ML022260643
| ML022260643 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/13/2002 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Vissing G, NRR/DLPM, 415-1441 | |
| References | |
| TAC MB3333 | |
| Download: ML022260643 (3) | |
Text
JAFNPP 3.7 (cont'd) 4.7 (cont'd)
(2)
During testing which adds heat to the suppression pool, the water temperature shall not exceed 10°F above the normal power operation limit specified in (1) above. In connection with such testing, the pool temperature must be reduced to below the normal power operation limit specified in (1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(3)
The reactor shall be scrammed from any operating condition if the pool temperature reaches 1 10'F.
Power operation shall not be resumed until the pool temperature is reduced below the normal power operation limit specified in (1) above.
(4)
During reactor isolation conditions, the reactor pressure vessel shall be depressurized to less than 200 psig at normal cooldown rates if the pool temperature reaches 1 20'F.
- 2.
Primary containment integrity shall be maintained at all times when the reactor is critical or when the reactor water temperature is above 21 2°F, and fuel is in the reactor vessel, except while performing low power physics tests at atmospheric pressure at power levels not to exceed 5 MWt.
Amendment No. 16, 234, 23, 275
- 2.
- a.
Perform required visual examination and leakage rate testing of the Primary Containment in accordance with the Primary Containment Leakage Rate Testing Program.
- b.
Demonstrate combined Main Steam Line leakage rate of _< 46 scfh when tested at > 25 psig. The testing frequency is in accordance with the Primary Containment Leakage Rate Testing Program.
- c.
Once per 24 months, demonstrate the leakage rate of 10AOV-68A,B for the Low Pressure Coolant Injection system and 14AOV-13A,B for the Core Spray system to be less than 11 scfm per valve when pneumatically tested at > 45 psig at ambient temperature, or less than 10 gpm per valve if hydrostatically tested at >
1,035 psig at ambient temperature.
166
4.7 BASES (cont'd) assumption of no holdup in the secondary containment, resulting in a direct release of fission products from the primary containment through the filters and stack to the environs. Therefore, the specified primary containment leak rate and filter efficiency are conservative and provide additional margin between expected offsite doses and 10CFR100 guidelines.
The leakage rate testing program %es originally based on NRC guidelines for development of leak rate testing and surveillance schedules for reactor containment vessels.
Containment structural integrity is currently verified with visual inspections and containment leak tightness is verified by the leakage rate surveillance testing described in the JAFNPP Primary Containment Leakage Rate Testing Program.
The following are the exemptions to 10 CFR 50 Appendix J, Option A, that have been approved by the NRC, and remain applicable to Option B of 10 CFR 50, Appendix J:
- 1.
The Type C exceptions listed on Table 4.7-2, "Exception to Type C Test", as of the date of issuance of Amendment 194 (July 29, 1993).
- 2.
Valves which are sealed with fluid from a seal system, such as the liquid in the suppression chamber are not required to be Type C tested. This exemption was approved by the NRC in the original Technical Specifications (SR 4.7.A.2.c(3)).
Amendment No. 97,*34,4234, 2 75 JAFNPP
- 3.
When MSIVs are tested at a pressure less than Pa and
> 25 psig, the limit for the combined main steam leakage rate is < 46 scfh. The exemption for reduced pressure testing was approved by the NRC in the original Technical Specifications (Table 4.7-2).
The Program as implemented meets the requirements of Option B of 10 CFR 50 Appendix J (16) and Regulatory Guide 1.163 (13), with the exception stated in Specification 6.20.
This exception applies to valves currently installed in this configuration, and does not apply to new installations. This exception is consistent with TS Table 4.7-2, previously contained in the TS, which allows reverse direction testing of valves as an exception to the requirements of the draft,
Appendix J, on the basis that pressurization direction was not a requirement at the time of plant design.
B.
C.
Standby Gas Treatment System and Secondary Containment Initiating reactor building isolation and operation of the Standby Gas Treatment System to maintain at least a 1/4 in.
of water vacuum within the secondary containment provides an adequate test of the operation of the reactor 194
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.7 Verify each automatic PCIV actuates to 24 months the isolation position on an actual or simulated isolation signal.
SR 3.6.1.3.8 Verify each reactor instrumentation line In accordance EFCV actuates to the isolation position with the on a simulated instrument line break.
Inservice Testing Program SR 3.6.1.3.9 Remove and test the explosive squib from 24 months on a each shear isolation valve of the TIP STAGGERED TEST System.
BASIS SR 3.6.1.3.10 Verify combined main steam line leakage In accordance rate is ! 46 scfh when tested at 2 25 with the psig.
Primary Containment Leakage Rate Testing Program SR 3.6.1.3.11 Verify the leakage rate of each air In accordance operated testable check valve associated with the with the LPCI and CS Systems vessel Primary injection penetrations is within limits.
Containment Leakage Rate Testing Program Amendment 275 3.6.1.3-9 I