ML20078G162
| ML20078G162 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/31/1995 |
| From: | Drawbridge B NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20078G165 | List: |
| References | |
| NYN-95010, NUDOCS 9502020433 | |
| Download: ML20078G162 (60) | |
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b i North Nordi Adande Energ Senim Corporadon P.O. Box 300 I
Atlantic Se broet, Nii 03874 (603) 474-9521 )
The Nordm.st Utilities System NYN. 95010 January 31,1995 ;
United States Nuclear Regulato y Commission i Washington, D.C. 20555 ,
Attention: Document Control Desk
References:
(a) Facility Operating License No. NPF-86, Docket No. 50-443 (b) North Atlantic letter NYN-93080 dated May 26,1993, "10CFR50.50 Annual Report and Revision 2 to the Seabrook Station Updated Final Safety Analysis .
Report", T.C. Feigenbaum to USNRC (c) North Atlantic letter NYN 94096 dated August 26,1%4, " Revised Schedule for the 10CFR50.59 Report and UFSAR Revision Submittal", T.C. Feigenbaum to USNRC Subiect: 10CFR50.59 Annual Report and Revision 3 to the Seabrook Station Updated Final Safety Analysis lieport Gentlemen:
North Atlantic Energy Senice Corporation (North Atlantic) encloses herein the 10CFR50.59 I Annual Report and Revision 3 to the Seabrook Station Updated Final Safety Analysis Report (UFSAR).
The 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 Atlantic's letter (Reference (b)] and updated in North Atlantic 's letter [ Reference (c)]. This report covers the period from March 16,1993 though October 25,1994. UFSAR Revision 3 incorporates approved and implemented design chages and UFSAR changes identified through October 25,1994. 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.
Eac.. "FSAR replacement page includes the revision number and a verii:al line (revision bar) in tL; left margin, adjacent to the actual change. Please note that some replacement pages have a revision nui.Joer at the top of the page but no revision bar. This indicates that text pocMon has changed as a result of text changes on previous pages and no other changes have occurred. sumniaries of the 10CFR50.59 safety evaluations for the changes incorporated in Revision 3 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 perfarmed during this reporting period that were performed for conservatism and did not meet the reporting requirements as outlined in 10CFR50.59 9502020433 950151 9j l
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United States Seclear Regulatory Commission January 31,1995 Attention: '>ocument Control Desk Page two This UFSAR submittal, specifically, Chapter 17 and Appendix 17A, addresses the reporting requirements of 10CFR50.54(a).
The signed original and ten copies of the UFSAR revision are being submitted to the Document Control Desk, Washington, D.C., along with a copy to 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 submittal, please contact Mr. Terry L. ilerpster, Director of Licensing Services at (603) 474-9521, extension 2765.
Very trul ours, e
- / 4dv 3ruce . Drawbridge Executive Directo Nuclear Production STATE OF NEW IIAMPSlilRE Rockingham, ss. January 31,1995 Then personally appeared before me, the above-named Bruce L. Drawbridge, being duly sworn, did state that he is Executive Director - Nuclear Production of the Nonh Atlantic Energy ServL.
Corporation that he is du!y authorized to execute and file the foregoing information in the name and on the behalf of North Atlantic Energy Service Corporation and that the statements therein are true to the best of his knowledge and belief.
M Susan J. Mildr, Notary Public My Commission Expires: December 22,1998 TCF:TGP/act Enclosures
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United States Nuclear Regulatory Commission January 31.1995 Attention: Document Control Desk Pege three cc: Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 ,
Mr. Albert W. De Apzio, Sr. Project Manager l Project Directorate 1-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Richard 1.aure NRC Senior Resident inspector P.O. Box 1149 Seabrook, N!! 03874 I
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Nonh Atlantic January 31,1995 ENCLOSURE 1 TO NYN-95010 Summaries of the 10CFR50.59 Safety Evaluations for the Revision 3 of the UFSAR I
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DESIGN COORDINATION REPORTS (DCRs):
Design changes documented in the following design coordination reports (DCRs) were installed 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 DCRs and their safety evaluations are provided below. i DESIGN COORDINATION REPORT (DCR) NtatBER: 86-174 TIILE: Steam Generator Blowdown System Modifications StatNtARY DEscRirTION AND Pt'RPGsE: This design change incorporated various temporary modifications to the Steam Generator Blowdown (SB) Demineralizer System into the permanent system design. These modifications included: the installation of iron filters upstream of the demineralizers; installation of a corrosion product transport box for sampling upstream of the iron filters; provisions for a final demineralizer bed rinse path directly to the discharge structure; provisions for a sample line and flush path off of the SB return header to the turbine building sump; installation of tell-tale drain valves i between the manual and pneumatic operated valves off the demineralizer bed bottoms. Additionally, this ;
design change ad'ed a particulate centrifugal separator off of the SB sump pump discharge.
SAFETY EVAEt?ATION St3tNIARY: The above design changes affected the facility as described [
on UFSAR Figure 10A-13 Sheet 2. The modifications did not alter the function of the system or affect its operation. The cbuge afTected only the non-safety related ponion of the Steam Generator Blowdown l System. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 93-027 l I
DESIGN COORDINATION REPORT (DCR) NtatBER: 87-237 TITI.E: Screen Wash System Completion ;
St31%iARY DESCRIPTION AND Pt'RPOSE: This design change provides for the construction of ;
reinforced concrete piping to provide a flow path for traveling screens wash water from the CW Pump ilouse Fish Count Pit to the intake Transition Structure and replaces temporary sump pumps and piping which were provided under a temporary modification. The new reinforced concrete piping gravity drain ;
is routed underground between the CW Pump House Fish Count Pit and the intake Transition Structure. i SArETY EVA1.tfATION St31%tARY: The DCR mr.de changes in the facility as described UFSAR Figures 10.4-3 Sheet 2. The new piping will direct screen wash water taken from the Service Water and Circulating Water Pump 11ouse into the intake Transition Structure after debris has been removed in the Fish Count Pit. The CW screen-wash system is not a safety-related system and will not impair the safety functicm of any safety system. The addition of passive underground piping for the i Screen Wash System win have no impact on equipment imponant to safety. The safety evaluation determined that this change did not involve an unreviewed safety question. t I
UFCR 90-086 l
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DESIGN COORDINATION REPORT (DCR) NUMBER: 88-152 l l
TITI.E: Nitrogen Gas (NG) Piping and Check Valve Modifications ,
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SUMMARY
DESCRIPllON AND PURPOSE: This design change made piping and valve modifications l to the N2/II2 gas feed line to the Chemical Volume Control Tank (VCT) for the purpose of reducing the incidence of sticking check valves. Operating history had shown that the original configuration allowed j for boron crystal precipitation on the valve internals. The design change incorporated the use of rise / loop seals to provide a wet environment for the valves associated with borated water and a dry environment for the valves associated with the N2 /II 2 gas supply. ;
SAFE 1T EVAL.UATION
SUMMARY
- The DCR made changes to the facility as described in the l UFSAR. Although the UFSAR text does not go into the level of detail associated with the hardware !
changes mede by this DCR, UFSAR Figures 9.3-14 and 11.31 depict the original piping design and therefore require revision to reflect the modifications. It was also concluded that the modifications did !
not impact the intended design function of the N2 /II2 Systems and their interface with the VCT. The safety ,
evaluation determined that the DCR did not involve an unreviewed safety question. .
UFCR 89-050 l DESIGN COORDINATION REPORT (DCR) NUMBER: 88-197 i TITI.E: Gland Steam Exhauster (GSE) Radionuclide Sampling
SUMMARY
DESCm' TION AND PURPOSE: This design change provided modifications in the GSE !
sample lines to facilitate continuous monitoring of radionuclides in the gland steam exhauster vent. This !
change added a sample pump to provide the necessary suction capability to draw a sample through the ;
cartridge filter. In addition, the previous specified FI has been replaced with a FI having a smaller i pressure drop to facilitate sample flow. The addition of the sample pump per this DCR affects UFSAR !
Figure 10.4.2. This DCR makes no change to the text of the FSAR Sections 10.4.3,11.1,11.3.3, or Table l 11.5-3. The operation of the sample pump and sample probe heaters are interlocked with GSE fans !
(which are controlled from the main control room). Loss of sample flow is alarmed in the control room. !
Ilowever, this level of detail is not discussed in FSAR Section 13.5. This DCR does not involve tests or I experiments not described in the FSAR.
SAFETY EVAL.UATION
SUMMARY
- The DCR made changes in the facility as descrihd in'the UFSAR Figure 10.4-2. The components of the gland steam exhauster radionuclide sampling system are located in the Turbine Building and are non-seismic and non-safety related. The operation of the sampling l pump ad probe heaters are slaved to the GSE fans and therefore, do not affect their mode of operation.
The modification implemented by this DCR does not atTect the accident analysis in FSAR Chapter 15 or function of amy safety related equipment. The margin of safety as defined on the basis of Technical Specificatiem 3.3.3.10 is not compromised by this change. The safety evaluation determined that this change did not involve an unreviewed safety question.
i UFCR 89-001 t
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DESIGN COORDINATION REPORT (DCR) Nt3ttiEn: 89-044 TITI.E: ASDV's Actuator Modification St31stAny DESCRIPTION AND Pl'RPOSE: This design change incorporated modifications te the Atmospheric Steam Dump Valves (ASDV) and the associated valve actuators. The valve and actuator modifications were made in response to NRC Information Notice 89-038. Infom.ation Notice 89-038 identified the failure of valves to open due to excessis e pressure above the valve plug as the result of seat leakage. These concerns were reviewed by engineering and the valve manufacturer, Control Components Inc. and modifications were prescribed. The modifications resulted in an increased closure time from 50 to 70 seconds, and a decrease in opening time from 30 to 15 seconds.
SwrTY EVAt t!ATION SL31stARY: The 10CFR50.59 evalua' ion for this design change concluded that this represented a change to the facility as described in the UFSAR due to the resultant change in valve closure time from 50 to 70 seconds. This change required revision of UFSAR Section 10.3.2.4 and Table 6.2-83, Sh. I and 2 of 13. The safety evaluation determined that the increased closure time for the ASDV's did not involve an unreviewed safety question.
