ML19323B062
| ML19323B062 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/11/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19309H415 | List: |
| References | |
| NPF-7, NUDOCS 8005090191 | |
| Download: ML19323B062 (15) | |
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-339 NORTH ANNA POWER STATION, UNIT N0. 2 LICENSE FOR FUEL LOADING AND LOW POWER TESTING License No. NPF-7 1.
The Nuclear Regulatory Commission (the Comission) having found that:
A.
The application for license filed by the Virginia Electric and Power Company (the licensee) complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B.
Construction of the North Anna Power Station, Unit No. 2 (facility) has been substantially completed in conformity with Construction Permit No. CPPR-78 and the application, as amended, the provisions of the Act and the regulations of the Comission; C.
The facility requires an exemption from certain requirements of Appendix J to 10 CFR Part 50. This exemption is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No.10. This exemption is authorized by law and will not endanger life or property or the comoc +fense and security and is otherwise in the public interest. The exemption is, therefore, hereby granted. With the granting of this exemption, the facility will operate, to the extent authorized herein, in conformity with the application, as emended, the provisions of the Act, and the rules and regulations of the Comission.
D.
The facility will operate in conformity with the application, as amenced, the provisions of the Act, and the regulaticns of the Comission; E.
There is reascnable assurance: (1) that the activities authorized by this license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Ccmission;
. F.
Virginia Electric and Power Company is technically and financially qualified to engage in the activities authorized by this license in accordance with the regulations of the Commission; G.
The Virginia Electric and Power Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and
'ndemnity Agreements", of the Commission's regulations; H.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; I.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of License No. NPF-7 subject to a condition for protection of the environment set forth herein is in accordance with 10 CFR Part 51, of the Commissicn's regulations and all applicable requirements have been satisfied; and J.
The receipt, possession, acd use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Part 30, 40, and 70, including 10 CFR Sections 30.33, 40.32, 70.23 and 70.31.
2.
Pursuant to approval by the Nuclear Regulatory Commission at a meeting on April 10, 1980 License No. NPF-7 is hereby issued to the Virginia Electric and Pcwer Ccmpany to read as folicws:
A.
This license applies to the North Anna Power Station, Unit No. 2, a pressurized water nuclear reactor and associated equiprent (the facility),
cwned by the Virginia Electric and ?cwer Ccacany (VEPCO). The facility is located near Mineral in Lcuisa County, Vircinia and is described in the " Final Safety Analysis Repert" as suppiemented and amended (Amendments 17 througn 68) and the Environmental Re ert as supplemented and amended (Supplements 1 througn 4).
B.
Subject to the conditions and requirements incorporated herein, the Commissicn hereby licenses VEPCO:
(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to pcssess, use, and cperate the facility at the cesignated lccation in Lcuisa Ccunty, Virginia, in accordance with the limitatiens set forth in this license;
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(2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calit ration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
VEPCO is authorized to perform steam generator moisture carryover studies at the North Anna Power Station. These studies involve the use of an aqueous tracer solution of two (2) curies of sodium-24.
VEPC0's personnel will be in charge of conducting these studies and be knowledgeable in the procedures. VEPC0 will impose personnel exposure limits, posting, and survey requirements in conformance with those in 10 CFR Part 20 tc minimize personnel exposure and contamination during the studies.
Radiological controls will be established in the areas of the chemical feed, feedwater, steam, condensate and sampling systems where the presence of the radioactive tracer is expected to warrant such controls. VEPC0 will take special precautions to minimize radiation exposure and contamination during both the handling of the radioactive tracer prior to injection and the taking of system samples l.
following injection of the tracer. VEPC0 will insure that all regulatory requirements for liquid discharge are met during disposal of all sampling effluents and when reestablishing continuous bicwdcwn frcm the steam generators after completion of tne studies.
D.
This license shall be deemed to contain and is subject to the conditions specified in the following Comission regulaticns in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 20.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulaticns, and orders of the Ccmission acy cr hereafter in effect; and is subject to the additional conditions specified or incorporated below:
-4 (1) Maximum Power Level VEPC0 is authorized to Ia) load fuel, (b) proceed to initial criticality, (c) perform startup testing at zero power in Operational Mode 2, and (d) after prior written approval by the Director of Nuclear Reactor Regulation, operate the facility for testing at reactor core power levels not in excess of 139 megawatts thermal (five percent of rated power).
(2)
Technical Specifications The Technical Specif. cations contained in Appendices A and B attached hereto are hereby incorporated into this license.
VEPC0 shall operate the facility in accordance with the Technical Specifications.
