ML20044F907
| ML20044F907 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/19/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044F904 | List: |
| References | |
| NUDOCS 9306010181 | |
| Download: ML20044F907 (5) | |
Text
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t UNITED STATES f
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20EEE-0001 i
MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION-AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No. 138 License No. DPR-36 I
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that A.
The application ~for amendment filed by the heine Yankee Atomic Power Company (the licensee), dated March 4, 1993, complies with.the standards and 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; 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:
(1) that the activities authorized'by this amendment can be conducted without endangering the health and
-i safety of the public, and (ii) that such activities will be conducted j
.. 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.
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- 2. - Accordingly.. the lieense 'is amended by changes to the Technical Specifica.
l tions as indicated in the attachment to this license amendment, and
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paragraph 2.B.(6)(b) of Facility Operating License No.- DPR-36 is.hereby 5
amended-to read as-follows.
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9306010181 930519 PDR-ADOCK 05000309 p.
PDR i
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. MaY 19,1993 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.138, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director l
Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation f
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 19, 1993 l
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-ATTACHMENT TO LICENSE AMENDMENT NO. 138 FACILITY OPERATING LICENSE NO. DPR-36 i
DOCKET NO. 50-309 Replace the following pages of the Appendix A Technical. Specifications with the attached pages. The revised pages are identified by Amendment number and i
contain vertical lines indicating the area of change.
Remove Insert 4.1-10 4.1-10 4.1-12 4.1-12 i
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%A Table 4.1-3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls Channel Description Surveillance Frequency Surveillance Method Function
- l. Reed Switch Rod Check S
Compare rod position indication from the Reed Switch Position Indication Position Indication System with that of the Pulse System Counting Position Indication System whenever the reactor is critical and the plant computer is available.
- 2. Pulse Counting Rod Check S
Compare rod position indication from the Pulse Counting Position Indication Position Indication System with that of the Reed Switch System Position Indication System whenever the reactor is critical and the plant computer is available.
- 3. Radiation Area
- a. Check D"2 a.
Internal test signals used to check instrument Monitors operation.
- b. Functional M"'
b.
Expose the detector with either an internal or an Test external radiation source or an electronic signal to verify instrument operation.
- c. Calibrate R
c.
Exposure to known radiation source.
- 4. Emergency Plant
- a. Check D("
a.
Internal radiation source provides continuous signal Radiation verifying instrument operations.
Containment High Range
- b. Calibrate R
b.
Exposure to known radiation source.
- 5. Environmental
- a. Check M
a.
Operational Check.
Monitors
- b. Calibrate A
b.
Verify airflow indicator.
6.
Pressurizer
- a. Check S("
a.
. Comparison of independent level readings.
Level
- b. Calibrate R
b.
Known differential pressure applied to sensor.
Amendment l81,86,94,138 4.1-10 L a \\9 hm\\9 323
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Table 4.1-3 (Continued)
Surveillance Channel Description Function Frequency Surveillance Method
- 13. Safety Valve Position
- a. Calibrate R
Apply known frequency to sensor.
Indicator (Acoustic Flow Sensor)
- 14. PORV Actuation Circuit
- a. Check M"'"'
a.
Bistable trip test
- b. Calibrate R
b.
Apply known pressure to sensors.
15.
Pressurizer Power
- a. Calibrate R
Apply known pressure to the pressure sensor.
Operated Relief -
Manual actuation of each PORV to verify Variable Pressure
- b. Test R"'
solenoid operation Setpoint
- 16. Purge Valve Isolation on High Radiation Signal
- a. High Containment
- a. Calibrate R
Exposure to an external radiation source.
Gaseous Activity
- b. High Primary Vent
- b. Calibrate R
Exposure to an external radiation source.
Stack Gaseous Activity
- 17. Containment Hydrogen
- a. Check W
- a. Verify expected values on readout.
Monitors
- b. Calibrate SA
- b. Apply gasses containing known concentration of H2 with balance N2.
- 18. Radiation Process and
- a. Check D"'
- a. Internal test signals used to check Effluent Monitors instrument operation.
- b. Functional M")
- b. Expose the detector with either an Test internal or an external radiation source to verify instrument operation.
- c. Calibrate R
- c. Exposure to known radiation source.
- 19. Containment Water level
- a. Check M
- a. Compare readings of the two channels for consistency.
- b. Calibrate R
- b. Adjust indicator and verify readouts based on signals.
Amendment Thi. 52, /2, ll, 83, 94,138 4.1-12 L : \\9 3.m\\932 3
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