UFCR 94-036 DESIGN COORDINATION REPORT (DCR) Nt3tnEn: 90-017 TITI.E: Fire Detection System Upgrade Si31st sny DESCRIPTION AND Pt'HPOSE: This design change upgraded a portion of tne non nuclear safety fire detection system. The DCR provided a digital addressable fire detection system which eliminated the need to perform field calibration of some 800 remote fire detectors. The change allows for considerable radiation exposure savings as well as improved worker safety by precluding extensive time consuming field work.
SAI ETY EVAL.t!ATION St31.stARY: The DCR made changes to the facility as described in the UFSAR. specifically, Chapters 9 and 16. The safety evaluation concluded that the new design enhanced the reliability of the fire detection system and improved the alarm information presentation to operators.
The safety evaluation determined that the DCR did not involve an unreviewed safety question.
UFCR 92-81 DESIGN COOllDINATION RI: PORT (DCR) Nt3tnEn: 90-029 TITI.1:: DJsel Generator Fuel Oil Vents St3t%IARY DESCRIPilON AND Pt'nPOsE: This design change replaced strainer vent plugs with capped vent valves on diesel generator fuel oil strainers DG-S-5A,B and DG-S-6A,B. It also provided ,
vent and drain valves for the diesel generator lube oil filters DG-F 23A,B. This modification provided 1 a controlled means of venting the strainers and filters, eliminating the pctential for oil sprays that could l be ? rsonnel hazard and a housekeeping problem. This design change also replaced bleed valves on the '
di" cenerator starting air receiver tanks with standard valves to serve as test connections. l l
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l SArETY EVAL,t!ATION St31%IARY: The above change required a revision to UFSAR Figures 9.5-10 and 9.5-13, thus changing the facility as described in the UFS AR. The safety evaluation concluded 1 that this change did not involve an unreviewed safety question. I 1
UFCR 93-056 DESIGN COORDINATION REPORT (DCR) Ntaturn: 90-039 T m.E: Liquid Process Radiation Monitor Filter Modifications St3t%tARY DESCRIPTION AND Pt'nPOsE: The isolation valves associated with the in-line filters on the Steam Generator Blo vdown (SB) radiation monitor sample lines have experienced excessive leakage.
It was determined that the excessive leakage was due to wear caused by the presence of abrasive particulate in the system. This modification replaces these valves with severe service globe valves.
SAFETY EVAL.l!ATION St31%tARY: This modification represented a change to the facility as described in the UFSAR. Figures 9.3-13 and 10.4-11 were revised to reflect the change in the type of valves. The safety evaluation concluded that this modification did not involve an unreviewed safety question.
UFCR 93-036 DESIGN COORDINATION REPORT (DCR) Ntaintn: 90-041 TITI.E: Steam Generator Level Channels Filter Card Addition and Setpoint Program Deletion Stat %tARY DEsenirnON AND Pt'HPGsE: This design change installed filter cards in the circuitry for narrow range steam generator instrumentation to provide a 1.0 second time constant. Westinghouse letter NAll-90-3612, dated 05/10/90, identified a potential multiple loop feedwater malfunction event due to failure of the steam generator level setpoint controller program circuitry. The DCR also modified the setpoint 4:ontroller program circuitry thus eliminating this source of potential multiple loop feedwater malfunction.
SAFETY EYAll'ntoN Sl3t%tARY: The DCR made changes in the facility as described in the UFSAR Section 7.7.1.7, Figures 7.2-13, Sheets 1 & 2. The safety evaluation for this DCR documented that this change would eliminate the consequences of a single failure of the steam generator level setpoint controller from afTecting feedwater flow to all four steam generators. Steam generator levels will continue to be controlled at 50% of the narrow range measurement and there is no change to the Technical Specifications. The safety evaluat;on determined that this change did not involve an unreviewed safety question.
UFCR 91-054
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DESIGN COORotNATION REPORT (DCR) NtalBER: 90-060 Trrt.E: llot Water Systems Modifications l
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St31%1ARY DESCRIPTION AND Pt'RrosE: This design change involved the replacement and setpomt ,
reset for safety relief valves on the hot water systems located throughout the plant. These changes were '
implemented to resolve glycol leakage problems from the valves onto building floors which migrate into l the floor drain system. In conjunction with these changes, the air pressure to some of the expansion tanks has been limited by the installation or adjustment of pressure reducing valves in the service air supply lines to improve operating conditions and improved safety. In conjunction with the review of the hot :
water system, thermal overpressure protection has been incorporated onto the heaters.
SAIETY EVAL t!ATION Sl31%tARY: Fhe DCR made changes in the facility as described in the UFSAR Figures 9.3-9, Sheet 3 and 9.418. The 110t Water and Service Air systems are classified as non-safety related as described in Chapters 9.3.1 and applicable sections of Chapter 9.4 of the UFSAR. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 92-030 DESIGN COORDINATION REPORT (DCR) NtatHER: 91-013 TITEE: RCDT Level Transmitter Replacement l
Stat %tARY DESCRIPriON AND PI'RPGsE: This design change reconfigured the Reactor Coolant Drain Tank (RCDT) level transmitter reference leg piping to prevent undesirable filling with water. The l normally dry reference leg; was susceptible to water accumulation from condensation and RCDT level i fluctuations occurring during normal operation. With a wet reference leg, errors were introduced to indicated tank level which resulted in improper RCDT pump operation. The DCR also replaced the original level transmitter manufactured by Foxboro with one manufactured by Rosemount. Rosemount transmitters have outperformed Foxboro transmitters in similar applications. ;
SAFETY EVAEt!ATION St31%IARY: The DCR made changes to the facility as described in the ;
UFSAR. Although the UFSAR text does not go into the level of detail associated with the changes made by this DCR, UFS AR Figure 9.3-17 does, depict the RCDT level transmitter. Since the replacement level r transmitter incorporates diaphragm seals and filled capillaries which were not part of the original Foxboro transmitter design and therefore not snown in this Figure, this DCR required that Figure 9.3-17 be changed ;
to reflect the new transmitter. The safety evaluation concluded that the design change affected only r non-safety related components and that the change would enhance system performance without compromising nuclear safety. The safety evaluation determined that the DCR did not involve an unreviewed safety question.
UFCR 92-007 P
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- a DESIGN COORDINATION REPORT (DCR) NtatIIER: 91-023 TITI E: Service Water (SW) System Tower Actuation (TA) Logic - Loop During Normal CT Operation Stat %tARY DESCRIPTION AND PL'RPOSE: This DCR provides the control circuitry modi 0 cations necessary to automatically actuate a TA signal if a loss of offsite power occurs following a manual transfer of plant heat loads to the SW Cooling Tower.
SAFETY EVAL.liATION St31% ARY: The DCR made changes in the facility as described in the UFSAR Sections 7.4.5.5,9.2.5.5 and Appendix R. If a loss of offsite power occurs after plant heat loads have been manually transferred to the SW Cooling Tower an automatic TA signal will be generated and the Cooling Tower pumps will be powered by the EDGs. No changes were made which would prevent the SW system from performing its safety related function. The safety evaluation determined that this change did not involve an unreviewed safety questior.
UFCR 93-062 DESIGN COORDINATION REPORT (DCR) Nt3tiiER: 91-031 TITI.E: Instrument Air Loop Isolation St3tStARY DI:SCRIPTION AND Pt'RPGsE: This DCR implemented several modi 0 cations to enhance plant reliability with respect to instrument air. Speci0cally the atrument air loops and associated receivers were separated, back up air compressor tie-in was relocated to the inlet of receiver"A" and the internals for check valves SA-Vil75/1176 were removed to allow the Centac compressor to feed all four receivers.
SAFETY EVAL.lfATION S13tStARY: The DCR made changes in the facility as described in the UFSAR Figure 9.3-8 and the Appendix R Report. This DCR increases the reliability of the instrument air system by separating the "A" & "B" instrument air loops at the receivers thereby providing redundancy.
The likelihood that instrument air will be unavailable for post accident recovery is reduced. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 91-079 DnsicN COORDINATION Rl: PORT (DCR) Ntatt ER: 91-045 TITI.E: Condenser Air in-Leakage Flow Monitor Installation St31%tARY DiscRIPTION AND Pt RPGsE: In order to determine the amount of condenser air in-leakage, an accurate measurement of the amount of non-condensibles flowing to the air removal pumps is required. This design change installs a new flow monitor in the common air removal line to the three air removal pumps. The Dow monitor is speci0cally designed for this application and contains both static pressure and temperature compensation.
SA ETY EVAL.liAllON St3t\tM(Y: The DCR made changes to the facility as described in the l UFSAR Section 10.4.2.5. This Section was revised to identify that the new monitors output signal is read l
8 4 locally and on the Main Plant Computer. In addition, UFSAR Figure 10.4-1 was revised to identify the new monitor tag identification number. The safety evaluation concluded that the Air Removal (AR) syrtem is non-safety related system. Failure of the AR system would cause a turbine trip which is accounted for in the safety analysis described in UFSAR Chapter 15.2.5. The safety evaluation determined that the DCR did not involve an unrenewed safety question.
UFSAR 93-006 DESIGN COORDINATION REPORT (DCR) Nt'% nER: 91-060 Trrt.E: Containment Instrument Air Dewpoint Monitors St 31%3ARY DESCRIPTION AND PrRrost: UFSAR Figure 3.11-1 states that the minimum containment
- emperature dudng refueling is 74 degrees F and Section 9.3.1.5 states that moisture instrumentation is used to monitor the performance of the instrument air dryers and that any malfunction of the dryers is alarmed at the MCB. A setpoint of 56 degrees F was setected for the high dewpoint alann setting based on 18 degrees below the expected minimum containment temperature of 74 degrees F. Existing relative humidity switches I-IA-MSil-8027 & 8028 w:re constantly in alarm. Instrument air dryers, I-IA-D-2A
& 2B were unable to maintain a relative humidity of less than the 4% setpoint. As a result of both moisture switches being constantly in alann, a malfunction or degradation of either dryer could occur and go undetected. Replacement of the existing relative humidity switches with dewpoint indicating transmitters with an analog output signal to the main plant computer resolved this concern. A dewpoint alarm will occur on the VAS if the dewpoint exceeds 56 degrees F. Other minor enhancements to isolation valves and pressure regulation was accomplished under this DCR.
