ML042920525
| ML042920525 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/27/2004 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Donohew J N, NRR/DLPM,415-1307 | |
| Shared Package | |
| ML042940657 | List: |
| References | |
| TAC MA9990 | |
| Download: ML042920525 (9) | |
Text
TABLE OF CONTENTS 3.7 PLANT SYSTEMS...........................................
3.7-1 3.7.1 Main Steam Safety Valves (MSSVs)...........................................
3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs)........................................, 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs)....................................... 3.7-7 3.7.4 Atmospheric Relief Valves (ARVs).......................................
3.7-9 3.7.5 Auxiliary Feedwater (AFW) System.......................................
3.7-11 3.7.6 Condensate Storage Tank (CST).......................................
3.7-14K 3.7.7 Component Cooling Water (CCW) System...................................... 3.7-16 3.7.8 Essential Service Water System (ESW).......................................
3.7-18 3.7.9 Ultimate Heat Sink (UHS).......................................
3.7-20 3.7.10 Control Room Emergency Ventilation System (CREVS)................. 3.7-22 3.7.11 Control Room Air Conditioning System (CRACS)............................ 3.7-25 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System - Not Used........................
3.7-28 3.7.13 Emergency Exhaust System (EES)........................
3.7-29 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) -
Not Used....................................................................................3.7-33 3.7.15 Fuel Storage Pool Water Level................................
3.7-34 3.7.16 Fuel Storage Pool Boron Concentration................................
3.7-35 3.7.17 Spent Fuel Assembly Storage................................
3.7-37 3.7.18 Secondary Specific Activity.................................
3.7-39 3.8 ELECTRICAL POWER SYSTEMS................................
3.8-1 3.8.1 AC Sources --Operating................................
3.8-1 3.8.2 AC Sources - Shutdown.................................
3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air................................
3.8-20 3.8.4 DC Sources - Operating................................
3.8-23 3.8.5 DC Sources - Shutdown................................
3.8-27 3.8.6 Battery Cell Parameters................................
3.8-29 3.8.7 Inverters - Operating.................................
3.8-33 3.8.8 Inverters - Shutdown.................................
3.8-34 3.8.9 Distribution Systems - Operating.................................
3.8-36 3.8.10 Distribution Systems - Shutdown.................................
3.8-38 3.9 REFUELING OPERATIONS................................
3.9-1 3.9.1 Boron Concentration................................
3.9-1 3.9.2 Unborated Water Source Isolation Valves................................
3.9-2 3.9.3 Nuclear Instrumentation.................................
3.9-3 3.9.4 Containment Penetrations..................................
3.9-5 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level.
3.9-7 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level.
3.9-9 Wolf Creek - Unit 1 fll Amendment No. 123132, 134
Definitions 1.1 Table 1.1-1 (page 1 of 1)
MODES MODE TITLE REACTIVITY
% RATED AVERAGE MODETITE CNDIION THERMAL REACTOR COOLANT CODIIO POWER(a)
TEMPERATURE (0F)
I Power Operation
Ž 0.99
> 5 NA 2
Startup 2 0.99
- 5 NA 3
Hot Standby
< 0.99 NA 2 350 4
Hot Shutdown(b)
< 0.99 NA 350 > T,,, > 200 5
Cold Shutdown(b)
< 0.99 NA
< 200 6
Refueling(C)
NA NA NA (a)
Excluding decay heat.
(b)
All reactor vessel head closure bolts fully tensioned, except as specified in Specification 5.5.17, "Reactor Vessel Head Closure Bolt Integrity."
(c)
One or more reactor vessel head closure bolts less than fully tensioned, except as specified in Specification 5.5.17, "Reactor Vessel Head Closure Bolt Integrity."
I Wolf Creek - Unit 1 1.1-7 Amendment No.4=, 142
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Technical Specifications (TS) Bases Control Program (continued)
- d.
Proposed changes that meet the criteria of Specification 5.5.14b above shall be reviewed and approved by the NRC prior to implementation.
Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.15 Safety Function Determination Program (SFDP)
This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:
- a.
Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;
- b.
Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;
- c.
Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and
- d.
Other appropriate limitations and remedial or compensatory actions.
A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
- a.
A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or
- b.
A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or
- c.
A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.
