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| e a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,, VIRGINIA 23261 R.H.LEASBURG VICE PRESIDENT NucLEA.R OPERATIONS June 16, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Serial No. NO/GSS:ddp Docket Nos. Operating Reactors Branch No. 1 Division of Licensing License Nos. 355 50-280 50-281 DPR-32 DPR-37 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen: | | e a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,, VIRGINIA 23261 R.H.LEASBURG VICE PRESIDENT June 16, 1982 NucLEA.R OPERATIONS Mr. Harold R. Denton, Director Serial No. 355 Office of Nuclear Reactor Regulation NO/GSS:ddp Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D.C. 20555 Gentlemen: |
| AMENDMENT TO OPERATING LICENSE DPR-32 AND DPR-37 SURRY POWER STATION UNITS NO. 1 & 2 PROPOSED TECHNICAL SPECIFICATION CHANGE Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an Amendment, in the form of changes to the Technical Specifications, to Operating License DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 & 2. The proposed changes are enclosed. | | AMENDMENT TO OPERATING LICENSE DPR-32 AND DPR-37 SURRY POWER STATION UNITS NO. 1 & 2 PROPOSED TECHNICAL SPECIFICATION CHANGE Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an Amendment, in the form of changes to the Technical Specifications, to Operating License DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 |
| The proposed change is to revise specification 6.7(A) Environmental cations, to extend the deadline for the Environmental Qualification of all safety related electrical equipment to the end of the second refueling outage after March 31, 1982. Surry Power Station Units 1 & 2 Technical Specifications 6.7(A) currently states the deadline of June 30, 1982 for the Environmental Qualification of all safety related electrical equipment. | | & 2. The proposed changes are enclosed. |
| The extended deadline is according to the Proposed Rule 10CFR50.49(h) dated January 15, 1982. Prior to issuance of the Operating License for Surry Power Station the Commission made favorable findings regarding compliance with all applicable regulatory requirements, including equipment qualification. | | The proposed change is to revise specification 6.7(A) Environmental Qualifi-cations, to extend the deadline for the Environmental Qualification of all safety related electrical equipment to the end of the second refueling outage after March 31, 1982. |
| Now, the main issue is regarding appropriate documentation for environmental qualification of Class lE equipment. | | Surry Power Station Units 1 & 2 Technical Specifications 6.7(A) currently states the deadline of June 30, 1982 for the Environmental Qualification of all safety related electrical equipment. The extended deadline is according to the Proposed Rule 10CFR50.49(h) dated January 15, 1982. |
| The NRC staff issued a Safety Evaluation Report for Surry setting forth the results of its analysis of Vepco's Submittals on the env:i,,r:onmental qualification of Class lE equipment. | | Prior to issuance of the Operating License for Surry Power Station the Commission made favorable findings regarding compliance with all applicable regulatory requirements, including equipment qualification. Now, the main issue is regarding appropriate documentation for environmental qualification of Class lE equipment. |
| In the SER, the NRC staff listed several issues not having satisfactory documentation for environmental qualification. | | The NRC staff issued a Safety Evaluation Report for Surry setting forth the results of its analysis of Vepco's Submittals on the env:i,,r:onmental qualification of Class lE equipment. In the SER, the NRC staff listed several issues not having satisfactory documentation for environmental qualification. There was some disagreement between Vepco and the staff on the interpretation of the DOR Guidelines and NUREG-0588 regarding the items listed in the SER. However, despite the unsettled technical positions, the SER did not contain any item which neeeded corrective action for the safe operation of the plant. |
