ML20056D023
| ML20056D023 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/23/1993 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9308020168 | |
| Download: ML20056D023 (6) | |
Text
p Beaver Valley Power Station Shippmgport, PA15077-0004 JOHN D SIEBER (412) 393-5255 Sensor Vice President and Fax (412) 643-8069 cruet Nuclear onice, July 23, 1993 Nuclear Power Devesjon U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Subject:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Status of Outage Commitments On June 18,
- 1993, Beaver Valley Unit 1
completed its ninth refueling outage (1R9).
This provides notification of completion of the modifications which were implemented to address regulatory issues.
Attached for your.information is a
status of those modifications performed during 1R9.
Pleace be advised that the status of actions taken to satisfy Station Blackout commitments was previously addressed in our lotter dated June 21, 1993.
If you have any questions concerning this letter, please contact Nelson Tonet at (412) 393-5210.
I r
Sincerely,
[ T.
D.
Sieber
)
Attachment cc:
Mr. L.
W.
Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr.
G.
E.
Edison, Project Manager Mr. M.
L. Bowling (VEPCO)
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Beaver Valley Unit 1 (BV-1) i Ninth Refueling Outage (1R9)
Status of Outage Commitments 1.
Subject:
Instrument Air System (TAC 71624) j
References:
NRC Generic Letter (GL) 88-14 " Instrument Air Supply
[
Problems Affecting Safety-Related Equipment" dated 8/8/88.
DLC reply dated 2/14/90 to GL 88-14.
i NRC (A.
W.
De Agazio) letter dated 10/22/91 requested notification upon completion of actions.
Action:
Design Change Package (DCP) 1672 added an air filter and dryer in the BV-1 Containment Instrument Air j
system per the DLC reply to GL 88-14.
A surveillance
^
test of the air quality of the system performed subsequent to the completion of the modification indicated that all the acceptance criteria established for the system (dew point, particulate, oil and flammable gas) were met.
Status:
Complete
[
t f
l 2.
Subject:
Emergency Diesel Generator (EDG)
Fuel Oil Storage
}
(TAC 81766) l
References:
NRC Inspection Report 50-334/91-22; 50-412/91-21 dated 11/18/91.
NRC (A. W.
De Agazio) letter dated 11/25/91 requested notification upon completion of actions.
Action:
DCP-1860 installed a cross-connection on the BV-1 EDG fuel oil transfer pumps suction piping to correct a variance from the original design which had been identified during an internal BV-1 design review.
This modification was completed and operationally 4
accepted on 5/21/93.
Status:
Complete 4
5 J
I Page 1 of 5 r-r
i Beaver Valley Unit 1 (BV-1) l Ninth Refueling Outage (1R9)
Status of Outage Commitments 3.
Subject:
Conformance to Regulatory Guide (RG) 1.97 Steam Generator Wide Range Level (SGWRL) 1 (TAC M75944)
References:
NRC Inspection Report 50-334/89-25 and 50-412/89-23 dated 2/7/90.
BV-1 Unresolved Item 89-25-01 identified SGWRL RG 1.97 concerns.
NRC RG 1.97 Supplemental Safety Evaluation (SSE) for BV-1 dated 12/30/91.
NRC (A. W. De Agazio) letter dated 6/15/92 requested notification upon completion of actions.
Action:
DCP-1504 upgraded the SGWRL instrumentation to address the concerns of the RG 1.97 SSE and Unresolved Item 89-25-01.
This included isolating each instrument loop from its respective computer inputs with a
QA Category 1,
Class 1E isolation device and replacing SGWRL recorder.LR-FW-477 at the vertical board with three QA Category 1 recorders.
The modification was operationally accepted on 6/5/93.
i Status:
Complete 4.
Subject:
Conformance to Regulatory Guide 1.97 Containment Isolation Valves (TAC M75944)
References:
NRC RG 1.97 Safety Evaluation Report (SER) dated 11/20/89.
DLC response dated 1/30/90 to RG 1.97 SER.
NRC RG 1.97 SSE for BV-1 dated 12/30/91.
