ML20117N027
| ML20117N027 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/10/1996 |
| From: | Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20117N030 | List: |
| References | |
| NYN-96039, NUDOCS 9606190235 | |
| Download: ML20117N027 (50) | |
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+ 1 North North Atlantic Energy Service Corporation P.O. Box 300 I
Atlantic Seabroot, Nii O3874 (603) 474-9 Tat The Northeast Utilities System
,1N I O 1996 Docket No. 50-443 l
NYN-96039 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 2/
Seabrook Station 10CFR50.59 Annual Report and Revision 4 to the j Seabrook Station Undated Final Safety Analysis Reoort , I i
1 North Atlantic Energy Service Corporation (North Atlantic) encloses herein the 10CFR50.59 Annual Report and Revision 4 to the Seabrook Station Updated Final Safety Analysis Report (UFSAR). The l 10CFR50.59 Report and the UFSAR are submitted pursuant to the requirements of 10CFR50.59(b)(2 and 10CFR50.71(e), and in compliance with the 18 month schedule established in North 2
and the updated schedule contained in North Atlantic's subsequent letter . This report covers the period from October 26,1994 through December 31,1995. UFSAR Revision 4 incorporates approved and implemented design changes and UFSAR changes identified through December 31, 1995. The incorporated changes to the UFSAR have been subject to review in accordance with 10CFR50.59. The reviews determined that these changes did not constitute unreviewed safety questions.
i Each UFSAR replacement page includes the revision number and a vertical line (revision bar) in the left margin, adjacent to the actual change. Please note that some replacement pages have a revision number at the top of the page but no revision bar. This indicates that text position has changed as a result of text l changes on previous pages aiid no other changes have occurred. Summaries of the 10CFR50.59 safety evaluations for the changes incorporated in Revision 4 of the UFSAR are attached as Enclosure 1.
Enclosure 2 provides a summary of the 10CFR50.59 safety evaluations performed to support facility and procedure changes during the reporting period that were determined to be reportable pursuant to 10CFR50.59(b)(2). Enclosure 3 is a listing of 10CFR50.59 safety evaluations performed during this reporting period that were performed for conservatism and did not meet the reporting requirements as outlined in 10CFR50.59.
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' North Atlantic letter NYN-93080 dated May 26,1993,"10CFR50.59 Annual Report and Revision 2 to the Seabrook Station Updated Final Safety Analysis Report," T. C. Feigenbaum to USNRC.
2 North Atlantic letter NYN-94096 dated August 26,1994," Revised Schedule for the 10CFR50.59 Report and UFSAR Revision Submittal," T. C. Feigenbaum to USNRC.
.fObh 9606190235 960610 PDR ADOCK 05000443 K PDR t
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. U.S. Nuclear Regulatory Commission s NYN-96039/Page 2 Included in Revision 4 of the UFSAR is a change that removes the technical requirements from UFSAR Chapter 16 and directs the user to the Technical Requirements Manual. This change eliminates the need to maintain information in two separate controlled documents.
This UFSAR submittal, specifically, Chapter 17 and Appendix 17A, addresses the reponing requirements of10CFR50.54(a).
The signed original and ten copies of the UFSAR revision are being submitted to the Document Control Desk, Washington, DC, along with a copy of the Regional Office, King of Prussia, PA and a copy to the Resident Inspector at Seabrook Station. This distribution complies with the requirements of 10CFR50.4(b)(6).
Should you have any questions regarding this letter, please contact Mr. Anthony M. Callendrello, Licensing Manager, at (603) 474-9521, extension 2751.
Very truly yours, NORTH ATLANTIC ENERGY SERVICE CORP.
b& #f Ted C. Feigenbaum [ dent & Chief Nuclear Executive Vice Presi STATE OF CONNECTICUT Hartford, ss. Date: d-/d-7[
Then personally appeared before me, the above-named Ted C. Feigenbaum, being duly sworn, did state that he is Executive Vice President and Chief Nuclear Officer and is a duly authorized officer of North Atlantic Energy Service Corporation and is authorized to execute and file the foregoing information in the name and on behalf of North Atlantic Energy Service Corporation and that the statements therein are true to the best of his knowledge and belief.
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PEGGY L. MANNELLO NOTARY PUBLIC MY COMMISSION EXPIRES $[P. 30,1997 cc: T. T. Martin, Region I Administrator A. W. DeAgazio, NRC Senior Project Manager, Seabrook Station J. B. Macdonald, Senior Resident Inspector, Seabrook Station
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l ENCLOSURE I TO NYN-96039 Summaries of the 10CFR50.59 Safety Evaluations for the Revision 4 of the UFSAR j l
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l Decion Coorrlination Renorts (DCRs) ,
Design changes documented in the following design coordination reports (DCRs) achieved operability status ;
during the period covered by this 10CFR50.59 Report. A safety evaluation was performed for each DCR. Each ,
safety evaluation concluded that the DCR did not involve an unreviewed safety question. Summaries of these i DCRs and their safety evaluations are provided below. l l
l l Design Coordination Report (DCR)- 86-110 l
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Title:
Relief Valve CS-V794 S< tpoint Change and Tailpiece Addition l l l
! Summary Description and
Purpose:
Relief valve CS-V794 is a 3/4 inch thermal relief valve which provides overpressure protection to the chemical and volume control system (CVCS) seal water return line containment
. penetration piping in the event of T-signal isolation dur ing an accident. This change raised the setpoint of CS- l V794 from 150 to 200 psig to eliminate the possibility of it being challenged except upon containment isolation !
during an accident. He increase in set pressure requires that the valve inlet flange be replaced with one of a l higher pressure rating in order to maintain piping stresses below the allowable limits imposed by the ASME Boiler l and Pressure Vessel Code. Tail piping and a support were added to the discharge of CS-V794 to route relief flow !
to the pressurizer relief tank (PRT). This relief piping prevents undetectec' spills of primary coolant within the shielded cubicle in the event that this valve inadvertently lifts or experiences leakage. l Safety Evaluation Summary: His DCR made changes to the facility as described in FSAR Figure 9.3-13, Sheet j 4 and Table 5.4-13. The safety evaluation determined that the increase in the set pressure of CS-V794, j replacement of the relief valve inlet flange with one of higher rating and recertification of the seal water return line design pressure are all in accordance with ASME Code Section 111 NC for Safety Class 2 components. The ,
tail piping addition from the valve discharge to the PRT is per ANSI B31.1 and meets seismic Category I support requirements. Since the setpoint of CS-V794 will be increased above the maximum lift pressure of the seal water ;
return relief valves, this valve will not be challenged during non-accident pressure transients. Therefore, the !
probability of lifting and creating a loss of reactor coolant during normal operations is greatly decreased. The j safety evaluation concluded that this change did not involve an unreviewed safety question. c UFCR 90-081 Design Coordination Report (DCR): 86-420
Title:
Steam Generator Recirculation and Wet Lay-up Summary Description and
Purpose:
This change added minor piping and support design alterations to the Steam Generator Recirculation and Wet Lay-up System. This modification was made to enhance the reliability and the chemistry control of the steam generators during extended cold shutdown maintenance evolutions.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Section 6.8.2 and Figure 6.8-1. The safety evaluation determinert that the steam generator recirculation and wet lay-up system is non safety-related and changes to the system would not compromise plant safety. This system is administratively isolated during plant operations. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 88-045 1
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Title:
Cap Unit H Circulating and Service Water Piping Summary Description and
Purpose:
This change cut and capped piping associated with partially constructed l Unit 11 systems to prevent unauthorized intrusion into the Protected Area. Isolation valve 1-SW-V105 was !
removed as part of this change. i Safety Evaluation Summary: This DCR made changes to the facility as described in FSAR Secton 9.2 and Figure 9.2-1, Sheet 2. The safety evaluation determined that removal of the isolation valve and iMlation of a i blind flange provided a superior isolation boundary between the Unit I service water system and the nonfunctional Unit 11 piping. The changes were made in accordance with ANSI B31.1. This piping is classified as non-nuclear i safety class, non-seismic and performs no function related to accident mitigation. The safety evaluation concluded j that this change did not involve an unreviewed safety question.
UFCR 91-008 Design Coordination Report (DCR): 90-005 i
Title:
WRGM Modification to Improve lodine Sample Factor Summary Description and
Purpose:
This change added several features to improve the sampling capabilities of l the plant vent wide range gas monitor (WRGM). A continuously operating sample pump and a flow control system were installed to maintain isokinetic conditions. Particulate and iodine grab sample cartridges were provided as a back-up to the WRGM high flow path. An additional flow path was provided to allow continuous tritium sampling. Thia modification provided permanent installation for equipment installed by MMOD 89-0627 (Backup instmmentation for WRGM). The existing indicator and an additional recorder were permanently installed in the main con:rol room. Five grab sample valves associated with the WRGM were replaced with valves that have packing suitable for high radiation service.
Safety Evaluation Summary: This DCR made changes to the facility as described in FSAR Section 11.5, Figure 9.4-3 and Table 12.3-4. This safety evaluation determined that the WRGM is not safety-related and the additional equipment was installed to the same seismic requirements as the original equipment. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 90-036 Dasign Coordination Report (DCR): 90-034 Thle: Data Acquisition System Sunmary Description and
Purpose:
This change installed additional telephone extensions to support the istallation of the data acquisition system. Extensions were installed at five control panel locations in the plant.
The telephone system was the only plant system affected.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Figures 1.2-8,1.2-37,1.2-38 and 1.2-59. The safety evaluation determined that this installation did not affect the plant facilities and did not connect to any plant system. The materials of construction and the installation details and techniques did not permit interaction with equipment important to safety. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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UFCR 93-042 Design Coordination Report (DCR): 90-052
Title:
Divert Site Storm Drainage to Unit #2 Circulating Water (CW) Piping and Provide Radiation Monitoring Summary Description and
Purpose:
This change eliminated water discharges to the Browns River by redirecting to the CW intake structure the discharges that normally collect in the settling basin. This was done via a new connection between the existing storm drain system and the Unit 2 CW discharge piping. A radiation monitoring subsystem was also installed to continuously sample the storm drain system discharge and alarm on levels of radioactivity indicative of contaminated liquid intrusion.
Safety Evaluation Summary: This DCR made changes to the facility as described in FSAR Sections 2.4,11.5, Table 11.5-1 and Figures 2.4-22,9.3-9 Sheet 1,10.4-4 Sheet I and 11.5-1. The safety evaluation determined that the storm drainage and interconnecting systems serve no safety function, nor do they interface with any system performing a safety function or having the potential to impact plant safety, except for the power supply to the radiation monitor and recorder. Since this power supply is powered from a diesel generator load panel, this added l load was evaluated and determined not to affect the total loading. The safety evaluation concluded that this change l did not involve an unreviewed safety question.
l UFCR 91-028 l Design Coordination Report (DCR): 92-024 l
Title:
Condensate Water Return to the Auxiliary Steam Condensate (ASC) System l l
Summary Description and
Purpose:
This DCR added piping to the condensate system to return condensate to the auxiliary steam condensate system. This was done to recover condensate for reuse in the auxiliary steam system during plant start-up. The condensate was previously discharged to the plant drain system.
Safety Evaluation Summary: This DCR made a change to the facility as described in UFSAR Section 10.4 and l Figures 10.4-6 and 10.4-17. The safety evaluation determined that the affected portions of these systems are not required for any safety function and are not required to support any safety related equipment. The design is in accordance with the applicable code standards. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 93-048 l
Design Coordination Report (DCR): 92-030 I i
Title:
Turbine Building Sodium Analyzer Replacement ;
I Summary Description and
Purpose:
This change replaced the existing condenser sodium analyzer with a state, 4 of-the-art model with digital readout, auto ranging and the resolution needed to track small water chemistry l changes. An analyzer was installed at each sample point rather than the current arrangement of one analyzer with ;
a sequencer for six sample points. This system will provide a more rapid response to small seawater leaks.
i Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR 10.4.1. The safety evaluation determined that the sampling system is not safety-related and that although the installation and 3
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mounting configuration is slightly different, it is qualified to the same criteria as the original installation. This change is an enhancement to the present system and does not change the basic function or failure mode. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 93-025 Design Coordination Report (DCR): 92-037
Title:
Permanent Reactor Cavity Seal Ring / Neutron Shield !
Summary Description and
Purpose:
This change replaced and upgraded the removable reactor cavity seal ring and neutron shield panels with a permanently installed design. This design incorporated neutron shielding integral to the ses.1 ring. The seal ring is used to seal the annulus between the reactor vessel sealing flange and the cavity floor to allow cavity flooding for refueling. The permanent seal ring eliminated the need to remove and install the existing seal ring and neutron shield panels for each refueling.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Sections 6.2.1.2 and 12.3.2.1. The safety evaluation determined that the seal ring does not perform any safety related function.
The design of the permanent seal ring and neutron shielding met or exceeded the criteria of the existing seal ring.