(continued)
Wolf Creek - Unit 1 5.0-23 Amendment No. 123
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Reactor Vessel Head Closure Bolt Integrity This program provides the requirements to support normal plant operation with one reactor vessel head closure bolt less than fully tensioned for one operating cycle. The provisions of this program shall be implemented when a head closure bolt becomes stuck in a partially inserted position such that the amount of thread engagement is not sufficient to take the tensioning loads without damage to the vessel threads or a bolt is not capable of being inserted into the bolt hole.
Prior to operation with one reactor vessel head closure bolt less than fully tensioned, the following conditions shall apply:
- a.
The circumstances associated with the less than fully tensioned closure bolt will be verified to be bounded by the analysis that was referenced in the letter dated September 15, 2000 (WO 00-0036).
- b.
A review of the results of the visual examinations performed on the closure bolts shall be performed to ensure that there is no indication of sufficient degradation of closure bolts that could affect the conclusions of Specification 5.5.17a. above.
Within 30 days following startup of the plant, a report shall be submitted to the Commission identifying the circumstances for operation with one reactor vessel head closure bolt less than fully tensioned.
Operation with the same reactor vessel head closure bolt less than fully tensioned shall be limited to one operating cycle (i.e., until the next refueling outage).
Wolf Creek - Unit 1 5.0-25 Amendment No. 423,142
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1.
Specification 3.1.3: Moderator Temperature Coefficient (MTC),
- 2.
Specification 3.1.5: Shutdown Bank Insertion Limits,
- 3.
Specification 3.1.6: Control Bank Insertion Limits,
- 4.
Specification 3.2.3: Axial Flux Difference,
- 5.
Specification 3.2.1: Heat Flux Hot Channel Factor, F0(Z),
- 6.
Specification 3.2.2: Nuclear Enthalpy Rise Hot Channel Factor (FXH),
- 7.
Specification 3.9.1: Boron Concentration, and
- 8.
SHUTDOWN MARGIN for Specification 3.1.1 and 3.1.4, 3.1.5, 3.1.6, and 3.1.8.
(continued)
Wolf Creek - Unit 1 5.0-27 Amendment No. 423, 142 I
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 9.
NRC Safety Evaluation Report dated June 23, 1986, "Acceptance for Referencing of Topical Report WCAP 10965-P and WCAP 10966-NP-ANC: A Westinghouse Advanced Nodal Computer Code."
- 10.
NRC Safety Evaluation Reports dated July 1, 1991, "Acceptance for Referencing of Topical Report WCAP-12610, VANTAGE+ Fuel Assembly Reference Core Report' (TAC NO. 77258)," and September 15, 1994, "Acceptance for Referencing of Topical Report WCAP-12610, Appendix B, Addendum 1, 'Extended Burnup Fuel Design Methodology and ZIRLO Fuel Performance Models' (TAC NO. M86416)" (WCAP-12610-P-A).
- c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a.
RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
- 1.
Specification 3.4.3, "RCS Pressure and Temperature (P/T) Limits,"
and
- 2.
Specification 3.4.12, "Low Temperature Overpressure Protection System."
- b.
The analytical methods used to determine the RCS pressure and temperature and Cold Overpressure Mitigation System limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
(continued)
Wolf Creek - Unit 1 5.0-29 Amendment No. 123,13, 142 l
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.10 Steam Generator Tube Inspection Report (continued)
- 2)
Location and percent of wall-thickness penetration for each indication of an imperfection, and
- 3)
Identification of tubes plugged.
- c.
Results of steam generator tube inspections, which fall into Category C-3, shall be reported in a Special Report to the Commission within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Wolf Creek - Unit 1 5.0-31 Amendment No. 4.23,142 l
High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation: (continued)
(i)
Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
- e.
Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation:
- a.
Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
- 1.
All such door and gate keys shall be maintained under the administrative control of the Shift Manager/Control Room Supervisor or health physics supervision, or his or her designee.
- 2.
Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
- b.
Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
(continued)
Wolf Creek - Unit 1 5.0-33 Amendment No. 423, 142 l
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30.
Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation: (continued)
- e.
Except for individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
- f.
Such individual areas that are within a larger area, such as PWR containment, where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.
Wolf Creek - Unit 1 5.0-35 Amendment No. 43, 142 l