ML20113A305
| ML20113A305 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/20/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20113A307 | List: |
| References | |
| NUDOCS 8504100165 | |
| Download: ML20113A305 (2) | |
Text
__
4.2.5 The liceisee shall submit a report or application for license raend-ment to the NRC within 90 days after any time'that Crystal River Unit No. 3 fails to maintain a cumulative reactor utilization factor of at least 65%.
The report shall provide justification.for continued operation of TMI-1 with the reactor vessel surveillance prograre conducted at Crystal River Unit No. 3, or the appitcation for license amendment shall propose an alternate program for conduct of the 1NI-1 reactor vessel surveillance program.
For the purpose of this technical specification, the definition of commercial operation is that given in Regulatory Guide 1.16. Revision 4.
The def%ition of cisnulative reactor utilization factor is:
Cumulative reactor utilization factor - (Cisn'ulative megawatt hours (thermal) since attainment of connercial operation at 100% power x (100)) divided by (licensed power (mt) x (Cumulative hours since attainment of commercial operation at 100% power)).
4.2.6 In addition to the reports required by Specification 4.2.4, a report shall be 'sibmitted tu the NRC prior to September 1,1982, which suussarizes the first five years of operating experience with the TMI-1 integrated surveillance program performed at a host reactor. If, at the time of submission of this report, it is desired to continue the surveillance program at a host reactor, such continuation shall be justified on the basis of the attained operating experience.
4.2.7 A surveillance program for the pressure isolation valves between the primary coolant system and the low pressure injection system shall be as follows:
1.
Periodic leakage testing ("} at test differential pressure gmater i
than 150 psid shall be accomplished for the valves listed in Table l
3.1.6.1 for the following conditions:
(a) prior to achieving hot shutdown after returning the valve to service following maintenance repair or replacement work, and (b) prior to achieving hot shutdown following a cold shutdown of greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> duration unless testing has been per-formed within the previous 9 nonths.
2.
Whenever integrity of a pressure isolation valve listed in Table 3.1.6.1 cannot be demonstrated, the integrity of the other renminino valve in each high pressure line having a leaking valve shall be determined and recorded daily. In addition, the position of one other valve located la the high pressure piping shall be recorded' daily.
- n
- To satisfy A1. ARA requirements, leakage may be measured indirectly (as frots the performance of pressure indi:ators) if accomplished in accordance with approved i
procedures and supported by computations showin;; that the method 'is capable of demonstracing valve compliance with the leakage criteria.
8504100165 050320 3
PDR ADOCK 05000289 d
j p
PDR I
Amendment No..W. Ar, 45, pr,11efgpr" j,/W1f), 71, Corr,1.tr. dtd.11/2/81,.
!.-:2
~
Reissued 3/20/85 a,. - -
4 g
~
., ~
Ease.
Specifications 4.2.1 and 2 ensure that inservice inspection of ASME Code a.
Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodi-cally updated version of Section XI of the ASME Boiler and Pressure Relief from Vessel Code and Addenda as required by 10. CFR 50.55a(g).
any of the above require:nents has been provf ded in writing by the NRC and is not a part of these technical specifications.
J i
j l
-(
7
. Amendment No.E, X,4([ gjdggf
(
j
-I)81)f,' 71,: Corr. Ltr. dtd. 11/2/81, Q 2a Reissued-3/20/85