(3) Secondary Water Chemistry VEPC0 shall perform a secondary water chemistry program to inhibit steam generator tube degradation. This program shall include:
a.
Identification of a sampling schedule for the critical parameters and control points for these parameters; b.
Identification of the procedures used to quantify parameters that are critical to centrol points; c.
Identification of process sampling points; d.
?recedure for the recording and management of data; e.
Precedures defining corrective actions for off centrol point chemistry conditions; and f.
A procedure identifying the authcrity responsible for the data and the sequence and timing of acainistrative 0 Vents required to initiate c0rrective action.
g.
Senitor the cencensate at the affluent en the c:ndensate pump. When cencenser leakage is confirmac repair or plug the leak in accordance with Branen Technical Position MTE3 5-3.
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5-(4)
Initial Test Program VEPC0 shall conduct the post-fuel-loading initial test program (set forth in Section 14 of the Final Safety Analysis Report and its amendments) that has been reviewed and approved by the Connission at the time of issuance of this license without making any major modification of this program. Major modifications are deemed to involve unreviewed safety questions under 10 CFR Section 50.59 and are defined as:
a.
Elimination of any test identified in Section 14 of the Final Safety Analysis Report as essential.
b.
Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of the Final Safety Analysis Report as essential.
c.
Performance of any test at a power level different from there described.
d.
Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized powerlevel).
(5) Fuel lead and Zero Power (i.e., oower recuired to perform chysics testing) Testing Conditions The following conditions shall be ccmpleted to the satisfaction of the Commission. Unless otherwise noted, these conditions shall be completed prior to fuel loading. The following conditions are related to matters specified in the TMI Action Plan, Near Term Operating License (NT0L) Requirements, dated February 6,1980, and applicable to feel load and zero power testing. Each of the following conditions references the appropriate section of Part II of Supplement No.10 to the Safety Evaluation Report (NUREG-0053 Suppl. No.10) for the North Anna Power Station, Unit 2 and follows the numbering sequence utilized in the February 6,1980 NTOL Requirements list.
a.
Shift Technical Advisor (!.A.I.1)
VEPC0 shall provide on each shift a Shift Technical Advisor (STA) whose principal cuty shall be to act as an advisor to the shift supervisor primarily in assessing accicent/ transient occurrences.
During 1980, at least one Senior Reactor Cperator (SRO) or an ex:eriencad degreed engineer who is a memcer of :he site Safety Engineering Staff shall be cesignated as the Shift Technical Advisor.
. The STA shall interface with the Safety Engineering Staff whose function is to perform operating experience assessments, for the purpose of disseminating operating experience to the other members of the plant staff.
At no time shall the SR0/STA, who is under the functional supervision of the Shift Supervisor, assume command or control function nor function as the Shift Supervisor or Assistant Supervisor.
b.
Shift Suoervisor Duties (I. A.l.2) and Shift Personnel Responsibilities (I.C.3)
VEPC0 shall issue a management directive, signed by the highest level of corporate management, which emphasizes t'
- assignment of primary management responsibility to the Shift aupervisor.
This directive shall be reissued on an annual basis.
The responsibility of the Shift Supervisor shall be that defined in VEPC0 Administrative Procedure ADM-1.0, " Station Organization and Responsibility."
The shift supervisor shall remain in the control room at all times when either unit is operating in Modes 1, 2, 3 or 4, except that he may be allowed to De absent proviced an individual, other than the shift technical adviser, who ocssesses a valid SR0 license assumes the control room ccmmand function during his absence. The indivioual who assumes the control room cominand function must remain in the control rocm until the shift supervisor returns and reassumes the ccanand function.
The shift supervisor shall only be relievea by an individual who possesses a valid SR0 license. Indivicuals who do not possess i
a valid SR0 license, including members of station management, shall not relieve the shift supervisor, nor shall they direct the I
licensed activities of licensed coerators.
c.
Shift Manning (I. A.1.3)
The shift crew ccmposition for the coeraticn of North Anna, Unit 2, in conjunction with Unit I snall be in accordance with Table 6.2.1 cf the Technical Specifications. An additicnal recuirement is that one senior licensed coerator, licensed en Ncrth Anna, Unit 2 shall be stationec in the Unit 2 control recm at all times during Unit 2 operaticn in Modes 1 thrcugn 4
- VEPC0 shall have administrative procedures to assure that qualified individuals to man the operational shifts are readily available in the event of an abnormal or emergency situation.
These administrative procedures shall include provisions which limit the amount of overtine worked by licensed operators.
The need for a licensed operator to exceed the limits on over-time shall be infrequent. The limits on overtime work hours are:
(1) An individual should not be permitted to work more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> straight (not including shift turnover time).