The ring is not part of the reactor coolant pressure boundary nor does it provide structural support for the reactor coolant pressure boundary or any safety related equipment. The design ensures that the ventilation air flow through the ring will maintain the existing ambient temperature profile of the reactor cavity. The ring does not perform any safety related function. It is a passive componem that does not functionally interact with any equipment important to safety. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-06 Design Coordination Report (DCR): 92-042
Title:
Primary Auxiliary Building and Steam Generator Blowdown Sodium Analyzer Replacement Summary Description and
Purpose:
This change replaced the sodium analyzer used in the primary steam and sampling system and the steam generator blowdown (SGBD) system with a state-of-the-art instrument with digital readout, auto ranging and the resolution needed to track small water chemistry changes. This design change required a modification of Panel CP-166B for the removal of analyzers and recorders and the rerouting of tubing and electrical wiring to the analyzers at the new location, below the panel.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Figt;re 9.3.13. The safety evaluation determined that the new sodium analyzers are an enhancement to the present system. The installation and mounting configuration is different but is qualified to the same criteria as the original installation.
The instrumentation and sample panel installed in the primary auxiliary building and SGBD recovery room do not provide any safety related functions and do not control or interact with any safety related equipment. The safety evaluation concluded that this change did not involve an unreviewed safety question.
j UFCR 95-03 1
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l Design Coordination Report (DCR): 92-067
Title:
Feedwater Ultrasonic Flowmeter Replacement Summary Description and
Purpose:
This DCR replaced the obsolete electronics for the four ultrasonic feedwater flow transmitters with new digital processors, provided test valves for the main feed pump pressure switches and modified the handrails by the main feed pumps. The existing flow probes in the feedwater lines were l used.
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l Safety Evaluation Summary: This DCR made a change to the facility as described in the figures in UFSAR )
l Section 10.4. The safety evaluation determined that these flowmeters are non-nuclear safety related and are not j relied on for plant control or accident mitigation. The test valves and connections are designed and installed in '
accordance with requirements that are equal to or bettec <han the vendor supplied tubing. The safety evaluation i concluded that this change did not involve an unrevievec aafety question. ,
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UFCR 93-028 l
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Design Coordination Report (DCR): 93-016
Title:
Replacement of Turbine Building (TB) Service Air Compressors Summary Description and
Purpose:
This change provided the design and engineering details necessary to replace the existing compressors, prepare foundations for the new compressors and reconfigure the secondary component cooling water and fire protection system piping for the compressors and instrument air dryers. These changes were made to improve overall plant reliability.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Sections 1.2.8.5, 9.3.1.2, 9.3.1.5, 10.4.10.2, Appendix "R", Section 3.2, Appendix "R", Table M 3.1.3.10-1; M 3.1.3.10-5; M 3.1.3.16-1; M 3.1.3.16-2; M 3.1.3.16-4 and Figures 8.3-1; 8.3-11; 8.3-14; 8.3-52, Sheet 1; 8.3-54; 9.3-8; 10.4-
- 14. The safety evaluation determined that the reliability of affected systems is maintained or improved and no new failure modes have been introduced. These changes are consistent with existing design criteria for the affected systems and malfunction of affected components would not affect the safety function of systems or components that are credited in the UFSAR. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 93-059 Design Coordination Report (DCR): 94-002
Title:
Bypass Test Instrumentation. Technical Specification Bases 3/4.3.1 and 3/4.3.2 Changes Summary Description and
Purpose:
This change added bypass test instrumentation (BTI) to the process instrumentation and nuclear instrumentation systems. This modified the way these systems, the reactor trip system and engineered safety features actuation system are tested.
Safety Evaluation Summary: This DCR made changes to the facility and procedures as described in UFSAR l Sections 7.1,7.2,7.3,8.3 and Figures 7.1-1; 7.2-3, 5, 6, 7, 8, 15; 7.3-1; 8.3-5, 6; 7.2-4 The safety evaluation l determined that the BTI does not change the function, setpoints, or failure modes of the 7300 process protection l
or nuclear instrumentation system (NIS). The Westinghouse BTI system is designed, constructed and installed to the same standards as the 7300 Process Protection and NIS. The DTI system has been designed to fail safe for credible failures. The instrument channels affected by the addition of BTI act to mitigate accidents and do not act 5
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1 as initiators of accidents. Only one channel will be bypassed at a time so the redundant channels will be available
' to initiate required safety function. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-024 Design Coordination Report (DCR): 94-027
Title:
Condensate Storage Tank Valve Room Heater Summary Description and
Purpose:
This change added an electric heater in the condensate storage tank valve room and provided a low room temperature alarm in the main control room. Also, several heat tracing circuits in the valve room were disconnected and abandoned in place. This change was initiated as a result of a station concern with heat tracing circuits. To address this issue a review of the freeze protection for safety related piping was conducted. This review indicated that in the event that the single circuit of heat tracing failed in this room, the water in the piping could freeze without an additional source of heat. The addition of a room heater and the i installation of the low room temperature alarm eliminated the need for heat tracing in this room.
l Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Figures 10.4-7, Sheet 5 and 6.8-2. The safety evaluation determined elimination of the existing heat tracing circuits and addition of a low room temperature alarm will provide a more reliable means of preventing line freezes and alerting the control room operators to a low area temperature. The safety evaluation concluded that this change did not involve an unreviewed safety question.
'JFCR 95-001 1
Design Coordination Report (DCR): 94-036
Title:
Replacement of Air Removal Piping Summary Description and
Purpose:
This change replaced the piping in the air removal system from the waterbox priming drop out tank to the priming pumps. The replacement items are fabricated from non-metallic or coated material to eliminate the corrosion currently being experienced with carbon steel equipment. A gate valve in the line was replaced with a butterfly valve and a pressure indicator was eliminated.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Figure 10.4-1.
The safety evaluation determined that the replacement of the piping and equipment of the same design but l fabricated from more corrosion resistant material does not affect the ability of the system to perform its design function. The air removal system is a non-safety related system. The safety evaluation concluded that this change did not involve an unreviewed safety question.
1 UFCR 95-018 i
l Design Coordination Report (DCR): 94-039
Title:
Feedwater System Overpressure Mitigation l
Summary Description and
Purpose:
This change modified the feedwater (FW) system to prevent an l overpressurization condition occurring after a reactor trip. The following modifications were made: increased the 1 I
maximum main feedwater isolation valve stroke time to 10 seconds, delayed the main feedwater control isolation l
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valve stroke time, limited the main feedwater pump speed after a reactor trip, decreased the low reactor coolant system average temperature (RCS Tave) setpoint (FW isolation with reactor trip) and added control logic to initiate the tripping of the main feedwater pumps on a low RCS Tave signal coincident with reactor trip isolation indication.
Safety Evaluation Summary: This DCR made changes to the facility as described in the UFSAR Section 6.2.1, Tables 6.2-13, 6.2-14, 6.2-15, 6.2-66, 6.2-68, 6.2-69a, 6.2-69b, 6.2-83, 7.3-2, 16.3-2 and Figures 7.7-7,7.2-2, 7.7-1, 7.2-1, 7.2-13 Sheets 1 and 2. The safety evaluation determined that the implementation of these changes did not increase the probability of a malfunction of equipment important to safety. The increase in feedwater isolation valve stroke time to 10 seconds had no impact on a loss-of-coolant-accident (LOCA) transient analysis.
The delay in the stroke time had a negligible impact on the non-LOCA analysis. Limiting the speed of the feedwater pump and changing the RCS Tave setpoint did not increase the probability of an accident. The safety l evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-053 Design Coordination Report (DCR): 94-043
Title:
MS-V94 and V% Relocation Summary Description and
Purpose:
This change relocated the emergency feedwater pump (EFW) turbine steam supply check valves MS-V94 and 96 downstream of the branch header vent lines to eliminate valve l chattering.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Figure 10.3-3. The safety evaluation determined that the relocation of the check valves and the modification of the piping meets all original design and code requirements. This change is downstream of the normally closed isolation valves and will not functionally impact the turbine-driven EFW pump to mitigate the consequences of an accident previously evaluated. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-019 Design Coordination Report (DCR): 95-003
Title:
Containment Pressure Control During Mode 6 Summary Description and
Purpose:
This change provided the design and installation details for the addition of a manually operated flow control damper in the containment air purge (CAP) supply duct to the containment. In addition, this DCR provides for a locally mounted pressure gauge to assist personnel in adjusting the flow control damper.
Safety Evaluation Summary: This DCR made changes to the facility as described in the UFSAR Figure 9.4-14.
The safety evaluation determined that this change was implemented to enhance the operators ability to control the levels of tritium and temperature in containment within acceptable limits. The CAP system functions are non-safety related and are not relied upon to support operation of any safety-related systems or components. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-046 l
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Design Coordination Report (DCR): 95-023
Title:
Valve blodifications To Prevent Pressure Locking Summary Description and
Purpose:
This change added a vent path to the following system valves: reactor coolant system, RC-V22, V23, V87, V88: residual heat removal system, RH-V32, V70: and, safety injection system, SI-V77, V102. Lines were provided to vent the bonnet cavity of these valves back to the process fluid, via the valve stem leakoff connection, to preclude the pressure buildup in the bonnet cavity thereby preventing ,
pressure locking of these valves. Liquid entrapment pressure locking may occur when a gate valve is closed with a system full of cold liquid, trapping the liquid in the bonnet cavity. When the liquid in the closed valve is heated, it l expands, potentially producing high pressure in the valve bonnet and disc if not relieved. Valves that are closed in a cold liquid-filled system and then heated are susceptible to this condition. The source of heat can be direct hot system fluid, or conduction of heat through piping in proximity to hot system fluid, or a surrounding air temperature rise.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Sections 5.4.12.2 and 6.3.2.2. and Figures 5.1-3, Sheet I and Sheet 4. The safety evaluation determined that the addition of the vent lines to the valves ensures that the valves will function properly when required to fulfill their safety function. The containment isolation function of valves RC-V23, V88, Ril-V32, V70, SI-V77 and V102 is not affected by this modification, nor is the operation of the RC, RHR or SI systems. The piping and valves added by this modification are designed to the same requirements as the existing system. No other safety systems are affected by this modification. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UCFR 95-044 Design Coordination Report (DCR): 95-029
Title:
hiain Steam Safety Valve Drain blodification Summary Description and
Purpose:
This change added an orifice in the common drain line serving the main steam safety valves associated with each steam generator thereby allowing the orifice bypass isolation valves in the drains for each individual safety to remain open. The presently installed orifices have experienced plugging because of the small bore size. The new orifices in the common drain header are larger and will preclude a strainer installed immediately upstream. Orifices are designed to limit steam release to the main steam /feedwater pipe chases if the safety valves lift and discharge steam through the drain lines.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Figure 10.3-2, Sheets I and 2. The safety evaluation determined that the enhanced drainage capability resulting from this change will increase the reliability of the safety valves and further ensure that the discharge stack is free of obstructions.
The probability and consequences of a malfunction of equipment important to safety is unaffected by this change.
The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-047 Design Coordination Report (DCR): 95-032
Title:
hfain Steam Safety Valve (hISSV) Setpoint Changes l Summary Description and
Purpose:
This change revised the MSSV setpressures and the power range neutron ;
flux high setpoints to ensure that the secondary system pressure will be limitc<1 to 1320 psia (110% f the design l pressure of 1200 psia) to mitigate an overpressure transient. These changes were made as a result of l 8
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Westinghouse Nuclear Safety Advisory Letter 94-001, which identified non-conservatisms in the original l calculations for the power range neutron flux high setpoints. i Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Sections 10.3.2.4 and 10.3.2.6 and Figures 10.3-2, Sheets 1 and 2. The safety evaluation determined that for postulated events that result in secondary system overpressurization, with challenges to one or more MSSVs in a loop, the effect of these revised setpressures is to reduce the peak transient secondary system pressure. Actual flow capacities are not changed and the MSSVs would lift earlier in any postulated event. The combination of these setpoint and setpressure changes ensure compliance with the bases for Technical Specification 3.7.1.1. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-043 Design Coordination Report (DCR): 95-042
Title:
Feedwater Isolation Valves' Drain Valve Summary Description and
Purpose:
This change eliminated the drain valves from the feedwater isolation valves. The valves were leaking and were not needed for operation. The valves were replaced by welded end caps.
Safety Evaluatian Summary: This DCR made a change to the facility as described in UFSAR Figures 6.2-91 and 10.4-9. The safety evaluation determined that this change did not affect the function or operability of the feedwater system. Elimination of the valves has no impact on the ability of this system to perform its design function.
UFCR 95-055 Design Coordination Report (DCR): 95-047
Title:
AMP-CAP and Circuit Breaker Instantaneous Trip Time Test Setpoint Summary Description and
Purpose:
This change revised the instantaneous trip response time acceptance criteria for Molded Case Circuit Breakers (MCCBs) and AMP-CAP Motor Circuit Protectors (MCPS) based on recommendations provided in current industry standards. The MCCBs and MCPS affected by this change are used in both safety-related and non safety-related applications. Previous instantaneous trip response time acceptance criteria was based on vendor recommendations for field testing. The maximum response time provided by the ,
i vendor was more restrictive than the acceptance criteria provided in industry standards. To prevent unnecessary replacement of protective devices due to inappropriate acceptance criteria, the acceptance criteria was changed.
Safety Evaluation Summary: This DCR made changes to the facility as described in UFSAR Tables 16.3-8 and :
16.3-10. The safety evaluation determined that the changes to the instantaneous trip response time acceptance criteria have been evaluated within design basis calculations with no impact on the results or conclusions.
