ML20236V590
| ML20236V590 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/30/1987 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NYN-87138, NUDOCS 8712040389 | |
| Download: ML20236V590 (10) | |
Text
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George S. Thomas Vice President-Nuclear Production m
Public Service of New Hampshire NYN 87138 New Hampshire' Yankee Division November 30, 1987 United States. Nuclear Regulatory Commission Washington, DC 20555 Attention: Document' Control Desk
References:
(a)
Facility Operating License No. NPF-56. Docket ~No. 50-443' (b) PSNH Letter (SBN-1211) dated.0ctober. 9,.1986,'"10 CFR 50.59
' Evaluations" G. S. Thomas to V. S. Noonan
Subject:
10 CFR 50.59 Quarterly Report f
Gentlemen:
Enclosed please find the Quarterly Report of 10 CFR 50.59 Safety Evaluations for Seabrook Station. This report covers the period of July 1, 1987 to September 30, 1987, and is-being submitted pursuant to the:
reporting requirements outlined in Reference (b).
Should you require further information regarding this matter, please-contact Mr. Warren J. Hall at (603) 474-9574, extension 4046.
Very.truly yours, fc8/
Georgd S. Thomas Enclosure cc:
Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Mr.
A..C. Cerne-NRC Senior Resident Inspector
.Seabrook Station Seabrook, NH 03874 l
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8712040389 871130 PDR ADDCK 05000322 g
PDR L
. P.O. Box 300. Seabrook, NH 03874. Telephone.(603) 474-9574 j
ENCLOSURE TO NYN-87138 SEABROOK STATION 10 CFR 50.59 SAFETY EVALUATIONS QUARTERLY REPORT JULY 1, 1987 TO SEPTEMBER 30, 1987 1.
Design Changes The below listed design changes have been made at Seabrook Station and safety evaluations have been performed pursuant to the requirements of
]
]
Design Coordination Report: Number 86-441
Title:
Additional Heat Tracing for Solid' Waste System j
t
==
Description:==
This Design Coordination Report was initiated to add an additional section of heat tracing to the Solid Waste System. A " dead leg" section of piping, off the bottom of the Concentrates Bottom Tank, TK 200, was identified as an area for possible crystallization of waste solids inside the piping.
The heat tracing will maintain the section of pipe at 210 F with an ambient temperature of 50 F.
The addition of heat tracing to this piping is not safety-nelated.
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns.
Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report Humber 87-034
Title:
Turbine Building Tool Crib and Storage Area
==
Description:==
This Design Coordination Report was implemented to add a j
Tool Crib and Rigging Storage Area Enclosure on the ground I
level, 21' 0" elevstion, in the Turbine Building.
The new Tool Crib and Storage Area will be equipped with electrical I
power, service air and a fire protection sprinkler system.
Engineering evaluations were performed to verify that the additional loads for electrical service, service air, and the sprinkler systcm will not create a safety concern.
The j
I new Tool Crib and Storage Area Enclosure is a non-safety-related facility and is located in a non-safety-related, i
non-seismic area.
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l ENCLOSURE TO NYN-87138 i
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by.
means of a future amendment.
Design Coordination Report: Number 87-114
Title:
Post Accident Sample System Panel Valve Replacement and Deletion
==
Description:==
This Design Coordination Report was initiated to correct various problems associated with leaking valves located in the Post Accident Sample System (PASS) Panel.
An engineer-ing evaluation has resalted in the deletion of four solenoid valves and their isolation functions will be performed by existing manual values. In addition, leaking ball valves will be replaced with a bellows valve design and remote operators will be added, as necessary, to reduce personnel exposure.
This design cLange will improve the reliability of the PASS Panel and enhance system performance.
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
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Design Coordination Report: Number 87-157
Title:
Addition of a Remote Operator to Manual Valve FP-V497
==
Description:==
This Design Coordination Report vas initiated to install a remote chain operator on manual fire protection valve FP-V497 to provide a means for remote operation in the event of a fire. Fire protection valve FP-V497 is located approxi-mately 20 feet above the floor and is inaccessible for operation by normal means.
The Appendix R Safe Shutdown Analysis requires FP-V497 to be opened to supply water to the Service Air Compressors in the event Secondary Component Cooling Water is isolated by closure of service water valves SW-V4 and SW-V5.
The addition of a chain operator does not affect the normal operation of FP-V497. -
ENCLOSURE TO NYN-87138
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this j
design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report: Number 87-185
Title:
Replacement of Main Control Board Block / Reset Switches
==
Description:==
This Design Coordination Report was initiated to modify the Block / Reset Function Switches for three Safety Injection (SI) channels in each train.
