ML20236W274
| ML20236W274 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/29/1998 |
| From: | Dacimo F COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-06, GL-96-6, NUDOCS 9808050184 | |
| Download: ML20236W274 (4) | |
Text
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Commonweahh libusn Company IMalle Generating Station 2601 North 21st Road
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Marwilles. IL 613119757 Tel Mi 43574376I July 29,1998 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Supplemental Response to NRC Generic Letter (GL) 96-06 LaSalle County Nuclear Power Station, Unit 1 Facility Operating License NPF-11 NRC Docket No. 50-373
References:
1.
NRC Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated September 30,1996 2.
W. T. Subalusky (Comed) letter to the NRC Document Control Desk, " Response to NRC Generic Letter 96-06", dated June 4,1997 3.
NRC Generic Letter (GL) 96-06, Supplement 1,
" Assurance of Equipment Operability and Containment Integrity During Design-Basis l
Accident Conditions," dated November 13,1997 In response to the United States Nuclear Regulatory Commission (NRC)
Generic Letter 96-06 (Reference 1), Commonwealth Edison Company (Comed) committed, in part, to perform corrective actions to address the Reference 1 overpressurization conditions prior to restart of LaSalle Unit 1 from the current forced outage (L1F35) (Reference 2). The purpose of this letter is to inform the NRC of the status of these commitments, including
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i revising our commitment for Penetrations M-49 and M-50. Additionally, this hs \\\\ '
letter corrects a typographical error that was identified in the Reference 2 letter.
9808050184 980729 PDR ADOCK 05000373 i
P PDR A Unicom Company L
Penetrations M-49 and M-50; Status of Reactor Recirculation Flow Control
' Valve 1B33-F060A/B Hydraulic Piping l
l These penetrations are bounded by solenoid operated valves that are open l
during normal plant operation. The affected piping contains Fyrquel EHC l
fluid. LaSalle stated in Reference 2 that it is not appropriate to relieve the l
Fyrquel EHC fluid inside the drywell and that the appropriate fix will be implemented prior to unit startup. The final resolution for these penetrations has not been determined. LaSalle is revising the Reference 2 commitment and has performed an. interim operability determination. The operability l
determination is available at LaSalle Station if review is desired. Prior to startup from L1 R08, LaSalle will permanently resolve the GL 96-06 issues for LaSalle Unit 1 Penetrations M-49 & M-50, Reactor Recirculation Flow L
Control Valve,' 1833-F060A/B Hydraulic Piping.
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Typographical Correction L
in the enclosure to Reference 2, page 7 of 7 under the description of the Fyrquel l-EHC, it was stated that the fluid could contain as much as 20% water during l
operation. This % water is not correct, and should read 0.2% instead, which is consistent with vendor manual GEK-46357A, EHC Fluid Specification and L
Maintenance (VETIP Manual J-0843.000).
t Penetration M-36, Reactor Recirculation Sample Line Piping Reference 2 stated that a design change will be implemented to provide a l
pressure relieving device for Penetration M-36, Reactor Recirculation Sample -
L Line Piping, prior to startup. For LaSalle Unit 1, Design Change Package (DCP) 9700343 was implemented to add a bypass line with a new check valve around the inboard containment isolation valve. The new check valve is positioned -
l such that the trapped fluid between the containment isolation valves would be l
relieved to the larger volume of the Reactor Recirculation B Loop, which can not be isolated from the reactor vessel.
L Penetration M-30; Suction Piping to the Reactor Water Cleanup (RT)
Recirculation Purap i
Reference 2 stated that a design change will be implemented to provide a pressure relieving device for Penetration M-30, Suction Piping to the Reactor Water Cleanup (RT) Recirculation Pump, prior to startup. For LaSalle Unit 1, Design Change Package (DCP),9700518 was implemented to drill a vent hole in the inboard disc of the inboard containment isolation valve. Based on a calculation performed by the original valve manufacturer, the outboard disc I
would unseat at a pressure less than the piping maximum stress code allowable and provide a pressure relief path to the reactor vessel. The vent hole size was f
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selected compatible with the relief capacity of the isolated water volume
- following a LOCA. The valve function as a containment isolation valve will still I
be met because the leakage boundary of the outboard disc is maintained and will be ensured by the leak rate testing requirements of 10CFR50 Appendix J.
Penetrations M-16 and M-17, Supply & Return to the Reactor Building Closed Cooling Water Piping for the Seals of the Reactor Recirculation Pump l
Reference 2 stated that a design change will be implemented to provide a i
pressure relieving device for Penetrations M-16 and M-17, Supply & Return to the Reactor Building Closed Cooling Water Piping for the Seals of the Reactor Recirculation Pump, prior to startup. For LaSalle Unit 1, Design Change Package (DCP) 9700339 was implemented to add a relief valve between each penetration and its corresponding inboard containment isolation valve. The new relief valve discharges the relief capacity directly to the containment atmosphere away from any safety related components.
Penetrations M-25, M-26, M-27, and M-28; Supply & Return to the Chilled Water Piping for the Primary Containment Ventilation Heat Exchanger Coils I
Reference 2 stated that a design change will be implemented to provide a pressure relieving device for Penetrations M-25, M-26, M-27, and M-28, Supply
& Return to the Chilled Water Piping for the Primary Containment Ventilation Heat Exchanger Coils, prior to startup. For LaSalle Unit 1, Design Change Packages (DCP) 9700335 and 9700336 were implemented to add a relief valve between each penetration and its corresponding inboard containment isolation valve. The new relief valve discharges the relief capacity directly to the containment atmosphere away from any safety related component.
Penetration M-7, Residual Heat Removal (RHR) Piping for Shutdown Cooling Mode RHR Pump Suction Piping from Reactor Recirculation Reference 2 stated that a design change will be implemented to provido a pressure relieving device for Penetration M-7, Residual Heat Removal (RHR)
Piping for Shutdown Cooling Mode RHR Pump Suction Piping from Reactor Recirculation, prior to startup. For LaSalle Unit 1, Design Change Package (DCP) 9700341 was implemented to add a relief valve between the penetration and the inboard containment isolation valve. The new relief valve discharges the relief capacity directly to the containment atmosphere away from any safety related components.
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i If there are any questions or comments concerning this letter, please refer them to Harold D. Pontious, Jr., Regulatory Assurance Manager, (815) 357-6761, extension 2383.
Res etfully, f
~V l
Fred R. Dacimo Site Vice President LaSalle County Station 1
cc:
C. A. Paperiello, Acting NRC Region 111 Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle l
F. Niziolek, Office of Nuclear Facility Safety - IDNS 1
f o_______________________________
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