These changes do not introduce any new failure modes for the protective devices. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-064 9
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Design Coordination Report (DCR): 95-062
Title:
Shunt Trip Circuit Breaker Replacement Summary Description and
Purpose:
This change provided supporting evaluations to allow the use of circuit breakers with or without shunt trip capability. Breakers with or without shunt trip have the same time current characteristic curves and they are equally qualified for environmental and seismic requirements. Functionally there will be no difference between the breakers with or without the shunt trip.
Safety Evaluation Summary: This DCR made changes to the facility as described in the UFSAR Figures 8.3-28, 29, 30, 31 and 41. The safety evaluation determined that an analysis has shown that the breakers with or without shunt trip have the same time-current characteristics, are equally qualified and these breakers do not affect the functional requirements of any equipment or system. This change is in compliance with existing design criteria for electrical distribution systems. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 954)62 l
10
1 Niinor hiodifications (hih10Ds)
The following minor modifications (MMODs) achieved operability status during the period covered by this 10CFR50.59 Report. A safety evaluation was performed for each MMOD. Each safety evaluation concluded that the MMOD did not involve an unreviewed safety question. Summaries of these MMODs and their safety evaluations are provided below.
Minor Modification (Mh10D): 90-571
Title:
1-PAH-AC-86A, Standard Instrument Schedule (SIS) and Miscellaneous Air llandling System Modifications Summary Description and
Purpose:
This change added evaporator and condenser isolation valves and replaced the main feed breaker shaft extension on 1-Pall-AC-86A. This modification also removed the service valve on 1-Pall-AC-86B and revised the fuel storage building differential pressure loop and computer logic. The SIS ,
revision reflected the installation of thermostats on two non safety related fans. !
l i
Safety Evaluation Summary: These modifications made changes to the facility as described in UFSAR Section '
9.4.2 and Figures 9.4-5,9.4-7 and 9.4-9. The safety evaluation determined that the new evaporator and condenser isolation valves are classified non-safety related, non-seismic and do not interface with safety related components or systems. The removal of the service valve will not affect any safety related equipment. The changes to the fuel buildigt alarm and computer logic are not safety related. The safety evaluation concluded that these changes did not involve an unreviewed safety question.
UFCR 914)02 Minor Modification (MMOD): 90-598
Title:
Removing the Internals of Check Valve SI-V297 4
Summary Description and
Purpose:
This change provided the evaluation to support the removal of the internals for check valve SI-V297. This valve was originally installed to prevent backflow into the boron injection tank (BIT). Later design changes eliminated the BIT and BIT bypass system. Since these systems have been eliminated, the valve is not required.
Safety Evaluation Summary: This modification made changes to the facility as described in the FSAR Figures 6.2-78; 6.2-94, Sheet 3; and 6.3-1, Sheet 6 and Table 3.9(B)-23, Sheet 38. The safety evaluation determined that upon activation of the emergency core cooling high head injection system that this valve is expected to open.
There is no credit taken for this valve to prevent backflow. By removing the internals, the potential for operational failures is eliminated. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 91-012 11
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1 Minor Modification (MMOD): 90-667
Title:
Penetration Protection - Deletion of Requirements for Locked Open Breakers Summary Description and
Purpose:
This modification was initiated to implement a design change to the containment electrical penetration and electrical protection devices. The change was subsequently revised through Change Authorization 01 to eliminate the need for hardware modifications. As part of the original modification l
change, it was identified that a penetration protection coordination concern existed when unit substation tie breakers were closed. As a result of this concern, a note was added to the Technical Requirements Manual and supporting procedure changes were made to address the coordination concern when the substation tie breakers are closed.
! Safety Evaluation Summary: This modification made changes to the Technical Requirements Manual and procedures to address the penetration protection coordination concern. No hardware changes were required as a result of this modification. The safety evaluation concluded that this change did not involve an unreviewed safety question.
l UFCR 91-082 l
l Minor Modification (MMOD): 92-510
Title:
Service Water Strainer Vent and Drain Addition 1
1 Summary Description and
Purpose:
This modification added vent and drain isolation valves and hose connections to the service water strainers to allow the effluent to be directed to the proper drains. This reduced the amount of salt water required to be processed via the liquid radioactive waste system.
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figure 9.2-2, Sheet 2. The safety evaluation determined that this change did not already affect the service water system or any of its components. The piping and valves added, which are part of the strainer pressure boundary, are the same Code Class as the strainers. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 92-051 Minor Modification (MMOD): 92-517 CA-01,02
Title:
Miscellaneous Document Corrections l Summary Description and
Purpose:
This modification reviews and updates the thermal overload sizing l calculations for the motor operated valves in the Generic letter 89-10 program and revised the emergency diesel generator (EDG) loading tables. This MMOD makes documentation corrections to reflect design information, to l reflect the sources of this information and to provide consistency in the use of this information within various design documents. The changes made by this MMOD did not result in any hardware changes.
1 Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Section 8.3.1.1 and Figures 8.3-1, 2, 6,18,19, 28, 29, 30, 31, 32, 33, 34, 35, 39, 40, 41, 42, 52 (Sheet 1), 53 (Sheet 1),54,58 and 59. 'lhe safety evaluation determined that the changes made by this MMOD are consistent with the existing design criteria for the affected systems and equipment. All equipment affected by this MMOD still 12
4 perform the same safety function. The analyses affected by this MMOD show that the affected equipment and systems operate in accordance with design requirements and that the EDG loading is within rated values. The safety evaluation concluded that this change did not favolve an unreviewed safety question.
UFCR 92-073 1
Minor Modification (MMOD): 92-542
Title:
SW-FI-6150 & 6151 l Summary Description and
Purpose:
This modification changed the configuration of the test connections for the service water flow instruments (1-SW-FI-6150 and 6151) to minimize the safety hazard and ease maintenance tasks. Additionally, the flow instruments were replaced with similar instruments with material more suitable for salt water service.
Safety Evaluation Summary: The replacement of the instruments made a change to the facility as described in UFSAR Figure 9.2-2 Sheet I and 2. The modification of the test connections did not change the facility as described in the UFSAR. The safety evaluation determined that these instruments provide local indication only.
There are no control or alarm functions associated with these flow instruments. No setpoints or operating parameters are affected. The safety evaluation concluded that this change did not inalve an unreviewed safety question.
UFCR 94-061 Minor Modification (MMOD): 92-550
Title:
1-SS-CP-166A Modification for Oxygen and Hydrogen Monitoring Summary Description and
Purpose:
This modification installed two inline flow chambers with probes for analysis of dissolved oxygen and hyarogen in the reactor coolant system. The information provided by these probes to the respective analyzers enhanced the sample results for these parameters. In addition to the flow chambers, flowmeters and isolation valves were installed. ,
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figure 9.3- ,
- 12. The safety evaluation determined that these instruments are an enhancement to the present sampling system. I These devices are not safety related and are not required for plant safe shutdown. The chambers allow plant personnel to sample for oxygen and hydrogen more easily and with a greater degree of accuracy. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-010 Minor Modification (MMOD): 93-538
Title:
Back Flow Prevention For Auxiliary Steam and Condensate System (ASC) Line in Steam Generator Blowdown (SB) Sump Summary Description and
Purpose:
This modification provided for the installation of a reverse flow device to prevent steam generator blowdown system flow from entering the auxiliary steam system.
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I Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figure 2
10.4-13, Sheet 2. The safety evaluation determined that the affected portion of the ASC system is non-safety
- related and the addition of this valve on the discharge piping does not impact the operation of the system. The safety evaluation concluded that this change did not involve an unreviewed safety question.
I UFCR 93-055 1
1 4
, Minor Modification (MMOD): 93-544
Title:
Relief Valves for WG-C-5A/B Bypass Lines
- Summary Description and
Purpose:
This modification added relief valves to the primary component cooling water (PCCW) side of the hydrogen gas compressors. The addition of relief valves will render the existing relief f bypass lines obsolete. This modification also disconnected the relief bypass connections on the upstream side of j the isolation valves. The existing check valves were also removed. The relief valves were added on the remaining j portions of the relief bypass lines that are located on the downstream side of the isolation valves.
l 4 Safety Evaluation Summary: This modification made changes in the facility as described in UFSAR Figures l 9.2-4 Sheet 2 and 9.2-6 Sheet 3. The addition of relief valves will allow for maintenance of the hydrogen gas
} compressors during periods other than normal outages. The addition of the relief valves and the removal of the i relief bypass lines will not affect the normal operation of the hydrogen gas compressors or the PCCW system.
I The relief valves will protect the hydrogen gas compressors and the aftercoolers from overpressurization if the 1 PCCW supply lines are inadvertently isolated. The relief valves perform the same function as the relief bypass lines. The addition of relief valves will not affect the operation of any equipment important to safety. The safety
, evaluation concluded that this change did not involve an unreviewed safety question.
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] UFCR 94-042 i
4 Minor Modification (MMOD): 94-501
Title:
Service Water Air Handling System Configuration i
Summary Description and
Purpose:
This modification updated the as-built configuration of the service water air handling (SWA) system. The Unit 2 SWA fans were intended to be replaced during construction of Unit 2.
- Due to the cancellation of Unit 2, the fans were never replaced and were still depicted on design documentation.
t The dampers were also incorrectly depicted on design documentation, i
Safety Evaluation Summary: This MMOD made changes to the facility as described in UFSAR Figures 1.2-46, 9.3-6 and 9.4-23. The safety evalitation determined that the installed system did not change. The design document i revisions did not change the Unit 1 SWA system configuration such that the probability of equipment malfunction would be increased. The safety evaluation concluded that this change did not involve an unreviewed safety
! question.
i
, UFCR 94-004 e
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1 14 i
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l Minor Modification (MMOD): 94-514 l
Title:
Fire Protection Pumps Recire. Header Bypass Line to Equalize Pressure 1
Summary Description and
Purpose:
This modification added a bypass line from the fire protection booster (jockey) pumps to the recirculation header. The bypass will serve to equalize the pressure across the recirculation valves allowing these valves to be opened with less force.
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figure 9.5-l 5. The safety evaluation determined that the modification did not increase the probability or consequences of an accident, did not increase the probability of vital equipment malfunction, and did not affect the margin of safety.
The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-045 Minor Modification (MMOD): 94-524
Title:
MSD-V34 and V35 Replacement Summary Description and
Purpose:
This modification replaced main steam drain valves MSD-V34 and MSD-V35 with valves having stainless steel gates. Additionally, this modification changed the logic of these and two other drain valves to eliminate spurious operation.
Safety Evaluation Summary: This MMOD made a change to the facility as described in UFSAR Figure 10.3-
- 11. The safety evaluation determined that these changes are associated with non-nuclear safety related components. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-030 Minor Modification (MMOD): 94-535 l
Title:
Delete Interlocks Between Switchgear Supply Air and Battery Room Exhaust Fans Summary Description and
Purpose:
This modification deleted the interlock that prevented the emergency switchgear room air supply fans from operating unless the exhaust fans were energized. The interlock ensured that the battery rooms were maintained at a negative pressure with respect to the surrounding areas. In the event the exhaust fans were not in service, the supply fans were also prevented from operating, possibly allowing hydrogen gas to accumulate in the room. Ample ventilation flow through the room was shown by calculation to be achieved with only the supply fans operating. Although the pressurization of the battery rooms may allow some migration l of a diluted air-hydrogen mixture into the surrounding areas, these adjacent areas are well ventilated such that l l hydrogen gas accumulation will not occur. In place of the interlock, an alarm in the main control room will I indicate when both battery room exhaust fans are non-functional. l Safety Evaluation Summary: This modification made changes in the facility as described in UFSAR Section 9.4.10. The safety evaluation determined that the changes complied with the guidelines in Regulatory Guide 1.128. These guidelines do not require that battery areas are maintained at a negative pressure with respect to the surrounding areas. The deletion of this interlock will increase the likelihood that adequate ventilation will be maintained in the battery room at all times. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-005 15 J
Minor Modification (MMOD): 94-540
Title:
Nitrogen Bottle Rack Modification Summary Description and
Purpose:
This modification removed two nitrogen cylinders from the nitrogen bottle rack to provide better access to NG-V30 in response to an industrial safety concern. This valve controls the high pressure nitrogen supply to the four safety injection accumulators. The deletion of two bottles will bring the number of remaining bottles to 46.
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Table 9.5.9 and Figure 11.3-3. The safety evaluation determined that the deletion of two nitrogen bottles will not affect the _
overall operation of the nitrogen system and that the system is still capable of maintaining the nitrogen blanket on !
the accumulators at the required Technical Specification pressure of between 585 and 664 psig. The safety ;
evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-059 Minor Modification (MMOD): 94-547
Title:
Plugging of Miscellaneous Drains Summary Description and
Purpose:
This modification permanently plugged two drains in the primary auxiliary building (PAB) and other sanitary and storm drainage system drains located in buildings or areas on site. The plugging of these drains eliminated the potential release paths for the inadvertent discharge of contaminates to the environment.
Safety Evaluation Summary: The modification of the drains in the PAB made changes to the facility as described in UFSAR Figure 9.3-21, Sheet 1. The safety evaluation determined that with these drains plugged, flooding in the PAB due to a service water line break adjacent to the primary component cooling water heat exchangers would not compromise the capability of any essential components. The other plugged drains are in plant drainage systems that are non-nuclear related and do not impact plant safety. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-015 l I
Minor Modification (MMOD): 94-548 l
Title:
Modification to FP Line 8134-1-M3-1 Summary Description and
Purpose:
This modification removed a drain line on the fire protection system in the turbine generator building. This drain line has experienced freezing resulting in damage to a valve in the line. The i
review of the fire protection piping identified sufficient alternate locations where fluid can be drained from the I system.