| There was some disagreement between Vepco and the staff on the interpretation of the DOR Guidelines and NUREG-0588 regarding the items listed in the SER. However, despite the unsettled technical positions, the SER did not contain any item which neeeded corrective action for the safe operation of the plant. ---,., *--8206240344 820616 PDR.ADOCK 05000280 :P= -PDR .: w/cJe,,fr: | | --- ,., *- - |
| / Y'loo.oo | | w/cJe,,fr: |
| -e VIROINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton Vepco has been working to resolve all environmental qualification issues for Class lE equipment and is proceeding on an orderly schedule to provide adequate documentation or replace equipment. | | 8206240344 820616 PDR.ADOCK 05000280 |
| The schedule is based upon realistic assessments of equipment availability, procurement times, and plant refueling cycles. The continued operation of Surry pending resolution of the environmental qualification matter is justified based upon Vepco's responses dated August 24, 1981 to the staff's Equipment Evaluation Reports dated May 21, 1981, and upon the results reflected in the SER. Thus the interim operation of Surry Power Station does not pose any danger to the safety of the plant or any threat to public health. The requested change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not involve an unreviewed safety question. | | :P= -PDR .: / Y'loo.oo |
| We have evaluated this request in accordance with the criteria in 10CFR170.22 and it has been determined that a Class III license amendment fee is required. | | |
| A voucher check in the amount of $4,400 is enclosed in payment of the required fee. Attachments: | | - |
| Proposed Technical Specification Change Voucher Check No. 30299 for $4,400 cc: Mr. James P. O'Reilly, Regional Administrator Region II Very truly yours, | | VIROINIA ELECTRIC AND POWER COMPANY TO e |
| -COMMONWEALTH OF VIRGINIA) ) CITY OF RICHMOND ) ------~----- | | Mr. Harold R. Denton Vepco has been working to resolve all environmental qualification issues for Class lE equipment and is proceeding on an orderly schedule to provide adequate documentation or replace equipment. The schedule is based upon realistic assessments of equipment availability, procurement times, and plant refueling cycles. |
| ---e The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by R.H. Leasburg, who is Vice President-Nuclear Operations, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document _in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. -cL Acknowledged before me this / /o day of , 19 "y .;;i...
| | The continued operation of Surry pending resolution of the environmental qualification matter is justified based upon Vepco's responses dated August 24, 1981 to the staff's Equipment Evaluation Reports dated May 21, 1981, and upon the results reflected in the SER. Thus the interim operation of Surry Power Station does not pose any danger to the safety of the plant or any threat to public health. |
| * My Commission expires: ,,x -(,,, , 19 ~_::--. Notary Public (SEAL) | | The requested change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. |
| I (' (10-80) U.S. NUCLEAR REGULATORY COMMISSION | | It has been determined that this request does not involve an unreviewed safety question. |
| : 1. FEE FORM TYPE (Check one} REACTOR FACILITY FEE DETERMINATION INSTRUCTIONS.
| | We have evaluated this request in accordance with the criteria in 10CFR170.22 and it has been determined that a Class III license amendment fee is required. A voucher check in the amount of $4,400 is enclosed in payment of the required fee. |
| Fill-in items 1 through 14, as applicable, and send the original copy to the License Fee Management Branch. ., 3. ACCESSION NUMBER t2.°'24-~34(- | | Very truly yours, Attachments: |
