ML20117B446
| ML20117B446 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/16/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, PECO Energy Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20117B448 | List: |
| References | |
| DPR-44-A-216 NUDOCS 9608270058 | |
| Download: ML20117B446 (6) | |
Text
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UNITED STATES p
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2006H001
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PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.216 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated June 13, 1996, as supplemented by letter dated August 7, 1996, complies with the standards ar.d requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by change's to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
9608270058 960816 PDR ADOCK 05000277 P
s
. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment,No. 216, are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and is to be implemented within thirty days.
FOR THE NUCLEAR REGULATORY COMMISSION Jh F. Stolz, Director p ject Directorate I-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 16, 1996 o
l i
e ATTACHMENT TO LICENSE AMENDMENT NO. 216 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 3.3-5 3.3-5 3.3-6 3.3-6 B 3.3-33 8 3.3-33 4
RPS Instrumentation 4
3.3.1.1 j
SURVEILLANCE REQUIREMENTS (continued) l i
SURVEILLANCE FREQUENCY SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.
92 days i
1 1
1 SR 3.3.1.1.10
NOTE-------------------
Radiation detectors are excluded.
)
Perform CHANNEL CALIBRATION.
92 days i.
4 SR 3.3.1.1.11
NOTES------------------
1.
Neutron detectors are excluded.
4 J
l 2.
Not required to be performed when entering MODE 2 from MODE 1 until i
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL CALIBRATION, 184 days SR 3. 3. '1.1.12 * ------------------ NOT E S------------------
j 1.
Neutron detectors are excluded.
i 2.
For Function 2.a, not required to be performed when entering MODE 2 from I
MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
3.
For Function 2.b, until completion of refuel outage 2R11, entry into I
associated Conditions and Required i
Actions may be delayed for up to 6 4
hours provided core flow is i
maintained at or above 82%. This is i
an exception to Surveillance Requirements Note 2.
Perform CHANNEL CALIBRATION.
18 months (continued)
PBAPS UNIT 2 3.3-5 Amendment No. 210, 216
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY 24 months SR 3.3.1.1.13 Verify Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip i
011 Pressure-Low Functions are not bypassed when THERMAL POWER is a 30% RTP.
SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST.
SR 3.3.1.1.15 Perform CHANNEL CALIBRATION.
24 months j
SR 3.3.1.1.16 Calibrate each radiation detector.
24 months i
SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within 24 months limits.
i l
PBAPS UNIT 2 3.3-6 Amendment No. ZIO, 216
RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.10. SR 3.3.1.1.11. SR 3.3.1.1.12.
RE0VIREMENTS SR 3.3.1.1.15. and SR 3.3.1.1.16 (continued) are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal. Changes in neutron detector sensitivity are compensated for by performing the 7 day calorimetric calibration (SR 3.3.1.1.2)and the 1000 MWD /T LPRM calibration against the TIPS (SR 3.3.1.1.8).
A second note is provided for SRs 3.3.1.1.11 and 3.3.1.1.12 that allows the APRM and IRM i
SRs to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 from l
MODE 1.
Testing of the MODE 2 APRM and IRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads or movable links. This Note allows entry into MODE 2 from MODE 1, if the 184 day or 18 month Frequency is not met per SR 3.0.2.
Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR. A third note is provided for SR 3.3.1.1.12 that allows the APRM SR to be performed without entering the associated Conditions and Required Actions for up to six hours provided core flow is maintained at or above j
82% where the APRM scram setpoint becomes clamped. Once core flow drops below 82%, and the APRM scram setpoints become flow biased, associated Conditions and Required Actions must be entered. As noted for SR 3.3.1.1.10, 4
radiation detectors are excluded from CHANNEL CALIBRATION due to ALARA reasons (when the plant is operating, the radiation detectors are generally in a high radiation area; the steam tunnel). This exclusion is acceptable because the radiation detectors are passive devices, with minimal drift.
The radiation detectors are calibrated in accordance with SR 3.3.1.1.16 on a 24 month Frequency.
1 The 92 day Frequency of SR 3.3.1.1.10 is conservative with respect to the magnitude of equipment drift assumed in the setpoint analysis.
The Frequencies of SR 3.3.1.1.11 and SR 3.3.1.1.12 are based upon the assumption of a 184 day or l
an 18 month calibration interval, respectively, in the determination of the magnitude of equipment drift in the setpoint analysis. The Frequencies of SR 3.3.1.1.15 and SR 3.3.1.1.16 are based upon the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the applicable setpoint analysis.
(continued)
PBAPS UNIT 2 B 3.3-33 Revision No.
Amendment No. 216 i