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figure 9.5-7 Sheet.1. The safety evaluation determined that the elimination of this line reduced the potential of an accidental opening or leak due to freeze damage that would incapacitate a portion of the fire protection system. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-049 16
O j Minor Modification (MMOD): 94-553 i
Title:
Battery Charger Failure Light / Alarm l
l Summary Description and
Purpose:
This modification eliminated the safety related battery charger failure lights and related computer logger points because they could not be set sufficiently low. to avoid nuisance alarms, eliminating a potential source of operator confusion. The station battery current digital ammeters, a more reliable indication of battery charger failure, were substituted for the failure lights and logger points.
i Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Sections 8.3.2.1.f .2 and 9 Tables 8.3-6 and 8.3-7 and Figure 8.3-37. The safety evaluation determined that the battery charger and the direct current system alarms were sufficient to provide the required status indication. This assures l
prompt operator alert of system / component failures that could degrade the system and compromise safe plant operations. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-058 Minor Modification (MMOD): 94-556
Title:
Steam Generator Blowdown Isolation Bypass Summary Description and
Purpose:
This modification provided A and B train switches on the main control board for bypassing steam generator blowdown on an emergency feedwater (EFW) actuation signal. Steam generator blowdown (SB) is isolated by the outboard isolation valves on a high energy line break (HELB) signal, phase A containment isolation "T" signal and on a start of the EFW pumps. Since isolating SB while the plant is in operation can result in chemistry transients, temporary modification, TMOD 93-0016, was implemented to provide accessible jumper terminals for preventing blowdown isolation during the performance of surveillance testing. This MMOD incorporated the function of this TMOD into a permanent plant design. The new bypass switches, indication lamps and related wiring were purchased and installed as Safety-Related Class lE components. Additionally, video annunciator system alarms were installed to support the use of the new steam generator blowdown bypass switches.
Safety Evaluation Summary: This modification made changes to the facility as describ.d in the UFSAR Section l 6.8.3. and Figure 7.2-14. The safety evaluation determined that the addition of these switches will not affect the function or failure modes of the isolation valves. The switches will only bypass steam blowdown isolation on l EFW actuation signals. The containment isolation ("T") and high energy line break (HELB) signals will not be l bypassed. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-048 Minor Modification (MMOD): 94-565 ;
Title:
Sample System Modifications Summary Description and
Purpose:
This modification added a check valve to the post accident sampling system (PASS) to ensure consistent sampling results. Additionally, a drawing was revised to reflect the correct time j delay for the starting circuit for the sample pumps.
Safety Evaluation Summary: This modification made changes in the facility as described in UFSAR Figure 9.3-
- 14. The safety evaluation determined that the PASS is not required to prevent an emergency condition and hcs no safety function. This system provides the capability of collecting liquid samples from reactor coolant loops 1 and 17
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3, emergency core cooling system pump room sumps and the containment recirculation sumps under post-accident conditions. Isolation valves that separate the PASS from the plant safety systems were not affected by this modification. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-002 i Minor Modification (MMOD): 94-570
Title:
Safety Classification Review l
Summary Description and
Purpose:
This modification clarified the ANS Safety Classification boundaries on the piping and instrumentation diagrams and the engineering database lists. These discrepancies were uncovered as part of an ANS Safety Classification review in response to a corrective action identified in SIR 93-105.
Safety Evaluation Summary: This modification made changes in the facility as described in UFSAR Figures 6.2-92, 6.8-2, 9.2-2 (Sheet 1-3), 9.3-3, 9.3-6 (Sheet 2), 9.4-2, 9.4-3, 9.4-6, 9.4-7, 9.4-8, 9.4-13 (Sheet 2), 9.4-14, 9.4-15, 9.4-16, 9.4-19, 9.4-20 and 9.4-23 were revised. Minor changes were also made to UFSAR Tables 3.2-2 and 3.2-4. The safety evaluation determined that the design documents and UFSAR changes resulting from this MMOD provide additional assurance that programs and procedures will procure and maintain these components consistent with their classification. No hardware changes were made as a result of the UFSAR and design document changes, therefore, there is no functional impact on any safety related system. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UI-CR 95-011 Minor Modification (MMOD): 94-572
Title:
Air Compressor DG-C-2A/B Oil Sump Temperature Switch Setpoint Revision Summary Description and
Purpose:
This modification revised the crankcase heater setpoints for the diesel generator air compressors from 95 F to 125 "F. The setpoint was revised to eliminate the accumulation of water in the compressor oil sump due to condensation.
Safety Evaluation Summary: This modification made changes in the facility as described in UFSAR Figure 9.5-12 Sheets 1 and 2. The safety evaluation determined that the air compressor crar kcase heaters and thermoswitches a~ classified as functionally non-1E, ANS safety class 3 components. As determined by Engineering Evaluation 9t 039, the operation of these components is not required to maintain diesel generator air start compressor functionality. The structural integrity of the immersion heaters is required to maintain the compressor crankcase pressure boundary. This integrity is not affected by the setpoint change. The switches do not perform a safety function. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-012 I
18 1
1
d Minor Modification (MMOD): 94-575
Title:
Pressurizer Relief Tank (PRT) Pressure Setpoint Change Summary Description and
Purpose:
The modification changed the PRT high pressure alarm setpoint to eliminate spurious and standing alarms. The setpoint was raised from 4 to 10 psig. Instrument cable shield grounds were also modified.
Safety Evaluation Summary: This MMOD made a change to the facility as described in UFSAR Section 5.4 and Tables 5.4-12 and 16. The safety evaluation determined that the PRT is non-nuclear safety related equipment.
PRT pressure does not adversely affect any equipment important to safety. The elimination of a second shield ground conforms to the plant's shielding design. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-009 Minor Modification (MMOD): 95-505
Title:
Release Recovery Tank Nitrogen Supply Valve Line-up Change Summary Description and
Purpose:
This modification changed the normal valve position for NG-V-185 from normally closed to normally open. This valve is in the nitrogen supply line to the release recovery tank and provided additional isolation between the potentially contaminated waste and vent gas (WG) system headers and the normally clean nitrogen supply header. Because of its location the operation of this valve created an industrial safety hazard each time the tank was filled with nitrogen. Leaving this valve open eliminated this hazard. To ensure adequate isolation is maintained between the WG system headers and relief valve NG-V-190, valves NG-V-131 and NG-V-132 , which are normally closed, will be administratively locked c.losed.
Safety Evaluation Summary: This modification made changes in the facility as described in UFSAR Figure l 11.3-2, Sheet 1. The safety evaluation determined that these valve lineup changes do not affect the nitrogen gas I system functionally. Leaving valve NG-185 normally open, places the system in a configuration that is normally used for pressurizing the release recovery tank. Having the normally closed NG-131 and 132 administratively locked closed, provides additional assurance that a release through the relief valve would not occur. This valve lineup change does not introduce an unanalyzed configuration and does not affect any safety related systems. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-023 Minor Modification (MMOD): 95-506
Title:
DM System Fill for RMW-TK12 with Spool Piece Permanently Installed Summary Description and
Purpose:
This modification permanently installed a spool piece to fill the reactor makeup water (RMW) storage tank from the demineralized makeup (DM) water system. This storage tank may be filled from either the DM system or the boron recovery system (BRS). With this installation the normal source of water will be the DM system.
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figure 9.3-38 and Section 9.2.7.2. The safety evaluation determined that the contamination of the DM system with tritium will be prevented by two manual isolation valves and a check valve. The isolation valves will normally be closed when the storage tank is not being filled. Administrative procedures will control the filling of the storage tank.
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I The DM system, RMW system and BRS do not perform any safety related functions and are not required for the
, safe shutdown of the plant. The safety evaluation concluded that this change did not involve an unreviewed safety question. l UFCR 95-017 l
Minor Modification (MMOD): 95-509
Title:
CBS Sump Isolation Valve Modifications Summary Description and
Purpose:
This modification provided a vent line on the containment building sump isolation valves, CBS-V-8 and 14. Following a LOCA, these valves open upon receipt of refueling water storage tank 10-10 signal to allow the containment building spray (CBS) and residual heat removal (RIIR) pumps to take suction from the containment sumps. It has been postulated that if liquid became entrapped in the valve bonnet and was subsequently heated due to :he increased temperature following a LOCA, the valve could be prevented from opening due to excessive bonnet pressure. This change added a line to vent the bonnet side of the valve to the upstream (sump side) piping to ensure the continued operability of these valves.
Safety Evaluation Summary: This modification made changes to the facility as described in UFSAR Figures 6.2-74 and 6.2-91, Sheet 2. The safety evaluation determined that the addition of the vent lines to the CBS sump isolation valves ensures that the valves will function properly when required to fulfill their safety function. The containment isolation function of the sump isolation valms is not affected by this modification, nor is the operation of the CBS or RiiR systems. The piping and valves added by this modification are designed to the same requirements as the existing system. No other systems are affected by this modification. All systems will continue to function as designed. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-033 l
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O UPDATED FINAL SAFETY ANALYSIS REPORT CHANGE REOUESTS (UFCRs)
The following UFCRs, not related to DCRs or MMODs, were incorporated ino this revision of the UFSAR. A l safety evaluation was performed for each UFCR. Each safety evaluation concluded that the UFCR did not involve
, an unreviewed safety question. Summaries of these UFCRs and their safety evaluations are provided below. ;
1 '
1 Updated Final Safety Analysis Report Change Request (UFCR): 93-021
Title:
UFCR 93-021 j Summary Description and
Purpose:
The UFCR deleted Table 9.5-9, " Listing of Unusually Hazardous Material" and clarified the design requirements of the fire protection water storage tanks. The need for the table no longer exists because the description of fire hazards are listed in the BTP APCSB9.5-1 Appendix A Report.
Safety Evaluation Summary: This UFCR made changes to the facility as described in UFSAR Sections 1.8, 9.5; Table 9.5-9 and BTP APCSB 9.5-1 Appendix A. The safety evauation determined that the fire protection j system is a non safety related system. The deletion of Table 9.5-9 and the clarification of the storage tank
- capacities did not make any changes to the design basis of the fire protection system and does not change the j operation or setpoints of any equipment. The safety evaluation concluded that these changes did not involve an
- unreviewed safety question.
- Updated Final Safety Analysis Report Change Request (UFCR): 94-003 and 96-005
Title:
Storage of Non-Processed Resin in HICs in the Waste Processing Building Summary Description and
Purpose:
The UFCR clarified that the storage of polyethylene high integrity containers in steel overpacks are not a fire hazard and will not add to the combustible loading of the building.
Safety Evaluation Summary: The UFCR made a change to the facility as described in BTP APCSB9.5-1 Appendix A Report and Section i1.4. The safety evaluation determined that the storage of non-processed resin does not affect the operation of the plant. There is no safety related equipment within the storage area. The safety j evaluation concluded that this change did not involve an unreviewed safety question. j i.
Updated Final Safety Analysis Report Change Request (UFCR): 94-011
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Title:
Communications System I
Summary Description and
Purpose:
The UFCR identified several microwave channels which changed to an l alternative system.
I Safety Evaluation Summary: This UFCR made changes to the facility as described in UFSAR Section 9.5. The i safety evaluation determined that the microwave and telephone access changes are not safety related and will have 1 no effect on safety related equipment. This change will provide an enhancement and alternative method of communication. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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I Updated Final Safety Analysis Report Change Request (UFCR): 94-056 Safety Evaluation: SE-95-121-01 Technical Requirements Change Request: 95-06 l
Title:
Changes for Wide-Band Operation Core Design Enhancements and Cycle 5 Summary Description and
Purpose:
The UFCR mcorporated the changes that address the Cycle 5 mechanical, nuclear and thermo/ hydraulic aspects of the fresh fuel and reload core designs. This core loading pattern features a low leakage configuration, which is achieved by placement of fresh fuel assemblies on the core edge. The benefit of such a core design are reduced irradiation exposure to the reactor pressure vessel, extended cycle full-power lifetime and improved stability to axial xenon oscillations near rnd of core.
Safety Evaluation Summary: This UFCR made changes to facility and procedures as described in several UFSAR Sections, Tables and Figures in Chapters 1,4,5,6,7,15, and 16. The safety evaluation determined that the Cycle 5 reload core design meets all applicable design criteria and ensures that all pertinent licensing basis acceptance criteria are met. Adherence of the fresh fuel and reload core C. signs to these standards and criteria precludes new challenges to components and systems that could introduce a new type of a malfunction of equipment important to safety. All original design and performance criteria continue to be met. No new failure modes have been created for any system, component or piece of equipment. No new single failure mechanisms have been introduced.
Update Final Safety Analysis Report Change Request (UFCR): 94-060
Title:
Service Water Cooling Tower Piping Heat Tracing Summary Description and
Purpose:
This UFCR revised the text in Section 9.2.5 to incorporate a description of the existing safety related freeze protection features provided for service water system piping in the cooling tower. l This was a recommendation as a result of the evaluation of station Mcident report (SIR) 93-76. l Safety Evaluation Summary: This UFCR made a change in the facility as described in UFSAR Section 9.2. The !
safety evaluation determined that incorporating a description of the existing safety related freeze protection j features provided for service water system piping in the cooling tower had no effect on the current system i function or capability. The safety evaluation concluded that this change did not involve an unreviewed safety question. j Updated Final Safety Analysis Report Change Request (UFCR): 95-013
Title:
Reactor Vessel Behline Material Chemistry Revisions Summary Description and
Purpose:
The UFCR revised Table 5.3-3, "Seabrook Unit No. I Reactor Vessel l Material Properties", to incorporate the mean value of copper content for the intermediate and lower shell plates.