(2) There should be at least a 12-hour break between all work periods (shift turnover time is included in this 12-hour break).
(3) An individual should not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period.
(4) An individual shculd not work more than 14 consecutive days without having 2 consecutive days off.
However, for those circumstances which arise requiring deviation from the above, such deviation may be authorized by the plant manager or high levels of the VEPC0 management in accordance with established procedures and with appropriate documentation of the cause.
d.
Revised Scope and Criteria for Licensing Examinations (I. A.3.1)
VEPC0 shall train all shift personnel (licensed and non-licensed) at North Anna Power Station, Units 1 and 2 in all the TMI related design changes which have been incorporated in the station.
e.
Organization and Management Criteria (I.B.I.1)
With respect to offsite technical support to the plant staff in the event of an emergency, VEPC0 shall develco procedures delineating the responsibility and authority of corporate office personnel in providing technical supper:.
The shift supervisor for Unit 2 shall report to an individual holding a senior operator license en Unit 2 (as required by Technical Specification 6.2) at all times during Unit 2 operation in Modes 1 through 5.
8 f.
Safety Engineering Grouc and Cnsite Evaluation Cacability, and Dissemination of Operating Excerience I.B.l.2 (!.5.1.4 and I.C.5)
VEPC0 shall establish an on-site Safety Engineering Staff which shall be technically responsible to off-site management. The plant Safety Engineering Staff shall combine the review functions of engineering assessment, evaluation and dissemination of plant operating experience, and functions of the Shift Technical Advisor. The group shall consist of at least seven engineers, four of whom shall be designated Shift Technical Advisor. The group shall functionally report to the station Superintendent of Technical Services and technically offsite to the Director, Safety Evaluation and Control.
The plant Safety Engineering Staff is required to function only on the day shift, Monday through Friday. The technical disciplines represented in the group shall be electrical, mechanical, radiation protection and nuclear. The duties and responsibilities of this group shall be as follows:
1.
Be cognizant of the scope and intent of the test program 2.
Be cognizant of the tests being conducted 3.
Be familiar with the operation of a pressurized water type reactor 4.
Provide daily status reports to the Director, Safety Evaluation and Control at the corporate office.
VEPC0 shall establish an onsite capability to evaluate operating history of North Anna Unit 2, in conjunction with that of North Anna Unit 1, and also plants of similar design.
g.
Shift Relief and Turnover Precedures (I.C.21 VEPC0 shall implement the shift and relief turnover procedures in accordance with VEPC0 Administrative Procedure ADM-29.3--
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" Conduct of Operations."
VE?C0 shall establish a system *o evaluate the effectiveness of the turnover procedures.
h.
Control Recm Access (I.C.O VEPC0 shall implement centrol recm access procedures in i
acccreance with ADM-6.0, " Control Recm Access."
. 1.
Degraded Core - Training (II.B.41
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VEPC0 shall initiate preparation of a program to ensure that all operating personnel are trained in the use of installed plant systems to control or mitigate an accident in which the core is severely damaged. The training program shall include the following topics:
Incore Instrumentation 1.
Use of fixed or movable incore detectors to determine extent of core damage and geometry changes.
2.
Use of thermocouples in determining peak temperatures; methods for extended range readings; methods for direct readings at terminal juncti_ons.
Excore Nuclear Instrumentation (NIS) 1.
Use of NIS for determination of void formation; void location basis for NIS respcnse as a function of core temperatures and density changes.
Vital Instrumentation 1.
Instrumentation response in an accident environment; failure sequence (time to failure, method of failure); indication reliability (actual vs. indicated level).
2.
Alternative methods for measuring flows, pressures, levels, and temperatures, a.
Determination of pressurizer level if all level transmitters fail.
b.
Determination of letdown ficw with a clogged filter (low flav).
c.
Determination of other Reactor Coolant System parameters if the primary method of measurement has failed.
Primary Chemistry 1.
Expected chemistry results with severe core camage; consequences of transferring small quantities of liquid cutside containment; importance of using leak tignt systems.
2.
Expected isotopic breakdcwn for core camage; for clad damage.
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Corrosion effects of extended immersion in primary water; time to failure.
Radiation Monitoring 1.
Response of Process and Area Monitors to severe damages; behavior of detectors when saturated; method for detecting radiation readings by direct measurement at detector output (overanged detector); expected accuracy of detectors at different locations; use of detectors to determine extent of core damage.
2.
Methods of determining dose rate inside containment from measurements taken outside containment.
Gas Generation 1.
