ML20195J967
| ML20195J967 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/16/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195J971 | List: |
| References | |
| NUDOCS 9906210169 | |
| Download: ML20195J967 (7) | |
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UNITED STATES si j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. ensas anni
' +, * * * *
- ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 152 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 January 25,1999, as supplemented by letter dated April 16,1999, complies with I
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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; O.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the J
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.
9906210169 990616 PDR ADOCK 05000382 P
. 2.
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 Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.152, 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.
i 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date ofissuance.
FOR THE NUCLEAR REGULATORY COMMISSION bA lMC Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: June 16, 1999
ATTACHMENT TO LICENSE AMENDMENT NO.152 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove IDss!!
6-1 6-1 6-13 6-13 6-14 6-14 6-24 6-24
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 4
6.1.1 The General Manager Plant Operations shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
The General Manager Plant Operations or hiis designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that may affect nuclear safety.
6.1.2 The Shift Superintendent, or during his absence from the control room, a designated individual shall be responsible for the control room command fu,nction. A management directive to this effect, signed by the Vice President Operations, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate managemer,t, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating crganization -
positions. These relationships shall be documented and updated, as appropriate, in the form of omanization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR.
b.
The General Manager P! ant Operations shall be responsible for overall unit safe operation and shall have control over tho'se onsite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 UNIT STAFF s.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; WATERFORD - UNIT 3 6-1 AMENDMENT NO. 10,41,00446 152
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e a
ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 1C CFR Part 50, and 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
AMENDMENT NO. 10,03,100, WATERFORD-UNIT 3 6-13 400 152
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Vice President Operations j
and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, and the Vice President Operations within 14 days l
of the violation.
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCLJURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below; s.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1g78 and Emergency Operating Procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Not used.
e.
Not used, f.
Fire Protection Program implementation.
g.
Modification of Core Protection Calculator (CPC) Addressable Constants, including independent verification of modified constants.
NOTES:
(1)
Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the PORC.
(2)
Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be applicable to the j
facility. Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limits values shall not be implemented without prior NRC approval.
h.
Administrative procedures implementing the overtime guidelines of Specification 6.2.2e., including provisions for documentation of deviations.
i.
PROCESS CONTROL PROGRAM implementation.
WATERFORD - UNIT 3 6-14 AMENDMENT NO. 5 "i,00,100,100 1$I
ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 2.
A determination that the change will rnaintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other
' applicable regulations.
b.
Shall become effective after the approval of the General Manager Plant Operations.
l 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retaine'd as required by Specification 6.10.3p. This document shall contain:
1.
Sumcient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2.
A determination that the change will maintain the level of radioactive emuent ccatrol required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the
. accuracy or reliability of emuent, dose or setp') int calculations.
b.
Shall become effective after the approval of the General Manager Plant Operations.
I c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Emuent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
The peak calculated containment intemal pressure for the design basis loss of coolant accident, P., is 44 poig.
l The maximum allowable containment leakage rate, l, is 0.5% of containment air weight per day atP j
WATERFORD - UNIT 3 6 24 Amendment No. 00 04,110,-424,446