This revision was as a result of a commitment in letter NYN-94087 to update applicable licensing documents with this mformation.
Safety Evaluation Summary: This UFCR made changes to the facility as described in UFSAR Table 5.3-3. The safety evaluation determined that this revision did not change the safety function of systems or components and it is consistent with existing design criteria. The design function of the reactor vessel remains undanged. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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- Updated Final Safety Analysis Report Change Request (UFCR)
- 95-028 and %-005
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Title:
Steam Generator Blowdown Evaporators l
l' Summary Description and
Purpose:
This UFCR incorporated information on the current plant status regarding the use of steam generator blowdown evaporators. A permanently installed vendor supplied resin skid will be
]' used, in lieu of the blowdown evaporators, to process radioactive secondary system liquids in the event of a steam q
generator tube leak. The resin skid technology generates less waste, is more economical and produces a higher quality effluent.
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'j Safety Evaluation Summary: This UFCR made changes to the facility as described in UFSAR Sections 1.2, 10.4, 11.1, 11.2, Appendix 11.A and 12.3 and Table 1.3-2. The safety evaluation determined that the evaporator subsystem of the steam generator blowdown system is non-nuclear safety related. No changes were made to the blowdown evaporator system. The liquid radwaste treatment system remains available for use to reduce the release of radioactivity. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Report Change Request (UFCR): 95-029
Title:
Secondary Chemistry Program Changes Summary Description and
Purpose:
This UFCR incorporated changes to the description of the secondary chemistry program designed to reduce the corrosion product transport to the steam generators and enhance long l term steam generator reliability. These changes were based on the latest EPRI guidance and recent industry operating experience.
Safety Evaluation Summary: This UFCR made changes to the facility and procedures described in UFSAR Sections 9.3,10.3; Tables 9.3-1, 10.3-1; and Figures 9.3-15. The safety evaluation determined that these changes to the secondary chemistry program were designed to reduce carbon steel and copper alloy corrosion of I secondary components which, in turn, reduces the corrosion product transport to the steam generators. The reduction in sludge loading is expected to improve the long term steam generator reliability. The safety evaluation !'
concluded that these changes did not involve an unreviewed safety question.
Updated Final Safety Analysis Report Change Request (UFCR): 95-038
Title:
UFSAR Revision for the Regenerative Heat Exchanger (RIIE) Block Valve Summary Description and
Purpose:
This UFCR incorporated an explanation of the exception to the requirements of the ASME Code for the configuration of manual block valve, CS-V183, that is in the discharge path of relief valve, CS-V184. The code requires positive controls and interlocks on this type of valve to ensure that the pressure relieving function of the relief valve is met at all times. The plant block valve and relief valve configuration was part of the original standard design specified by the vendor. The purpose of the block valve is to facilitate maintenance. Administrative controls are in place to ensure that the block valves remain open when the RHE is operable.
Safety Evaluation Summary: This UFCR made changes to the facility as described in UFSAR Section 9.3. The safety evaluation determined that the exception to the ASME Code is acceptable because the block valve is part of the original standard design provided by Westinghouse, facilitates maintenance of the component and has strict administrative controls for maintaining the valve in an open position during plant operation to ensure overpressure protection is not defeated. In the event that the block valve is mispositioned, the plant capability of shutdown and 23 J
n0 operation of the emergency core cooling system would not be impaired. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Report Change Request (UFCR): 95-048
Title:
Revision of Technical Requirement 11 Summary Description and
Purpose:
This UFCR clarified the requirements for the inspection of penetration fire i seals. This change defires an operable fire seal as one that can perform its designed fire function. It also specified
! the criteria for inspection of additional seals in the event of a penetration seal failed inspection.
Safety Evaluation Summary: This UFCR made changes to the procedures described in UFSAR Section 16.3.
The safety evaluation determined that this change did not degrade the fire protection system's ability to perform its design function. The ability to achieve and maintain safe shutdown in the event of a fire is not being adversely affected by this change request. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): 95-051
Title:
UFCR No.95-051 Summary Description and
Purpose:
This UFCR added a discussion on the operation of the residual heat removal (RHR) system when the level in the reactor coolant system is above midloop. Varying flow rates are necessary to prevent RHR pump vortexing, air entrainment, cavitation, and subsequent loss of RHR cooling.
Safety Evaluation Summary: The UFCR made changes to the facility as described in UFSAR Section 5.4 and Table 6.2-83. The safety evaluation determined that the RHR system will be operated at varying flow rates that are governed by strict administrative controls. The operation of the RHR system in this manner does not affect the i integrity of the RHR pumps or the system that its function in the control of radiological consequences is affected. I Operating in this manner does not affect any fission barriers or create an unmonitored release path. Equipment important to safety will not be affected by RHR reduced flow operation. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): 95-054
Title:
Revised Post LOCA Hydrogen Vent Analys'.s for UFSAR Chapter 15 Summary Description and
Purpose:
This change revised the conservative assumptions for the aluminum and zinc inventories in containment and the respective hydrogen generation rates. This allowed an increase in the available contingency for these potentially hydrogen generating materials. The calculation also revised the start time for post LOCA containment purging for hydrogen control (in the event of recombiner failure) to 16 days.
The previous start time for containment purge was 22 days after an accident.
Safety Evaluation Summary: This UFCR made a change to the facility and the procedures as described in UFSAR Section 15 and Appendix 15B and Tables 15.6-19 and 15.6-23. The safety evaluation determined that the l primary control of post LOCA hydrogen is accomplished by redundant hydrogen recombiners. Venting for l hydrogen control is only required in the unlikely event that both recombiners fail. The total LOCA dose is within l the existing criteria in the Seabrook Station safety evaluation report NUREG 0896. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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Updated Final Safety Analysis Change Request (UFCR): 95-058
Title:
Spent Fuel Pool Bridge Holst Summary Description and
Purpose:
This UFCR clarified the overload cutoff for the spent fuel pool bridge hoist. The limit applies when a fuel assembly is raised from the seated position.
Safety Evaluation Summary: This UFCR was issued to cr) vide additional detail to Section 9.1 to slarify the text and did not constitute a change in the facility or procedures as de.ccribed in the UFSAR nor did it invalve tests or experiments not described in the UFSAR. The safety evaluation determined that this change does not affect the design, operation or testing of the hoist. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): 96-006
Title:
Section 1.9 Task IH.D.1.1 Change Summary Description and
Purpose:
This UFCR described enhancements to the boric acid leakage reduction program. The changes maintain ihe required actions as described in .NUREG 0737. The major enhancement will be to allow the use of the minor maintenance program to accomplish inspections of systems during or after operation. This program enhancement will reduce personnel exposure by eliminating repetitive inspections.
Safety Evaluation Summary: This UFCR made a change to the procedure described in UFSAR Section 1.9.
The safety evaluation determined that this change enhanced the effectiveness for detecting boric acid leakage. The changes associated with the boric acid leakage reduction program deal with the inspection, documentation and correction of findings. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): 96-009
Title:
Health Physics Organizational Change Summary Description and
Purpose:
This UFCR updated the description of the Health Physics organization.
This change maintains the responsibilities of the heahh physics functions while allowing some flexibility in organizational structure.
Safety Evaluation Summary: This UFCR made a change to the facility as described in UFSAR Section 12.5 and Table 12.5-1. The safety evaluation determined that this change was admiaistrative only. The responsibilities for providing radiation protection functions to the organization still resides with the health physics organization. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Chr.nge Request (UFCR): % -010
Title:
Elimination of Duplicate Technical Requirements from the UFSAR, Chapter 16 Summary Description and
Purpose:
This UFCR removed the technical requirements from Chapter 16 of the UFSAR and referenced the Technical Requirements (TR) Manual as the controlling document for technical requirements. This was done to eliminate any possible inconsistencies, since the technical requirements could be found in the UFSAR and TR Manual.
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I I Safety Evaluation Summary: This UFCR made a change to the procedures described in UFSAR Chapter 16 and !
Sections 9.5 and 13.5. The safety evaluation determined that this change would remove duplicate information from the UFSAR. The Technical Requirements Manual is the primary source of this information. The manual changes are reviewed by SORC and NSARC prior to issue. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): 96-011
Title:
Delete Storage Requirements For Food, Water and Emergency Facilities in the Technical Support Center Summary Description and
Purpose:
This change eliminated the need to maintain emergency rations of food and water and potable toilet facilities for emergency personnel. In the event of an emergency, the acquisition and distribution of food and beverages and toilet facilities for the site will be directed by personnel at the emergency operation facility.
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Safety Evaluation Summary: This UFCR made a change to the facility as described in UFSAR Section 6.4. The safety evaluation determined that this change is consistent with NUREG 0737. Reg. Guide 1.78 and Reg. Guide 1.95. Depending on the nature and severity of an accident, food and beverage for site emergency responders can be obtained from onsite cafeteria facilities, vending machines, or from area food service providers. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): % -015
Title:
UFSAR Annual Update Chapter 13.2, Training Summary Description and
Purpose:
This UFCR updated the training program and organization descriptions.
l This change eliminated the expanded descriptions of various training programs and referenced the respective program descriptions.
Safety Evaluation Summary: This UFCR made a change to the procedures as described in UFSAk Chapter 13.
The safety evaluation determinert that this change was administrative and addressed programmatic and organizational changes in the training organization. The change did not involve' plant equipment. The training program for operators meets the requirements of 10 CFR Part 55. The safety evaluation concluded that this change did not involve an unreviewed safety question.
l Updated Final Safety Analysis Change Request (UFCR): 96-016
Title:
Revision to UFSAR Chapter 9 l
l Summary Description and
Purpose:
This UFCR clarified specific elements of the chemistry monitoring program. Changes were made to the sampling and analysis requirements for the reactor makeup water and its sources, to reflect current industry standards with respect to the spent fuel pool chemistry and to clarify sampling locations.
{ Safety Evaluation Summary: This UFCR made changes to the procedure described in UFSAR Sections 9.1, l 9.2,9.3 and Table 9.2-17. The safety evaluation determined that this che.cee does not alter the design or manner l in which any system component operates and will have no impact on any component opnion. The safety j evaluation concluded that this change did not involve an unreviewed safety question.
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. l Updated Final Safety Analysis Change Request (UFCR): % -019
Title:
Administrative Changes to UFSAR Description of Effluent Analysis Summary Description and
Purpose:
This UFCR clarified the sampling and analysis description for radiological effluents to accurately reficct current practices.
Safety Evaluation Summary: This UFCR made changes to the procedures described in UFSAR Section 11.5.
The safety evaluation determined that this change does not affect plant design or equipment. Equipment important to safety is unaffected by this change. The safety evaluation concluded that this change did not involve an l unreviewed safety question. I Updated Final Safety Analysis Change Request (UFCR): % -020
Title:
Corrections to Sections 12.3 and 12.5 i
Summary Description and
Purpose:
This UFCR updated and corrected descriptions for the neutron shield, q counting room equipment, contamination control and instrumentation. The proposed changes are considered j administrative relative to plant equipment. j Safety Evaluation Summary: This UFCR made a change to the facility as described in UFSAR Section 12.3, l 12.5; Tables 12.5-1, 12.5-2 and Figure 12.3-3. The safety evaluation determined that these changes do not '
introduce new equipment or plant equipment processes. The changes are administrative only. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): % -022
Title:
UFSAR Update for Chapter 13.1 Summary Description and
Purpose:
This UFCR provided a description of the organizational structure for North Atlantic Energy Service Corporation (NAESCO) and the relationship to Northeast Utilities (NU). The ultimate responsibility for the operation and maintenance of Seabrook Station is with the NU Executive Vice President and Chief Nuclear Officer. This UFCR reflects the changes through the position of Director.
Safety Evaluation Summary: This UFCR made changes to the procedures described in UFSAR Section 13.1.
The safety evaluation determined that this change is administrative in nature and does not involve any plant equipment. Plant operation will not be adversely affected by this change. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Updated Final Safety Analysis Change Request (UFCR): 4 023
Title:
Operation Quality Assurance Program Manual Summary Description and
Purpose:
This UFCR updated the description of the Quality Assurance Program.
This change meets the submittal requirements of 10CFR50.54(a)(3) for changes to the program that do not reduce its effectiveness. This change reflects the new NU/ NAESCO organization and incorporates changes in review responsibilities, program manual titles and the methodology for nuclear fuel procurement.
Safety Evaluation Summary: This UFCR made changes to the procedures described in UFSAR Section 17.2 and Figure 17.2-1. The safety evaluation determined that this change does not impact plant operations. This i
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change represents minor changes to organization, reporting and responsibilities, as well as, updates to procedure references and editorial corrections. The safety evaluation concluded that this change did not involve an t.nreviewed h-ty question.