SAFETY EVAI.UATION StalNIARY: The DCR made changes in the facility as described in UFSAR Section 9.3.1.1, Tables 6.2-87 and Figure 9.3-5. The replacement of containment instrument air system dewpoint instrumentation, replacement of isolation valves to service air pressure indicators and addition of a pressure regulator on the service air line to the containment compressor's unloader valves all pertain to changes made on non-safety related systems. These change are provided to enhance primary plant reliability by providing clean dry air to safety related and important to safety plant components. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 93-049 DEsicN COORDINATION REPORT (DCR) Nt31riER: 92-013 TITI.E: Valve Position Indication RC-FV-2881 St3 NtARY DI.scRIPTION AND Pt'RPGsE: This DCR rewires the valve position indication for the Reactor llead Vent isolation Valve, RC-FV-2881. This rework provided indication of" valve full closed" from the valve closed limit switch. Previously this indication was developed from the valve open limit switch via an auxiliary relay. Modification of this circuitry allowed the stroke time of the valve to be measured as required by the IST program.
SriviY EVAI.tfATION St31%lARY: The DCR made changes in the facility as described in the Appendix R Report. Modification of the valve position indication only afTects the closure indication and does not change the operation of the valve. Position indication on this valve provides no control ftmetions l
and the valve closed position will provide an accurate indication of valve position on the MCB. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 92-032 DESIGN COORinNATION REPORT (DCR) NtrMBER: 92-014 TITLE: CAP Valve Modifications S13tstARY DESCRIPTION AND Pt'RPOSE: This design change allowed fv the installation of blind flanges in place of containment air purge (CAP) valves CAP-VI and CAP-V4 during plant Modes 1,2, '
- 3. and 4. The CAP valves had proved to be troublesome when trying to meet containment isolation leakage criteria. The blind flanges are able to be tested to ensure the integrity of the CAP penetrations.
Surly EVAL.itATION StatstARY: The text, figures, and tables affected by the DCR are Sections 3.8.2.1, 6.2.4.2, 6.2.6.2, 9.4.5.2, Tables 3.2-2, 3.8-13, 6.2-83, 16.3-3, 16.3-11, and Figures 3.8-26,6.2-91, anal 9.4-14. The safety evaluation concluded that the blind flanges provided a better means to maintain ceintainment penetration integri'y than the original valves. Further, the testable feature of the flanges allowed for early detection of any seal degradation. The safety evaluation determined that the DCR did not involve an unreviewed safety question.
UFCR 93-013 DESIGN COORDINATION REPORT (DCR) NtainER: 92-026 TITI.E: Auxiliary Air Conditioning For Turbine Building I&C Shop Complex SrsistARY DESCRIPTION AND Pt'RPGst: This DCR provided four packaged self-contained air conditioning units for the I&C Maintenance Workshop, I&C Maintenance Office and the I&C Maintenance Utility Room, which are located at Elevation 75' of the Turbine Hall.
SAFETY EVAtt!ATION StmlARY: The modifications afTected UFSAR Section 9.4.14, Table 9.4-19 and Figure 9.4-24 Sheet 3. The 7urbine Building Heating and Ventilating and Air Conditioning Systems is described in Section 9.4.1.E.3 of the UFSAR. The addition of small supplementary air conditioning units does not introduce ars unreviewed safety question.
UFCR.92-050 DESIGN COORDINATION REPORT (DCR) Nt3tHER: 92-035 TITt.E: 345 Kv Termination Yard Lightning Protection SrstsARY DESCRIPTION AND Pt'RPGsE: This DCR removed the static wire across the termination yard and the pole that supports the static wire, and adds two new poles with air terminal points in the yard at locations which provide adequate lightning protection. The new design provides the same degree of protection as the previous lightning protection in the termination yard; however, it eliminates the concern of potential failure of the static wire affecting all three lines and causing loss of offsite power. With this I
new design, a pole failure could potentially affect one line only thus ensuring offsite power availability.
This modification is considered non-safety related and was accomplished within the termination yard.
SAFE 1Y EVAEUATION St31stARY: The modifications afrected UFS AR Section 8.3.1.1.k. The ,
new lightning protection design provides protection similar to the existing design m the termination yard while at the same time eliminates the concern ofloss of ofTsite power caused by failure of a component of the lightning protection. The new design adds poies with air terminal points which provide adequate lightning protection. In the new design, a pole failure may cause one line to fail but will not cause a total ,
loss of offsite power. The operation or misoperation of the lightning protection does not degrade the perfonnance, change the failure modes or alter the function of any plant equipment important to safety.
The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 92-049 DEstGN COORDINATION REPORT (DCR) NtainEn: 92-058 TITEE: Containment Tool Crib SUststARY DFsCRIPTION AND PI'RPOSE: This design change installed a pennanent galvanized wire mesh tool crib inside containment to provide for efficiency in dispensing tools during plant outages.
SAFETY EVAL,UATION St'ststARY: The DCR made changes to the facility as dscribed in the UFSAR. Although the text of the UFSAR does not include any descriptis of a containment toel crib in the General Plant Description Sections 3.8.1 and 3.8.2 or the Containment Systems Section 6.2, the galvanized wire used in this DCR adds to the containment inventory of zine and therefore, the values of zine inventory within containment described in UFSAR Section 6.2.5.3 and Table 6.2-88 are affected and changes are required. The safety evaluation concluded that the increased inventory of zine inside containment was insignificant and would not affect the volume of hydrogen formation postulated during accident conditions. The safety evaluation determined that the DCR did not involve an unreviewed safety question.
UFCR 93-024 DEslGN COORDINATION REPORT (DCR) Nt'sIBER: 93-003 TiTEE: Service Water Diesel Generator Piping Replacement St'ststARY DESCRIPTION AND Pt'nPOst: This DCR involved the replacement of cement lined Service Water (SW) piping associated with the Diesel Generator with plastical PVC lined carbon steel piping spool. Also associated with this DCR is the modification and removal of certain hangers supporting SW piping and relocation of flow detectors.
SAFi:TY EVAll!ATION St sistARY: The modifications afTected UFSAR Section 9.2.1.3 and Figure 9.2-2 sheet 2. The SW piping provides the safety related function of transferring heat from the Diesel Generator cooling Water System to the SW system. The accident analysis concerning SW in the UFSAR is the development of a through wall crack and /or break. The replacement of the cement lined piping with plasticol PVC lined carbon steel spools is intended to reduce the development of such through wall defects. The removal and modification of hangers was determined to be acceptable based on 1
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calculations C-S-1-45285,45286 and 45287. The relocation of the flow element to a pipe location with 1 a more symmetrical flow profile will improve detector performance and provide a more reliable signal.
The safety evaluation determined that this change did not involve an unreviewed safety question.
1 UFCR 93-035 DESIGN COORDINATION REPORT (DCR) NtainER: 93-011 ;
TITEE: Jib Crane at Personnel Hatch SioDtARY DESCRIPTION AND Pl'RPOSE: The design change added a small 1% ton jib crane to the containment building to facilitate material handling through the personnel hatch during plant outages.
Previously the polar crane had been used to handle heavy material loads through the personnel hatch.
During outages, tM availability of the polar crane is limited and the use of the polar crane for material passing through the personnel hatch is not an efficient use of that crane. The improved material handling capability of the jib crane will result in lower radiation exposure to plant personnel over the life of the plant.
SAFETY EVAEt!ATION Sl3151ARY: The DCR made changes to the facility as described in UFSAR Figure 1.2-4. The safety evaluation concluded that the addition of the jib crane represents an enhancement that will streamline handling of outage material and thereby reduce personnel exposure. The installation of the jib crane does not impact the safety function of other components located inside containment. The safety evaluation determined that the DCR does not involve an unreviewed safety question.
UFCR 94-012 DESIGN COORDINATION REPORT (DCR) NtainER: 93-016 TITEE: Replacement of TB Service Air Compressors Sl'SDIARY DESCRIPTION AND PURPOSE: This design change replaced the three Turbine Building Service Air water cooled reciprocating piston type air compressors with two air cooled rotary screw compressors. The purpose of the design change was to improve the reliability of the Station Air system which had experienced performance problems.
SAFlav EVAEUATION St3 DIARY: The DCR made changes to the facility as described in UFS AR Sections 1.2.8.5, 9.3.1.2, 9.3.1.5, 9.5.3,10.4.10.2; Tables 8.3-1, 8.3-2,16.3-10 and Figures 8.3-1, 8.3-11, 8.3-14,8.3-54,9.3-8, and 10.4-14. The safety evaluation concluded that the changes made by this DCR would improve overall system reliability by providing more reliable compressors, and, by eliminating previous required operator actions associated with the reciproca. ting compressors during a loss of ofTsite power event. The safety evaluation detennined that the DCl. did not involve an unreviewed safety question.
UFCR 93-059
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DESIGN COORDINATION REPORT (DCR) NUhlBER: 93-021 1
TITLE: Fire Detection - Turbine Building Relay Room ,
i SU%1%1ARY DESCRIPTION AND Pt'RPOSE: This design change added fire detection instrumentation I for the Turbine Building Relay Room. No fire detection had been provided previously for this location.
An Individual Plant Examination of Extemal Events (IPEEE) and Probabilistic Risk Assessment (PRA) ;
indicated that a fire detection system was wa: ranted. Protection for this area was also recommended by i American Nuclear Insurers (ANI). l sal'ETY EVALUATION St315tARY: The safety evaluation applicability determination j established that this design change affected the facility as described in the UFSAR, Appendix A, l "Seabrook Station Fire Protection Program, Evaluation and Comparison to BTP APCSB 9.5-1." The i addition of fire detection capability in this area was determined not to involve an unreviewed safety question. ,
UFCR 93-047 !
