ML20111B407
| ML20111B407 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/03/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20111B410 | List: |
| References | |
| NUDOCS 8501080631 | |
| Download: ML20111B407 (10) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20555
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t VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 59 License No. NPF-4 a
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the-licensee) dated July 26, 1983 as superseded March 30, 1984 complies.with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and egula-tions set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application,
-the provisions of the Act, and the ru as and regulations of the Comission; C.
There is reasonable assurance (i) th6t the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that suca r.;.tilities will be conducted in compliance with tha Comission's regJlations; D.
The issuance of,this amendment will not be-inimical to the comon defense and secur*fty 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 Comission's regulations and all applicable requirements have been satisfied.
8501080631 841203 i
PDR ADOCK 05000330 P
. 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.D.(2) of Facility Operating License No. NPF-4 is hereby
.:nended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, 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.
FOR THE NUCLEAR REGULATOR COMMISSION 4
me James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 3, 1984
d ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amemdment nuinber and contains vertical lines indicating the area of change.
The. corresponding overleaf page is also provided to maintain document completeness.
Page 6-19 i
L I
1 ADMINISTRATIVE CONTROLS (Continued) at least 60 days prior to cycle initial criticality unless otherwise approved by the Commission by letter.
In addition, in the event that the limit should change requiring a new submittal or an amended sub-l mittal to the Core Surveillance Report, it will be submitted 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter.
RTP Any additional information needed to support the F and P submittal willbebyrequestfromtheNRCandneednotbeincNdedin,this report.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- i 6.9.1.11 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.
i l
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compar-ison (as appropriate) with preoperational studies, operational controls, and previous environmental surveillance reports, and an assessment of.the observed impacts of the plant operation on the environment. The reports shall also j
include the results of land use censuses required by Specification 3.12.2.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental 4
radiation measurements taken during the period pursuant to the locations speci-fied in the-Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format'of the table in the t
Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a-supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program; at least two legible maps **
covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the sampling schedule of Table 4.12-1 and discussion of all analyses in which the LLD. required by Table 4.12-3 was not achievable.
- A single submittal may be made for a multiple unit station.
- 0ne map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
NORTH ANNA-UNIT 1 6-19 Amendment No. 37, $$, 59
i ADMINISTRATIVE CONTROLS (Continued)
S mIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT *'
6.9.1.12 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.
The period, of the first report shall begin with the date of initial criticality.
Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1. June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Radioactive Effluent Release Report shall be submitted within 60 days after January 1 of each year. This report shall include an assessment of the radiation doses to the maximum exposed MEMBERS OF THE PUBLIC due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. Annual meteorological data collected over the previous year shall be in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
This meteorological data shall be retained in a file on site and shall be made available to the NRC upon request.
All assumptions used in making these assessments (i.e.,
specific activity, exposure time and location) shall be included in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
Concurrent meteorological conditions or historical annual average atmospheric dispersion conditions shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
If the dose to the maximum exposed MEMBER OF THE PUBLIC due to the radioactive liquid and gaseous effluents from the station during the previous calendar year exceeds twice the limits of Specification 3.11.1.2a, 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11. 2. 3.a. or 3.11.2.3.b the dose assessment shall include the contribution from direct radiation.
The dose to the maximum exposed MEMBER OF THE PUBLIC shall show conformance with 40 C7R Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
The Radioactive Effluent Release Reports shall include a list of unplanned releases as required to be reported in Technical Specification 6.9.1.9.e from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the taporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP).and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
- A single submittal may be made for a' multiple unit station.
The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems. the submittal shall specify the releases of radioactive material from each unit.
NORTH ANNA - UNIT 1 6-20 Amendment No. 43 J
/
UNITED STATES T
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment.by Virginia Electric and Power Company (thelicensee)datedJuly 26, 1983 as superseded March 30, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regula-tions 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 Comission;.
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 Comission'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 amendmenc is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
i
' 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amencment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B,
.as revised through Amendment No. 43, are hereby incorporated in the license. The licensee shall opArate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h+
L t James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 3, 1984
,2
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 43 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 amemdment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Page 6-18 f
i i
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4 1
ADMINISTRATIVE CONTROLS b.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.
f c.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
d.
Reactivity anomalies involving disagreement with the predicted value i
of reactivity balance under steady-state conditions during power operation greater than or equal to 1% delta k/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in.the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if L
subcritical, an unplanned reactivity insertion of more than 0.5%
delta k/k; or occurrence of any unplanned criticality.
l e.
Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.
l f.
Personnel error or procedural inadequacy which prevents or could-prevent, by itself, the fulfillment of.the functional requirements of systems required to cope with accidents analyzed in the SAR.
g.
Conditions arising from natural or man-made events that, as a direct F
result of the event, require plant shutdown, operation of safety i
systems, or other protective measures required by technical specifications.
L h.
Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative
[
than assumed in the analyses.
s 1.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses
- ~
'in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require 4
remedial action or corrective measures to prevent the existence or development of an unsafe condition.
i l
1 4
4 NORTH ANNA - UNIT 2 6-17 i
i
ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of occurrence of the event. The written report shall include, as a minimum, a completed copy i
of the 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.
Reactor protection system or engineered safety feature instrument
- settings which are found to be less conservative than those estab-lished by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation, or plant shutdown required by a limiting condition for operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
d.
Abnormal degradation of systems other than those specified in item 6.9.1.8(c) above designed to contain radioactive material re witing i
from the fission process.
i, CORE SURVEILLANCE REPORT l
6.9.1.10 The F limit for Rated Thermal Power (F " ) in all core plares xy xy containing Bank "D" control rods and in all unrodded core planes, the surveillance power level, P.-for Technical Specifications i
3.2.1 and 3.2.6, and the F flyTpeck basis as determined using the definitionsandmethodologhinWCAP-8385andWestinghouseletterto NRC dated April 6,1978,. Serial No. NS-CE-1749 shall be provided to the Regional Administrator, Region II, with a copy to:
Director, Office of Nuclear Reactor Regulation Attention: Chief, Core Performance Branch U. S. Nuclear Regulatory Commission Washington, D. C. 20555 at least 60 days prior to cycle initial criticality unless other-wise approved by the Commission by letter.
In addition, in the i
event that the limit should change requiring a new submittal or an t
amended submittal to the Core Surveillance Report, it'will be submitted 60 days prior to the date the limit would become.
effective unless otherwise approved by the Connission by letter.
s
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NORlH ANNA-UNIT 2 6-18 Amendment No. J7,43 a
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