ML20029B244
| ML20029B244 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/28/1991 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-91031, NUDOCS 9103060290 | |
| Download: ML20029B244 (15) | |
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New Hampshire fed C. Ieigenbovm hh (( Preudent und th44 I newi ve ottor N Y N. 91031 g February 28, 1991 United Sta,es Nuclear Regulator) Commission Washington, D.C. 20555 Attention: Document Control Desk
References:
(a) Facility Operating License No. NPF 86, Docket No. 50 443 (b) PSNil Letter (5tlN 1211) dated October 9, 1086,
- Evaluation *, O.S. Thotaas to V.S. Noonan SubjtcP 10CFR50.59 Quarterly Report Gentlemen:
Enclosed please find the Quarterly Report of 10CFR$0.59 Safety I!valuati as for Scabrook S'ation. Thi6 report covers the period of October 1,1990, to December .41,1990, and is being submitted pursuant to the reporting requiremtnts outlined in Refeunte (b).
Should you require further informa' ion regarding this mattre, please t.ontt et Mr. James M. Feschel, Regulatory Compliance Manager at (603) 474 9521, extension 377 .
Very truly yours. ,
'~~
nY Ted C. Felgenhan Enclosure (s)
TCP:J ESlact/ss!
9103060290 910228 PDR ADOCK 050004#3 R pop New Hompshire Yankee Division of Public Service Company of New Hampshire epr
'W A uub P.O. b 300
- Scobrook, NH 03874
- Telephone (603) 474 9521
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United States Nuclear Regulatory Commission Februa*y 28, 1991 Attention: Document Control Desk Page two cc: Mr. Thomas T. Martin Regi.. .sl Administrator Unit".) States Nuclear Regulatory Commission Region !
475 Allendale Roa3 King of Prusbia, PA 19406 Mr. Gordon Edison, Sr. Project Mgr.
Project Directorate I 3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 Seabrook, Nil 03874 s
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A New ilarapshire Yankee Prbruary 28, 1991 ENCLOSURE 1 TO NYN 91031 Seabrook Station 10CFR50.59 Safety Evaluntloa Quarterly Report October 1,- 1990 . December 31, 1990 t;
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- 1, Desien Chances The below listed des!gn changes were implemented at Seabrook Station and safety evaluations were performed pursuant to the requirements of 10CFR50.59. ,
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Deslen Coorc,thuiQpn Renott! Number 87 0340
Title:
Waste Concentrates Tank Level Transmitter Modifications
Description:
This Design Coordination Report (DCR) adds a reference leg to the low pressure taps of both Waste Concentrates Tank level transmitters. This !
modification is to compensate for errors induced by negative pr:ssure in tbc tank c used by the vent gas system. This DCR also relocates i the Waste Concentrates Tank's level switch from its current high radiation area to a low radiation area.
This DCR r.lso ternoves three local temperature indicators from the Waste Solidification System. These indicators were originally installed for start up purposes, and their continued snaintenance in a high radiation area is not justified.
This DCR requires modification of Final Safety Analysis Report (PSAR)
Figures 11.41 and 9.2 3. These changes do not alter the pro 6uct quality or function of the Waste Solidification System.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this *hange will not create an unreviewed safety question. The change will be reflected in the Updated Final Safety
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Analysis Report.
Desien Coonllpation Report Number 88 00$9.
Title:
Spent Resin Transfer Pump Pressure Transmitter l
Description:
- "Ihis Design Coordinatica Report (DCR) provides for two new in line isolation valves and a test connection located in the discharge of the spent resin transfer pump in order to isolate the pressure transmitter for calibration of the instrument loop. The transmitter monitors system pressure and alarms on increased pressure which may indicate in.line blockage. This change reduces the potential for resin transfer to an interfacing system or for the spill of resin.
l This DCR requires modification of Final Snfety Analysis Report (FSAR) l- Figure 11.41.
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Conclusion:
A. safety evaluation was performed for this design change, and it was l
- determined that this change 'will not~ create an unreviewed safety question. The change will be reflected in the Updsted Final Safety Analys!s Report.