Action:
DCP-1514 upgraded the environmental and seismic qualification of limit switches for containment isolation valves located outside of containment.
This modification was operationally accepted on 6/7/93.
Status:
Complete Page 2 of 5
l Beaver Valley Unit 1 (BV-1) j
~
Ninth Refueling Outage (1R9)
Status of Outage Commitments i
t 5.
Subject:
Reactor Coolant System (RCS) Level Indications (TAC 69723, TAC 69724)
References:
NRC Generic Letter 88-17 " Loss of Decay Heat Removal" dated 10/17/88.
DLC supplemental reply dated 1/31/93 to GL 88-17.
NRC Inspection Report 50-334/90-20 and 50-412/90-28 dated 2/27/91.
Unresolved Items 90-28-02 (for each unit) identified concerns for mid-loop operation.
Action:
DCP-1230 (and DCP-1018 for BV-2 during 2R3) provided instrumentation for use during refueling, reduced inventory and mid-loop operation.
Each DCP permanently installed an ultrasonic sensor mounting bracket on the "A"
hot leg near RHR suction.
When
- needed, an ultrasonic sensor is installed in the mounting bracket and is temporarily connected to an electronics package in the cable vault, which in turn is temporarily connected to an existing loop to provide control room indication.
The ultrasonic transmitter (a
sensor plus an electronics package) provides redundant level indication for mid-loop operation.
Each Unit now has a
wide range (refueling)
Rosemount level transmitter and a narrow range (reduced inventory and mid-loop)
Rosemount level transmitter.
Status:
DCP-1230 and DCP-1018 have been completely installed 3
and have been pre-operationally accepted with open items for testing when RCS level is lowered into mid-loop range.
4 Page 3 of 5
Beaver Valley Unit 1 (BV-1)
Ninth Refueling Outage _(1R9) i Status of Outage Commitments t
6.
Subject:
Cable Separation Deficiencies
References:
NRC Inspection Report 50-334/89-12 and 50-412/89-13 dated 8/11/89.
BV-1 Violation 89-12-01 identified ineffective corrective action for previously cited i
cable separation deficiencies.
NRC Inspection Report 50-334/91-80 and 50-412/91-80 dated 4-1-92.
Provided status and closure of BV-1 Violation 89-12-01.
2 Action:
Extensive corrective actions had already been accomplished for the resolution of the BV-1 cable separation deficiencies, enabling the closeout of this item during Inspection 91-80.
The only remaining deficiencies at that time involved those requiring cable rerouting which were scheduled for 1R9.
These deficiencies have now been resolved with the operational acceptance of DCP-1519 on 5/18/93 and DCP-1768 on 5/11/93.
Status:
Complete 7.
Subject:
Safety Parameter Display System (SPDS)
References:
NRC Generic Letter 89-06 " Task Action Plan Item I.D.2 Safety Parameter Display System - 10 CFR 50.54(f)"
dated 4/12/89.
DLC reply dated 4/5/89 to GL 89-06.
NRC (P.
S.
Tam) letter dated 4/23/90 requested notification upon completion of actions.
DLC SPDS schedule extension request dated 4/12/91.
Action:
A control room vertical board monitor has been installed as part of DCP-812 "In-Plant Computer."
This monitor will enable display of plant data and graphics.
Dedication of an SPDS display in the control
- room, to continuously show the top level
- iconic, is now administratively controlled by the i
Operations group.
4 Status:
Complete 4
i Page 4 of 5
Beaver Valley Unit 1 (BV-1)
Ninth Refueling Outage (1R9)
Status of Outage Commitments 8.
Subject:
Solid State Protection System (SSPS)
Reference:
" Inadequate Physical Separation and Electrical Isolation of Non-Safety-Rirlated Circuits from Reactor Protection j
System Circuits" dated 2/20/91, i
Action:
DCP-1887 "SSPS Isolation" implemented wiring changes to provide isolation from non-safety inputs to the SSPS input-relay cabinets.
Operational acceptance occurred on 5/18/83.
Status:
Complete i
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Page 5 of 5
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