ML20155A449
| ML20155A449 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/02/1988 |
| From: | Kuncl L NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CNSS886131, IEB-85-003, IEB-85-3, NUDOCS 8806100070 | |
| Download: ML20155A449 (5) | |
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8 GENERAL OFFICE Nebraska Public Power District
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_ mmmmm CNSS886131 June 2, 1988 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Response to NRC Bulletin No. 85-03, St.opleme.c 1
Cooper Nuclear Station NRC Docket No. 50-298
References:
- 1) Letter from R. F. Janecek (BWR Owners' Group) to J. H. Sniezek (NRC), BWROG 8815/OTR1, dated March 28, 1988
- 2) Letter from J. M. Pilaat to R. D. Martin dated November 26, 1986, "Revised Response to IE Bulletin No. 85-03" Gentlemen:
Supplement 1 to IE Bulletin No. 85-03 directed BWR licensees to include inadvertent mispositioning of safety-related motor operated valves in certain high pressure systems within the scope of the bulletin. Any valves added as a result of this scope change were to be reported to the Commission, along with the pertinent information discussed in the bulletin.
Prior to its issuance, the intent of the supplement was discussed with the NRC staff by the BWR Owners' Group of which the District is a member.
Based on these discussions and a review of generic BWR high pressure piping configurations, nine (9) valves were identified by the Owners' Group to be added to the scope of the bulletin (Reference 1).
A review of these additional valves determined that only four (4) were applicable to Cooper Nuclear Station.
These four valves (HPCI-MOV-M017, HPCI-MOV-M020, RCIC-MOV-M018, and RCIC-MOV-M020) were already included in the District's previous response to the bulletin as contained in Reference 2.
As a result, the District considers its previous response to encompass the scope of Supplement 1 to the Bulletin and no additional valves will be added to our test program.
Per our original schedule, IE Bulletin 85-03 valve testing will be completed during the 1988 Spring Refueling Outage and the Phase II report will be submitted within 60 days of the completion of testing.
No further submittals are expected after the Phase II report, provided no additional guidance is received that would necessitate additional testing.
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U.S. Nuclear Regulatory Commission June 2, 1988 Page 2 Finally, enclosed is a revision to Table 2-1 (Reference 2) that changes the maximum expected operational differential pressure for five valves.
The affected valves are indicated by revision bars in the margin and the new
- differential pressure figures are generally more conservative than before.
These revised figures will be used in calculating the necessary valve thrust requirements used to determine torque switch settings.
If you have any questions or require further information, please call.
,OA L. G. Kuhel Nuclear Power Group Manager LCK/gmc:rs(2E)
Enclosure cc: Regional Administrator NRC Region IV Arlington, Texas NRC Senior Resident Inspector Cooper Nuclear Station a
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U.S. Nuclear Regulatory Commission June 2, 1988 Page 3 STATE OF NEBRASKA
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Platte County
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G. Kuncl, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this information on behalf of Nebraska Public Power Distr..
L, and that the statements contained herein are true to the best of his knowledge and belief.
L. G. }tuncl Subscribed in my presence and sworn to before me this $//)
day of O,I j fh0_ _
, 1988.
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Revised 06/88 NPPD-CNS IEB85-03 RESPONSE TABLE 2-1 MOV Data Summary Table (RCIC)
MAX. EXPECTED COMPONENT DESIGN OPERATIONAL REQUIRED IDENTIFICATION COMPONENT DIFFERENTIAL DIFFEFENTIAL ACTIVE CODE (CIC)
DESCRIPTION OPERATIONAL REQUIREMENTS PRESSURE PRESSURE OPERATION COMMENT RCIC-MOV-MOIS RCIC Steam Open for Core Cooling 1146 psi 1091 psi Close Valve not required Inboard Isolation Supply to be tested at Close for System Steam maximum A P Line Isolation RCIC-MOV-M016 RCIC Steam Open for Core Cooling 1146 psi 1091 psi Close Valve not required Outboard Isolation Supply to be tested at Close for System Steam maximum A P Line Isolation RCIC-MOV-M018 RCIC Supply from Open/Close for Core 50 psi 14 psi Close Emergency Conden-Cooling Supply sate Storage Tank RCIC-MOV-M020 System Pump Open for Core Cooling 1925 psi 1222 psi None Valve not required Discharge Block Supply to be tested at maximum A P RCIC-MOV-M021 RCIC Injection to Open for Core Cooling 1925 psi 1222 psi Open Reactor Supply RCIC-MOV-M027 RCIC Pump Minimum Close/Open for Core 1500 psi 1335 ps_i_
Open Flow Recirc to Cooling Supply 1338 psi Close Torus i
RCIC-MOV-M030 RCIC Test Close for Core Cooling 1923 psi 1299 pai None Valve not required Return to ECST Supply to be tested at maximum A P RCIC-MOV-M041 RCIC Supply from Close/Open for Core 50 psi 88 psi Open Torus Cooling Supply 65 psi Close RCIC-MOV-M0131 RCIC Steam Supply Open for Core Cooling 1146 psi 1091 psi Open to RCIC Turbine Supply RCIC-MOV-M0132 Auxiliary Coolinh Open for Core Cooling 1500 psi 1311 psi Open Supply Supply Paea H @2 2
9 Revised 06/88 NPPD-CNS
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IEB85-03 RESPONSE TABLE 2-1 MOV Data Summary Table (HPCI)
MAX. EXPECTED COMPONENT DESIGN OPERATIONAL REQUIRED IDENTIFICATION COMPONENT DIFFERENTIAL DIFFERENTIAL ACTIVE CODE (CIC)
DESCRIPTION OPERATIONAL REQUIREMENTS PRESSURE PRESSURE OPERATION COMMENT HPCI-MOV-M014-Steam Supply to Open for Core Cooling 1146 psi 1091 psi Open Turbine Supply
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11PCI-MOV-M !G i Steam Supply Open for Core Cooling 1146 psi 1091 psi Close Valve not required to be tested at Inboard Isolation Supply maximum A P Close for System Steam l
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IHPCI-MOV-M016 Steam Supply Open for Core Cooling 1146 psi 1091 psi Close Valve not required Outboard Isolation Supply to be tested at Close for System Steam maximum A P Line Isolation 1-HPCI-MOV-M017 Pump Suction from, Open/Close for Core 150 psi 14 psi Close Emergency Conden-Cooling Supply sate Storage Tank IIPCI-MOV-M019 HPCI Injection Open/Close for Core 1325 psi 1118 psi Open Cooling Supply HPCI-MOV-M020 Steam Pump Open for Core Cooling 1925 psi' 1118 psi None Valve not required Discharge Block Supply to be tested at maximum A P HPCT-MOV-M021 HPCI Pump Test. -
Close for Core Cooling 1925 psi 1284 psi None Valve not required l
Eypass to ECST Supply to be tested at maximum a P s
l HPCI-MOV-M025 HPCI-Pump Minimum Close/Open for Core 1500 psi 1326 psi p'
Open Flow Bypass Line Cooling Supply 1340 psi Close l
Isolation' Close/_ pen for Core 150 psi 98 psi Open O
HPCI-MOV-M058 HPCI Pump Suction from Suppression Cooling Supply 64 psi Close l
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