ML081690094
| ML081690094 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/07/2008 |
| From: | Muniz G NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | |
| muniz A, ADRO/DORL/415-4044 | |
| References | |
| TAC MD8048 | |
| Download: ML081690094 (5) | |
Text
(5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No291, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993),
190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision:
ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 291
A.'.
Frequency 1.4 1.4 Frequency EXAM PLES (continued)
EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
- NOTE-------------
Not required to be performed Until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after 25% RTP.
Perform channel adjustment.
7 days The interval continues whether or not the plant operation is < 25% RTP between performances.
As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches 2: 25% RTP to perform the Surveillance. The:
Surveillance is still considered to be within the "specified Frequency."
Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (plus the extension allowed by SR 3.0.2) with power > 25% RTP.
Once the plant reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.
(continued)
I JAFNPP 1.4-5 A
Anendment
Control Rod Operability 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.3 Perform SR 3.1.3.2 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from each withdrawn discovery of Condition OPERABLE control rod.
A concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> A.4 Perform SR 3.1.1.1.
B.
Two or more withdrawn B.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> control rods stuck.
C.
One or more control rods C.1 NOTE -----
inoperable for reasons RWM may be bypassed other than Condition A or B.
as allowed by LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.
Fully insert inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> control rod.
AND C.2 Disarm the associated CRD.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)
I JAFNPP 3.1.3-2 Amendment 291
Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine tie position of each control rod.
.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.1.3.2 NOTE----------------
Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.
Insert each withdrawn control rod at least one notch.
31 days SR 3.1.3.3 Verify each control rod scram time from fully In accordance with withdrawn to notch position 04 is < 7 seconds.
SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.4 Verify each control rod does not go to the withdrawn Each time the overtravel position.
control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling I
JAFNPP 3.1.3-4 Amendment
!291
Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page I of 1)
Control Rod Scram Times NOTES--------------------------
- 1.
OPERABLE control rods with scram times not within the limits of this Table are considered "slow.u
- 2.
Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY,"
for control rods with scram times > 7 seconds to notch position 04. These control rods are inoperable, in accordance with SR 3.1.3.3, and are not considered "slow."
SCRAM TIMES (a) (b) when REACTOR STEAM DOME NOTCH POSITION PRESSURE >Ž800 psig (seconds) 46 0.44 36 1.08 26 1.83 06 3.35 (a). Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids at time zero.
(b). Scram times as a function of reactor steam dome pressure, when
< 800 psig, are within established limits.
JAFNPP 3.1.4-3 Amendment 291 I