ML17058B886
| ML17058B886 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/09/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058B887 | List: |
| References | |
| NUDOCS 9308260097 | |
| Download: ML17058B886 (10) | |
Text
~g REGS
~o ty 0 $
+0 gO
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 N AGARA MOHAWK POWER CORPORATIO DOCKET NO 50-220 N
N MIL POINT NUCLEA STATION UNIT: NO.
D TO FACI Y 0 RATI G
CENS Amendment No.
144 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 26,
- 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; 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 changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
9308260097 930809%
- DOCK 05000220 P
PDQR
(2) ec ical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.144
, 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 the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 9, 1993 Robert A. Capra, Director Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
h
ATTACHMENT TO LICENSE AMENDMEN AMENDMENT NO. 1.44 TO FACILITY OPE TING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 360 361 Insert Pa es 360 361
6 6 R
abl rr n Ac ion 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 Sections 50.72 and 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC and the results of this review submitted to the SRAB and the Vice President - Nuclear Generation.
67 af Limi Vil in 6.7.1 The following actions shall be taken in the event a Safety Limitis violated:
a.
The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately.
b.
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 - Nuclear Generation and the SRAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety LimitViolation Report shall be prepared.
The report shall be reviewed by the SORC.
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.
The Safety LimitViolation Report shall be submitted to the Commission, within 30 days of the violation, and to the SRAB, and the Vice President - Nuclear Generation within 14 days.
6.8
~Pr
~dr 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.
a.
Written procedures shall be established, implemented, and maintained for activities involving the Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation by the branch manager for the functional area of the procedure or higher levels of management as governed by administrative procedures.
Each procedure and administrative policy of 6.8.1 above shall be reviewed periodically as set forth in administrative procedures.
AMENDMENTNO. )ME
.144 e
360
h
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed and approved within 14 days of implementation by the branch manager for the functional area of the procedure or higher levels of management as governed by administrative procedures.
6.9 R
in R
ir men In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted in accordance with 10 CFR 50.4.
aO d
t i
i hllb b i<<dftl of an operating license, (2) amendment to the license involving a planned increase power level, (3) installation of 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, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general 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 specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
AMENDMENTNO. )Mk 144 361