Methods of H2 generation during an accident; other sources of gas (Xe, Kr); techniques for venting or disposal of noncondensibics.
2.
H flammability and explosive limit; sources of 0 2
2 In containment or Reactor Coolant System J.
Relief and Safety Valve Test (II.D.2)
VEPC0 shall carry out a testing program to qualify the relief and safety valves under expected operating ccnditions for design basis transients and accidents in accordance with the requirements and schedule provided in NUREG-0573, Section 2.1.2, as clarified in NRC letter to operating license applicants dated November 9, 1979.
k.
Relief and Safety Valve Position (II.D.5)
VEPC0 shall provide reactor system relief and safety valves with a positive indication in the control room derived frca a reliable valve position detection device or a reliable indication of flow in the discharge pipe. The indication shall comply with the requirements contained in NUREG-0578, Section 2.1.3.a, as clarified in NRC letter to operating license applicants dated November 9,1979.
Installation and calibration of control roan indicators shall be ccmpleted prior to operation in Mode 2.
1.
Auxiliary Feedwater Initiation and :ncication (!!.E.1.21 VEPC0 shall provide for automatic initiation of the auxiliary feedwater system and shall provide for inoication, in the control room, of auxiliary feedwater ficw to each steam generator.
These requirements shall ccmaly with NUREG-0573, Sections 2.1.7.a and 2.1.7.b, as clarified in NRC letter to operating license acpiicants dated Novemcer 9,1979.
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Inadequate Core Cooling - Subcooling Meter (II.F.2)
VEPC0 shall provide a subcooling meter to provide on-line indication of coolant saturation condition. The meter shall comply with the requirements of NUREG-0578, Section 2.1.3.b, as clarified in NRC letter to operating license applicants dated November 9,1979.
Inadequate Core Cooling - Additional Instrumentation (II.F.2) n.
VEPCO shall provide a design of additional instruments to provide an unambiguous indication of inadequate core cooling.
This requirement shall comply with NUREG-0578, Section 2.1.3.b, as clarified in NRC letter to operating license applicants dated November 9, 1979.
o.
Emergency Power for Pressurizer Equipment (II.G)
VEPCO shall provide emergency power for the pcwer-operated relief valves (PORVs), the PORV block valves and pressurizer level instrument channels. This requirement shall comply with NUREG-0578, Section 2.1.1, sub-section 3.2, as clarified in NRC letter to operating license applicants dated November 9, 1979. Calibration and checkout will be completed prior to operation in Mode 2.
p.
IE Bulletins on Measures to Mitigate Small Break LOCAs and Loss of Feecwater Accidents (II.K.1)
VEPC0 scall review the operating procedures and operator training related to the measures to mitigate small-break LOCAs and loss-of-feedwater transients. These requirements shall comply with Items 1 through 13 of IE Bulletin 79-06A, as modified by IE Bulletin 79-06C. The recuirements of Item 7(b) of IE Bulletin 79-06A have been superseded by the requirements set out in Section 2.0.6.a of this license.
q.
Imorove Licensee Facilities for Resconding to Emergencies -
Onsite Technical Succort Centar (III.A.l.2(a))
VEPC0 shall establish a technical support center to meet the January 1,1980 requirements of NUREG-0578, Section 2.2.2.b, as clarified by NRC letter to operating license applicants dated November 9, 1979.
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Improve Licensee Facilities for Resconding to Emernencies -
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Onsite Operational Supoort Center (!!!.A.l.2(D))
VEPC0 shall provide an onsite operational support center to meet the requirements of NUREG-0578, Section 2.2.2.c. as clarified by NRC letter to operating license applicants dated November 9, 1979.
s.
Emergency Preparedness of State and Local Governments -
Near-Term Actions (!!!.8 and !!!.B.1)
During the period of this license, VEPC0 shall maintain in effect an emergency plan that meets:
(1) Regulatory requirements of 10 CFR Part 50, Appendix E (2) Regulatory Position Statement in Regulatory Guide 1.101
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(March 1977)
(3) The Essential Planning Elements in NUREG-75/lli and Supplement 1 thereto defined by NRR as significant for fuel load and low power testing.
t.
In-Plant Radiation Monitoring - Partial (III.D.3.3)
VEPC0 shall provide equipment and associated training and procedures for accurately cetermining the airborne iodine concentration throughout the plant under accident conditions.
u.
Communications (III.A.3.3)
VEPC0 shall install and maintain direct dedicated telephone lines between the North Anna plant control room, Site Technical Support Center and NRC Incident Response Center in Bethesda, Maryland.
v.