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- 2. M,lnor Modifications The below listed minor modifications were made at Seabrook Station and safety evaluations were performed pursuant to the requirements of 10CFR$0.59.
Minor Modification: Number 89 0624
Title:
Circuit Breshw t oordination Curves
Description:
This Minor Modification (MMOD) revises the test and acceptance criteria for specific electrical protective devices (type 118 breakers) identified in Final Safety Analysis Report (FSAR) Tables 16.3 8 and 16.3 10. These breakers provide electrical protection for both safety-related and non safety related loads. The tett and acceptance criteria were selected to ensutt, that electrical coordination is provided for the
-installed applicatio.u. These criteria are utilized in the routine testing of the breakars to asure the devices are operable.
This MMOD does not change the design or function of the electrical system or its protective devices, in addition, there are no changes in the operation of the connected loads and all modifications are consistent with the criteria in the design base calculations.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create an unreviewed safety question. The change will be reflected in the Updated Final Safet/
Analysis Report.
Minor Modification: Number 00 0576
Title:
Main Steam isolation Valve Pressure Switch Replacement
Description:
This Minor Modification (MMOD) replaces the Whitman General pressure switches associated with the Main Steam isolation Valves (MSIV) with equivalent switches manufactured by Barksdale, The a sisting switches are no longer manufactured and are difficult to maintain withia calibration limits.
This MMOD also installs manualisolation valves and pressure gauge test connections on the gas side of the pressure switches. This facilitates future maintenance by alleviating the need to vent the nitrogen gas .
system in order to replaec the pressure switches.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create an unreviewed safety question.
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l f j tjuor Modification: Number 90 0505 3 TiSe: Containment isolation Valve Positions f
Description:
This Minor Modification (MMOD) revises Final Safety Analysis Report (PSAR) Figure 6.2 94, ' Containment isolation Valve Diagrams' to reflect the 'As Built' configuration of test, vent and drain connections within the containment isolation boundary, it also corrects Figure 6.2 94, Figure 9.3 4 and Table 6.2 83 to show the normal position of manual containment isolation valves to be ' Locked Closed'.
The containment isolation valve positions provided by this MMOD comply with the containment isolation design basis and the requirements of 10CFR50, Appendix A.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create an unreviewed safety question. The change will be reflected in the Updated Final Safety Analysis Report, hijnor Modlfication: Number 90 06Q1,
Title:
Miscellaneous Systems . Minor Changes to P&lDs
Description:
This Minor Modification (MMOD) makes minor changes to various Piping and Instrumentation Diagrams (PklDs) for consistency and accuracy. These changes are non functional and do not change plant design or system operations as described in the Final Safety Analysis Report (PSAR),
Conclusion:
A safety evaluation was performed for this design change, and it was dete_rmined that this change will not create an unreviewed safety question The change will be reflected in the Updated Final Sefety Analysis Report.
Minor Modification: Number 90 0610_
Title:
Floor Drain Tank' Level Transmitter Replacement
Description:
This Minor Modification (MMOD) replaces the four Foxboro level transmitters on the Floor Drain Tanks in the Waste Processing livilding with Rosemount transmitters Replacements are no longer evallable for the existing Foxboro transmitters.
This modification has no affect on the performance of the liquid waste system and'it meets the existing design criteria.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create an unreviewed safety question. The change will be reflected in the Updated Final Safety Analysis Report.
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Minor Modificattore Number 90 06M
Title:
Adjustment of Feed Pump Speed Control Gain and Reset
Description:
This Minor Modification (MMOD) changes the gain setting and reset on the Steam Generator Feedwater Pump master speed controller. This change will make the speed controller less responsive to deviations in measured steam and feed differential pressure and the programmed differential pressure setpoint. This MMOD was initiated based on s recommendation by Westinghouse.
The Steam Generator Feedwater Pump speed controller is non safety related and is not seismically or environmentally qualified.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create an unreviewed safety question.
