ML20235V599
| ML20235V599 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/09/1989 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235V603 | List: |
| References | |
| NUDOCS 8903100248 | |
| Download: ML20235V599 (10) | |
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION
@l,ICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF CALTON, GEORGIA DOCKET NO. 50-425 V0GTLE ELECTRIC GENERATING PLAhT, UNIT 2 FACILITY CFERATING LICENSE License No. NPF-79 1.
The Nuclear Regulatory Cormission (the Ccmissien or the NRC) has found that:
A.
The application for license filed by the Georgia Power Company (GPC)*
dcting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) complies with the standards and requirements 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 mace; B.
Construction of the Vogtle Electric Cenerating Plant, Unit 2 (the facility) has been substantially corrpleted in conformity with Construction Permit No. CPPR-109 and the application, as amended, the provisions of the Act and the regulaticos of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D.
below);
D.
There is reasonable assurance:
(i) that the activities authorized by this operating license can be concucted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in cornpliance with the Commission's regulations set Section 2.D. below)pter I (except as exempted from compliance in 48; forth in 10 CFR Cha o
000-l E.
Georgia Power Company is technically qualified to engage in the SS l
activities authorizeo by this license in accordance with the
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Commission's regulations set forth in 10 CFR Chapter I; ya
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- Georgia Power Company is authorized to act as agent for the Cglethorpe Pcwer E
Corporation, Municipal Electric Authority of Georgia and City of Dalton gj Georgia, and has exclusive responsibility and cor.troi over the physical,
ir a.c.
construction, operation, anc maintenance of the facility.
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F.
The. licensees have satisfied the applicable provisions ofl10 CFR Part 140, " Financial Protection Requirements and. Indemnity Agreements," of the Comission's regulations; G.
The issuance 'of this license will not be inimical to the comon -
defense and security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and o
considering available alternatives,'the issuance of this Facility Operating License No. NPF-79, subject to the conditions for-protection' of the environment set forth in the Environmental-Protection Plan attached as Appendix B, is in accordance with 10 CFR' Part 51 of the Comission's regulations and all applicable requirements have been satisfied;-
I.
The receipt, possession, and use of source, byproduct and special nuclear material-as authorized by this license will be in accordance with the Comission's regulations in 10 CFR. Parts.30, 40, and 70.
2.
Based on the foregoing findings and the Partial Initial Decision and the Concluding Partial Initial Decision issued by the Atomic Safety and Licensing Board on August 27 and December 23, 1986, respectively, regarding this facility and satisfaction of conditions therein imposed, Facility Operating License No. NPF-79, is hereby issued to the Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority -
uf Georgia, and City of Dalton, Georgia to read as-follows:
A.
This license applies to the Vogtle Electric Generating Plant, Unit 2, a pressurized water reactor and associated equipment (the facility) owned by GPC, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia..and City of Dalton, Georgia. The. -
facility is located on the licensees' site in Burke County, Georgia,
.on the west bank of the Savannah River approximately 25 miles south of Augusta, Georgia, and is described in Georgia Power Company's Final Safety Analysis Report, as supplemented-and amended, and in its Environmental Report, as supplemented and amended; B.
Subject to the conditions and requirements incorporated herein, the Comission hereby licenses:
(1) GPC, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this license; (2) Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, pursuant to the Act and 10 CFR Part 50, to possess the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this license;
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-(3)-..GPC, 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 '
j and amounts required for. reactor operation, as described in the-j Final Safety Analysis Report, as supplemented and amended,.
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-(4)' GPC,. pursuant to the-Act 'and 10- CFR Parts 30,.40 and 70 to j
receive, possess, and.use at any time any byproduct, source and 1
special-nuclear material as sealed neutron sources for1 reactor' startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as' fission detectors ~1n amounts as required; (5) GPC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to
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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-calibration or associated with radioactive apparatus or components; (6) GPC, pursuant to the Act and 10 CFR Parts.30', 40,'and 70, to
-possess, but not' separate, such byproduct and special nuclear materials as.may be produced by the operation of Vogtle Electric Generating Plant, Units 1.and 2.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations' set forth in 10 CFR Chapter I and is subject to all applicable provisions'of the Act and to the rules,' regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.
(1) Maximum Power Level GPC is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100 percent power) in accordance with the conditions specified herein.-
Pending further Commission approval, the facility may not be 1
operated at power levels exceeding 5 percent of full power (170 l
megawatts thermal).
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
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. i (3)
Initial Startus Test Program (Section 14, SIR)*
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59shallbereportedinaccordancewith50.59(b)withinone month of such change.