The original switch design was j
i a three position (Reset / Neutral / Block) spring-return-to-neutral switch. A problem was identified with the switch operation when they were rotated to the Block position and 1
then released. The spring-return-to-neutral spring action j
was sufficient to cause an overshoot of the switch's neutral
~
position and momentarily make up the reset contacts. The overshoot of the neutral position was only a problem in the three switches installed in the Solid State Protection System (SSPS) circuits.
This Design Coordination Report also modified the Main Control Board to separate each of the six affected Block / Reset switches into two switches each, one providing the Block function and one providing the Reset function.
The switches that were modified are the Low Main Steamline SI Block / Reset (Train A and B), Low Pressurizer Pressure SI Block / Reset (Trains A and B), and Nuclear Instrumentation (NI) SI Block / Reset (Train A and B).
This design change has had a Human Factors Analysis performed and it was determined that reliable operation of the SSPS will continue.
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns.
Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
ENCLOSURE TO NYN-87138 Design Coordination Report: Number 87-193
Title:
Lifting Device For Component Cooling Water Heat Exchangers 1-CC-E-17A and 17B Covers.
==
Description:==
This Design Coordination Report was initiated to provide a j
monorail and laydown area for removal and storage of the head of-heat exchangers 1-CC-E-17A and 17B.
The monorail system and laydown area anchor clamps for the heads has been designed to meet all appropriate seismic requirements.
The new monorail system has been installed to the requirements of NUREG 0612 for Heavy Loads.
The monorail has been-qualified for the seismic loads generated by the monorail and its accessories.
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==
Conclusion:==
A 10 CFR 50.59' safety evaluation was performed for this design change and it.has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by.
means of a future amendment.
Design Coordination Report:
No.87-196
Title:
Auxiliary Boiler Feedwater Pump Seal Water Isolation
==
Description:==
This Design Coordination Report was implemented to eliminate 1
the possibility of chemical contamination of the Demineralized Water System (DM) from the Auxiliary Boiler Feedwater System (AB).
The Auxiliary Boiler Feedwater Pump Seal Water is supplied by the Demineralized Water System.
j Should the DM supply to the AB feedwater pump seals fall below the required 30-35 psig seal water injection pressure, a backflow from the AB feedwater pump to the DM system could result. To eliminate this possibility, a check valve was installed in the seal water injection line.
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
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ENCLOSURE TO NYN-87138 Design Coordination Report: Number 87-257
Title:
Diesel Generator Ethylene Glycol Concentration
==
Description:==
This Design Coordination Report was initiated to document a change in the ethylene glycol concentration for Emergency Diesel Generators DG-1A and DG-1B.
Diesel Generators DG-1A and DG-1B initially had two different ethylene glycol concentrations specified for a summer and winter condition.
The stronger athylene glycol concentration of 46-50% for winter could not be used for summer because of insufficient heat transfer capability when the ambient temperature reached 94 F.
The summer concentration of 25-28% glycol was thought not to be sufficient for the projected winter conditions. An analysis was performed to trend the actual winter conditions and to identify the minimum temperature that DG-1A and DG-1B would encounter. The results of this analysis has determined that there is no potential for freezing the DG coolant lines and that sufficient conserva-tism exists to maintain an ethylene glycol concentration of 25-28% continuously.
The 25-28% ethylene glycol concentra-tion conforms to the Diesel Generator manufacturer's recommendations.
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed for this temporary modification and it has been determined that the change will not create any unreviewed safety concerns.
Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
RDMS Data Base Item Change Request: Number 87-117
Title:
Wide Range Gas Monitor Flow Rate Setpoint
==
Description:==
A change was made to the Radiation Data Monitoring System (RDMS) data base to reduce the flow rate for the Wide Range Gas Monitor (WRGM).
The change from 2.15 scfm to 1.67 scfm is in conformance with the vendor recommended flow rate setpoint and is therefore conservative.
This value will provide accurate isokinetic flow for Plant Vent Stack samples at stack flow retes between 186,000 cfm and 312,535
{
cfm.
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i ENCLOSURE TO NYN-87138
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==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed for the RDMS data base change and it has been determined that the change will not create any unreviewed safety concerns.
l 2.
The below listed Temporary Modifications have been made at Seabrook Station and evaluations have been performed pursuant to the requirements i
of 10 CFR 50.59.
Temporary Modification Request: Number 86-116
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1
Title:
Polar Gantry Crane Geared High Lindt Switch By-Pass l
==
Description:==
This temporary modification was installed to determine if l
sufficient additional lifting clearance could be made l
l available to facilitate the lifting of the reactor vessel j
l missile shield from its storage area. -The Polar Gantry
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l Crane has two safety limit switches that prevent the crane's j
l block and sheave assembly from becoming two blocked.