Minor Modification: Number 90 0639
Title:
Sample Sink Modifications
Description:
This Minor Modifir tion (MMOD) replaces the Tcledyne Farris Model 1850 pressure relief valves, associated with the Sample System and Chemical Analysis System within the Primary and Secondary Sample Sink, Auxiliary Boiler Sample Sink and Feedwater Sample Sink, with comparable valves made by Nupro. These Teledyne Farris valves are no longer manufactured.
This MMOD also increases the setpoint for the relief valves associated with the Primary Sample Sink from 75 to 9^ psig to increase the margin between the setpoint and the pressure required to purge sample flow up to the Volume Control Tank.
This MMOD also replaces the gas stripping container in the primary sample panel with a smaller unit to reduce the volume, and hence pressure, of the Reactor Coolant System sample.
The modifications provided by this MMOD improve the overall reliability and performance of the affected systems. These modifications affect the Piping and Instrumentation Diagrams (P&lDs) in the Final Safety Analysis Report (FSAR).
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create ' an unreviewed safety question. The change will be reflected in the Updated Final Safety Analysis Report, i
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o Minor Modification: Number 00 0650
Title:
Main Generator Ground Pault Relay Rewiring
Description:
This Minor Modification (MMOD) makes Temporary Modification.
TMOD 90 0021 a permanent installation. Specifically, it bypasses the trip function of the turbine generator ground fault relay and modifies the relay's setpoint. This MMOD prevents a turbine trip resulting from spurious ground fault relay operation thus improving the reliability of the turbine generator.
This MMOD does not modify the function of the turbine generator or jeopardize the ability of the protection system to isolate the generator.
The affected relay circuit does not interface with safety related equipment.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not create an unreviewed safety question.
Minor Modification: Number 90 06$1
Title:
Hydrogen Analyzer Scale Changt.
Description:
This Minor Modification (MMOD) disables the range switch on the Class 1E liydrogen Analyzer Remote Panel. Specifically, it disables the 0 20 percent scale on the remote panel and thus ensures the range
. selector will always be on the 010 percent position as is required by Regulatory Guide 1.97, Rev. 3.
Conclusion:
A safety evaluation was performed.for this design change, and it was determined that this change will not create an unreviewed safety question.
M[nor Modification: Number 90 0060
Title:
Feedwater Regulating Valve and Ilypass Regulating Valve Volume flooster Relocation
Description:
This Minor Modification (MMOD) relocates the volume booster relay-off the valve actuator for the feedwater regulating valves and feedwater bypass valves. Th's eliminates the potential for vibration induced failures at the volume boosters'- threaded fittings.
This MMOD does not affect the response or function of the feedwater regulating valves and bypass valves.
Conclusion:
- A safety evaluation was performed for this design change,- and it was determined that this change will not create an - unreviewed safety question.
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4 Minor Modification: Number 90 0673
Title:
Altertex Brush flolder Alternate Meanc of Attachment
Description:
This Minor Modification (MMOD) replaces the main generator alternator field brush holder with a split ring brush holder, The split ring holder will allow replacement of the brush rigging while the unit is operating. The split ring holder is equivalent to the vendor supplied le ider and does not compromise mechanical or electrical integrity.
Conclusion:
A safety evaluation was performed for this design change, and it was determined that this change will not crcate an unreviewed safety -
question.
- 3. Temocrary Modifications The below listed temporary modifications were made at Srabrook Station and safety -
evaluations were performed pursuant to the requirements of 10CFR$0.59, Temocrary Modification: Number 90 TMOD 0030
Title:
Temporary instrumentation for Check Valves FW V 82 and FW V 88
Description:
This Temporary Modification (TMOD) installs Resistance Temperature .
Detectors (RTD's) and motion detectors on emergency feedwater piping ,
in the East Main Steam Feedwater Flpe Chase. 11 also installs a pressure transmitter at drain valve FW V 89 in the Emergency Feedwater ,
Fump ilouse to monitor the performance of feedwater stop check valves FW '.f 82 and FW V 88. The instrumentation installed by this TMOD is passive in nature and is for data co!'ection purposes only. The connection of the pressure transmitter at the normally closed drain valve will net alter the operating characteristics of the system.
