ML20247P482
| ML20247P482 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/30/1989 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-89070, NUDOCS 8906060184 | |
| Download: ML20247P482 (5) | |
Text
. _ _
George S. Thomas jNe, w, Hampsh.. ira wo. a. m.nimoc e n w ucuen g
NYN 89070 May 30, 1989 United States Nuclear Regulatory Commission-
' Washington, DC 20555 Attention ~: Document Control Desk
References:
' (a)- Facility Operating License No. NPF-67, Docket No. 50-443 (b) PSNH Letter (SBN-1211) dated October 9, 1986, "10CFR50.59 Evaluations," G. S. Thomas to V. S..Noonan
' Subjects 10CFR50.59 Quarterly Report Gentlemen 1
Enclosed please find the Quarterly Report of 10CFR50.59 Safety Evaluations
-for Seabrook Station'.
This report covers the period of January 1, 1989, to March 31, 1989, and is being submitted pursuant to the reporting requirements outlined in Reference (b).
Should you require further information regarding this matter, please contact Mr. Timothy Pucko at (603) 474-9521, extension 4428.
Very truly yours, Pyc lA eorge S. Thomas Enclosure cc: Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20555 NRC Senior Resident Inspector P.O. Box 1149 Seabrook Station. NH 03874 Ji 8906060184 890530 ff(
PDR ADOCK 05000443 R
PDC fi New tiompshire Yonkee Division of Public Service Compony of New Hampshire f
P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474-9521 L___
L ENCLOSURE TO NYN-Seabrook Station 10CFR50.59 Safety Evaluations Quarterly Report January 1, 1989 to March 31, 1989 Design Changes The below listed design changes have been made at Seabrook Station and safety evaluations have been performed pursuant to the requirements of 10CFR50.59.
' Design Coordination Report Number 86-513
Title:
Wide Range Steam Generator Level Indication
==
Description:==
The steam generator wide-range level transmitters must be re-calibrated when plant operating conditions transit from MODE 4 to MODE 3 and back again.
The requirement for a hot.and cold calibration is created by the change in density of the steam generator liquid variable leg. To eliminate the necessity for this calibration schedule, this design change was implemented to add a density compensation circuit to the wide-range level transmitter on each of the four steam generators.
The wide-
-range steam generator level transmitters are used as Accident Monitoring Instrumentation. The wide-range level transmitters provide indication only, and the new density compensation will improve the accuracy of the level readings over a wide variety of plant conditions.
The new density compensation circuit was installed to the same design criteria as the existing circuitry. The new density compensation circuit is Class IE, and the circuit cards have fuses on the' power input to ensure their fallare prior to affecting the power supply to the protection _ cabinet.
==
Conclusion:==
A 10CFR50.59 safety evaluation was performed for this design change and it has been determined that this change will not create an unreviewed safety question. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
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' Design Coordination Report: Number 87-236-
' Title Ozonator-Piping
Description:
Duringl construction, a temporary modification was made to install a ozonator sterilization unit to the Demineralized Water System to control. bacteria-growth.
Subsequently, an ultraviolet:
g sterilization unit was installed rendering the ozonator. unit obsolete.
p This' Design Coordination Report was initiated.to modify.the temporary piping and make the.new modified design ~part of the
-permanent plant design. The piping provides a header cross-m connection should the ozonator sterilization unit be needed in the future and provides a connection source of flush water to p
l the Water Treatment System sodium and silicaLanalyzers. All piping.was installed consistent with the' design requirements of.
the Demineralized Water System.
==
Conclusion:==
A 10CFR50.59 safety-evaluation was performed for.this design-change and it has been determined.that this change will not create an unreviewed safety. question. Changes to the Final Safety,AnalysisLReport:and the Technical Requirements Manual-
.will be incorporated by means of:a future amendment.
