ML20006A145
| ML20006A145 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 01/16/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006A143 | List: |
| References | |
| NUDOCS 9001250286 | |
| Download: ML20006A145 (5) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION i
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I WASHINGTON. D. C. 2055$
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LONG ISLAND LIGHTING COMPANY D0cKET.NO. 50-3F2 l
SHOREHAM NUCLEAR F'0WER STATION
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AMEl4W ENT TO FAC [LITY OPERATING LICENSE l
Amenoment Nc. 1 License No. NPF-36 1.
The Nuclear Regulatory Comn.ission (the Commission) has found that
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A.
The application f or amencrent by Long Island Lighting Company
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(the licensee), dateo July 13, 1989, complies with the standards ano l
requirements of the Atomic Energy Act of 1954, as amended (the Act),
I and the Concission's rules anc regulations set forth in 10 CFR Chapter I; j
B.
The f acility will operate in conformity with the applicatico, the provisions of the Act, and the rules and regulations of the Commission; C.
Thtre is reesocable assurance (i) that the activities authori7ed by this amendment can be conducted without endancering the health and i
safety of the public, end (ii) that such actifities will be conducted in ecmpliance with the Corr.ission'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 1
been satisfied.
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Accoroingly, the license is amended by changes to the Technical Specifications as ircicated in the attachment to this license amendment, ano paragraph 2.C.(2) of Facility Operating License No. NPF-82 is tereby amenced to read as follows:
Technical Specifications The Technical Specifications containeo in Appendix A and the l
Environmental Protection Plan contained in Appendix B, as revised through Amenoment No.
I are hereby incorporated into this license.
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Long Island Iighting Company shall eperate the facility in i
l accordance with the Technical Specifications and the Environmental' Protection Plan.
9001250286 900116 r
PDR ADOCK 05000322 P
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
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Walter R. Butler, Director
-Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical
-Specifications Date of 1ssuance: January.16, 1990 R
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ATTACHMENT TO LICENSE AMENDMENT NO. 1 FACILITY OPERATING LICENSE NO. NPF-8?
DOCKET NO. 50-322 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. T1e revised page is identified by Amendment number and contains vertical lines indicating the area of. change.
Overleaf page is provided to maintain document completeness.*
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6-13 6-13 I
6-14 6-14*
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ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below; a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, b.
The applicable procedures required to implement the requirements of NUREG-0737, c.
Refueling operations.
d.
Surveillance and test activities of safety-related, equipment, e.
Security Plan implementation, f.
Emergency Plan implementation.
9 Fire Protection Program implementation.
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PROCESS CONTROL PROGRAM implementation, i.
OFFSITE DOSE CALCULATION MANUAL implementation.
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Quality Assurance Program for effluent and-environmental monitoring.
6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed by the ROC prior to implementation.
The Plant Manager shall approve l
i Station Administrative procedures, Security Plan implementing procedures and Emergency plan implementing procedures prior to implementation.. Other procedures of Specification 6.8.1 shall be approved by the appropriate plant Division Manager or by the Plant Manager prior to implementation.
Each Plant Division Manager shall be responsible for a designated set of procedures. These procedures shall be reviewed periodically as_ set forth in administrative i
procedures.
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6.8.3 Temporary changes to procedures of Specific'ation 6.8.1'may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's license on l
the unit affected; and The change is documented, reviewed N the ROC, and approved by the c.
Plant Manager within 14 aays of irc mentation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those_ portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The j
systems include the Core Spray, High Pressure Coolant Injection.
.j Residual Heat Removal, Reactor Core Isolation Cooling, Hydrogen Recombiners, Reactor Water Cleanup, Coolant Sampling, Reactor Building Equipment Drain, Reactor Building Floor Drain, and Reactor 1
Building Standby Ventilation System, Instrumentation Lines and-1 Post Accident Monitoring System.
l SHOREHAM - UNIT I 6-13 Amendment No. 1
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i ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
The program shall include the following:
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Preventive maintenance and periodic visual inspection' require-1 ments, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less.-
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in. vital areas under accident conditions.
This program shall include the following:
1.
Training-of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
c.
Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant,_ radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
1.
Training of personnel, 2.
Procedures.for sampling and analysis, and 3.
Provisions for maintenance of sampling and analysis equipment.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title.10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise'noted.
STARTUP REPORT
- 6. 9.1.1 A summary report of plant startup and power escalation.-testing shall-be submitted following (1) receipt of an Operating License, (2)' amendment to the license involving a planned increase in power level, (3)-installation of
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fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the.
nuclear, tnermal, or hydraulic performance of the station.
- 6. 9.1. 2 The startup report shall address each of the tests-identified in the-Final Safety Analysis Report and shall include a description of the measured-values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifi-cations.
Any corrective actions that were required.to obtain satisfactory operati ihall also be described.
Any additional specific details required in license unditic s based on other commitments shall be' included in t-!s report.
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