Conclusion:
A safety evaluation was performed for this Temporary Modification change and it was determined that this change will not create an unreviewed safety question.
Temocrary Modification: Number 90 TMOD 0042
Title:
Oil Water Separator Vault Discharge Reroute
Description:
This Temporary Modification (TMOD) reroutes the discharge of Oil Water Separator Vault (OWSV) Number 2 to the Circul:. ting Water System. This TMOD ensures liquid effluent release from OWSV Number 2 conforms to the requirements of thc Offsite Dose Calculation Manual.
Conclusien: A safety evaluation was performed for this Temporary Modification change and it was determined that this change will not create an unreviewed safety qacstion. .
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Temocrary Modification: Number 90 TMOD 0043
Title:
Startup Feed Pump Lube Oil Cooling Water Flow Indicator Iteplacement
Description:
This Temporary Modification (TMOD) replaces a flow indicator in the Startup Feed Pump (SUFP) lube oil cooling water system with a spool piece. The flow indicator was originally intended to assist in manually setting the throttling valve that controls cooling water flow to the SUPP lube oil cooler. With the spool piece installed, cooling water flow will be set using pressure drop acro',s the heat exchanger. This TMOD affects only the non. safety related portions of the SUFP lube oil cooling water system and will not cause any design limits to be exceeded.
Conclusion:
A safety evaluation was performed for this Temporary Modification change and it was determined that this change will not create an unreviewed safety question.
I.gmrietary Modifiention: Number 90 TMOD 0045
Title:
Cross connect Iletween Steam Generato Illowdown and Condensate Storage Tank
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Description:
This Temporary Modification (TMOD) installs a fire hose and associated fittings between the discharge of the Steam Generator Illowdown demineralizers and the inlet of the Condensate Storage Tank. This TMOD enables the transfer of high quality water to the CST, enhancing i the ability to maintalu the CST's water quality. Secondary water chemistry requirements will not be altered as a resuit of this TMOD.
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Conclusion:
A safety evaluation was performed for this Temporary Modification change and it was determined that this change will not create an unreviewed safety question.
,Iemocrarv Modifichtlon: Number 90 TMOD 0049
Title:
Steam filowdown Demineralizer Rinse to Discharge '
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Description:
This Temporary Modification (TMOD) connects the discharge of the steam generator blowdown deminnrallects through the liquid waste system to the intake / discharge structure. This flow path is used in conjunction with the final conductivity rinse of the demineralizer regeneration cycle where the fluid from the steam generator blowdown flesh tank- or deminerallred water is used as the rinse media. This TMOD will enable the rinae to be pe: formed using warm water which will reduce rinse time. The portions of the steam generator blowdown and liquid waste systema affected by this TMOD are non safety related.
Conclusion:
A safety evaluation was performed for this Temporary Modification change and it was determined that this change will not create an unreviewed safety question.
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Temocrary Modification: Number 90-TMOD.0054
Title:
Installation of Temporary Pressure Gauges on the Vent Oas Waste Gas System
Description:
This Temporary Modification (TMOD) installs temporary pressure gauges, additional drain valves and caps on the Vent Gas Waste On System for monitoring pressure variations in this system. All affected valves are non nuclear safety related.
Conclusion:
A safety evaluation was performed for this Temporary Modification change and it was determined that this change will not create an unreviewed safety question.
Ternoorary Modification: Number 90-TMOD.0059
Title:
Alternate Suction Path for Demineralizer Water Transfer Pumps
Description:
This Temporary Modification (TMOD) provides an alternate suction path for the demineralized water transfer pumps. This will allow for the installation of n new valve in the normal suction line without
- deactivating the Demineralized Water (DM) system. The alternate
- suction line will utilize the DM tank fill line. This line runs in close proximity to the DM transfer pumps' suction und therefore, will be connected by use of a 3' stainless steel spool. Due to the reduced suction size, one DM transfer pump will be entition tagged to prevent operation of both pumps. This alignment is adequate for all but the most extreme DM demand periods. To avoid a peak demand, evolutions which require large quantitles of DM water will be completed prior to installing this temporary modification.