| : 4. LICENSEE VePco 5. PLANT NAME AND UNIT(S) s u f?.Q 7. FEE REMITIED 8. LICENSEE FEE DETERMINATION C:LASSII CLASSY CLASS VI EXEMPT SUBJECT 10. TAC NUMBER ASSIGNED(/( available} | | Proposed Technical Specification Change Voucher Check No. 30299 for $4,400 cc: Mr. James P. O'Reilly, Regional Administrator Region II |
| e ~v, OIJ Mel..ff'A t-~c)At /PICA11 oAJ A/11.lt:E | | |
| : 11. APPROVAL LETIER ORDER AMENDMENT NUMBER(S) | | - e COMMONWEALTH OF VIRGINIA) |
| | ) |
| | CITY OF RICHMOND ) |
| | The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by R.H. Leasburg, who is Vice President-Nuclear Operations, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document _in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. |
| | -cL Acknowledged before me this / /o day of ~ , 19 "y .;;i... |
| | * My Commission expires: ,,x - ~ (,,, , 19 ~_::--. |
| | Notary Public (SEAL) |
| | |
| | I |
| | (' |
| | (10-80) |
| | U.S. NUCLEAR REGULATORY COMMISSION 1. FEE FORM TYPE (Check one} |
| | REACTOR FACILITY FEE DETERMINATION INSTRUCTIONS. Fill-in items 1 through 14, as applicable, and send the original copy to the License Fee Management Branch. |
| | ., 3. ACCESSION NUMBER |
| | : 4. LICENSEE t2.°'24-~34(- |
| | VePco |
| | : 5. PLANT NAME AND UNIT(S) s u f?.Q 7. FEE REMITIED 8. LICENSEE FEE DETERMINATION C:LASSII CLASSY CLASS VI EXEMPT NONE e ~v, ~ OIJ Mel..ff'A t-SUBJECT |
| | ~c)At /PICA11 oAJ |
| | : 10. TAC NUMBER ASSIGNED(/( available} |
| | A/11.lt:E |
| | : 11. APPROVAL DATE OF ISSUANCE LETIER ORDER AMENDMENT NUMBER(S) |
| : 12. NRG FEE DETERMINATION The above application has been reviewed in accordance with Section 170.22 of Part 170 and is properly categorized. | | : 12. NRG FEE DETERMINATION The above application has been reviewed in accordance with Section 170.22 of Part 170 and is properly categorized. |
| The above application has been reviewed in accordance with Section 170.22 of Part 170 and is incorrectly classified. | | The above application has been reviewed in accordance with Section 170.22 of Part 170 and is incorrectly classified. |
| Fee should be class(es): | | Fee should be class(es): |
| * n and is exempt from fees because ii is: Filed by a Government agency and is not for a power reactor. DATE OF ISSUANCE NONE For a Class I, II, or Ill amendment which results from an NRG request dated for the application and the amendment is to simplify or clarify License or Technical Specifications; has only minor safety significance; and is being issued for the convenience of NRG (must meet all of the criteria). | | * n and is exempt from fees because ii is: |
| Other (State reason therefor) | | Filed by a Government agency and is not for a power reactor. |
| ******-~-i v'* ~:,.. ...... . ' . ' *, /L+ ..... * .. ENT BRANCH USE ONLY (All others do not write below this line) DATE l DISTRIBUTION BY LFMB DL Branch Chief LFMB Exemption File LFMB Reactor File /.i ,.,}}
| | For a Class I, II, or Ill amendment which results from an NRG request dated for the application and the amendment is to simplify or clarify License or Technical Specifications; has only minor safety significance; and is being issued for the convenience of NRG (must meet all of the criteria). |
| | Other (State reason therefor) |
| | . v'* ~:,. ......i*,. |
| | ******-~- |
| | ' ' |
| | /L+ ..... *. |
| | ENT BRANCH USE ONLY (All others do not write below this line) |
| | DATE l |
| | DISTRIBUTION BY LFMB DL Branch Chief LFMB Exemption File LFMB Reactor File |
| | ,.,/.i}} |