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DESIGN COORDINATION REPORT (DCR) Ntaintm: 93-023 l l
TITLE: System Interface Modifications to Prevent Cross Contamination i
St31%IARY DESCRIPTION AND Pt'RPGsE: This DCR provided a new design for the nitrogen supply !
line to the Reactor Coolant Drain Tank (RCDT). This supply line is normally isolated at valve NG-VI 16 !
and nitrogen is only introduced when purging is required. The nitrogen supply line piping is re-routed !
such that nitrogen is brought in to the RCDT gas space. This re-route includes the addition of a new ball valve for isolation and a check valve to provide reverse flow protection. Old lines and NG-V116 were !
capped and abandoned in place.
sal'ETY EVALUATION St31stARY: The DCR made changes in the facility as described in UFSAR Figures 10.4-13 Sheet 1,11.3-4, 9.3-17 and 11.3-2 Sheet 1. The re-routing of the Reactor .
Coolant Drain Tank (RCDT) nitrogen supply line does not alter the function of the Nitrogen Gas System.
- The addition of a check valve in the nitrogen supply line enhances the systems' ability to preclude reverse flow but does not inhibit the nitrogen gas supply during RCDT purging. NG system functionality is maintained. This modification did not affect any safety related systems. The safety evaluation determined that this change did not involve an unreviewed safety question. '
l UFCR 93-038 !
DESIGN COORDINATION REPORT (DCR) N13tBER: 93-029 TITI 0: Motor Operated Valve Changes i i
StatstARY DESCRIPTION AND Pt RPOSE: This DCR modified valves 1-CS- V460, V461, V475, LCVil2D, and LCV112E, to meet the recommendations of Generic Letter 89-10 " Safety-Related Motor-Operated Valve Testing and Surveillance" These changes will increase the actuator output capability while reducing the stroke time. Changes to the electrical protection in motor control centers were implemented to support these changes. UFSAR Section 8.3.1.1.i was revised to acknowledge that l
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h exceptions to the 80% voltage and 95% horsepower criteria for selection of safety related motors are !
evaluated on a case by case basis.
SAFETY EVAElfATION Sl31%1ARY: The DCR made changes in the facility as described in the UFSAR Section 8.3.1.1, Tables 8.3-1, 8.3-2, & 16.3-9 and Figures 8.3-17, 8.3-23. The probability and consequences of a malfunction of equipment imponant to safety will not be increased as a result of this DCR. Modifying / replacing the operators to increase the motor-operator output torque provides additional assurance that the MOVs will function as designed. These changes do not affect the norma 1' function or !
design function of the MOVs. Testing the valves to the provided criteria will assure that the MOVs are i capable of functioning under all design basis conditions. The safety evaluation determined that this change !
did not involve an unreviewed safety question. .
UFCR 93-041 i
DESIGN QORolNATION REPORT (DCR) Nt3tnER: 93-040 l l
fiTEE: Associated Circuits inside Containment ,
St31%IARY DESCRIPTION AND Pl*RPOSE: His design change modined some of the power distribution network associated with circuits inside containment. Power panel ED-PP-8A was removed .
from containment and a new power panel, ED-PP-8J, was added in the "A" Train Electrical Tunnel. In l addition, one circuit supplied by Panel ED-PP-8B located inside containment, was removed from existing l cable tray and routed in conduit to separate it from Class IE circuits. The purpose of this DCR was to j resolve NRC Electrical Distribution System Functional Inspection items that identified potential challenges to IE circuits that might be caused by a post accident harsh environment affect on non-lE circuit breakers. ;
SAFETY EYAEt'ATION St31%1ARY: The DCR made changes to the facility as described Appendix "R" Section 3.2, Tables MCR 3.1.3.17-13, 3.1.3.16-4, 3.1.3-17-27 and Figure 8.3-53 Sheet 1 of the UFSAR. The safety evaluation concluded that the modification did not afTect the safety function of any system or component and that the reliability of the Electrical Distribution System was maintained. i The safety evaluation determined that the DCR did not involve an unreviewed safety question.
UFCR 93-065 ;
3 DESIGN COORnINATION REPORT (DCR) Nt3fBER: 93-044 ,
TITI.E: DAll Supply and Exhaust Fan Logic Revision !
Stat %tARY DiscRIPTION AND Pl'RPOSE: This design change allows for independent operation of l the supply and exhaust ventilation fans associated with the emergency diesel generators rooms. The ,
I char.ge was made in response to an Engineering Evaluation (93-21) that specified compensatory ventilation plans that could be taken when safety related 11VAC systems and components are out of service. EE93-21 determined that the diesel rooms temperatures could be maintained below limiting values necessary for equipment qualification under cenain outside ambient temperature conditions with only partial ventilation available. The supply fans or exhaust fans could provide that partial ventilation but the original control circuit design did not allow for independent operation of these fans.
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l SAFETY EVALUATION SU31%IARY: The DCR made changes to the facility as described in Appendix "R" Tables MCR 3.1.3-11-1, 2, and 3 as well as UFSAR Figures 9.4-16, 8.3-20, 8.3-25, 8.3-34, ;
and 8.3-35. The modification allows for an alternate means of cooling the diesel generator rooms with !
certain HVAC equipment out of service. The change represents an enhancement to one of the support systems for the emergency power system and therefore provides improved operational safety. The safety evaluation determined that the DCR did not involve an unreviewed safety question.
UFCR 94-013 ,
i DESIGN COORDINATION REPORT (DCR) NUS HER: 93-045 3 TITLE: Corrosion Product Samplers Installation SU3t%IARY DESCRIPTION AND PURPOSE: This DCR implemented changes to adequately monitor the cffectiveness of secondary chemistry additives and verify compliance with EPRI Guidelines for the system lr Iron and Copper Transports. This design change installed four new Corrosion Product Transport (CPT)
Samplers near the Turbine Building. These CPT Samplers are dual channel NWT Model 200-BI, !
m.nufactured by NWT Manufacturing Corporation. These CPT Samplers sample the Main Steam, the i Condensate Pump Discharge, the Heater Drains and the Feedwater Heater 26 outlet sample points. .
SAFETY EVALUATION SU%t%tARY: The DCR made changes in the facility as described in the !
UFSAR. The modifications affected UFSAR Figure 1.2-38. These CPT Samplers do not provide any i safety related functions. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 93-050 DESIGN COORDINATION REPORT (DCR) NU3tHER: 94-013
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TITLE: RCP No. I Seal Leakoff Transmitter Replacement SU%i%tARY DESCRIPTION AND Pt'RPOSE: This design change replaced seal leak-off transmitters, l l-CS FT-158,159,160, and 161, for the Reactor Coolant Pump (RCP) No.1 Seal Leakoff lines. The replacement transmitters provide a higher range for monitoring seal leakage. The new instrument range
.is 0-10 gpm.and the Main Control Board recorders and Main Plant Computer analog points have also been appropriately rescaled.
SAFETY EYALUATION SU3t%1ARY: The design change does not alter the descriptions of the RCP operations or the seal leakofT monitoring provisions as currently described in the UFSAR. Because the new instrument enclosures are constructed of aluminum, this change required the addition of the new quantity of aluminum to UFSAR Table 6.2-87, Containment Building Aluminum inventory. Evaluation of the additional inventory of aluminum concluded that this did not increase the probability or consequences of any accident as evaluated in the UFSAR. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-028 DESIGN COORDINA110N REPORT (DCR) Nt'stnEn: 94-014 TITLE: Remote Indication For RCP # 2 Seal Leakoff Flow St'ststany DESCRIPTION AND Pt nPOsE: This DCR replaces the existing Reactor Coolant Pump (RCP) number 2 seal leak off local flow indicating switches with transmitters. The transmitters provide input to the MPCS that can be read on demand in the control room. The transmitters have the same span of 0.0 to 1.5 gpm as the existing FIS's. These transmitters will provide the necessary #2 seal leak-off indication to comply with the recommendations of Westinghouse Technical Bulletin NSD-TB-93-01-RO.
SAI'ETY EVAEllATION St:ststARY: The DCR made changes in the facility as described in UFSAR Section 5.2, Table 6.2-87 and Figures 5.13 Sheets 1,2,3 and 4, and 5.2-2 Sheet 1. Replacing the existing flow indicating switches with transmitters with the same span, that provide indication in the control room does not change the function, scope or intent of the RCP #2 seal flow. Providing RCP #2 seal leak oft flow indication in the main control room is an aide to the operator in evaluating abnormal RCP seal leak off flow conditions. The flow indication is non-safety related and does not interact with any safety related control systems. The transmitter power supplies do not add any new class IE/non IE interfaces. The additional load on the diesel generator has been reviewed and found to be within the total load design rating. The effects of failure of a transmitter is the same as the original design. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 94-020 DESIGN COORDINATION REPORT (DCR) Nt stnEn: 94-016 TITLE: Class IFJNon-Class lE and Train Interactions St'ststAny DESCRIPTION AND Pl'RPGsE: This design change addressed hardware and documentation changes for various Class IE/non-Class 1E and train interaction concerns that were not previously identified by the methodology in design calculations. Specific changes addressed by this design change ;
included hardware and documentation changes to correct inadequate separation for lighting panel circuits. .
Documentation and design changes as specified in Engineering Evaluation Number 94-19 and the Train l Interaction and Protective Devices with Associated Circuit Requirements (PDWACR) review were !
incorporated in this design change. l SAIETY EVAEl'ATION St sistAny: This design change revised UFSAR Table 7.5-1, Sheet 25, j Accident Monitoring Instrumentation List to clarify voltage transducer identification numbers and display ;
identification for the 480-V Emergency Bus Availability indication. Table 16.3-10 was revised, deleting two breakers that analysis showed would not experience simultaneous failure of the associated Class lE equipment. Appendix R, Table MCR 3.1.3.4-9, 3.1.3.4-10, 3.1.3.5-4 and 3.1.3.6-14, Safe Shutdown Equipment List was revised to reflect changes in the location reference drawings which were editorial in nature. The 10CFR50.59 evaluation for this design change concluded that this did not involve an unreviewed safety question.