This TMOD does not make changes to DM system equipment which interfaces with safety related components.
Conclusion:
A safety evaluation was performed for this Temporary Modification change .and it was determined that this change will not eteate an unreviewed safety question.-
4 Teebnical Recuirements Manual The below listed Technical Requirements-Manual changes have been approved for use and safety evaluations were performed pursuant to the requirements of 10CFR50.59.
Technical Heauirements Manual Chance Reaqut: Number 90 01
Title:
Circuit Breaker Coordination Curves '
Description:
This Tcchnical Requirement Manual Change request modifies Technical Requirements 13 and 15 to revise test setpoints and verification response times for type HE breakers. This change was initiated by MMOD 89 ;
0624 which is discussed in this report. '
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Technical Reaulrements Manual Chance Reauest: Number 40 07 (continued)
Conclusion:
A safety evaluation was performed for the Minor Modification which initiated this Technical Requirements Change and it was determined that this change will not create an unreviewed safety question.
Technical Reauirements Manual Chance Reauest: Number 90 09
Title:
Fire Pump Surveillance
Description:
This Techr>ical Requirements Manual Change Request deletes the requh ament that surveillance 4.7.9.1.2c, pertaining to demonstration of fire pump diesel engine operability, be performed only during shutdown.
Since the system design includes three pumps and the Technical Requirement requires that two pumps be OPERABLE, it is possible to survell the diesel at times other than during shutdown.
Conclusion:
A safety evaluation was performed for this Technical Requirements Manual Change and its was determined that this change will not create an unreviewed safety question,
- 5. Final Safety Analysis Report The below listed Final Safety Analysis Report (FSAR) change requests were issued and safety evaluations were performed pursuant to the requirements of 10CFR$0.59.
FCR 90 087 Updated FSAR Chapter 4 FCR 90 094, Updated FSAR Chapter 17 FCR 90 095, Updated FSAR Chapter 5 FCR 90 098, Updated FSAR Chapter 14 FCR 90104, Updated FSAR Chapter 16 FCR 90108, Updated FSAR Chapter 2 FCR 90116, Updated FSAR Chapter 13 New Hampshire Yankee has ~ committed to submit an Updated PSAR pursuant to "
10CFR50.71(c) by May 26, 1991. The Updated FSAR chapters are currently being prepared.
Each Updated FSAR chapter is required to be supported by a safety evaluation which addresses the Updated PSAR changes from the existing FSAR. These changes which will be summarized in the Updated FSAR transmittal result primarily from the following:
Design changes and modifications recently implemented and made operable.
incorporation of responses to NRC Requests for Additional Information and other. Information previously submitted.
Elimination of Unit 2 references.
Editorial Changes.
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Thus far, safety evaluations have been completed for the above listed Us.dsted FSAR Chapters and it was determined that the changes involved do not constitute an unreviewed safety question.
Final Safets Analysis Reoort Chance Reauest: Number 90-078 i
Title:
Slave Relay Testing Change
Description:
This Final Safety Analysis Report (FSAR) Change Request (FCR) modifies FSAR Chapter 7, Instrumentation and Controls, to include five additional isolation valves which are not to be tested at full power operation so as not to damage plant equipment. In lieu of a valve stroke, the slave relay operation will be verified, but valve closure will be blocked. This testing will be performed on a quarterly basis. This testing modification will not alter the Seabrook Station Inservice Test Program requirements since these valves will be stroked during cold shutdowns.
Conclusion:
A safety evaluation was performed for this FCR, and it was determined I that these changes will not create an unreviewed safety question. These changes will be incorporated into the Updated FSAR.
Final Safety Analysis Reoort Change Reauest: Number 90 093
Title:
FSAR Table 7.51 Clarification
Description:
_ - This Final Safety Analysis Report (FSAR) Change F.cquest (FCR) revises PSAR Table 7.51, Accident Monitoring instrumentation List, to show Steam Gen:rator Wide Range Level Recorders XR 501, 502, 503 and 504 as the trend Indication for variable A4, steam generator level.