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O ENCLOSURE 2 TO NYN-96039 Summaries of the Remaining 10CFR50.59 Safety Evaluations Performed for Temporary Modifications, Procedure Changes, l Commitment Changes, and Miscellaneous Changes l l
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1 TEMPORARY MODIFICATIONS (TMODs) l l
l The following temporary modifications (TMODs) were installed during the period covered by this 10CFR 50.59 Report and have remained installed. In each case, a safety evaluation was performed. UFSAR changes were not made due to the temporary nature of the modificatien s' Safety evaluation concluded that the TMOD did not involve an unreviewed safety question. Summario t va fMODs and their safety evaluations are provided below.
Temporary Modification (TMOD): 88-002
Title:
Chiller Surge Tank, CS-TK-3, Nitrogen Blanket Summary Description and
Purpose:
This modification provides the temporary equipment and connectiois necessary to establish a nitrogen blanket on CS-TK-3 for the purpose of long term lay-up and corrosion control. A regulated supply of low pressure nitiogen and a water seal device were installed on the tank. This tank is part of the boron thermal regeneration subsystem.
Safety Evaluation Summary: This TMOD affected the facility as described in UFSAR Figure 93-15. The safety evaluation determined that this system has no emergency function and is not required for safe shutdown.
The use of the nitregen blanket was evaluated by engineering and the tank vendor. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Temporary Modification (TMOD): 90-053
Title:
Improved Monitoring of Secondary Chemistry Summary Description and
Purpose:
This modification installed a modular structure in the turbine building and provided the electrical connections, process tubing and fire protection modifications. This structure houses chemistry monitoring equipment that will help locate minute condenser leaks.
Safety Evaluation Summary: This TMOD did not make changes to the facility and the procedures in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The sampling system and the wet pipe sprinkle systems are non-safety related and do not interact with any safety related control system. The systems affected by this modification have no design basis in the safe operation or shutdown of the plant. The ,
safety evaluation concluded that this change did not involve an unreviewed safety question. !
l Temporary Modification (TMOD): 92-015 l
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Title:
Addition of Oxygen Monitoring Equipment Summary Description and
Purpose:
This modification provides a method of obtaining a continually monitored sample stream at the discharge of the condensate pump to evaluate oxygen levels at the condensate pump discharge as well a method of testing for inleakage into the system.
Safety Evaluation Summary: This TMOD affected the facility as described in UFSAR Figure 10.4.7. The safety evaluation determined that the affected portion of the condensate system is non-nuclear, non-safety and does not impact any safety related equipment. This change will improve the monitoring of oxygen and the ability to detect air inleakage. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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1 Temporary Modification (TMOD): 95-006
Title:
345KV Line 394 Fault Locator '
Summary Description and l'urpose: This modification added a relay with fault locating capability to the 345 kv terminal of the 394 line to study and identify the cause of numerous recent faults. The relay stores voltage and current data coincident with a line fault but does not perform any control or tripping functions.
Safety Evaluation Summary: This TMOD affected the facility as described in UFSAR Section 8. The safety evaluation determined that this change does not impact the fanction, performance or reliability of the offsite power supply and associated distribution systems. The installation of this equipment does not affect the ability to monitor the 345 kv line and to protect and recover from system faults. The safety evaluation concluded that this change does not involve an unreviewed safety question.
1 Temporary Modification (TMOD): 95-039
Title:
Remove Internals of BRS-%231 Summary Description and
Purpose:
This modification removed the internals of check valve BRS-%231 to allow water to be pumped from the waste test tanks to the unused recovery test tanks. This increases the storage capacity for waste water. This water can be drained to the floor drain tanks for processing or returned to the waste test tanks for discharge.
Safety Evaluation Summary: This TMOD affected the facility as described in UFSAR Sections 9.3 and 11.2 and Figure 9.3-38. The safety evaluation determined that there is no potential to impact equipment important to safety. The boron recovery system is class 1fied non safety related. The fluids transferred are normal for the systems involved. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Temporary Modification (TMOD): % -008
Title:
Chemical Cleaning of the Generator Stator Cooling (GSC) System Summary Description and
Purpose:
This modification added the equipment to clean the GSC system on-line using a disodium salt of the complexing agent EDTA (ethylene diamine tetra acetic acid). This cleaning was performed using an established process directed by the vendor to reduce the copper oxide blockage in the stator cooling loop.
Safety Evaluation Summary: This TMOD affected to the facility as described in UFSAR Section 8.2 and 10.2.
The safety evaluation determined that the GSC system is non-safety related. This system provides cooling for components of the non-safety related turbine generator. The only credible event which could be initiated by a malfunction in the GSC system is a turbine trip, which has been evaluated in UFSAR Section 15. The GSC system is a closed loop system which does not interface with other systems. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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Temporary hiodification (TMOD): % 012 ;
Title:
FW-V-153 Seat Leakage Repair i Summary Description and
Purpose:
This modification was developed to install an injection valve on steam generator recirculation isolation valve, FW-V-153, to allow a sealant to be pumped into the space above the valve plug to stop leakage past the valve. Leakage past this valve collects in the emergency feedwater (EFW) discharge header, which could cause steam binding as described in NRC Information Notice 84-06 and IE Bulletin 85-01.
This modification is intended to eliminate the seat leakage until permanent repairs can be made.
Safety Evaluation Summary: This TMOD did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined, based on calculation C-S-1-45408, that the valve components are capable of withstanding the additional forces resulting from the injection pressure. This valve is not required to support EFW system l operation. The injection process is procedurally controlled to ensure that sealant material will not enter the EFW or feedwater systems. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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Temporary Modification (TMOD): % 014 ;
Title:
Disabling DG-C-2A Oil Sump Level Switch IX;-LSL-9519A ,
Sunmary Description and
Purpose:
This modification disables the diesel generator air compressor tube oil smrp level switch, DG-LSL-9519-A. This switch is constantly in alarm due to a switch malfunction, resulting in alarms at the local annunciator and the digital point. 'Ihis interferes with receiving other alarms in the control reom from the diesel generator. Disabling the level switch input restores the ability to monitor the diesel g:nerator. The switch will be repaired at the next available opportunity.
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Safety Evaluation Summary: This TMOD made a change to the facility as described in UFSAR Section 9.5.
The safety evaluation determined that additional compensatory measures will be taken to verify adequate sump oil level in the compressor. The reliability of the compressor is not affected by this modification. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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COhih1ITh1ENT CHANGE REOUESTS (CCR)
The following CCRs not related to UFCRs, DCRs or MMODs were approved. A safety evaluation was performed ;
for each CCR. Each safety evaluation concluded that the CCR did not involve an unreviewed safety question. l Summaries of these CCRs and their safety evaluations are provided below.
j Commitment Change Request (CCR): 94-07
Title:
Submerged Cables and Supports Summary Description and
Purpose:
This request changed several commitments related to the monitoring of electrical manway enclosures to ensure that power cables are maintained in a satisfacto*y condition. The initial commitment required the monitoring of water level, the inspection of cable supports and the meggering of cables to demonstrate this capability. Dased on an engineering evaluation, a revised cable monitoring program and a sampling inspection program were established.
Safety Evaluation Summary: This request did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that cables are capable of satisfactory performance under submerged conditions for 40 years.
Approved cable testing methods will be used to monitor the cable condition. The safety evaluation concluded that these changes did not involve an unreviewed safety question.
Commitment Change Request (CCR): 95-02
Title:
Seabrook Station Secondary Chemistry Annual Report Summary Description and
Purpose:
This change deleted the requirement to submit an annual secondary j chemistry report as delineated in NUREG-0896, Supplement 1. NUREG-0896, Supplement 5 further concluded I that the secondary chemistry program described in Technical Specification 6.7 was an acceptable alternative to the requirements of Supplement 1. This technical speciFcation does not require an annual report.
Safety Evaluation Summary: This request did not make a change to the procedures or the facility as described )
in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation j determined that the secondary water chemistry program retains the same commitment to reduce secondary i material corrosion and transport into the steam generators. He discontinuation of the submittal of an annual report does not reduce the effectiveness of the secondary water chemistry program. The safety evaluation ;
concluded that this change did not involve an unreviewed safety question. I Commitment Change Request (CCR): 95-04
Title:
Removal of Locked High Radiation Area Control Commitment Summary Description and
Purpose:
This change removed the commitment for a door guard when a locked high i radiation area (LHRA) door is opened to permit work in the area and the double verification sign-off when the l door is subsequently secured. These commitments were unnecessarily burdensome and are not necessary to control LilRA access in all cases. Increased training and the heightened worker awareness on LHRA controls, along with the programmatic requirement for workers are sufficient to ensure the doors are locked.
i Safety Evaluation Summary: This request did not make a change to the procedures or the facility as described I in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation l
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i determined that this change was administrative in nature and did not involve any plant equipment, processes, I l evaluations or accident analysis. The safety evaluation concluded that this change did not involve an unreviewed I safety question.
1 Commitment Change Request (CCR): 95-05
Title:
Reply to Notice of Violation l
Summary Description and
Purpose:
This request changed the rigging equipment inspection from a monthly l
l inspection to a prior to use inspection. The commitment to perform a monthly inspection was made in response to a Notice of Violation in NRC Inspection Report 91-80. This inspection report identified that equipment was checked out for use that had exceeded its inspection date. The actual use of expired rigging was not cited as a concern. Frequent inspections prior to use of lifting equipment has been successful in preventing the use of lifting equipment whose periodic inspections have expired.
i Safety Evaluation Summary: This request did not change the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that this change does not alter any system, structure or component. This change is limited to the administrative control l of nonsystem related rigging equipment. Rigging equipment that has an expired inspection date is not used until l
the inspection is performed. The safety evaluation concluded that this change did not involve an unreviewed safety question.
1 Commitment Change Request (CCR): 95-06
Title:
Revise Commitment to Provide Annual Vendor Interface with Key Safety Related Vendors l
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Purpose:
In response to Generic letter 90-03, a program was developed to contact key safety-related vendors annually. The letter recommended periodic contact with these vendors. Subsequent experience with this program has indicated that a triennial vendor contact is adequate since many of the vendors provide the necessary information on a pro-active basis. Other utilities have also adopted this contact interval.
This change is consistent with Generic Letters 83-28 and 90-03.
Safety Evaluation Summary: This change did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that changing this commitment does not introduce any new equipment, operating procedures or modifications to existing equipment or systems, nor does it involve any potential initiating events that would create the possibility of a new or different kind of accident or malfunction than any previously evaluated. The safety evaluation concluded that this change did not involve an unreviewed safety question. i l
l Commitment Change Request (CCR): 95-07 1
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Title:
NUREG - 0612 Special Lifting Device Examination l l
l l l Summary Description and Parpose: This request revised commitments made in response to NUREG-0612 to clarify the frequency of tests and inspections, to exempt inaccessible (underwater) welds from visual examination during the load test for the upper internals lifting rig and allow the non-destructive examination of the lifting welds at the end of an outage.
Safety Evaluation Summary: This CCR did not make a change in the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined i
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that the changes are clarifying in nature and do not change the overall number of examinations or inspections to be performed on the special lifting devices. The design margins of the reactor head and internals lifting devices are not affected by the changes. The structural integrity of the lifting devices is not degraded. The safety evaluation I concluded that this change did not involve an unreviewed safety question.
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Commitment Change Request (CCR): 95-08 I
Title:
Delete Drop Testing of Technical Requircraent Fire Dampers )
Summary Description and
Purpose:
This request deleted the commitn.ent to drop test fire dampers. Drop testing of fire dampers is not required by the Technical Requirement surveillance requirements. The commitment '
was documented in a 1986 NRC inspection report as a result of the failure of some fire dampers to close under design air flow conditions during the initial startup testing of the plant. The CCR concluded that drop testing was not required to ensure operability of the dampers. Operability will be ensured by the visual inspections of the dampers which will ensure they are in good condition.
Safety Evaluation Summary: This CCR did not make a change to the facility or procedures described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the fire protection system is a non-safety related system. This change will not adversely affect the operation of any equipment important to safety. Eliminating the drop test of the fire dampers may reduce the likelihood of damage to the dampers. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Commitment Change Request (CCR): 95-09
Title:
Emergency Diesel Generator Control Air Commitment Change Summary Description and
Purpose:
A commitment was made in response to a Notice of Violation that a program to trend air consumption of the emergency diesel generator (EDG) air system would be developed. This data would be used to write a Technical Clarification to address the impact of the air system's preventative maintenance history on the EDG operability. Instead of this Clarification, it was determined that during maintenance activities on the control air system the EDG must be considered inoperable. The need to trend this data was no longer required and the commitment was deleted.
Safety Evaluation Summary: This change did not make a change to the facility or the procedures in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the trending of the EGD control air consumption is not required to support the operability of the air control system.
Requiring the operability of the air system at all times to support the EDG operability is a conservativ approach, ensuring the availability of the EDG to mitigate the consequences of an accident. The safety evaluation concluded that this change did not involve an unreviewed safety question. l Commitment Change Request (CCR): 96-01
Title:
Roving Nuclear Shift Operator Logs 1
Summary Description and
Purpose:
The response to NRC Bulletin 85-01 committed to the use of a contact pyrometer to monitor Emergency Feedwater discharge pipe temperatures. This change added the touch of the hand as an acceptable method to monitor the EFW discharge pipe temperature as allowed by Bulletin 85-01.
Safety Evaluation Summary: This request did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation 34 ie
c, determined that touching the pipe to monitor the temperature is consistent with IE Bulletin 8541 requirements.