(4) Transamerica Delaval, Inc. (TDI) Diesel Generators (Section 9.5.4, SER ano SSERs 4 and 5)
GPC shall implement the TDI diesel generator requirements as specified in Attachment 1. is hereby incorporated into this license.
(5) NUREG-0737 Item II.F.2 (Section 4.4.8, SER and SSERs 1, 4,'7, and 8)
In accordance with NUREG-0737, Item II.F.2, GPC shall submit the proposed reactor vessel level instrumentation system (RVLIS) implementation report prior to comniercial operation.
(6) Pressurizer Surge Line Thermal Stratification (Section 3.6.3, SSErl 8)
GPC shall submit reports concerning their elastic-plastic analysis using code allowable values, hot functional temperature values, and forced cooldown values in accordance with the schedule contained in their letter of February 8, 1989. GPC shall submit a final evaluation concerning i
pressurizer surge line integrity and any remedial corrective i
i action for the NRC to review and confirra pressurizer surge line i
l integrity prior to issuance of a full-power license.
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D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, (b) on exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix J of 10 CFR Part 50, the testing of containment air locks at times when containment integrity is not required (c) an exemption from the schedule requirements of 10 CFR 50.33(k)(1) related to availability of funds for decommissioning the facility and (d) an exemption until April 1,1989, frcm the I
requirements of 10 CFR 50.54(w) related to property insurance. The l
special circumstances regarding exemptions b, c, and d are identified in Sections 6.2.6, 22.5, and 22.4 of SSER 8, respectively.
l The parenthetical notation following the title of some license conditions l
denotes the section of the Safety Evaluation Report and/or its supplements l'
wherein the license condition is discussed.
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.. An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1981, issued July 13, 1988, and relieved GPC from the requirement of having a criticality alarm system. GPC is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items b, c, and d above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission.
E.
GPC shall fully implement and maintain in effect all provisions of the Comission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Alvin W. Vogtle Nuclear Plant Physical Security Plan," with revisions submitted through July 11, 1988; "Alvin W. Vogtle Nuclear Plant Guard Training and Qualification Plan," with revisions submitted through January 15, 1988; and "Alvin W. Vogtle Nuclear Plant Safeguards Contingency Plan," with revisions submitted through January 6,1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
GPC shall comply with the antitrust conditions delineated in Appendix C to this license.
G.
GPC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as approved in the SER (NUREG-1137) through Supplement 8 subject to the following provision:
GPC may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
H.
Reporting to the Commission Except as otherwise provided in the Technical Specifications or i
Environmental Protection Plan, GPC shall report any violations of l
the requirements contained in Section 2.C. of this license in the l
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. following manner: initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the i
Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c),
and(e).
I.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as I
amended, to cover public liability claims.
J.
This license is effective as of the date of issuance and shall expire at midnight on February 9, 2029.
FOR THE NUCLEAR REGULATORY COMMISSION Awit {
Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. - TDI Requirements 2.
Appendix A - Technical Specifications 3.
Appendix B - Environmental Protection Plan 4.
Appendix C - Antitrust Conditions Date of Issuance: February 9, 1989 e
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following _ manner: initial-notific'ation shall be made within twenty-four (24) hours.to the.NRC Operations Center-via the Emergency Notification l System with written. follow-up within,30' days in~ accordance with the procedures described in 10 CFR 50.73(b),-(c),
and.(e).
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I; The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of-the Atomic Energy Act of 1954, as amended, to cover public liability claims.
J.
This' license is effective as of the date of. issuance and shall' expire at midnight on _ February 9,. 2029.
FOR THE-NUCLEAR R GULATORY COMMISSION-P Thomas E. Murley, Director
. Office of_ Nuclear Reactor Regulation
Enclosures:
- 1. - TDI Requirements 2.
Appendix A - Technical Specifications 3.
Appendix B.- Environmental Protection Plan
. 4.
Appendix _C - Antitrust Conditions Date of Issuance: February 9, 1989 l
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l February 9, 1989 ATTACHMENT 1 TO LICENSE NPF-79 TDI DIESEL ENGINE RE0VIREMENTS 1.
Changes to the maintenance and surveillance programs for the TDI diesel engines, as identified in Section 9.5.4.1 of Supplement 4 to the Vogtle Electric Generating Plant Safety Evaluation Report, shall be subject to the provisions of 10 CFR 50.59.
