ML020330029
| ML020330029 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/29/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB3249, TAC MB3250 | |
| Download: ML020330029 (2) | |
Text
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- 9.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;
- 10. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
- g.
Deleted
- h.
Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, and as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following deviations or exemptions:
- 1) Type A tests will be performed either in accordance with Bechtel Topical Report BN TOP-i, Revision 1, dated November 1, 1972, or the guidelines of Regulatory Guide 1.163.
- 2) Type A testing frequency in accordance with NEI 94-01, Revision 0, Section 9.2.3, except:
a) For Unit 3, the first Type A test performed after the November 1992 Type A test shall be performed no later than November 2007.
b)
For Unit 4, the first Type A test performed after October 1991 shall be performed no later than October 2006.
- 3)
A vacuum test will be performed in lieu of a pressure test for airlock door seals at the required intervals (Amendment Nos. 73 and 77, issued by NRC November 11, 1981).
The peak calculated containment interval pressure for the design basis loss of coolant accident, Pa, is 49.9 psig.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.25% of containment air weight per day.
Leakage Rate acceptance criteria are:
- 1)
The As-found containment leakage rate acceptance criterion is < 1.0La. Prior to increasing primary coolant temperature above 2001F following testing in accordance with this program or restoration from exceeding 1.0 La, the As-left leakage rate acceptance criterion is < 0.75 La, for Type A test.
- 2)
The combined leakage rate for all penetrations subject to Type B or Type C testing is as follows:
AMENDMENT NOS. 218 AND 212 TURKEY POINT UNITS 3 AND 4 6-17
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
The combined As-left leakage rates determined on a maximum pathway leakage rate basis for all penetrations shall be verified to be less than 0.60 La, prior to increasing primary coolant temperature above 2001F following an outage or shutdown that included Type B and Type C testing only.
The As-found leakage rates, determined on a minimum pathway leakage rate basis, for all newly tested penetrations when summed with the As-left minimum pathway leakage rate leakage rates for all other penetrations shall be less than 0.6 La, at all times when containment integrity is required.
- 3)
Overall air lock leakage acceptance criteria is < 0.05 La, when pressurized to Pa.
The provisions of Specification 4.0.2 do not apply to the test frequencies contained within the Containment Leakage Rate Testing Program.
6.8.5 Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety-related functions, e.g. licensed Senior Operators, licensed Operators, health physicists, auxiliary operators, and key maintenance personnel. The procedures shall include guidelines on working hours that ensure that adequate shift coverage is maintained without routine heavy use of overtime for individuals.
Any deviation from the working hour guidelines shall be authorized by the applicable department manager or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such tha~t.hdividual overtime shall be reviewed monthly by the Plant General Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the working hour guidelines shall not be authorized.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, DC pursuant to 10 CFR 50.4.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
AMENDMENT NOS. 218 AND 212 6-18 TURKEY POINT UNITS 3 AND 4