amendment No.
15,-35, 44
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LIMITINGCONDITIONSFOR-OPERATIONANDSURVEILLANCEREC)REMENTS 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 Leve1.........................................
3/4 9-9 Low Water Leve1..........................................
3/4 9-10 3/4.9.9 CONTAINMENT VENTI LATION 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 WATER LEVEL - STORAGE POOL..............................
3/4 9-14 3/4.9.12 S P ENT FU E L A S S EMB LY ST0 RAG E..............................
3/4 9-15 FIGURE 3.9 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITInL ENRICHMENT TO PERMIT STORAGE IN-REGION 2........................................
3/4 9-16 3/4.9.13 EMERGENCY EXHAUST SYSTEM.................................
3/4 9-17 WOLF CREEK - UNIT 1 XII
PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
The only snubbers excluded from the requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
APPLICABILITY:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8g on the attached component or declare the attached system inopera-ble and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the follow-
'ing augmented inservice inspection program and the requirements of Specifica-tion 4.0.5.
a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual Inspections Snubbers-are categorized as inaccessible or accessible during reactor operation._ Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule-determined by Table 4.7-2.
The visual inspection interval for each type snubber shall be determined based upon the criteria-provided in Table 4.7-2 and the-first inspection interval determined using l'
this criteria shall be based upon the-previous-inspection interval as established by the requirements in effect before amendment 44.
l WOLF CREEK - UNIT 1.
3/4 7-19 Amendment No. 44 1'.
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that:
(1) there are no visible indi-cations of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that: (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; or (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Speci-fication 4.7.8f.
All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unaccep:.nble for determining the next inspection interval. A review and evaluation shall be performed and documented to determine system operauility with an unacceptable snubber.
If cperability cannot be justified, the system shall be declared inoperable and the ACTION requirements shall be met, d.
Transicnt Event Inspections An inspection shall be performed of all hydraulic and mechanical snub-bers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of opera-tional data and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; (2) evaluation of in place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
i WOLF CREEK - UNIT 1 3/4 7-20 Amendment No. 44 1
PLANT SYSTEMS I
SURVEILLANCE REQUIREMENTS (Continued) g.
Service Life Monitoring Program (Continued)
For the snubbers.found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached.
The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be func-tionally tested.- This testing requirement shall be independent of the requirements stated in Specification 4.7.8e. for snubbers not i
meeting the functional test acceptance criteria.
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h.
Functional Testing of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the functional test criteria before installation in the unit.
Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.
1.
Snubber Service Life Program The service life of hydraulic and mechanical snubbers shall be moni-tored to ensure that the service life is not exceeded between sur-veillance inspections.
The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history.
Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.
The parts replacements shall be documented and the docu-mentation shall be retained in accordance with Specification 6.10.2.
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l WOLF CREEK - UNIT 1 3/4 7-23 l
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TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C per Catergory Extend-Interval Repeat Interval Reduce Interval (Notes 1-and 2)
(Extend 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1-0 0
1 80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber category shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined' separately or jointly. However, categories must be determined and documented before any inspection and that determination shall be the basis upon which to determine the next inspection ~ interval for that category.
Note 2:-
Interpolation between population per category and the number of 1
unacceptable snubbers is permissible.. Use next lower integer for the value of the limit for Columns A, B, and C if that integer ~
~ includes a fractional value of unacceptable snubbers as determined by interpolation.
WOLF CREEK - UNIT 1 3/4 7-24 knendment No 44
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-Table 4.7-2 (Continued?
SNUBBER VISUAL INSPECTION INTERVAL Note 3:
if the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4:
If the number of unacceptable snubbers is equal to or less than the i
number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous.
interval shall be reduced by_a factor that is one-third of the ratio of the difference between the number-of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers-in Column B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
WOLF CREEK - UNIT 1 3/4 7-25 Amendment No.44
10 9
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REJECT j
6 r
C 5
,r CONTINUE TESTING 2
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2 ACCEPT 1
r 0
10 20 30 40 50 60 70 80 90 100 N
FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST WOLF CREEK - UNIT 1 3/4 7-26 Amendment No. 44
PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9 Each sealed source.containing radioactive material either in excess of 100 microCuries of beta and/or gamma-emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY:
At all times.
ACTION:
a.
With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:
1.
Decontaminate and repair the sealed source, or 2.
Dispose of the sealed source in accordance with Commission Regulations, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below, a.
Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
1)
With a half-life greater than 30 days (excluding Hydrogen 3),
and 2)
In any form other than gas.
WOLF CREEK - UNIT 1 3/4 7-27 Amendment No.44
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months.
Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and Startup sources and fission detectors - Each sealed startup source c.
and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.
4.7.9.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.
1 WOLF CREEK - UNIT 1 3/4 7-28 Amendment No. 44
i 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 i
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.
With 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. ebove, 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 equips.ent in the affected area (s) inoperable.
SURVEILLANCE REQUIREMENTS 4.7.12 The temperature in eachlof 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 />.
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. WOLF CREEK - UNIT 1 3/4 7-29 Amendment No.-Z5,-44 l
l 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 37 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 Pump Room B 119 12.
Safety Injection Pump Room A 119 13.
Safety Injection Pump Room B 119 14.
Centrifugal Charging Pump Room 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 22.
Control Room 84 WOLF CREEK - UNIT 1 3/4 7-30 Amendment No.15,44
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