The frequency of the major engine overhauls referred to in the license conditions below shall be. consistent with Section IV.I. " Overhaul Frequency" in Revision 2 of Appendix II of the Design Review / Quality Revalidation report which was transmitted by letter dated May 1, 1986, from J. George, Owners Group, to H. Denton, NRC.
2.
Connecting rod assemblies shall be subjected to the following inspections at each major engine overhaul:
a.
The surfaces of the rack teeth shall be inspected for signs of fretting.
If fretting has occurred, it shall be subject to an engineering evaluation for appropriate corrective action, b.
All connecting-rod bolts shall be lubricated in accordance with i
the engine manufacturer's instructions and torqued to the specifi-cations of the manufacturer.
The lengths of the two pairs of bolts I
above the crankoin shall be measured ultrasonically are-and post-tensioning.
c.
The lengths of the two pairs of bolts above the crankpin shall be measured ultrasonically prior to detensioning and disassembly of the bolts.
If bolt tension is less than 93% of the value at installation, the cause shall be detemined, appropriate corrective action shall be taken, and the interval between checks of bolt tension shall be re-evaluated.
d.
All connecting-rod bolts shall be visually inspected for thread damage (e.g. galling), and the two pairs of connecting rod bolts above the crank pin shall be inspected by magnetic particle testing (MT) to verify the continued absence of cracking. All washers used with the bolts shall be examined visually for signs of galling or cracking, and replaced if damaged, e.
Visual inspection shall be performed of all external surfaces of the link rod box to verify the absence of any signs of service induced distress, f.
All of the bolt holes in the link rod box shall be inspected for thread damage (e.g., galling) or other signs of abnormalities.
In addition, the bolt holes subject to the highest stresses (i.e.,
the pair immediately above the crankpin) shall be examined with an appropriate nondestructive method to verify the continued absence of cracking. Any indications shall be recorded for engineering evaluation and appropriate corrective action.
. 3.
The cylinder blocks shall be subjected to the following inspections at the interval specified in the inspections:
a.
Cylinder blocks shall be inspected for " ligament" Cracks, " stud-to-stud" cracks and " stud-to-end" cracks as defined in a report
- by Failure Analysis Associates, Inc. (FaAA) entitled, " Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report no FaAA-84-9-11.1), dated December 1984.
(Note that the FaAA report specifies additional inspections to be performed for blocks with "known" or " assumed" ligament cracks). The inspection intervals (i.e., frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report.
In addition, the inspection method shall be consistent with or equiv-alent to those identified in the subject FaAA report.
b.
In. addition to inspections specified in the aforementioned FaAA
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report, blocks with "known" or " assumed" ligament cracks (as defined in the FaAA report) shall be inspected at each refueling outage to detennine whether or not cracks have initiated on the top surface exposed by the removal of two or more cylinder heads.
This process shall be repeated over several refueling outages until the entire block toD has been inspected. L14uid-Denetrant testing or a similarly sensitive nondestructive testing technique shall be used to detect cracking, and eddy current shall be used as appropriate to determine the depth of any cracks discovered.
c.
If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or " stud-to-end" cracks, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed dispsition and/or corrective actions have been approved by the NRC staff.
4.
The following air roll test shall be performed as specified below, except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources":
The engines shall be rolled over with the airstart system and with the cylinder stopcocks open prior to each planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but not more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown.
(In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service).
The origin of any water
- This report was transmitted to H. Denton, NRC, from C. L. Ray, Jr., TDI Owners Group, by letter dated December 11, 1984 I
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. detected in the cylinder must be determined and any cylinder head which leaks due to a crack shall be replaced.
The above air roll test may be discontinued following the first refueling outage subject to the following conditions:
All cylinder heads are Group III heads (i.e., cast after September a.
1980).
b.
Quality revalidation inspections, as identified in the Design Review /0uality Revalidation report, have been completed for all cylinder heads, Group III heads continue to demonstrate leak-free performance.
c.
This should be confirmed with TDI prior to deleting air roll tests.
5.
Periodic inspections of the turbocharger shall include the following:
The turbocharger thrust bearings shall be visually inspected for a.
excessive wear after 40 non-prelubed starts since the previous visual inspection.
b.
Turbocharger rotor axial clearance shall be measured at each refueling outage to verify compliance with TDI/Elliott specifications.
In addition, thrust bearing measurements shall be compared with measurements taken previously to determine a need for further inspection or corrective action.
Spectrographic engine oil and ferrographic engine oil (wear) analysis c.
shall be performed quarterly to provide early evidence of bearing degradation.
Particular attention shall be paid to copper level and particulate size which could signify thrust bearing degradation.
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