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ML18153A7121995-07-20020 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,proposing Changes to Ts,By Establishing New Setpoint Limit for Steam Generator high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6971995-07-14014 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing Su Accumulators in Lieu of Isolation ML18152A1841995-02-14014 February 1995 Application for Amends to Licenses DPR-32 & DPR-37,revising TS 4.4.D to Permit Approved Exemptions to ILRT Frequency Requirements,Including one-time Exemption Request from Section III.D.1(a) of 10CFR50,App J for Surry Unit 2 ML18153B2111995-01-24024 January 1995 Application for Amends to Licenses DPR-32 & DPR-37,modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1601994-11-29029 November 1994 Application for Amends to Licenses DPR-32 & DPR-37,revising TSs to Implement Zirlo Fuel Cladding ML18153B1561994-11-22022 November 1994 Application for Amends to Licenses DPR-32 & DPR-37,deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1481994-11-10010 November 1994 Application for Amends to Licenses DPR-32 & DPR-37 to TS Re Changes to TS to Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0921994-10-11011 October 1994 Application for Amends to Licenses DPR-32 & DPR-37,modifying Surveillance Frequencies of Hydrogen Analyzers in Accordance W/Generic Ltr 93-05 ML18153B0491994-08-30030 August 1994 Application for Amends to Licenses DPR-32 & DPR-37,revising TS to Accomodate Core Uprating,In Accordance w/WCAP-10263, Review Plan for Uprating Licensed Power of PWR Power Plant. ML18153B0041994-07-14014 July 1994 Application for Amends to Licenses DPR-32 & DPR-37, Requesting Amendments in Form of Changes to TS to Eliminate Remaining References to cycle-specific Parameters in Surry TS ML18153A9651994-06-0909 June 1994 Application for Amends to Licenses DPR-32 & DPR-37,modifying in Part,Chemical & Vol Control Sys Specs & Safety Injection Sys Specs in Accordance w/NUREG-0452,Rev 4,NUREG-1431 & Generic Ltr 93-05 ML18153A8801994-02-25025 February 1994 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs.... ML18153B4301993-12-27027 December 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,changing TS to Revise Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML18153B3481993-10-19019 October 1993 Application for Amends to Licenses DPR-32 & DPR-37,adding Operability & Action Statements for RSHX Service Water Outlet Radiation Monitors to TS Table 3.7-6 & SRs for Monitors to TS Table 4.1-2 ML18153B3301993-09-29029 September 1993 Application for Amends to Licenses DPR-32 & DPR-37,modifying TS to Require Insp Frequency of Low Pressure Turbine Blades to Permit Blade Insp to Perform Concurrent W/Disk & Hub Insp ML18153D3951993-07-20020 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 Proposing Changes of Deletion of Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3901993-07-16016 July 1993 Application for Amends to Licenses DPR-32 & DPR-37,proposing Changes to TS to Permit Operation W/Three Degree Increase in Svc Water Temp Limit for Containment Air Partial Pressures of 9.1,9.2 & 9.35 Psia ML18153D3931993-07-16016 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 to Implement Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from Semiannual to Annual & Clarify Site Maps ML18153D3791993-07-0202 July 1993 Application for Amends to Licenses DPR-32 & DPR-37,updating Augmented Insp Program for Sensitized Stainless Steel to Incorporate Newer Code Requirements While Maintaining Increased Insp Philosophy of ASLB ML18153D3781993-07-0202 July 1993 Application for Amends to Licenses DPR-32 & DPR-37 Modifying TS to Include COLR Which Presents reload-specific Limits for Key Core Operating Parameters ML18152A4471993-05-0606 May 1993 Application for Amend to License DPR-37,modifying TS to Support Operation of Unit 2 w/100 Psi Reduction in RCS Nominal Operating Pressure Through End of Operating Cycle 12,per Enforcement Discretion Granted by NRC on 930504 ML18153D3141993-04-21021 April 1993 Application for Amends to Licenses DPR-32 & DPR-37,providing Clarification of Design Response Time of Containment Hydrogen Analyzers & Deleting Unnecessary Channel Check for Analyzers ML18153D3111993-04-21021 April 1993 Suppl to 930315 Application for Amends to Licenses DPR-32 & DPR-37,modifying LCO & Action Statements for Main Control Room & Emergency Switchgear Room Air Conditioning Sys ML18153D2771993-03-19019 March 1993 Application for Amends to Licenses DPR-32 & DPR-37,revising TS to Address Operation W/Control