ML20155J010
| ML20155J010 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/06/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Tam P Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-43, REF-GTECI-ES, RTR-NUREG-0869, RTR-NUREG-0897, RTR-NUREG-1057, RTR-NUREG-869, RTR-NUREG-897, RTR-REGGD-01.082, RTR-REGGD-1.082, TASK-A-43, TASK-OR 2NRC-6-059, 2NRC-6-59, GL-85-22, TAC-62908, NUDOCS 8810250076 | |
| Download: ML20155J010 (2) | |
Text
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- t. PA 15077 June 6, 1986 United States Nuclear Regulatory Commission Washington, DC 20555 AG "V'
ATTENTION:
Mr. Peter Tam, Project Manager c7 Division of PWR Licensing - A t, p0 o Office of Nuclear Reactor Regulations
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 SER Confirmatory item 25, Containment Sump 50% Blockage Assumption
REFERENCES:
- 1) NUREG-1057
- 2) NUREG-0897, Rev. 1
- 3) NUREG-0869, Rev. 1
,w The BVPS-2 Safety Evaluation Report (SER), Ref' ence 1, confirmatory (V) '
t % r an,d transport analysis to justify the acceptability of the Regulatory item 25 recommends that Duquesne Light Company (DLC) pro ide a debris genera-Guide (R.G.) 1.82 (Rev. 0) assumption of 50% sump blockage af ter a LOCA.
Earl-ier responses to FSAR questions 480.2, 480.26 and 730.1 indicate that a minimum amount of fibrous insulation is employed within that containment and that a blockage of 50% of the flow area is assumed.
FSAR Section 1.8 indicates BVPS-2 meets the intent of the R.G. 1,82 (Rev. 0) and FSAR Section 1.9 indicates that BVPS-2 conforms with Standard Review Plan (SRP) Section 6.2.2 (Rev. 3).
Following the issue of the BVPS-2 SER, Generic Letter 85-22 was is-sued.
It states that this subject has been addressed in the efforts to resolve Unresolved Safety issue A-43 and it refers to the documented technical find-ings, Refennce 2.
The Generic Letter states that, as a result of these ef-forts, the staf f has issued R.G.1.82 (Rev.1) and SRP Section 6.2.2 (Rev. 4) which replace the 50% blockage assumption with a plant-specific debris evalua-tion.
However, the Generic Letter notes that the staff's regulatory analysis, Refer ice 3, does not support the @ plication of R.S.1.82 (Rev. 1) to any plant now licensed to operate or that is under construction.
As recomended in the Generic Letter, if an increase in the fibrous insulation on primary coolant system piping and components inside containment is considered after BVPS-2 becomes operational, its safety significance on potential sump blockage will be evaluated and reported in accordance with 10 CFR 50.59 and will appropriately consider available NRC guidance at that time.
8810250076 G60606 PDR ADOCK 05000412 M
m United States Nuclear Regulatory Commission Mr. Peter Tam, Project Manager SER Confirmatory item 25, f~}
Containnent Sump 50% Blockage Assumption g
Page 2 Based on the foregoing, DLC requests notification by July 31, 1986 that this SER confirmatory iten is closed.
DUQUESNE LIGHT COMPANY By A
J. J. Carey
/
Vice President JJS/kam cc: Mr. P. Tam, Project Manager Mr. L. Prividy NRC Resident Inspector Mr. W. Troskoski, Sr. Resident Inspector O
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