UFCR 94-034 p
l MINOR MODIFICATIONS (MMODs) ;
i The following minor modifications (MMODs) were installed during the period covered by this -l 10CFR50.59 Report. A safety evaluation was performed for each MMOD. Each safety evaluation i concluded that the MMOD did not involve an unreviewed safety question. Summaries of these MMODs and their safety evaluations are provided below.
MINOR MODIFICATION (MMOD) Nt3fBER: 89-506 i
TrrLE: Grab Sampling Provisions for Containment Air St3 DIARY DESCRIPlION AND Pl:RPOSE: Containment air grab sampling is performed by taking an e air sample from Rad Monitor Skid RM-60. This sampling takes approximately 4-hours to perform and i vents the discharge from the sample pump to the immediate area. The sampling pump hookup results in j a flow diversion that reduces the specified flow for Rad Monitor Skid 60 and causes a low flow condition. j The Rad Monitors performance is effected and the plant enters the associated Technical Specification Action Statement. To correct this problem, MMOD 89-506 was initiated to provide a new grab sample ;
connection between RM-SKD-60 and the Containment isolation valves. The installation will allow a sample to be taken from the inlet line and discharge the sample back to the sample return line. The new ,
separate sample path will improve ALARA and eliminate the need to enter a Technical Specification ,
Action Statement.
SAFETY EYAtt1ATION St31%IARY: The MMOD made changes in the facility as described in UFSAR Figure 9.4-6. Addition of grab sampling provisions only enhanced the operation of rad- !
monitoring skid without altering its functionality. The safety evaluation for this modification concluded !
that it did not involve an unreviewed safety question. !
UFCR 90-006 f MINOR MODIFICATION (MMOD) Nt31BER: 89-610 f
TrrLE: NIS Power Range Reactor Trip Setpoint Analysis S13 DIARY DESCRIPTION ASD PL RPOSE: This design change revised the Westinghouse Protection l System Setpoint Study to include the instrument uncertainties c f the Nuclear Instrumentation System (NIS) :
power range front panel meter in the setpoint analysis for the high and low power range reactor trips. The l revision was necessary because the original study assumed &at the NIS rack calibrations were performed i using measurement and test equipment (M&TE). The daily calorimetric adjustment is performed using l the front panel meter which does not have the precision of typical M&TE.
SAFETY EVAL 11ATION St31%IARY: The MMOD made changes to the facility as described in UFSAR Table 7.2-3. It was also concluded that the modification required a change to the Technical Specifications (Table 2.2-1). The Technical Specification change has been reviewed and approved by the NRC. The safety evaluation determined that the modification did not involve any equipment changes and
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that the inclusion of the added uncertainty of the front panel meter did not affect the safety analysis value
- of the power range neutron flux reactor trip setpoint. The safety evaluation also detennined that the change did not involve an unreviewed safety question.
UFCR 89-085 l l
MINOR MODIFICATION (MMOD) Nt!MBER: 90-616 TITLE: Steam Generator Blowdown Modifications St3tMARY DESCRIPTION AND PL'RPOSE: This MMOD initiated three minor changes to the Steam !
Generator Blowdown (SB) System. The three changes: 1) relocated a flow element ( blowdown discharge j to the transition structure) above its transmitter thus allowing the sensing lines to remain filled and vented !
when the flow path is not in use,2) relocation of the high side connections to the inlet lines for pressure differential switches across steam generator blowdown demineralizers to eliminate the high DP alarms -
when the demineralizer was valved out of the flow path and,3) the installation of a snubber in the !
instrument sensing line to a control valve controller which maintains a 5 psig back pressure to prevent flashing in the recovered blowdown retum line. ;
i SAFETV EVAll!ATION Sl3tMARY: The MMOD made changes in the facility as described in !
UFSAR Figures 9.3-2 Sheet 2,10.4-6 Sheet 2,10.4-7 Sheet 1, and 10.4-8 Sheet 1. The proposed changes i did not affect the function or the ability of the components to perform their function. The intent of the i changes were to enhance performance by eliminating the need for operator / technician assistance which l is now required for the components to perform as required. No change in UFSAR text is required, however changes to UFSAR Figures 10.4-6 Sheet 2,10.4-7 Sheet 1,10.4-8 Sheet I and 9.3-2 Sheet 2 was l
required. The changes enhance the component's reliability and performance. The changes do not affect .
the components functions. A safety evaluation determined that this modification does not involve an unreviewed safety question.
UFCR 90-071 {
l MINOR MODIFICATION (MMOD) Nt'MBER: 90-620 :
TITLE: Storage of flydrogen Gas in the Turbine Building i S13tMARY DFSCRIPTION AND Pt RPGsE: MMOD 90-0620 provided a storage rack so that additional [
hydrogen may be stored in the Turbine Building. This hydrogen is used for Turbine generator cooling l and is required as back up to prevent depletion if delivery is delayed. The storage is in compliance with the National Fire Protection Association Code 50A, " Storage of Gaseous flydrogen at Consumer Sites".
Fire hazard protection is also provided. :
SAFETY EVAll!ATION St3tMARY: The MMOD made changes in the facility as described in the BTP APCSD Appendix A. The storage of hydrogen gas in the Turbine Building affects Seabrook Stations, Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A, Section F.3, " Bulk Gas Storage"", The maximum amount of hydrogen stored shall be 2860 cubic feet. This is under the 3000 cubic feet permitted by NFPA 50A, Standards for Gaseous flydrogen Systems at Consumer Sites. All cylinders are attached to storage racks for stability. ,
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The evaluation and comparison to BTP APSCB 9.5-1 Appendix A, Fire Hazard Analysis for the Turbine Building , Fire Z<>ne TB F-1 A-Z (Tab 15) is unaffected. The worst case fire generated by the stored hydrogen gas will be tess severe than the design base fire for this zone. The safety evaluation determined that this modification does not involve an unreviewed safety question.
UFCR 90-063 MINOR MODIFICATION (MMOD) NtminER: 90-662 Tm.E: Type FJ Breaker Replacement StatstAnY DEsC7S clON AND PI'RPOSE: This design change deletes one of the two in-line circuit breakers that pro. Jes penetration protection and power to the pressurizer heater groups A and B. The breaker is being eliminated due to spare parts availability because the original type FJ breakers are no longer manufactured. The design change takes credit for the one remaining type FJ breaker and the associated unit substation feed breaker to satisfy the requirements of RG 1.63 for containment penetration protection.
SAFETY EVAttfATION St%tstARY: The MMOD made changes to the facility as described in UFSAR Section 8.3 and Table 16.3-8. The safety evaluation concluded that the design change does not affect the function of the pressurizer heaters and that the necessary primary protection and secondary protection for the associated containment penetrations required by RG 1.63 is still afforded by the modification. The safety evaluation determined that the change does not involve an unreviewed safety question.
UFCR 94-024 MINOR MODIFICATION (MMOD) Ntaintn: 91-507 TITI.E: Modify Equipment and Floor Drains for CS, SF, and WLD Equipment to Prevent Splashing of Radioactive Water StantARY DESCRIPTION AND Pt'nPOsE: This MMOD deletes open drain funnels from a drain manifold servicing Chemical and Volume Control (CS), Spent Fuel Pool Cooling (SF), and Waste Liquid
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1 Drain (WLD) system equipment drains and "hard pipes" the equipment drains with flexible tubing. In addition to the drain manifold discharge, the CS Letdown Heat Exchanger drain and the SF Demineralizer vent line discharge are extended into their respective floor drains with flexible tubing. These modifications will eliminate a concern with splashing of radioactive liquid onto adjacent surfaces during venting or draining operations and permit visual observation of any flow or leakage.
SAFETY EVAt.t'ATION St31stARY: The MMOD made changes in the facility as described in UFSAR Section 9.3.3.2.a.10 and Figures 9.1-2 Sheet 2,9.3-21 Sheets 1 & 2,9.3-28 and 9.3-29. The modifications to the equipment vents and drains, as depicted on these figures, do not affect the functions of the SF, WLD, and CS systems, as described in FSAR Sections 9.1.3,9.3.3, and 9.3.4 respectively.
The changes being made to the CS, SF, and WLD vents and/or drains by this MMOD are outside the operational boundaries of these systems. There are no changes required to any procedures described in
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the FSAR, nor do the changes involve any tests or experiments not described in the FSAR. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 91-061 MINOR MODiriCATION (MMOD) NUh!BER: 91-539 ,
TITI.E: EFW Pump Turbine Lube Oil Piping Modification ,
SUhl%tARY DESCRIPTION AND Pl'RPOSE: This design change added a drain valve to the EFW Pump !
Turbine lube oil system equalizer pipe and installed flanges on the lube oil cooler discharge piping. The changes were made to facilitate maintenance activities associated with changing and sampling the oil and inspecting the cooler.
san:TY EVAL,UATION SUNDIARY: The MMOD made changes to the facility as described in the UFSAR. The EFW pump turbine aux 4 y systems are not described in the UFSAR, however, the turbine lube oil system and oil cooler are s'rwn on UFS AR Figure 6.8-2. This change requires revision to this Figure. The safety evaluation detem..ned that this change does not impact the function or operation of the EFW pump turbine and that the change was intended to increase the availability of the pump. The -
safety evaluation determined that the MMOD did not involve an unreviewed safety question.
UFCR 93-012 MINOR MOnirlCATION (MMOD) NO3tHER: 91-555 TITI.E: RilR Vent and Drain Valve Replacement, Ril-V75, V76, V80, and V104 SU5ntARY DESCRIPTION AND PURPOSE: This design change replaced four %" RilR welded bonnet manually operated valves that had been leaking past their seats. Because maintenance of these valves proved to be difficult, superior performing bonnetiess valves were substituted.
1 SAFETY EVAt UATION SUhl%IARY: The MMOD made changes to the facility as described m '
the UFSAR. This change did not affect the text of the UFSAR but did affect UFSAR Figures 5.4-11 and 6.3-2. The safety evaluation determined that these valves are only used to facilitate maintenance activities when the RilR system is out of service and that since the replacement valves are built to the same design j criteria as the original valves, no new failure modes or other adverse affects on system performance are ,
introduced. The safety evaluation determined that the MMOD did not involve an unreviewed safety 1 question.
