ML18139B970: Difference between revisions

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| issue date = 07/01/1982
| issue date = 07/01/1982
| title = Notifies That Submittal of Tech Spec Responses Per Listed TMI Action Items Will Be Delayed Until 830101
| title = Notifies That Submittal of Tech Spec Responses Per Listed TMI Action Items Will Be Delayed Until 830101
| author name = LEASBURG R H, LEASBURG R J, LEASBURG R L
| author name = Leasburg R, Leasburg R, Leasburg R
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name = DENTON H R, EISENHUT D G
| addressee name = Denton H, Eisenhut D
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000000, 05000280, 05000281, 05000338, 05000339
| docket = 05000000, 05000280, 05000281, 05000338, 05000339
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=Text=
=Text=
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 R. H. LEASBURG VxcE PRESIDENT NUCLEAR OPERATIONS                       July 1, 1982 Mr. Harold R. Denton, Director                       Serial No. 395 Office of Nuclear Reactor Regulation                 NO/JHL/ddp Attn: Mr. Darrell G. Eisenhut, Director             Docket Nos. 50-280 Division of Licensing                                     50-281 U.S. Nuclear Regulatory Commission                                 50-338 Washington, D.C. 20555                                             50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:
VIRGINIA 23261 R. H. LEASBURG VxcE PRESIDENT NUCLEAR OPERATIONS July 1, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY EXCEPTIONS TO TECHNICAL SPECIFICATION REQUIREMENTS OF NUREG-0737 According to NUREG-0737, certain systems require submittal of Technical Specifications by July 1, 1982.           Vepco will submit the Technical Specifications for the following systems by January 1, 1983, Sections:
Serial No. 395 NO/JHL/ddp Docket Nos. 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 License Nos. VIRGINIA ELECTRIC AND POWER COMPANY EXCEPTIONS TO TECHNICAL SPECIFICATION REQUIREMENTS OF NUREG-0737 According to NUREG-0737, certain systems require submittal of Technical Specifications by July 1, 1982. Vepco will submit the Technical Specifications for the following systems by January 1, 1983, Sections:
II.B.3 - Modifications on Post-Accident Sampling, II.F.1.1 - Noble Gas Effluent Monitors, II, F .1. 2 - Sampling and Analysis of Plant Effluents, II.F.1.3       Containment High-Range Radiation Monitors, and II.F.1.6 Containemnt Hydrogen Monitors. In addition, Technical Specifications for Sections II.B.1- Reactor Coolant System Vents and II.F.2 - Installation of Instrumentation for Detection of Inadequate Core Cooling will be submitted by January 1, 1983. The Reactor Vessel Level Indication System (Section IL F. 2) has been installed and calibrated but it also requires a post-implementation review by the NRC Staff.       The Reactor Coolant System Vents (Section II.B..2) are also installed and they also require post-implementation review but they are dependent on the NRC Staff approval of the Reactor Vessel Level Indication System (Section II.F.2).
II.B.3 -Modifications on Post-Accident Sampling, II.F.1.1 -Noble Gas Effluent Monitors, II, F .1. 2 -Sampling and Analysis of Plant Effluents, II.F.1.3 Containment High-Range Radiation Monitors, and II.F.1.6 Containemnt Hydrogen Monitors.
Technical Specifications for Section II.F.1.4 Containment Pressure Monitors are installed but have open Equipment Qualification related items involved.
In addition, Technical Specifications for Sections II.B.1-Reactor Coolant System Vents and II.F.2 -Installation of Instrumentation for Detection of Inadequate Core Cooling will be submitted by January 1, 1983. The Reactor Vessel Level Indication System (Section IL F. 2) has been installed and calibrated but it also requires a post-implementation review by the NRC Staff. The Reactor Coolant System Vents (Section II.B..2) are also installed and they also require post-implementation review but they are dependent on the NRC Staff approval of the Reactor Vessel Level Indication System (Section II.F.2). Technical Specifications for Section II.F.1.4 Containment Pressure Monitors are installed but have open Equipment Qualification related items involved.
Technical Specifications for this system will also be supplied by January 1, 1983.
Technical Specifications for this system will also be supplied by January 1, 1983. The delay in submiting Technical Specifications for these systems will allow the coordination of Technical Specifications preparation along with the installation of these systems. Vepco will prepare Technical Specifications for the above systems using the guidance of the existing Technical Specifica-tions for similar or related systems. ~c:,l/t 820728012882070f PDR ADOCK 05000280 P PDR
The delay in submiting Technical Specifications for these systems will allow the coordination of Technical Specifications preparation along with the installation of these systems. Vepco will prepare Technical Specifications for the above systems using the guidance of the existing Technical Specifica-tions for similar or related systems.                                     ~c:,l/t 820728012882070f PDR ADOCK 05000280 P                     PDR
* -VIRGD!IA ELECTRIC AND POWER COMPANY TO Harold R. Denton If there are any questions regarding this information, please contact this office. cc: Mr. Steven A. Varga, Chief Operating Reactor Branch No. 1 Division of Licensing Mr. Robert A. Clark, Chief Operating Reactor Branch No. 3 Division of Licensing Very truly yours, R.H. Leasburg}}
 