Also, a footnote is added to clarify that Steam Generator Narrow Range Level- Recorders LR 539 ' and LR 549 receive their signals from I transmitters LT 539 and LT 549, respectively. Also, footnote (2) is added to Pressurizer Level Recorder LR 459 in Table 7 5.1 to clarify
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! that this recorder is similar to seismically qualified recorders. . These changes are non. functional and are in agreement will actual plant design and documentation.
Conclusion:
A safety evaluation was performed for this FCR, and it was determined that these changes will not create an unreviewed safety question. These changes will be incorporated into the Updated FSAR.
- 6. Annlications to Amend the Operatine License j The - below listed applications to- amend the Seabrook Station- Operaticg License were i
submitted and safety evaluations were performed pursuant to the requirements of 10CFR50.59.
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g Application to Amend Facility Oncratine Ileense: Antil 73.1990
Title:
Sale and Leaseback Transactans by The United Illuminating Company
Description:
This Application to Amend the Seabrook Station Operating License was to allow The United illuminating Company to enter into an arrangement for the sale and leaseback of a portion of their interest in Seabrook Station Unit No.1 to certain equity investors.
Conclusion:
A safety evaluation was performed for this proposed operating Ilcense amendment, and it was determined that this amendment would not create an unreviewed safety question.
Annikation to Amend Pacility Operatine Ileense: November 13. 1990 ,
Title:
Authorization for NAESCO to Act as Managing Agent for Seabrook
Description:
This Application to Amend the Seabrook Station Operating License would authorize North Atlantic Energy Service Company (NAESCO) to act as agent for other Licensees, to manage, operate and maintain Seabrook Station. ,
Conclusion:
A safety evaluation was performed for this proposed operating license amendment, and it was determined that this amendment would not create an unreviewed safety question.
Apol! cation to Arnend Facility Operatine License: November 13. 1990
Title:
Authorization for NAEC to 11ccome Licensee and Acquire and Possess PKNil's Ownership interest in Seabrook
Description:
This Application to Amend the Seabrook Station Operating License would authorize the North Atlantic Energy Corporation (NAEC) to be included as a Licensee and to acquire and possess Public Service Company of New Ilampshire's (PSNil) ownership interest in Seabrook Station.
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Conclusion:
A safety evaluation was performed for this proposed operating license amendment, and. it was determined that this amendment would not
- j. create an unreviewed safety question.
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- 7. Procedures l The below listed procedures were developed and safety evaluations were performed pursuant l to the requirements of 30CFR50.59.
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4 Procedutet Number v ddl
Title:
Realignruent of the #26 Feedwater licater Normal Cascade and liigh Level Dump Valven
Description:
This procedure was developed to dets:mine If the realignment of the
- 26 feedwater heater shell side normal cascade valve and high level dump valve will nullify or minimire the fluctuation present in tht hentet drain tank. Implementation of this procedure does not affect any !
equipment important to safety.
Conclusion:
A safety evaluation was performed for this procedure, and it was determined that this procedure will not create an unreviewed safety question.
- 8. Procedure Channes There were no procedure changes made during this reporting period that require safety evaluations in accordance with 10CFR50.59,
- 9. Tests or Experiments There were no tests or experiments performed during this reporting period that require safety evaluations in accordance with 10CFR50.59.
-10. Justifications for Continued Oncrations l A safety evaluation was performed for the following Justification for Continued Operation.
Titlet Justifiention for Continued Oncration While Renoirs Were Made to Valve MS V 127.
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Descriptionf . A Justification for Continued Operation of Seabrook Station in Mode 3, llot Standby, while repalts are ruade to valve MS.V 127 was transmitted to the NRC on November 21, 1990. Valve MS.V.127 is a dual function valve in the main steam system which provides the steam supply to the steam turbine driven emergency feedwater pump and -
functions as a containment isolation valve. This valve was inoperable in the open position. Downstream isolation valves were relled upon to provide containment isolation until MS.V127 was returned to service.
Conclusion:
A safety evaluation was performed for this Justification for Continued
' Operation, and it was determined that it will not create an unreviewed
. safety question.
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