UFCR 92-004
< a MINOR MODIFICATION (MMOD) NtINIBER: 91-639 TITEE: MCB Modifications i
S131%IARY DESCRIPTION AND Pt:RPOSE: This design change implemented ergonomic improvements to certain main control board indicators and switches. Included in the modifications were changes to recorder label and status light lens engraving, changes to labeling colors, the addition of control board ;
mimics, and the rearrangement of control switches. The changes were made to resolve issues raised by staff personnel concerning potential human factor weaknesses.
SAFETY EVAEllATION SttNI%lARY: The MMOD made changes to the facility as described in UFSAR Section 6.8.5, Table 7.5.1, and Figure 10.4-7, Sheet 5. The safety evaluation concluded that the ;
changes did not affect the function or failure mode of any of the carresponding equipment. The changes ;
reduce the potential for misoperation of equipment and potential for misinterpretation of control board >
indications. The safety evaluation determined that the MMOD did not involve an unreviewed safety question. l UFCR 92-039 MINOR MODIFICATION (MMOD) NtBIBER: 91-640 TITI.E: Electrical Distribution Panel Drawing Circuit identification Clarification ;
St31%IARY DESCRIPTION AND Pl'RPOSE: This modification revises several electrical distribution panel drawings and the corresponding UFSAR figures in order to clarify circuit descriptions.
SAFETY EYA1.ttATION Stal%IARY: This modification updates the facility's electrical ;
distribution panel descriptions as presented in UFSAR Figures 8.3-32, 8.3-33, 8.3-40, and 8.3-42. The -
changes include clarification of several circuit descriptions and an editorial change to one drawing i
reference, There was no impact on actual design, function, performance or reliability of the electrical distribution systems. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-038 MINOR MODIFICATION (MMOD) Nt31BER: 91-649 ,
TITEE: Revised Valve Stroke Times for Generic Letter 89-04 St313tARY DESCRIPTION AND Pt'RPGsE: This modification changed the values of certain power operated valve stroke times in accordance with the guidelines presented in NRC Generic Letter 89-04.
The existing close proximity of the Reference Stroke Time (RST) and the Specified Limiting Value (SLV) stroke times for these valves could have led to valve inoperability conditions caused by deviations in valve stroke time measurement. Changes were made to increase the difference in the RST and the SLV values so that deviations in stroke time measurement would not result in unnecessary instances of valve inoperability. Issues of minimum valve stroke times were also resolved by this design change.
4 g sal'E1T EVAL.liATION St!Nt%1ARY: The MMOD made changes to the facility as described in UFSAR Tables 6.2-83 and 16.3-4. The safety evaluation concluded that increasing the valve stroke time ,
limits broadened the Inservice Testing (IST) acceptance criteria without compromising system performance or altering the safety-related function of each valve. Normal deviations in stroke time measurement will not result in unnecessary valve maintenance. The safety evaluation determined that the modification did not involve an unreviewed safety question. ,
UFCR 93-058 MINOR MODIFICATION (MMOD) NUhlBER: 91-650 Tin.E: RCCA Repositioning SU31stARY DESCRIPTION AND PURPOSE: A Rod Repositioning Program was implemented to permit l variable positioning of stationary shutdown and control banks to reduce localized wearing. The Rod Repositioning Program permits locating fully withdrawn rod banks between 225 and 231 steps. This program was approved by the NRC in Amendment 8 to the Operating License. Equipment at CP-8 used ;
to generate bank insertion limit alarms is readjusted by this MMOD to account for the rod position i changes. The Seabrook Cycle 2 Reload Safety Evaluation indicates control bank tip to tip distances between i15 and i17 steps are acceptable. Bank overlap switch settings required for these tip to tip relationships have been provided by Westinghouse and are added to the Precautions, Limitations, anu Setpoints document by this MMOD. The rods are now set up for a 117 step tip to tip distance.
SAFETY EVALUATION SUNI3tARY: The MMOD affected UFSAR Figure 15.0-20. He rod insertion limits are discussed in UFSAR Sections 4.3.2 and 7.7.1.3. The bank overlap function is discussed in UFSAR Section 7.7.1.2. There is no change to these sections as a result of this MMOD.
A safety evaluation was performed to assess the effect on shutdown margin and boron dilution due to the change in the rod insertion alarm limits. UFSAR Figure 15.0-20 was reviewed as part of the safety l evaluation. It was determined that the " Audible Count Rate"," Rod Insertion Limit", "High Source Range Neutron Flux", and " Reactor Trip" alarms should have been denoted as non-safety per the existing plant configuration. Figure 15.0-20 was corrected by this MMOD to denote non-safety status of these parameters. Therefore, this MMOD makes changes in the facility as described in the UFSAR. Changes ,
in the control rod bank overlap and insertion limits do not create any procedure changes as described in !
UFSAR Chapters 4,7 and 13. The implementation of bank overlap and insertion limit changes do not '
require nor specify any test or experiment not described in the UFSAR. The safety evaluation determined ,
that this change did not involve an unreviewed safety question.
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UFCR 92-002 i
MINOR mon FICATION (MMOD) NUstBER: 92-533 TITI.E: Thermal Barrier Cooling Sample Connection Extension SU51%tARY DESCRIPTION AND PURPOSE: The Reactor Coolant Pump Barrier (RCPTB) cooling loop sample connection valve is not readily accessible. This valve has a pipe stub with an end cap which is currently approximately 8" below the pump suction line, but this sample point is approximately 7' above the -26' level in containment. In order to remove the pipe cap to sample the fluid, the technician is subjected to a potential personnel safety hazard. A review of other possible sample points on the thermal
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1 barrier pump loop finds no other points available outside the bioshield. Therefore this MMOD extended the pipe end beyond the cooling loop sample connection valve to approximately 16 inches above the -26' level of containment. An additional valve was added for isolation. The existing cooling loop sample connection valve, will remain normally open.
san:TY EYAl.UATioN SU%t% ARY: The MMOD afTected UFSAR Figure 9.2-13. This modification was performed to remove a potential personnel safety hazard. The RCPTB cooling loop is a closed loop system within the Primary Component Cooling Water System (PCCW). This alteration will not alter the performance the PCCW system or the RCPTB cooling loop during an accident. The RCPTB cooling loop is classified as non essential and does not need to function following a LOCA or M5LB.
Additionally, this modification affects only the sample drain piping. Failure of the sample drain line piping is not an initiating event for any accident analyzed in the UFSAR. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 93-037 MINon MoDilICATioN (MMOD) NUNuitn: 92-546 TITI.E: Diesel Generator Cooling Level Gauge Modification SU%t% ARY DESCRlrtloN AND PL'urosE: The level gauges for the Diesel Generator Jacket Coolant Expansion Tanks are not isolable by ASME Section 111 valves. The tanks are ASME 111, therefore, this arrangement does not meet Code requirements. This MMOD will add the ASME Ill isolation valves.
Additionally a walk down was performed on both diesel generator skids to verify the P & ID depicted configuration. This MMOD provides numerous minor corrections / enhancements to the diesel P&lD's.
sat:ETY EYAI.t'ATioN Sl31%tARY: The MMOD made changes in the facility as described in UFSAR Figures 9.5-10 Sheets 1 & 2, 9.5-11 Sheets 1 & 2, 9.5-12 Sheets 1 & 2 and 9.5-13 Sheets 1 & 2.
This MMOD adds an ASME 111 isolation valve upstream of thejacket coolant expansion tank level gauge.
This MMOD adds a normally open level gauge isolation valve and corrects minor P&lD inconsistencies with the installed configuration. Since this does not affect diesel operation no procedures within the UFSAR are affected. There are also no tests or experiments associated with this MMOD. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 93-008 MINOR MoDil'ICATioN (MMOD) Nt3:nEn: 92-552 TITI.E: RilR Pumps SA and 8B Seal, Seal Cooler Vent Line Installation St315tARY DEscuiriloN AND Pt'nrost: ne design modification was initiated to provide permanent vent lines with sight glasses for seal water coolers located on the Residual lleat Removal Pumps 1-Ril-P-8A and 1-Ril-P-8B. Permanent vent lines replace existing Tygon tubing and will significantly reduce maintenance time, personnel exposure rates, and the possibility of personnel or area contamination during the installation and removal of the Tygon tubing. This MMOD also corrects UFSAR Figures 5.4-10 and 5.4 11 to show the locations ofpressure transmitters 1-Ril-PT-2585 and 1-Ril-PT-2586 outside of the shielding.
SAFETY EVAltfATION St31%1ARY: The MMOD represented a change to the facility as described in the UFSAR replacing temporary tubing with non-safety-related permanent tubing, meeting the appropriate piping material, thermal and seismic design requirements for this application. The safety evaluation concluded that this did not involve an unreviewed safety question.
UFCR 93-016 MINOR MODIFICATION (MMOD) Nt3tBER: 92-556 Trite: Diesel Generator (EDG) Component Safety Reclassification Stat %1ARv DESCRIPTION AND PL'RPOSE: A condition was identified that was contrary to the design description stated in the UFSAR. The UFSAR states that the functional performance of the EDG cooling water system was not adversely efTected by environmental occurrences, abnormal operation, accident conditions and loss of power. It was identified that the EDG jacket cooling water temperature control valves would fail open on a loss of air during a seismic event, which could cause overcooling of the diesel generators and potentially preclude long term operation. An Operability Determination and Engineering Evaluation was performed to document the seismic functionality of the diesel air start skid, utilizing available seismic documentation and engineering judgement. The evaluation concluded that, with appropriate operator actions, the air start skid will function to support diesel generator operation during a seismic event. This modification updates design documents and the UFSAR to reflect the updated safety classification of starting air components, programs and procedura.
This condition was reported in LER 93-08-01.