Rod Urgent Failure Condition ML18153D2691993-03-15015 March 1993 Application for Amends to Licenses DPR-32 & DPR-37,changing TS to Permit Use of Two New Main Control Room & Emergency Switchgear Room Air Conditioning Sys Chillers,When Fully Operational,To Meet LCO ML18153D2281993-01-26026 January 1993 Application for Amends to Licenses DPR-32 & DPR-37,adding NRC Std Fire Protection License Condition to Each OL & Relocating Fire Protection Requirements from TS to Updated Fsar,Per GL 86-10 & GL 88-12 ML20128A5221993-01-22022 January 1993 Amends 173 & 172 to Licenses DPR-32 & DPR-37,respectively, Revising TS to Modify Acceptance Criteria for Functional Testing of Anchor Darling Mechanical Snubbers ML18153D1971992-12-11011 December 1992 Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Operability Requirements for RCS Loop Stop Interlocks & Establishing Requirements for Operation of Loop Stop Valves ML18153D1681992-11-10010 November 1992 Application for Amends to Licenses DPR-32 & DPR-37, Specifying Action Statement for Operable Svc Water Flow Paths to Main Control & Emergency Switchgear Room Air Conditioning Condensers Governed by TS 3.14.C ML18153D1611992-10-26026 October 1992 Application for Amends to Licenses DPR-32 & DPR-37 to Increase Limit for Intermediate Range High Flux Reactor Trip Setpoint & to Eliminate Redundant Stipulation That Predicted Critical Rod Position Be Above Zero Power Insertion Limit ML18153D1171992-09-0404 September 1992 Suppl to 911230 Amend Applications 165 & 164 to Licenses DPR-32 & DPR-37,respectively,reinstating Allowed Outage Time for Surveillance Testing of Nonessential Svc Water Isolation Actuation Logic & Reformatting Logic ML18153D1141992-09-0404 September 1992 Application for Amends to Licenses DPR-32 & DPR-37,changing TS to Modify Acceptance Criteria for Functional Testing of Anchor/Darling Mechanical Snubbers to Reflect Replacement of Pacific Scientific Snubbers W/Anchor/Darling Snubbers ML18153D0871992-08-0707 August 1992 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Operating Requirements for Recirculation Mode Transfer (Rmt) Function,Including LCO Action Statement & SR for Rmt & Deleting RWST Max Vol Requirements ML18153D0861992-08-0404 August 1992 Suppl to 911008 Application for Amends to Licenses DPR-32 & DPR-37,upgrading Portions of Section 3.0 & 4.0,per Generic Ltr 87-09 to Restrict Changes of Operational Conditions While in LCO & Delaying Entry Into Action Statement ML18153D0701992-07-28028 July 1992 Application for Amends to Licenses DPR-32 & DPR-37,deleting Operability & SRs of Hydrogen Monitor from Explosive Gas Monitoring Instrumentation Requirements for Waste Gas Holdup Sys & Including Requirements to Submit Special Rept to NRC 1999-04-28
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Text
e a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,, VIRGINIA 23261 R.H.LEASBURG VICE PRESIDENT June 16, 1982 NucLEA.R OPERATIONS Mr. Harold R. Denton, Director Serial No. 355 Office of Nuclear Reactor Regulation NO/GSS:ddp Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D.C. 20555 Gentlemen:
AMENDMENT TO OPERATING LICENSE DPR-32 AND DPR-37 SURRY POWER STATION UNITS NO. 1 & 2 PROPOSED TECHNICAL SPECIFICATION CHANGE Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an Amendment, in the form of changes to the Technical Specifications, to Operating License DPR-32 and DPR-37 for the Surry Power Station, Units No. 1
& 2. The proposed changes are enclosed.
The proposed change is to revise specification 6.7(A) Environmental Qualifi-cations, to extend the deadline for the Environmental Qualification of all safety related electrical equipment to the end of the second refueling outage after March 31, 1982.
Surry Power Station Units 1 & 2 Technical Specifications 6.7(A) currently states the deadline of June 30, 1982 for the Environmental Qualification of all safety related electrical equipment. The extended deadline is according to the Proposed Rule 10CFR50.49(h) dated January 15, 1982.