The safety evaluation concluded that this change did not involve an unreviewed safety question.
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MISCELLANEOUS SAFETY EVALUATIONS The following miscellaneous safety evaluations were performed during the period covered by the 10CFR50.59 Report. A safety evaluation as defined in the requirements for 10CFR50.59 may not be required, but a safety evaluation was performed for conservatism. Each safety evaluation concluded that the situation or activity did not involve an unreviewed safety question. Summaries of these safety evaluations are provided below.
Safety Evaluation: SE-94-124-01
Title:
Replacement Main Plant Computer System (MPCS) Software Summary Description and
Purpose:
This evaluation documented the testing of the MPCS software. To ensure that the information present to the operators and plant staff has not been affected by the installation of the new computer system and to ensure that all new features of the system are properly presenting informaticn, extensive testing of the hardware and software has been performed.
Safety Evaluation Summary: This evaluation made changes to the facility as described in the UFSAR. The safety evaluation determined that the MPCS is not a safety related system. The MPCS has undergone extensive testing to ensure that the information presented to the operators in the form of alarms, displays and calculations is accurate and reliable. The safety evaluation concluded that this change did not involve an unreviewed safety question. !
Enginecr!ng Evaluation: 93-021
Title:
Manual Operation of CBA Dampers Summary Description and
Purpose:
This evaluation documented the UFSAR Change Request made as a result of the engineering evaluation previously identified in the 10CFR 50.59 Annual Report submitted by North Atlantic letter (NYN-95010) on January 31,1995. This evaluation further clarified the description of the manual actions required to operate certain dampers in the control room heating, ventilation and air-conditioning system and the switchgear / battery room ventilation system.
Safety Evaluation Summary: This evaluation made changes to the facility as described in UFSAR Sections 9.3 and 9.4. The safety evaluation determined that this change did not add any new systems or components, or modify existing systems or components. This change only takes credit for the manual operations in the existing design.
The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 92-053 License Amendment Request (LAR): 93-08
Title:
Revisions to Technical Specification 6.2.3, Independent Technical Reviews Summary Description and
Purpose:
This request revised the Technical Specifications by retitling the Specification as Independent Techtbal Reviews and deleting the current requirement to have a five person organization assigned to carry out the prescribed reviews. The revised Specification maintains the review requirements and requires a Technical Review Program to be established and maintained to ensure that the reviews are completed.
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l Safety Eva antion Summary: This revision made changes to the facility and procedures as described in the UFSAR Sec'. ions 1.9 and 13.4.3. The safety evaluation determined that these changes were administrative and did not modify any plant structures, systems or components, revise plant operating procedures, introduce any equipmer.t malfunctions or failure mechanisms, or affect the plant's response to any transients. The safety evaluation concluded that this change did not involve an unreviewed safety question.
1 UFCR 93-019 License Amendment Request (LAR): 93-20
Title:
Technical Specification Administrative / Editorial Changes Summary Description and
Purpose:
This request revised the Technical Specifications to incorporate several administrative changes. These involved changes primarily to the Station Operating Review Committee, the Nuclear Safety Audit Review Committee, the addition of the Station Qualified Reviewer Program, the deletion of the requirement to review plant procedures at least every two years and other miscellaneous editorial revisions.
Safety Evaluation Summary: This revision made changes in procedures as described in UFSAR Sections 13.5.1, 17.2.6, 17.2.10, 17.2.11 and Appendix 17A. The safety evaluation determined that these changes did not involve any modifications to plant systems, structures or components nor is the design, function, or method of operation of any plant system, structure, or component altered. None of these changes reduced the margin of safety. The safety evaluation concluded that these changes did not involve an unreviewed safety question.
UFCR 93-045 l
l License Amendment Request (LAR): 95-02
Title:
Temperature Limit for Reactor Coolant System (RCS) Oxygen Control Summary Description and
Purpose:
This request raised the temperature limit for RCS oxygen control from 180 "F to 250 F. When operating at or above 250*F oxygen must be controlled to less than 0.1 PPM. This change is consistent with the NSSS vendor recommendations, EPRI lit-rature and standard technical specifications at other pressurized water reactors.
Safety Evaluation Summary: This request made a change to the procedures as described in UFFAR Section 5.2.3 and Table 5.2-5. The safety evaluation determined that the corrosion nechanisms due 'a the oxygen concentration on the RCS and relatea system materials are negligible below 250 'J. Oxygen control is conducted to minimize ccrrosion of RCS components. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-022 37
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License Amendment Request (LAR): 94-06 l
Title:
Modifying Seabrook UFSAR Chapter 15, Subsection 15.7.4, " Fuel Handling Accident", based on Revised Technical Specification 3.9.4, " Containment Building Penetrations" Summary Description and
Purpose:
This request revised the Technical Specifications to allow the use of an i alternate closure method for the containment building penetrations during core alterations or movement of irradiated fuel within containment. Additionally, the change allowed both personnel airlock doors to be open during core alterations or movement of irradiated fuel within containment. I Safety Evaluation Summary: This revision made changes to the facility and procedures as described in UFSAR Section 15.7.4. and Tables 15.7-18, 24 and 25. The safety evaluation determined that the radiological consequences associated with a fuel handling accident inside containment during core alterations or movement of irradiated fuel, are well within 10 CFR Part 100 limits. No credit was taken for closing the personnel airlock door or a penetration valve. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-025 License Amendment Request (LAR): 95-03 l
Title:
Relocate Pressure Isolation Valve Table 3.4-1 from the Technical Specifications to the Technical Requirements Manual Summary Description and
Purpose:
This request relocated Table 3.4-1, Reactor Coolant System Pressure Isolation Valves, from Technical Specification 3.4.6.2, Reactor Coolant System Operational Leakage, to the Technical Requirements Manual. This change is consistent with the Westinghouse Standard Technical Specifications, NUREG-1431.
Safety Evaluation Summary: This request made changes to the procedures as described in Technical Requirements Manual Table 16.3-12, considered part of the UFSAR. The safety evaluation determined that this change was administrative in nature and resulted in improved administrative practices and does not affect pla':t operations. The revision did not make changes to the plant or in the method that any safety related system is tested or performs its safety function. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 95-042 License Amendment Request (LAR): 95-01
Title:
Boron Concentration Changes Summary Description and
Purpose:
This request increased the boron concentrations required by Technical Specifications and decreased the post LOCA hot leg recirculation initiation time from 18 to 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. The increase in the boron concentrations ensured that sufficient negative reactivity remained available to offset the design increase in positive core reactivity due to the increase cycle length.
Safety Evaluation Summary: This request made changes to the facility and procedures described in the UFSAR Sections 6.1, 6.3, 6.5, 9.1, 15.1, 15.5 and Tables 6.2-75, 6.3-1, 6.3-7, 6.3-9, 9.1-1 and 9.3-7. The safety evaluation determined that the changes in boron concentrations assure the post-event shutdown margin required by Technical Specifications will be met by maintaining core sub-criticality. The change in the post-LOCA hot leg 38 1
switchover initiation time from 18 to 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> will prevent the core region from reaching the boron precipitation limit. The safety evaluation concluded that these changes did not involve an unreviewed safety question.
UFCR 95-057 Calculation 4.3.16-13F, Revision 3 Summary Description and
Purpose:
This calculation predicts hydrogen generation in containment after a LOCA. This revision identified additional design margin due to changes in the assumptions in the original calculation and more realistic assumptions for the modeling of hydrogen generation. Additional design margin was quantified in terms of more aluminum and zinc contingency.
l Safety Evaluation Summary: This calculation made changes in the facility as described in UFSAR Section 6.2-5; Tables 6.2-87,6.2-88, 6.2-89 and Figures 6.2-96 and 6.2-97. The safety evaluation determined that the ability l of the combustible gas control system to maintain the concentration of hydrogen below flammable limits in the post-LOCA environment is not impacted by this change. The plant design incorporates redundant hydrogen recombiner capability. The backup purge system is no longer required but represents additional safety margin if both recombiners are not available. This change does not affect the performance of the recombiners. This change has no impact on the safety related and seismic qualification requirements of the combustible gas control system.
The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 93-063 f
Technical Requirement Change Request (TRCR): 94-008
Title:
Technical Requirement II, " Fire Rated Assemblies & 12, " Fire Detection Instrumentation" Summary Description and
Purpose:
This TRCR revised Technical Requirement Number 11 and 12 to clarify the frequency of the fire watch patrol. This change was incorporated to allow the use of security personnel to perform the dual function of security rounds and fire watch patrols.
Safety Evaluation Summary: This TRCR made changes to procedures as described in UFSAR Section 16. The safety evaluation determined that the fire protection system is a non safety related system. The changes proposed l
in this change will not affect any equipment important to safety. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-057 Technical Requirement Change Request (TRCR): 95-001
Title:
Technical Requirement Number 6 and UFSAR Table 6.2-83 Summary Description and
Purpose:
This TRCR revised Technical Requirement Number 6 to incorporate several changes: revise valve stroke times for valves that receive a steamline isolation signal in Section E; correct the page reference for the administrative control requirements; revise the note that refers to the containment refueling purge and exhaust valves; and identify emergency feedwater steam supply bypass valves as manual ;
valves ( relocate from Section E to Section D).
Safety Evaluation Summary: This TRCR made changes to the facility as described in UFSAR Tables 6.2-83 l and 16.3-4. The safety evaluation determined that this revision made no physical change to plant equipment or the l 1
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O manner in which it is operated. Deleting valve stroke times in Section E is consistent with the UFSAR descriptions and the design basis as defined in engineering documents. Retaining a valve stroke time requirement for the containment refueling purge and exhaust valves for operation during Mode 6 ensures that the valves are capable of providing the required containment isolation in response to the containment ventilation isolation signal.
The safety evaluation concluded that these changes did not involve an unreviewed safety question.
UFCR 95 Mi Procedure Change: LS95-1-1/ LS95-1-2
Title:
Implementation of MMOD 94-0569 for 27B1/ 27B2 Relay l
Summary Description and
Purpose:
This change implemented the undervoltage relay modifications for the 4160 volt emergency bus loss of voltage protection scheme. The existing arr:mgement of internal relay terminal shorting bars is being reconfigured to assure the emergency bus undervoltage trip function is not disabled during testing.
The new design for the bus undervoltage scheme eliminates the need to install jumpers and lift wires to gain the required relay test configuration.
Safety Evaluation Summary: This procedure change made a change to the facility as described in UFSAR Section 8.3 and involves tests or experiments not described in the UFSAR. The safety evaluation determined that during the implementation of this modification, the 4160 volt bus would continue to response to control and protection demands. The most severe consequence of a failure or error during modification implementation is the loss of one emergency bus. With the loss of one power train, the second train would not be affected and there would be no change, degradation or prevention of acans assumed to take place during an accident. The loss of one power train is part of the design bases and has been analyzed in the safety evaluations. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Procedure Change: ON1055.02, Rev. 5, Chg. 8
Title:
Proposed Procedure to Align Manual Makeup to the Spent Fuel Pool Using Demineralized Water Summary Description and
Purpose:
This change identified a method of aligning manual makeup to the spent -
fuel pool using demineralized water. Makeup water is necessary to replenish the water lost to evaporation. This change was determined to be an acceptable method for filling the pool provided precautions were included to prevent inadvertent siphoning.
Safety Evaluation Summary: This procedure change did not make a change in the facility or procedures as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that this change did not impact the existing functions of the safety related equipment associated with spent fuel pool makeup. Siphoning of the pool was addressed by specifying that the hose will not contact the pool water and a check valve will be installed in the hose. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Procedure Change: OS1001.03
Title:
Reactor Coolant Drain Tank Operation, OS1001.03, Rev. 07, Change 05 Summary Description and
Purpose:
This change provided an alternate penetration for the containment sump discharge. The discharge will be routed through the reactor coolant drain tank (RCDT) penetration and to a floor drain in the mechanical penetration area. The ultimate destination remains the floor drain tanks.
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m Safety Evaluation Summary: This procedure change allows for normally closed valves to be positioned open creating a flow path that would differ from that shown on UFSAR Figures 9.3-17,18 and 21. The safety evaluation determined that the connections will be made on the non-nuclear safety portions of the liquid waste system. The containment isolations for the RCDT and the containment sump will still function as designed. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Procedure Change: OS1016.10
Title:
Maintenance / Inspection of the Cooling Tower Pumps with Divers Summary Description and
Purpose:
This procedure change addressed the service water cooling tower pump outage required for pump replacement and inspection. Restoration of the cooling tower to service, including removing the divers from the basin was estimated to require approximately 10 minutes. This interval provides sufficient margin for restoration of the cooling tower to service in the event of a tunnel collapse concurrent with a loss of offsite power.
Safety Evaluation Summary: This evaluation made a change to the procedures described in the UFSAR.
Additional administrative controls for service water system operation were provided. The safety evaluation determined that the manual actions established in this procedure ensured the continued availability of the service water system. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Procedure Change: OS1030.01, Rev.10, Chg.11
Title:
Main Steam Condenser Dump Valve Isolation Summary Description and
Purpose:
This change isolated two main steam condenser dump valves due to leakage past the valves. Isolating these valves increased plant efficiency.