SAIETY EVAlt!Ah0N St31%lARY: The MMOD involved a change to the facility as described in the UFSAR. Sections 9.5.5 and 9.5.6, Figures 9.5-12 Sheets 1 and 2, and Table 3.2-2 were revised to reflect the upgraded safety classifications. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 93-032 MINOR MODIFICATION (MM')D) Nt31HER: 92-576 TirlE: Diesel Generator Fire Hose Reel Elevation Corrections Stat %1ARY DESCRIPTION AND Pl'RPOSE: This MMOD was issued to correct the elevation shown on drawings for containment fire hose reels. Changes were also added to the UFSAR to clarify when containment fire hose stations should be operable.
SArETY EVALUATION St31%lARY: The MMOD made changes in the facility as described in UFSAR Tables 16.3-5 and Figure 9.5-8. The changes implemented by this MMOD corrected the elevation listed for the containment fire hose reels and revised the operability requirement for the Containment fire hose stations. The change did not increase the probability or the consequences of an accident previously evaluated in the UFSAR. This MMOD does not make any changes to the design basis of the Fire Protection System, or require any equipment changes and does not change the operation or set
point of any equipment. The safety evaluation detennined that this change did not involve an unreviewed safety question.
UFCR 92-072 MINOR MODIFICATION (MMOD) NUNIBER: 92-589 TITI.E: Condensate Pump Stuffing Box Bleed Line St31stARY DESCRIPTION AND Pl:RPOSE: This design modification provides for the installation of ball valves into the throttling bushing bleed off lines on the condensate pump stuffing box. The valves are modulated to increase stuffing box internal pressure thus minimizing oxygen intrusion into the secondary side water chemistry. In addition, the change also includes the incorporation of a pressure indicator and small relief device to protect tne gauge.
SAFETY EVAttrATION SU31%IARY: The MMOD represented a change to the facility as described in UFSAR Figure 10.4-7. The safety evaluation concluded that this change did not alter the ability of the pump to perform its function. The condensate system is non-safety related. Loss of the condensate pumps due to loss of AC power is evaluated in UFSAR Section 15.2.6.1. This modification does not alter any of the UFSAR accident analysis assumptions or results, therefore this change does not involve an unreviewed safety question.
UFCR 93-018 MINOR MOlillicATION (MMOD) NtainER: 93-501 TITI.E: Potable Water Backflow Prevention Addition StatstARY DESCRIPTION AND PURPOSE: This design change added backflow preventors and vacuum breakers to the Potable Water System to provide additional protection against the possibility of contaminating the supply system by a reversal of flow. The Potable Water System is supplied by the Town of Seabrook and without this change, abnormal system conditions might occur whereby the pressure in the various branch lines of the distribution system might exceed the pressure of the Potable Water supply. Water contained in the distribution lines could then flow into the supply lines and contaminate the supply with various chemicals, e.g. chlorine, that are introduced in the distribution network.
SAFETY EVALUATION Sl313tARY: The MMOD made changes to the facility as described in UFSAR Section 9.2.4.2 and Figure 9.5-5. The safety evaluation concluded that the change provides an additional protective barrier against a postulated water supply contamination. The safety evaluation also determined that the design intent and function of the Potable Water System are unchanged by this modification and further, that the modification does not involve an unreviewed safety question.
UFCR 93-022 MINOR MODIFICATION (MMOD) Nt31BER: 93-502 TITI.E: Low EHC Trip Header Pressure Switch MS-PSL-3075,3076, and 3077 Setpoint Revision St31stARY DESCRIPTION AND Pt'RPGsE: This modification changes the setpoint of the hydraulic pressure switches associated with the main turbine stop valves. The function of these pressure switches is to provide input to the Solid State Protection System (SSPS) and initiate a Reactor Trip signal should any 2 of the 3 pressure switches sense a loss of the EHC Fluid pressure that would indicate stop valve closure. The present prescribed setpoint tolerance for these switches has not always been met due to instrument drift and has resulted in exceeding Technical Specifications allowable values. The serpoint has been raised from 500 psig to 550 psig decreasing, which is consistent with Technical Specifications and is within the design specification for the switches (150 to 3000 psig) and is well below the normal system operating pressure of 1600 psig. The modification also makes changes to the Standard Instrument Schedule (SIS) regarding the reset values associated with various system pressure switches. These switches have a non-adjustable reset and the reset value is not a control point.
SAFETY EVAlrATION St31stARY: The MMOD did not make chuges to the facility as described in the UFSAR. However, it was deterrnined that a change to the Technical Specifications could be submitted to reflect the nominal value of the new setpoint. The safety evaluation concluded that the modification did not alter the function or operation of the afTected pressure switches and further, that the change did not involve an unreviewed safety question.
UFCR 94-027 MINOR MODIFicritON (MMOD) Nt31HER: 93-517 Tirt.E: Instruments Class Breaks Requiring Updating and Miscellaneous Changes St31stARY DESCRIPTION AND Pl'RPOSE: North Atlantic conducted a review of the ASME/ ANSI code classifications of all instruments installed in safety related systems to ensure compliance with Regulatory Guide 1.151 in respense to NRC Inspection 92-80. This review demonstrated compliance with Regulatory Guide 1.151, although several inconsistences required correction. MMOD 93.0517 corrected these inconsistencies along with addressing minor changes to P&lD's DBD's, Loops and Logics, and the UFSAR.
SA1:E~IY EVAirATION St31stARY: The MMOD made changes in the facility as described in UFSAR Table 9.2-7 ana Figures 6.2-92,6.3-4,6.3-5,6.8-2,9.2-2 Sheets 1 & 2,9.2-4 Sheets 1 & 3,9.2-6 Sheets 1 & 4,9.3-29 and 9.3-30. This modification was performed to reconcile instrument sensing line class breaks on the P&lD's verses the actual installation class breaks. The instrument sensing lines associated with this modification comply with the required recommendations and guidelines. This modification updates the P&lD's to reflect the actual plant conditions. The safety evaluation determined that this change did not involve an unreviewed safety question.
UFCR 93-046 I
j MINOR MOpirICATION (MMOD) Nt:MBER: 93-524 TITI.E: CAP Pressure S,vitch R&., val i
SUMMARY
DESCRIPTION AND Pt'RPOSE: 'll.is modification removes the Containment Air Purge (CAP) System pressure switches that interlock te npply and exhaust fans with the containment isolation valves. The CAP System is used to reduce airborne activity levels in containment below 10CFR20, Apper. dix B limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a reactor shutdown. The CAP System does not operate in Modes 1,2,3, or 4. The four class 1E pressure switches sense duct pressure / vacuum to conGrm that a supply and an exhaust fan are operating normally prior to opening the containment isolation valves. The need to remove the switches addresses a concern of isolatior valve cycling when the CAP System is operational ;
due to a very small onerating band for the switches. ;
SAFETY EVAIEATION St'MMARY: The MMOD made changes to the facility as described in -
the UFSAR. A change to UFSAR 9.4-14 was required to show the removal of the four pressure switches. ;
Operation without the switch interlocks isjustined since the safety function for closing the isolation valves ;
is performed by the containment ventilation isolation signal (Phase A isolation signals or high radiation). i The CAP System, other than containment isolation, is not relied upon for accident mitigation. The safety evaluation determined that this modification does not involve an unreviewed safety question. l UFCR 93-060 l
MINOR MOutrICATION (MMOD) NttMBER: 93-536 TITI.E: VAS Alarm Changes / UFSAR Updates St3tMARY DESCRIPTION ANIS PL'RPOSE: This MMOD makes changes to the non-nuclear safety Video Alarm System (VAS) and Updated Final Safety Analysis Report (UFSAR) to resolve the deviations between commitments in the UFSAR and the existing VAS configuration that were identified. in t Engineering Evaluation 93-036. Minor changes were made to drawings, including some that are UFSAR i Ogures. Most of the changes involve VAS changes to meet the UFSAR commitments. !
SAFETY EVAL.t!ATION St31 MARY: The MMOD made changes in the facility n described in l UFSAR Sections 1.8, 5.2, 6.3, 7.7, 8.3, 9.2, 9.3, 9.4, and 10.4, Tables 8.3-8 & 8.3-9 and Figures 7.2-7 ;
& 7.2-8. No changes were made to any procedures described in the UFSAR as only alarm response t guidelines are afTected. The probability of occurrence of an accident or equipment malfunction is not increased and the possibility of an accident or malfunction of a different type is not created. The ,
consequences of an accident or equipment malftmetion are not increased since the affected alarms are not relied on for accident mitigation. The margin of safety as defined in the basis for any technical .
specificatien is not reduced as the alarms are not required for meeting any Technical Specification. The ,
safety evaluation determined that this change did not involve an unreviewed safety question. ;
UFCR 93-034 :
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MINOR MODIHCATION (MMOD) NtainER: 93-539 TITLE: Spent Fuel Pool Demineralizer liigh Differential Setpoint Change 1
St3t%tARY DESCRIPTION AND PURPOSE: This design change provided the basis for increasing the i high differential pressure alarm setpoint for the spent fuel pool demineralizer from 10 psid to 20 psid and bypassing of the spent fuel pool pre-Giter. This change allows the required cleanup Dow rates to be maintained with higher loop differential pressures while staying within the design limits of the demineralizer.
SAM:IT EVAixATioN St3tstARY: The MMOD represented a change to the facility and to procedures as described in the UFSAR. Section 9.1.3.2.b and Figure 9.1-2 of the UFSAR were revised to reflect bypassing of the spent fuel pool pre-Giter. The revised operating condition for the spent fuel pool cleaning subsystem remains within the design limits of the system. The safety evaluatun concluded that this design change did not involve an unreviewed safety question.
UFCR 93-029 MINon MoDinCATION (MMOD) NtainEn: 93-545 TITI.E: Minor Changes to P&lDs St31.stAnY DESCRIPTION AND Pt RPosE: This modi 6 cation provided changes to P&lDs which have been identified by numerous Request for Engineering Services to be needed to maintain consistency within the design control system. The changes involve such items as the additionideletion of tag numbers, typographical corrections, drawing enhancements that identify hoses, capillaries, valves, instrument air connections, and revisions to P&lD supponing documents (Valve List, Line List, Equipment List). The ,
changes are administrative.
