ML20084A824
| ML20084A824 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/09/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084A828 | List: |
| References | |
| NUDOCS 8404250291 | |
| Download: ML20084A824 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Cornission) has found that:
A.
The application for anendment by Viroinia Electric and Power Company (the licensee) dated November 30, 1983, complies with the standards and requirements of the Atonic Energy Act of 1954, as amended (tho Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasnnable assurance (1) that the activities author 17ed by this amendment can he conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's reoulations; D.
The issuance of this amendment will not be ininical to the common defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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8404250291 840409 PDR ADOCK 05000338 s
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. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. NPF-4 is hereby anended to read as folinws:
(2) 7.chnical Specifications The Technical Specifii'ations contained in Appendices A and B, as revised through Amendment No. 55. art hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license,anendrient is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMtilSSION n3~
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. lanes R. Miller, Chief Operatino Reactors Branch #3 Division of Licensing i
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 9, 1984
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4 ATTACHMENTTOL(CENSEAMENDMENT MIENDMENT NO. t3 TO FACILITY OPERATINr. LICENSE NO. NPF-4 j
DOCKFM'O. 50-338 i
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Replace the folleving page of the Appendix A" Technical Specifications i.
I with the enclosz.d pace'ar, indicated. The revised page is identified by l
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amendment nu ' er anVcontains vertical fjren :ihdicating the area of change.
i The corresponding overleaf page is also provided to maintair', focoment comp?cteness.
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ADMINISTRATIVE CONTROLS ANNUALREPORhl 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reporcs required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposuresgreaterthan100 mrem /yrandtheirassogatedman-rem exposure according to work and job functions,-
e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
b.
The complete results of the steam generator tube inservice inspections performed during the report period (Reference Speci-fication 4.4.5.5.b.).
1/'A single submittal may be made for a multiple unit station. The submittal should combine those sections that are coninon to all units at the station.
2_/This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.
NORTH ANNA -' UNIT 1 6-15 Amendment No. 5
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ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the Reactor Coolant System PORVs l
or safety valves, shall be submitted on a monthly basis to the Director, Office of lianagement and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supple-mental reports, a licensee event report shall be completed and references shall be made to the original report date.
PROMPT NOTIFICATION WITH URITTEN F0LLOWUP 6.9.1.8 The types of event listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation,0f the circumstances surrounding the event.
a.
Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifications or failure to complete the required protective function.
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-NORTH ANNA - UNIT 1 6-16
. Amendment No. '), 5, 32, 55
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WASHINGTON, D. C. 20555
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VIRGIN!A ELECTRIC AND POWER COMPAtlY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT N0. 2 Af1ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for anendment by Virginia Electric and Power Company (the licensee) dated November 30, 1983, 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 conpliance with the Commission's regulations; D.
The issuance of this amendment' will not be inimical to the comon defense.and security or to the health and safety of the public;
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and E.
The issuance of this amendment is'in accordance with 10 CFR'Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license anendment, and paragraph ?.C.(?) of Facility Operatino License No. NPF-7 is hereby anended to read as follows:
(2) _ Technical Specificatinns The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMf1ISSION s&fk' c.
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Janes R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 9, 1984
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 37 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to naintain document completeness.
Page 6-16 l
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ADMINISTRATIVE CONTROLS 6.9.1.2 The startup report shall address each of the tests identified in the FSAR 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 specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.
6.9.1.3 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. -
ANNUAL REPORTS N 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, and other personnel (including c'ontractors) receiving exposures greater than 100 mrem /yr and their agsociated man-rem exposure according to work and job functions,t/ e.g., reactor operations and surveillance, inservice inspection, routi.ne maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements ~. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
1/
A single submittal may be made for a mtitiple unit station. The submittal should combine those sections that are common to all units at the station.
2_/
This tabulation supplements the requirements of 920.407 of 10 CFR Part 20.
NORTH ANNA - UNIT 2 6-15
ADMINISTRATIVE CONTROLS b.
The complete results of the steam generator tube inservice inspections performed during the report period (Reference Specifica tion 4.4.5.5.b. ).
MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the Reactor Coolant System PORVs l
or safety valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supple-mental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office or his designate no later than the first working day following the event, with a written followup report within 14 days.
The written followup report shall include, as a minimum, a completed copy of a licensee event report-form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a.
Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate the required j.
l protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifications or failure to complete the required protective function.
NORTH ANNA - UNIT'2L
.6-16 Amendment No. 37 b
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