ML20044H152
| ML20044H152 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/01/1993 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20044H151 | List: |
| References | |
| NUDOCS 9306080002 | |
| Download: ML20044H152 (7) | |
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.i Attachment IV to NA 93-0133 Page 1 of 7 i
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i Attachment IV Proposed Technical Specification Changes T
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l Attachment IV to NA 93-0133 Page 2 of 7 i
ADMINISTRATIVE CONTROLS SECTION PA_Gf 6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)
Function....................................................
6-9 Composition.................................................
6-10 Alternates..................................................
6-10 Consultants.................................................
6-10 Meeting Frequency...........................................
6-10 Quorum......................................................
6-10 Review......................................................
6-11 Audits......................................................
6-11 Records.....................................................
6-12 6.6 REPORTABLE EVENT ACT10N.......................................
6-13 6.7 SAFETY LIMIT VIOLATION........................................
6-13 6.8 PROCEDURES AND PR0 GRAMS.......................................
6-13 529 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REP 0RTS.............................................
6-17 Startup Report..............................................
6-17 AnnualReports..............................................
6-17 Annual Radiological Environmental Operating Report..........
6-18 i Annu
-Semiennua adioactive Effluent Release Report..............
6-19 G.al
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Monthly Operating Report....................................
6-20 Core Operating Limits Report...............................
6-21 6.9.2 SPECIAL REP 0RTS.............................................
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6.10 RECORD RETENT10N.............................................
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1 WOLF CREEK'- UNIT 1 XXI Amendment No. AZ. 61
Attachment IV to NA 93-0133 Page 3 of.7 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the fol-lowing unprotected outdoor tanks shall be limited to less than or equal to 150 Curies, excluding tritium and dissolved or entrained noble gases.
a.
Reactor Makeup Water Storage Tank, b.
Refueling Water Storage Tank, c.
Condensate Storage Tank, and d.
Outside temporary tanks, excluding demineralizer vessels and liners being used to solidify radioactive wastes.
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next-Semiannuai-adioactive Effluent Release Report, pursuant to Specification 6.9.'
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The-quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank.
WOLF CREEK - UNIT 1 3/4 11-1 Amendment No. 42
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Attachment IV to NA 93-0133 Page 4 of 7
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RADIOACTIVE EFFLUENTS
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GAS STORAGE-TANkt LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 2.5 x 105 Curies of noble gases (considered as Xe-133 equivalent).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any gas storage tank a.
exceeding the above limit, immediately suspend all additions of radioactive material to the tank, and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce tha tank contents to within the limit, and describe the events leading to this condition in the next-Seeiannuel, Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank.
WOLF CREEK - UNIT 1 3/4 11-3 Amendment No. 42 v,
Attachment IV to NA 93-0133 Page 5 of 7 j
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i ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) b.
Documentation of all challenges to the PORVs or safety valves.
The results of specific activity analysis in which the primary c.
coolant exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the Ifmit was exceeded; (2) Results of the last isotopic analysis for radiofodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiofodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 4-8 hours prior to the first sayle in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistant with the objectives outlined in (1) the ODCM and (2) Sections IV. 2 IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
h h MUAidRADI0 ACTIVE EFFLUENT RELEASE REPORT The(dhnn'ua N
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- 6. 9.1. 7 fannuaARadioactive Effluent Release Report covering the operation of the un during the previous 4-months-o -operat4en shall be i
submitted-within40-days-after-Januarj 1 ad MyJ'or each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the 00CM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, l
U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
4 WOLF CREEK UNIT 1 6-20 Amendment No. 42
Attachment IV to NA 93-0133
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ADMINISTRATIVE CONTROLS OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued) c.
Shall be submitted to the Commission in the form of a complete, leg *ible copy of the entire ODCM as a part of or concurrent with Annual the 4emiannual. Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
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WOLF CREEK UNIT 1 6-25 Amendment No. 42
Attachment IV to NA 93-0133 Page 7 of 7 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C. SOURCES. AND ONSITE P0WER DISTRIBUTION The OPERABILITY of the A.C. and D.C power sources and associated distri-bution systems during operation ensures that sufficient power will be avail-able to supply the safety-related equipment required for:
(1) the safe shut-down of the facility, and (2) the mitigation and control of accident condi-tions within the facility.
The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix A to 10 CFR Part 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commen-surate with the invel of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during acci-dent conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. source. The A.C. source and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93,
" Availability of Electrical Power Sources", December 1974.- When one diesel generator is inoperable, there is an additional ACTION requirement to verify that all required. systems, subsystems, trains, components and devices, that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE.
Thi: requirement is intended to provide assurance that a loss-of-offsite power event will not result in a complete loss of safety function of critical systems during the period one of the diesel generators is inoperable. The term verify as used in this context means to administratively check by examining logs or other information to determine if certain compenents are out-of-service for maintenance or other reasons.
It does not mean to perform the Surveillance Requirements needed to demonstrate the OPERABILITY of the component.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that:
(1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control capability are available for monitoring and maintaining the unit status.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Sup-plies," Revision 1, November 1978,1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977 as modified by Amendment No. 8 issued on May 29, 1987, and 1.137, " Fuel-Oil Systems for Standby Diesel Generators,"
Revision 1, October 1979.
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