Prior to issuance of the Operating License for Surry Power Station the Commission made favorable findings regarding compliance with all applicable regulatory requirements, including equipment qualification. Now, the main issue is regarding appropriate documentation for environmental qualification of Class lE equipment.
The NRC staff issued a Safety Evaluation Report for Surry setting forth the results of its analysis of Vepco's Submittals on the env:i,,r:onmental qualification of Class lE equipment. In the SER, the NRC staff listed several issues not having satisfactory documentation for environmental qualification. There was some disagreement between Vepco and the staff on the interpretation of the DOR Guidelines and NUREG-0588 regarding the items listed in the SER. However, despite the unsettled technical positions, the SER did not contain any item which neeeded corrective action for the safe operation of the plant.
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8206240344 820616 PDR.ADOCK 05000280
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-
VIROINIA ELECTRIC AND POWER COMPANY TO e
Mr. Harold R. Denton Vepco has been working to resolve all environmental qualification issues for Class lE equipment and is proceeding on an orderly schedule to provide adequate documentation or replace equipment. The schedule is based upon realistic assessments of equipment availability, procurement times, and plant refueling cycles.
The continued operation of Surry pending resolution of the environmental qualification matter is justified based upon Vepco's responses dated August 24, 1981 to the staff's Equipment Evaluation Reports dated May 21, 1981, and upon the results reflected in the SER. Thus the interim operation of Surry Power Station does not pose any danger to the safety of the plant or any threat to public health.
The requested change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
It has been determined that this request does not involve an unreviewed safety question.
We have evaluated this request in accordance with the criteria in 10CFR170.22 and it has been determined that a Class III license amendment fee is required. A voucher check in the amount of $4,400 is enclosed in payment of the required fee.
Very truly yours, Attachments:
Proposed Technical Specification Change Voucher Check No. 30299 for $4,400 cc: Mr. James P. O'Reilly, Regional Administrator Region II
- e COMMONWEALTH OF VIRGINIA)
)
CITY OF RICHMOND )
The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by R.H. Leasburg, who is Vice President-Nuclear Operations, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document _in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
-cL Acknowledged before me this / /o day of ~ , 19 "y .;;i...
- My Commission expires: ,,x - ~ (,,, , 19 ~_::--.
Notary Public (SEAL)
I
('
(10-80)
U.S. NUCLEAR REGULATORY COMMISSION 1. FEE FORM TYPE (Check one}
REACTOR FACILITY FEE DETERMINATION INSTRUCTIONS. Fill-in items 1 through 14, as applicable, and send the original copy to the License Fee Management Branch.
., 3. ACCESSION NUMBER
- 4. LICENSEE t2.°'24-~34(-
VePco
- 5. PLANT NAME AND UNIT(S) s u f?.Q 7. FEE REMITIED 8. LICENSEE FEE DETERMINATION C:LASSII CLASSY CLASS VI EXEMPT NONE e ~v, ~ OIJ Mel..ff'A t-SUBJECT
~c)At /PICA11 oAJ
- 10. TAC NUMBER ASSIGNED(/( available}
A/11.lt:E
- 11. APPROVAL DATE OF ISSUANCE LETIER ORDER AMENDMENT NUMBER(S)
- 12. NRG FEE DETERMINATION The above application has been reviewed in accordance with Section 170.22 of Part 170 and is properly categorized.
The above application has been reviewed in accordance with Section 170.22 of Part 170 and is incorrectly classified.
Fee should be class(es):
- n and is exempt from fees because ii is:
Filed by a Government agency and is not for a power reactor.
For a Class I, II, or Ill amendment which results from an NRG request dated for the application and the amendment is to simplify or clarify License or Technical Specifications; has only minor safety significance; and is being issued for the convenience of NRG (must meet all of the criteria).
Other (State reason therefor)
. v'* ~:,. ......i*,.
' '
/L+ ..... *.
ENT BRANCH USE ONLY (All others do not write below this line)
DATE l
DISTRIBUTION BY LFMB DL Branch Chief LFMB Exemption File LFMB Reactor File
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