Design Coordination Report: Number 88-010
Title:
BTRS Chiller Corrosion Coupon
==
Description:==
This Design Coordination Report was initiated to modify a previously installed temporary design and to-incorporate the-new design as part of the permanent. plant installation. The temporary modification had installed a corrosion-coupon in the Boron Thermal Regeneration Chiller System (BTRS) to monitor'the effects of corrosion to' system components.
Design Coordination Report 88-010 provided new tubing installation details but incorporated the existing corrosion coupon into the new design. The design was installed to the installation requirements of.the Boron. Thermal Regeneration System.
==
Conclusion:==
A 10CFR50.59 safety evaluation was performed for this design change and it has been determined that this change will not create an unreviewed safety question. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
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Design Coordination Report Number 88-189
Title:
Emergency Feedwater Steam Supply
==
Description:==
The steam supply to the steam-driven emergency feedwater pump is controlled by three valves, MS-V-393, MS-V-394 and MS-V-395.
Two of the valves, MS-V-393 and MS-V-394, have a DC powered pilot oolenoid valve that is powered from Train A and Train B respectively. The third valve, MS-V-395,00 has two DC powered pilot solenoid valves, one of which is powered from Train A and the other from Train B.
The steam supply valves are fail-open valves and are held closed by their respectively energized solenoid valves. Normally, when the turbine is required to run, either or both of the upstream valves, MS-V-393 and 394, open and after a seventeen second delay MS-V-395 opens to allow steam to the turbine. Upon a loss of a DC power supply, a combination of either MS-V-393 and MS-V-395 could open on a loss of Train A or MS-V-394 and MS-V-395 could open on a loss of Train B without the benefit of the seventeen second time delay. This could allow any condensate in the steam line to enter the turb!.ne and potentially cause an overspeed trip.
This Design Coordination Report was initiated to minimize the l
p).vibility of this scenario. The design change affects the l
pi7at solenoids of MS-V-395.
They will now be de-energized closed and energized to open. With this design, on loss of a DC power supply, either MS-V-393 or 394 will open and MS-V-395 will remain closed. Once power is restored, MS-V-393 or 394 will remain open and MS-V-395 will open, provided the seventeen second time delay has timed out, and allow steam flow to the turbine.
No other safety features of the system will be changed. Design was performed in accordance with the requirements of IEEE 279-1971 and Regulatory Guide 1.47.
==
Conclusion:==
A 10CFR50.59 safety evaluation was performed for this design change and it has been determined that this change will not create an unreviewed safety question. Changes to the Final Safety Analysis Report and the Technical Requirements Manual will be incorporated by means of a future amendment.
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Temporary Modifications-The below listed temporary modification has been made at Seabrook Station and a safety evaluation has been performed pursuant to the requirements of 10CFR50.59.
Temporary. Modification, Request: Number 89-007
Title:
Removal of Service Water Valve, SW-V-29, for Maintenance and Inspection.
==
Description:==
A maintenance / inspection activity on'the SW-P-41B Service Water Pump discharge valve, SW-V-29, required that the valve be removed from the system. To allow.for the valve-removal and still maintain the other
'B' Train Service Water-Pump, SW-P-41D, operable, a blind flange was installed on the octiet side of SW-V-29.
The temporary modification was limited to MODE 5 operation and system restoration was completed prior to entry into MODE 4.
==
Conclusion:==
A 10CFR50.59 safety evaluation was performed and it has been determined that installation of this temporary modification did not create an unreviewed safety question.
3.
Technical Requirements Manual No _ changes were made to the Technical Requirements Manual during this-reporting period.
4.
Final Safety Analysis Report No revisions have been submitted for the Final Safety Analysis Report during this reporting period.
5.
Procedure Channes Procedure changes that require review and approval by the Station Operation Review Committee (SORC) are subject to the requirements of10CFR50.59. No procedure changes have been made at Seabrook Station during this reporting period would require a change to the Final Safety Analysis Report.
6.
Test or Experiments-There were no tests or experiments performed during this reporting period that require evaluations in accordance with 10CFR50.59.
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