Safety Evaluation Summary: This change did not make a change to procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the main steam condenser dump valves are not safety related and are not required for a safe shutdown. The main steam safety valves prevent overpressurization of the secondary system. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Procedure Change: OS1035.02, Revision 7. Chg.1
Title:
Startup Feedpump Operation Summary Description and
Purpose:
This change provided the steps necessary to feed the steam generators from the startup feedpump via the emergency feedwater (EFW) cross connect lines. This configuration will be app;icable below 10% rated thermal power. This change was made to support operational flexibility. This procedure change was subsequently withdrawn due to circumstances described in Adverse Condition Report 95-511.
Safety Evaluation Summary: This change did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that this alignment does not affect the ability of the emergency feedwater pumps to start under an accident condition and the ability to automatically or marmally isolate EFW flow to all steam generators is maintained. The EFW system design basis includes this flow path capability. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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Procedure Change: IS1690.816; Work Request 95W000684 Safety Evaluation: 95-111-01
, Safety Evaluation: 95-143-01 i
Title:
Fixed Incore Instrumentation (FICI) Thimble Insertion l Summary Description and
Purpose:
This change allowed the tightening of the compression nut and the cap on i the flushing tee for the incore detector assembly while pressurized. Application of torque is limited to a maximum '
of 50 foot-pounds or until leakage has stopped.
1 j Safety Evaluation Summary: This procedure change and work request did not make any changes to the facility 1
or procedures in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety l evaluation determined that revising the procedure to allow in-service torquing of the compression nut and cap on a
! Swagelok fitting does not detract from the original design of the piping. Resultant preload stresses due to torque l are within normal allowable specifications, accordingly the margin of safety in the design of the joint is j maintained. The safety evaluation concluded that this change did not involve an unreviewed safety question.
j Procedure Change: MS0517.19, Revision 2, Chg.1, (Work Package 94W0003495) l t
Title:
Placement of Backfill Summary Description and
Purpose:
This change was prepared to authorize a one time exception to the j compaction testing requirements to permit the use of tunnel cutting materials in trenches for the cables of a non-i safety related lighting system. Instead of purchasing backfill material it was decided to use the material from the j tunnel excavation. The trenches were not in close proximity to a foundation or support for any structure, system
- or component.
i l Safety Evaluation Summary: This change did not make a change to procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that i this change was limited to a one time application to a non-seismic, non safety related activity and no seismic or safety class foundation, support, system or component was affected. The safety evaluation concluded that this j change did not involve an unreviewed safety question.
i Safety Evaluation: 95-05T-001 (95-078-001, Revision 1)
Title:
Operation at Power with Feedwater IIcaters 26A and 26B Out of Service Summary Description and
Purpose:
This safety evaluation documented the acceptability of operating the plant at power with both the 26A and the 26B feedwater heaters out of service. Operation of the plant in this configuration is necessitated by the damage sustained by the subject heaters during a plant trip and resultant transients.
Safety Evaluation Summary: This evaluation did not make any changes to the facility or procedures described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the plant will continue to operate within the licensed thermal and electrical rating and all safety systems will continue to be available and capable of functioning as required. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Safety Evaluation: 95-075-001 42 1
Title:
Unit Substation E51/E52 and E61/E62 Bus Tie Closure Summary Description and
Purpose:
This evaluation was performed to allow the closure of the 'ous ties in (
accordance with the Technical Specification requirements and entry into the Action Statement where necessary.
Sirety Evaluation Summary: This evaluation did not make a change to the facility or procedures as dertbed in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the closure of the tie breakers did not make any functional changes to plant equipment and uses equipment within its design capabilities. The appropriate calculations and evaluations required by the UFSAR and the Technical Specifications to maintain operability of the electrical distribution system have been completed. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Safety Evaluation: 95-094-001
Title:
Temporary Draindown of Cask Loading Pool Summary Description and
Purpose:
This evaluation documented a plant evolution involving the inspection and maintenance of the fuel transfer equipment without the use of divers. To accomplish this task, temporary closure of the spent fuel pool gate and draindown of the cask loading pool is required. Draindown will be accomplished by pumping the cask loading pool to the spent fuel pool using a temporary submersible pump.
Safety Evaluation Summary: This evolution did not make a change to the facility or procedures described in the l UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that I the spent fuel pool level will be maintained since the spent fuel pool gate will be closed with its seal inflated. The gate conforms with the original design requirements. This evolution did not involve spent fuel or shipping cask handling. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Safety Evaluation: 95-095-001
Title:
Technical Specification Bases 3/4.4.2 Change Summary Description and
Purpose:
This change clarified the Bases to allow the removal of pressurizer safety ,
valves to meet the intent of the corresponding Specification. This change will allow the removal of the three l pressurizer safety valves to provide a gravity vent path in place of removing the manway when the plant is at ;
reduced inventory conditions. The removal of the valves will afford the reactor coolant system equivalent or >
superior protection as an overpressure device. it will permit operation in a midloop condition without the removal of the pressurizer manway, saving critical path time during refuelings without any reduction in the margin of
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safety. '
Safety Evaluation Summary: This change did not make any changes to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the removal of a pressurizer safety valve provides increased reliability by immediately relieving pressure in the event of a reactor coolant system overpressurization condition. This change is conservative and consistent with the Technical Specifications. The safety evaluation concluded that this change did not involve an unreviewed safety question.
Safety Evaluation: 95-104-001
Title:
Technical Specification Bases 3/4.9.1 Change 43 1
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l Summary Description and
Purpose:
This change replaced the existing Bases discussion for Technical l Specification Bases 3/4.9.1 with a modified version of the same Bases section from NUREG 1431, Revision 1, Westinghouse Standard Technical Specifications, dated April 7,1995. The change provided a more complete
- discussion of the Bases for the refueling boron concentration requirements.
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- Safety Evaluation Summary
- This change did not make a change to the procedures or facilities described in the 4
UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that this change did not impact any of the initiating conditions or consequences for the accidents evaluated. The probability of a malfunction of equipment important to safety will not be increased by this change. The safety evaluation concluded that this change did not involve an unreviewed safety question.
! Safety Evaluation: 95-147-001 1
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Title:
Cycle 5 Safety Evaluation for F Delta H Increase 5
Summary Description and
Purpose:
This evaluation documented the 2% change in the F delta H limits allowed I during Cycle 5 operation. This increase was evaluated and determined to be bounded by the assumptions of the safety analysis performed for Cycle 5.
I Safety Evaluation Summary: This limit increase did not make changes to the facility or procedures described in
- the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined j that no new pet formance requirement were imposed on any system or component such that any design criteria will
! be exceeded nor will they cause the core to operate in excess of pertinent design basis operating limits. The safety
! evaluation concluded that this change did not involve an unreviewed safety question.
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- Safety Evaluation
- % -022-01
Title:
Storage of Radioactive Materials in the Sea-vans Containers in the Protected Area t
Summary Description and
Purpose:
This evaluation addressed the storage of low level contaminated or activated equipment and materials in closed sea-van containers in the protected area.
Safety Evaluation Summary: This evaluation did not make a change to the facility or procedures described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that the storage of radioactive material in sea-vans in the protected area does not affect the operation of the plant.
These containers are not located in or near safety related structures or systems. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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i Safety Evaluation: 96-022-02
Title:
Storage of Radioactive Wastes and Materials in the Waste Processing Building l
Summary Description and
Purpose:
This document evaluated the storage of wastes and material in waste ,
processing building (WPB) locations other than the drum storage areas (DSA). The operation of the facility l generates contaminated or activated items that may be stored in areas other than the DSA. Although the UFSAR does not prohibit storage of radioactive material in these areas, an evaluation was performed to clarify the storage requirements in the WPB.
Safety Evaluation Summary: This evaluation made a change to the facility as described in UFSAR Sections 1.2 l l and 11.4. The safety evaluation determined that there is no safety related equipment in the WPB. The storage of l waste and material in the WPB will not affect the operation of the plant. The safety evaluation concluded that this !
! change did not involve an unreviewed safety question.
I Procedure: ES94-1-80 l
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Title:
SW-P110 Pump Ilead Curve Verification Summary Description and
Purpose:
This evaluation documented a test procedure for verifying the head curve for the replacement cooling tower service water pumps. These pumps were replaced due to potentially degraded column flange bolts, column to bowl bolts, bowl studs and impeller thrust ring retainer cap screws.
Safety Evaluation Summary: This procedure did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that in the event that a cooling tower service water pump cannot obtain the required performance during the conduct of the test, the other service water pumps in the same train will remain fully operable and capable of supplying the necessary cooling. The safety evaluation concluded that this change did not i involve an unreviewed safety question. !
l Operability Determination (OD): 95-010 (ACR 95-500)
Title:
Loose Debris in Containment 1
Summary Description and
Purpose:
The purpose of the evaluation was to determine the acceptability of leaving minor debris inside containment while establishing containment integrity for operating cycle 5. Five items were identified in the pressurizer missile shield and several areas on the seal table trolley showed signs of flaking paint.
i Safety Evaluation Summary: This evaluation did not make a change to the procedures or the facility as described in the UFSAR nor did it involve tests or experiments not described in the UFSAR. The safety evaluation determined that if the debris were dislodged during an accident, that due to the size and geometry of the material, this debris would have a negligible effect on the flow through the recirculation sump screens. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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ENCLOSURE 3 TO NYN-96039 Listing of10CFR50.59 Safety Evaluations Completed But Not Required Pursuant to 10CFR50.59 i
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e Desien Coordination Reports (DCRsh Design modification described in the following DCRs were installed during the period covered by this 10CFR 50.59 report. These DCRs did not meet the requirements for performance of a safety evaluation as specified in 10CFR50.59, however, safety evaluations were performed for conservatism. Each safety evaluation concluded that the DCR did not involve an unreviewed safety question. The documentation for each DCR listed below is available onsite for review.
Number:
Title:
86 DCR 358 Oil Water Separator Vault Oil Analyzer Removal 88 DCR 030 Inappropriate Penetration Fire Seals 89 DCR 054 RIIR Pump Surveillance Instrumentation 92 DCR 062 Sample System Isolation Valve SS-FV-2857 Replacement 93 DCR 006 SGBD Waste Sump Access 93 DCR 009 Oil / Water Separator Vault #1 Ventilation 93 DCR 010 RCA Tunnel Monorail Sysiem 93 DCR 028 Erosion / Corrosion Program Piping Component Replacement 93 DCR 036 Install Nitrogen Generators for Explosive Detectors 93 DCR 055 Transformer Fire Detectwn Replacement 93 DCR 058 Area and localized Temp. Reduction for the Main Steam Feedwater Pipe Chases 94 DCR 011 Admin. Bldg. Power - Primary Chemistry Lab and Cafeteria 94 DCR 031 J10 Relay Replacement Interfacing with Westinghouse 7300 Cabinets 94 DCR 033 Permanent Access to Cooling Tower Fans 94 DCR 050 Add Power to Cold Machine Shop 95 DCR 007 Mast MTD CCTV for Refueling Time Reduction 95 DCR 040 Repairing the Charging Pump Main Lube Oil Pump Coupling Drive Pins and IIoles l
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a Minor Modifications 81MODsh Design modifications described in the following MMODs were installed during the period covered by this 10CFR50.59 report. These MMODs did not meet the requirements for performance of a safety evaluation as specified in 10CFR50.59, however, safety evaluations were performed for conservatism. Each safety evaluation concluded that the MMOD did not involve an unreviewed safety question. The documentation for each MMOD listed below is available onsite for review.
Number:
Title:
94 MMOD 517 Resize Circuit Protective Devices for CAS-CP-556 94 MMOD 518 Equipment Hatch Shield Wall Tensioning Rods 93 MMOD 552 Instrument Hoist for Service Water Cooling Tower 95 MMOD 502 Cooling Tower Fan 2-FN-51B Wiring Connection 94 MMOD 513 Chemical Addition System Minor Modification 94 MMOD 503 Containment Sump Level Alarm Setpoint 92 MMOD 586 Fuel Handling System Crane Modification 92 MMOD 518 Auxiliary Steam and Condensate System 1-ASC-PIC-9257 Setpoint 92 MMOD 519 I/P Replacement - MS Condenser Dump Valves 93 MMOD 557 Reinstate Stop Turbine Loading Control 91 MMOD 548 Disable High Alarm of Freeze Protection Circuits 94 MMOD 564 Jumper Installation in BTRS 93 MMOD $25 CC Inservice Testing Flow Indication 95 MMOD 519 Modification to Support MS-1301-SG-44 92 MMOD 550 CP-166A Modification for Oxygen and Hydrogen Monitoring 94 MMOD 547 Provide Details for Plugging of Miscellaneous Drains ,
93 MMOD 542 ITT Barton Switch Plastic Lens Changeout l 94 MMOD 563 Welding Canisters - Overnight Storage Within RCA 91 MMOD 583 1-PAH-UH-230 Removability l 94 MMOD 569 4160V Undervoltage Relay 27B Test Configuration Modification j 95 MMOD 501 Re-throttle Charging Pump to Cold Leg Valves i 93 MMOD 534 Safety Related UPS and Static Transfer Switch Setpoints 93 MMOD 547 MSIV Slow Closure Solenoid Reset Time Delay 91 MMOD $17 Turbine Generator Lube Oil Reservoir Piping 95 MMOD 503 S.G. Wet Layup System Isolation Flange Blanks 94 MMOD 567 Rod Control-CRDM Timing Change l
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