The temporary modification provided for a jumper and mechanical toggle switch to bypass the geared limit switch automatic function; however, the counter weight limit switch still remained functional.
The position of the hoist machinery i
j was monitored at all times by operating personnel in
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constant communication with the crane operator.
The vendor l
technical manual for the Polar Gantry Crane contains provisions for operation of the crane by manually observing l
the hoist position relative to the limit switch cutoff.
The temporary modification was installed for one day and no 1
i loads were lifted with the modification installed. This temporary modification did not provide the required additional clearance necessary for the missile shield lift. The temporary modification has been removed and a Design Coordination Report has been completed to modify the Polar Crane handling fixture linkage to permit lifting of the missile shield.
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed and it has been determined that installation of this temporary modifi-cation will not create any unreviewed safety concerns. l L
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ENCLOSURE TO NYN-87138 Temporary Modification Request: Number 87-046
Title:
Frequency Stabilization Modification for Westinghouse Uninterruptible Power Supply
==
Description:==
In response to a Field Change-Notice (FCN) from Westinghouse Electric Corporation, a resistor / thermistor was added to Westinghouse Inverters 1-EDE-I-1A, B, C and D to incorporate j
a stabilization network to compensate for frequency changes resulting from temperature changes.
The modification is an j
improvement on the existing equipment design which increases j
the reliability of loads being supplied by the uninterrupt-
{
ible power supply. A Design Coordination Report is being l
developed to make this temporary modification a permanent j
plant design.
-d
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed and it has
{
been determined that installation of this temporary modifi-I cation will not create any unreviewed safety concerns.
.)
Temporary Modification Requests:
Number 87-052 Number 87-054 Number 87-056 Number 87-061 Number 87-064
Title:
Modification to Service Water System Alignment
==
Description:==
During an inspection of Service Water System butterfly valves, the above referenced Temporary Modification Requests were initiated. The Temporary Modifications consisted of the removal of various passive instrumentation (pressure and temperature indicators) to facilitate the addition of temporary hose connections. The. temporary modifications involved non-safety-related systems and allowed for the isolation of five Service Water valves while still providing the intended cooling function.
Restoration of the system will be accomplished upon completion of the repairs to the liner / seats of the affected butterfly valves.
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t ENCLOSURE TO NYN-87138
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed and it has been determined that installation of this temporary modifi-cation will not create any unreviewed safety concerns.
Temporary Modification Request: Number 87-053
Title:
Mechanical Plug Installation at Field Weld
==
Description:==
A field weld attaching a low pressure test connection for Residual Heat Removal System flow element RH-FE-2474 failed 4
due to excessive vibration. This low pressure test connection is only used during pre-operational and start-up testing and is not used during normal operation. This temporary modification removed the test valve connection and inserted a stainless steel tapered plug which was seal welded in place.
The installation of the mechanical plug is a conservative seismic measure as the weight of the plug is less than that of the deleted test valve connection. An engineering analysis is being perfe-med to develop a revised test connection configuration. The removal of this temporary modification and installation of a new test connection will be completed prior to entry into Mode 4.
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==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed and it has been determined that installation of this temporary modifi-cation will not create any unreviewed safety concerns.
3.
Technical Requirements Manual t
No changes have been made to the Technical Requirements Manual during this
)
reporting period.
1 4.
Final Safety Analysis Report J
No revisions have been submitted for the Final Safety Analysis Report during this reporting period.
5.
Procedure Changes Procedure changes require review and approval by the Station Operation Review Committee (SORC) and are subject to the requirements of 10 CFR 50.59.
The below listed Procedure Changes require a change to the Final Safety Analysis Report. t
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ENCLOSURE TO NYN-87138 Procedure Changes:
Number OS1016.01 - Rev. 03 - Service Water Fill and Vent Number OS1016.01 - Rev. 03 - Service-Water Fill and Vent Number OS1016.03 - Rev. 02 - Train A Service' Water Operation Number ~0S1016.04'- Rev. 02 - Train B' Service Water Operation Number OS1490.01 - Rev. 02 - Periodic Locked Valve Verification
Title:
Service Water System Operating Procedures-
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Description:==
The method of operation of'the Service Water System has been changed.to allow the option of using the intake or discharge transition structure water. volume as a heat _ sink while in Modes 5 and 6 with no decay heat..The procedura1'modifica-tion provides backup sources of cooling water from either-the ocean or the Cooling Tower.
The purpose of this change
'is to.decreas>3 the amount of biofouling in the circulating Water Tunnels when.the Circulating Water Pumps are not available.
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed for these procedure changes and it has been determined that the change will not create any unreviewed safety concerns.
6.
Test or Experiments There were no tests or experiments performed during this reporting period that require evaluations in accordance with 10 CFR 50.59.
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