ML20058F573
| ML20058F573 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/22/1993 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058F575 | List: |
| References | |
| NUDOCS 9312080183 | |
| Download: ML20058F573 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20566-0001 gv,
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-JB2 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated October 21, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amerided (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 (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;
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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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e 9312080183 931122 PDR ADOCK 05000382 p
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance-with the Technical Specifications and the Environmental Protection Plan.
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation F
Attachment:
Changes to the Technical Specifications 3
Date of issuance: November 22, 1993 l
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-i ATTACHMENT TO LICENSE AMENDMENT NO. 91 TO FACILITY OPERATING LICENSE NO. NPF-38 l
DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and-contain vertical lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 3-29 3/4 3-29 i
3/4 3-31 3/4 3-31 3/4 ?-32 3/4 3-32 l
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TABLE 3.3-6 r
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RADIATION MONITORING INSTRUMENTATION
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2>'g MINIMUM CHANNELS APPL 1 CABLE ALARM / TRIP MEAS 11REMENT 1NSTRilMENT OPLRAHLE MODI S SEIPOINT RANGE Atil0N
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AREA MONITORS a.
Tuc1 Storage Pool Area fuel llandling Building Ventilation System Isolation 2
< 100 mR/h 10"I - 10 mR/h 24 4
- b. Containment - Purge &
1/ train 1,2,3,4&**komR/ hor 5
Exhaust Isolation 20 - Sx10 mR/h 25
< 2x background Ubichever is w
higher w
2.
PROCESS MONITORS a.
Containment Atmosphere
- 1) Gaseous Activity RCS Leakage Detection 1
1, 2, 3, & 4 Not Applicable 10
- 10 pCi/cc 23
-6
-1
- 2) Particulate Activity RCS Leakage Detection 1
1, 2, 3, & 4 Not Applicable 10 10-6 pCi/cc 23 b.
Control Room Intake Monitors 1/ intake All MODES
< 2x background 10
- 10 pCi/cc 26
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-2 e
c.
Steam Generator Blowdown g
Monitor 1
1, 2, 3, & 4
< 10 pCi/cc 10
- 10 pCf/cc 28
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-6
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A d.
Component Cooling Water z
Monitors A&B 1/line All MODES
< 10 pCi/cc 10
- 10 pCi/cc 28
-4
-7
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Component Cooling Monitor A/B 1
1, 2, 3, & 4
~< 10 pCi/cc 10
- 10 pCi/cc 28
-4
-7
-2
- With irradiated fuel in the storage pool.
- During CORE ALTERATIONS or movement of irradiated fuel within the containment
TABLE 3.3-6 (Continued)
ACTION STATEMENTS ACTION 23 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.
ACTION 24 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.
ACTION 25 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION l
requirements of Specification 3.9.9.
ACTION 26 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate s
and maintain operation of the control room emergency ventilation i
system in the recirculation mode of operation.
ACTION 27 -
With the number of OPERABLE Channels less than required by the t
Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
1.
Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2.
If the monitor is not restored to OPERABLE status within 7 days after the failure, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
ACTION 28 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, operation of the plant may continue for up to 30 days provided grab samples are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the monitor is not restored to OPERABLE status within 30
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days after the failure, continue sampling and prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
WATERFORD - UNIT 3 3/4 3-31 Amendment No. 91