VIRGD!IA ELECTRIC AND POWER COMPANY TO   Harold R. Denton If there are any questions regarding this information, please contact this office.
Very truly yours,
                                                            \J~~~
R.H. Leasburg cc:   Mr. Steven A. Varga, Chief Operating Reactor Branch No. 1 Division of Licensing Mr. Robert A. Clark, Chief Operating Reactor Branch No. 3 Division of Licensing}}

Latest revision as of 00:56, 3 February 2020

Notifies That Submittal of Tech Spec Responses Per Listed TMI Action Items Will Be Delayed Until 830101
ML18139B970
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 07/01/1982
From: Leasburg R, Leasburg R, Leasburg R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.2, TASK-2.B.3, TASK-2.F.1, TASK-2.F.2, TASK-TM 395, NUDOCS 8207280128
Download: ML18139B970 (2)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 R. H. LEASBURG VxcE PRESIDENT NUCLEAR OPERATIONS July 1, 1982 Mr. Harold R. Denton, Director Serial No. 395 Office of Nuclear Reactor Regulation NO/JHL/ddp Attn: Mr. Darrell G. Eisenhut, Director Docket Nos. 50-280 Division of Licensing 50-281 U.S. Nuclear Regulatory Commission 50-338 Washington, D.C. 20555 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY EXCEPTIONS TO TECHNICAL SPECIFICATION REQUIREMENTS OF NUREG-0737 According to NUREG-0737, certain systems require submittal of Technical Specifications by July 1, 1982. Vepco will submit the Technical Specifications for the following systems by January 1, 1983, Sections:

II.B.3 - Modifications on Post-Accident Sampling, II.F.1.1 - Noble Gas Effluent Monitors, II, F .1. 2 - Sampling and Analysis of Plant Effluents, II.F.1.3 Containment High-Range Radiation Monitors, and II.F.1.6 Containemnt Hydrogen Monitors. In addition, Technical Specifications for Sections II.B.1- Reactor Coolant System Vents and II.F.2 - Installation of Instrumentation for Detection of Inadequate Core Cooling will be submitted by January 1, 1983. The Reactor Vessel Level Indication System (Section IL F. 2) has been installed and calibrated but it also requires a post-implementation review by the NRC Staff. The Reactor Coolant System Vents (Section II.B..2) are also installed and they also require post-implementation review but they are dependent on the NRC Staff approval of the Reactor Vessel Level Indication System (Section II.F.2).

Technical Specifications for Section II.F.1.4 Containment Pressure Monitors are installed but have open Equipment Qualification related items involved.

Technical Specifications for this system will also be supplied by January 1, 1983.

The delay in submiting Technical Specifications for these systems will allow the coordination of Technical Specifications preparation along with the installation of these systems. Vepco will prepare Technical Specifications for the above systems using the guidance of the existing Technical Specifica-tions for similar or related systems. ~c:,l/t 820728012882070f PDR ADOCK 05000280 P PDR

VIRGD!IA ELECTRIC AND POWER COMPANY TO Harold R. Denton If there are any questions regarding this information, please contact this office.

Very truly yours,

\J~~~

R.H. Leasburg cc: Mr. Steven A. Varga, Chief Operating Reactor Branch No. 1 Division of Licensing Mr. Robert A. Clark, Chief Operating Reactor Branch No. 3 Division of Licensing

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