ML20137Z322
| ML20137Z322 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/07/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097 86-013A, NUDOCS 8603130016 | |
| Download: ML20137Z322 (2) | |
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t VluGINEA ELucTunc Ann l'owuu Coxi'Axy Ricnwonn,V wnix:A unuoi l
W.L.Mtewas.f vien l'ame,oest
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Norteam orsma. ome l
March 7, 1986 I
Mr. Harold R. Denton, Director Serial No.
86 013A Office of Nuclear Reactor Regulation N0/ ALM / ace i
Attn Mr. Lester S. Rubenstein. Director Docket Nos. 50 338 PWR Project Directorate #2 50-339 Division of PWR Licensing A License Nos. NPF-4 i
U.S. Nuclear Regulatory Commission NPF-7 Vashington, D.C. 20555 r
Gentlement i
l VIRGIN!A E!.ECTRIC AND POWER COMPANY l
NORTH ANNA POWER STATION UNITS NO. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE r
REQUEST FOR ADDITIONAL INFORMATION Virginia Electric and Power Company letter dated February 6,1986 Serial No.86-013, contained a request for en amendment to the North Anna i
Technical Specifications to reflect the installation of a new inside i
containment isolation valve (TV1'.04A and TV2204A) in the letdown line.
l On February 25, 1986 several members of our respective staffs met to discuss this proposed Technical Specification change. As a result of this meeting additional information was requested by your staff concerning 1) why the existing orifice letdown valves do not meet Regulatory Guide 1.97 criteria and 2) why the new inside containment isolation valve will meet Regulatory Guide 1.97 criteria?
In our letter of January 31, 1984, Serial No. 054, to you, we identified l
the Reg. Guide 1.97 variables for North Anna. Item No. B-14 Containment f
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! solation Valve Position Indication, was identified as a Category 1
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l variable, which is required to be environmentally and seismically qualified.
The existing inside containment isolation valves for the letdown line are the orifice isolation valves. HCV 1200A B.C and HCV 2200A,B,C for Units 1 and 2 respectively. A review of the qualifications for the valve position indication revealed that the Unit i valves (HCV I
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1200A,B,C) are quc.iitted and the Unit 2 valves (HCV 2200A,B.C) are not qualified. Although, all of these valves have identical indication, the Unit 2 valves are not qualified because the valves are located below the flood level inside containment and the position indication (limit switch)
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l 1s not submersible.
Therefore, to comply with Reg. Guide 1.97 a new i
inside isolation valve with qualified position indication will be 1
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o vnmmi nu, m *=n %ru com=v m Mr. H.irold R. Denton installed in the Unit 2 letdown line. A similar installation is planned for Unit 1 to maintain similarity between the two units.
The new inside containment iso *ation valves will be installed above the flood level inside containment and will have qualified position
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indication that meets the requirement of Reg. Guide 1.97.
The new vals es will replace the letdown orifice isolation valves, relief valves RV1203 and RV2203, and remote manual valves HCV 1142 and liCV 2142 on the containment isolation valve Table 3.6-1 of the Technical Specifications.
If you have any questions, please contact us.
Very truly yours, m ('N s
O <, "'
W. L. Stewart cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. Morris V. Branch NRC Senior Resident Inspector North Anna Power Station Mr. Charles Price l
Department of Health 109 Governor Street l
Richmond, Virginia 23219 i
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