Control Rocm Design (IV Item 1)
Prior to operation in Mode 2, VEPC0 shall implement the following corrective actions related to the control room:
(1) Add labeling and instrumentation demarcation to correct problems specifically identified by ESSEX (letter cated March 27, 1980). Assess the need for other imar;vements in the area of labeling and demarcation and mocify labeling and demarcate controls and displays as accr: riate (2) Color code annunicator windows as an aid in icentifying high priority alarms (3) Review, and improve where necessary. accinistrative controls used to ensure prc;er safety injection status
. (4) Correct problems associated with general maintenance and implement measures to prevent their recurrence (5). Institute controls to limit control room access (6) Test the adequacy of emergency lighting.
(7) Establish procedures to limit use of the public address system to plant related matters and take corrective action to reduce sound intensity in the control room.
(d) Conditions on Operations Beyond Zero Power Testing The following conditions shall be completed to the satisfaction of the Commission prior to proceeding beyond zero power testing.
The follow ng conditions are related to matters specified in the i
TMI Action -lan, Near Term Operating License (NTOL) Requirements dated February o,1980, and applicable to operation beyond zero aower testing. Each of the following conditions references the appropriate section of Part II of Supplement No.10 to the Safety Evaluation Report (NUREG-0053 Suppl. No.10) for the North Anna Power Station, Units 1 and 2 and folicws the numbering sequence utilized in the February 6,1980 NTOL Requirements list.
a.
Short-Term Effort-Analysis and Procedure Modifications (I.C.1)
VEPC0 shall revise its emergency operating instructions for dealing with small break LOCAs and inadequate core cooling based on its analysis of these events and the vendor guidelinas derived from these analyses. These requirements supersede the requirements specified in Item 7(b) of IE Bulletin 79-06A.
b.
NSSS Vendor Review of Lcw Power Test Procedures (I.C.7)
VEPCO's low pcwer test precedures shall be reviewed by the nuclear steam supply system vendor, Westinghouse, and documentation of the review sucmitted to NRC.
s c.
Low Power Test Program (I.G.1)
As set forta in Section I.G.1, VEPCO snall cotain staff approval of a low power test program.
d.
Additional Accident Monitorine Instrumentatien (II.F.1)
VEPCC shall ccmply with the requirements contained in NUREG-0578, Section 2.1.8.6 us clarified in NRC letter to operating license applicants catec Ncvemcer 9, 1979.
(7) Battery Rocm Ventilation System 1
Within 90 days from date cf issuance of :nis license, VEPCD shall provice for Ccmmission review an evaluation and assessmen:
of the industrial and safety hazards associated with the battery room ventilation system which exhausts air into one end of the control room. Proposed corrective actions including design modifications, if any, and an implementation schedule shall be included in this evaluation.
E.
VEPC0 shall report any violations of the requirements contained in Sections 2.0.(5) and (6) of this license in accordance with the prompt reporting requirements of Section 6.9.1.8 of Appendix A, which is attached to and is a part of this license.
F.
VEPC0 shall maintain and fully implement the physical security plan entitled, " Security Program, North Anna Power Station, Units 1 and 2,"
dated May 25, 1977, as amended, November 30, 1977, and revised September 25, 1978, October 25, 1978, January 12, 1979, March 23, 1979, April 30,1979, and December 1,1979, and as amended in accordance with the provisions of 10 CFR 50.54(p).
Pursuant to 10 CFR Section 2.790(d), the security plan is being withheld from public disclosure because it is deemed to be commercial or financial information within the meaning of 10 CFR Section 9.5(a)(4) and subject to disclosure only in accordance with 10 CFR Section 9.12.
G2 This license is subject to the following additional condition for the protection of the environment:
Before engaging in additional construction or operational activities which may result in an environmental impact that was not evaluated by the Commission, the licensee will prepare and record an environ-mental evaluation of such activity. When the evaluation indicates that such activity may result in a significant adverse environmental impact that was not evaluated, or that is significantly greater than that evaluated, in the Final Environmental Statement or any addendum thereto, VEPC0 shall provide a written evaluation of such activities and obtain prior approval frcm the Director, Office of Nuclear Reactor Regulation.
H.
If VEPC0 plans to remove or to ma'a significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents frcm the North Anna Power Station, the Staff should be notified in writing regardless of whether the change affects the amount of radioactivity in the effluents.
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This license is effective as of the date of issuance and shall expire one year after that date.
FOR THE NUCLEAR REGULATORY COMMISSION m
Harold R. Dentorr, Director Office of Nuclear Reactor Regulation
Attachment:
Appendices A and B Technical Specifications Date of Issuance:
Apg i1 D2')
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