SAFETY EYAixArioN St3 3tARY: The MMOD made changes to the facility as described in numerous UFSAR Figures in Sections 6, 9,10, and 11. The safety evaluation concluded that these changes eliminate potential errors by providing additional infonnation on the P& ids. The possibility of operator error regarding the mispositioning ofincorrectly labeled valves or maintenance activities being performed on the wrong equipment will be reduced. The safety evaluation determined that the modiGcation does not involve an unreciewed safety question.
UFCR 94-046 MINon MoDiriCATION (MMOD) Ntatus:R: 93-547 ,
Tirt.E: MSIV Slow Flow Valve Time Delay St3tstinY Di.SCRIPIlON AND PURPOSE: The Main Steam Isolation Valves (MSIV) Ere provided with restrictors (slow Dow valves) that are inserted in the hydraulic dump line to reduce the valve closing speed during normal closure or panial stroke exercise tests. Retraction of the slow flow valve is delayed at the end of the exercise test to provide time delay for closure of the main dump valve. The existing 0.1 second time delay is not long enough and results in a momentary fast closure before the main dump valve closes fully. This condition has resulted in plant trips and upsets. This modification increases the time l
delay for retraction of the slow flow valve to approximately 45 seconds. This will prevent spurious fast closure when a partial stroke exercise test is terminated and provide time for operator action to terminate a spurious MSIV closure as the result of a defective hydraulic component.
SAFETY I' st.t!A110N St31slARY: The MMOD made changes to the facility as described in UFSAR Sections 1.8,7.1.2.5,7.1.2.6,7.3.2.2(e)(9), and 10.3.2.7. The probability or concequences of an accident previously evaluated in the UFSAR will not be increased. The probability an inadvertent MSIV closure evaluated in Section 15.2.4, "Inadvenent Closure of Main Steam isolation Valves," is reduced by changing the valve :est interlock to " reset" oft the open position switch. This will terminate the test earlier and permit more time for operator response to stop an uncontrolled valve closure. The safety evaluation detemiined that this modification does not involve an unreviewed safety question.
UFCR 93-069 MINOR MODIFICATION (MMOD) NtainEn: 93-553 TIIEE: Jockey Pump Replacement Stats 1Any DESCRIPTION AND Pt'RPOSE: The modification replaces the original Fire Protection Jockey Pump with a similar style pump. The original pump (manufactured by Allis-Chalmers) was damaged during hydrostatic testing and spare pans were not readily available. The replacement pump is manufactured by Worthington Pump and has been used in another applicatian at the station with reported acceptable perfbrmance.
SAFETY EVArttATION StatstARY: The MMOD made changes to the facility as described in UFSAR Figure 9.5-5. The siety evaluation concluded that the modification had no functional impact on the performance of the Fire Protection System since the replacement pump was similar in form, fit, and function to the original. The change makes system maintenance easier and does not involve an unreviewed safety question.
UFCR 93-061 MINOR MODIFICATION (MMOD) NtainEn: 93-554 TIII 1:: Chain Operator ibr CO-V31 St31stARY DESCRIPilON AND Pt'RPGsi:: This modification provides for the installation of a chain-operator to a non-safety related manual valve. The modification provides for the safe operation of the valve from the 21'-0" elevation of the Turbine Building.
SA E1Y EVArttATION St31stARY: The MMOD made a change to the facility as described in UFSAR Figure 10.4-7, Sheet 1. The safety evaluation determined that this modification does not involve an unreviewed safety question.
UFCR 94-005 1
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MINOR TSODirlCATION (MMOD) NtainEn: 93-564 {
Tril.E: Mechanical Services For l&C Shop Sl3151ARY DESCRIPTION AND Pl'RPOSE: This modification provides mechanical services piping ;
systems to the proposed I&C Shop in the Administration Building Room 112. Specifically hot and cold l potable water, service air and instrument air. The services are tapped off existing system branch lines that i are located in the area.
i SAIETY EVAL,tIATION St31%IA:tY: The MMOD mace changes to the facility as described in -
UFSAR Figures 1.2-49,9.3-6, Sheet 3, and Figure 9.3-9, Sheet 1. The safety evaluation concluded that ;
the conversion of Administration Building Room 112 to an I&C Shop and the addition of potable water j and service / instrument air did not involve an unreviewed safety question.
UFCR 94-007 l
MINOR MODirlCATION (MMOD) Nt3inER: 94-505 i TIII.E: VCT 112 Supply Pressure Control Valve WG-PCV-8156 Replacement t
St3t%tARY DESCRIPTION AND Pt nPOSE: This design modification replaced the existing volume i control tank (VCT) 112 pressure control valve with a different design to improve pressure control capability and reduce leakage. The MMOD also relocated the pressure sensing line for the pressure controller from .
the hydrogen supply line downstream of the pressure control valve to the top of the VCT.
SAFETY EVAL.tfATION St3l%tARY: The change revised UFSAR Figures 11.3-1 and 11.3-2 to depict the revised location of valve WG-PCV-8156 and the controller WG-PIC-8156 in the system.
Revising the sensing line location to the top of the VCT required an additional change affecting UFSAR Figure 9.3 30. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UFCR 94-022 r
MINOR MODiricATION (MMOD) NtainER: 94-506 T!TI.E: Diesel Generator Control Valve Staking !
St3t\lARY DESCRIPTION AND PrRPGsE: This modification eliminates the modulating capability of I the Diesel Generator jacket and air coolant pressure control valves (PCVs). Instrumentation instabilities i have resulted in spurious valve oscillations that have interfered with proper cooling of, and therefore, the reliability of the Diesel Generators. In addition, the existing fail open position of these PCVs has been ;
identified as having the potential for overcooling the diesel engines. This design change stakes the PCVs in a throttled position that has been field tested to result in stable system operation. ;
SArl:Tv EVAt.t!ATION S13151ARY: The MMOD made changes to the facility as described in UFSAR Sections 9.5.5 and 9.5.6 as well as Figures 9.5-11 and 9.5-12. The safety evaluation concluded that the reliability of the Diesel Generators is enhanced and further that the potential for a significant
overcooling failure mode has been lessened by this design change. The safety evaluation determined that this modification did not involve an unreviewed safety question. -
UFCR 94-016 MINOR MODIFICATION (MMOD) NUNIBER: 94-509 3 TITLE: CAH-AC-1 A,B,C,D,E,F Filter Removal Sti>lNIARY DESCRIPTION AND PURPOSE: This modification removed the fibrous intake filters associated with the containment air handling units. The change was made in response to NRC Bulletin No. 93-02, which identified the potential for blockage of the containment s'. ed in the Emergency ,
Core Cooling System during a large break LOCA scenario. It was determit . 'he filters could not l withstand a LOCA, and therefore, the possibility of the filter medium being tra e a to the containment j sumps and plugging the intake filters made it necessary to take action i clude that postulated !
condition.
SAFETY EVALUATION SUhl%1ARY: The MMOD made changes to the facility as described in the UFSAR, Section 9.4.5.2 and Figure 9.4-13. The safety evaluation concluded that the removal of the air handling filters did not impact the safe operation of the plant. Some slight performance degradation of the containment cooling units can be expected due to the filter removal, however, compensatory action can be taken prior to exceeding the containment temperature limitation specified in Technical Specification Limiting Condition for Operation 3.6.1.5. The safety evaluation determined that this modification did not involve an unreviewed safety question.
i UFCR 94-015 ,
MINOR MoDirlCATION (MMOD) NUNIBER: 94-511 TITLE: Relief Valve SI-V-248 Replacement SrsistARY DESCRIPTION AND PrRPost: This MMOD replaced the existing valve SI-V-248 which ,
has a set pressure of 1850 psig with a similar valve having a set pressure of 1750 psig. For CBS -V-62,'
this MMOD provides correct set pressure information for Specification 248-43 and Calculatior.4.4.17.lF. ,
i SAFETY EVALUATION Sr31%IARY: The MMOD made changes in the facility as described m :
UFSAR Figure 6.3-4. The set point change and documentation update implemented by this modification !
do not affect the function of the related systems. The reduced set point (1750 psig) for SI-V-248 is higher than the maximum discharge pressure of the safety injection pumps. Both the Si and CBS systems will ?
remain capab:e of performing their design basis functions. With these systems functioning, oft site does will remain bounded by the analyses documented in Chapter 15 of the UFSAR. The safety evaluation i determmed that this change did not involve an unreviewed safety question. ;
UFCR 94-017 1
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MINOR MODIFICATION (MMOD) NL'MBER: 94-525 !
Tm.E: EFW Pump Rotor Replacement !
I SttMMARY DESCRIPTION AND Pt'RPOSE: This design modification documents the replacement of i the Motor-Driven Emergency Feedwater (EFW) Pump rotor. The pump rotor was replaced with the i corresponding element from the Unit 2 turbine-driven EFW pump. The EFW pur..p hydraulic !
performance is slightly improved by this design change. This change was required due to damage that occurred during a disassembly inspection. l SAFETY EVAI t!A110N St3tMARY: The replacement of the rotating element resulted in a slight .
increase in the pump brake horsepower, based on shop test curves. The KW values in UFSAR Tables 8.3-1 and 8.3-2 were increased as a result. The slight increase in diesel loading and fuel consump' .m remain within the design limits and rated values. The safety evaluation for this design change concluded i that this did not involve an unreviewed safety question. !
UFCR 94-031 i
MINOR MODIFICATION (MMOD) Nt3tnER: 94-530 [
TITt.E: Service Water Throttling for PCCW {
I StatMARY DESCRIPi1ON AND PL'RPOSE: This design modification documents the reanalysis of the !
PCCW lleat Exchangers design in order tojustify the existing limits for tube plugging. Additionally, this l' modification established throttle valve positions for Service Water flow to the heat exchangers in order to maintain a 1 psig nominal pressure at the heat exchanger outlet. The established throttle positions for !
valves 1-SW-Vl9 and 1-SW-V20 results in a change in the stroke time and running current test data. The :
changes necessitated resizing of the thermal overload heater for 1-SW-Vl9 to meet the criteria required !'
by the UFSAR Section 8.3.1.l(g) and design calculations.
SAI ETY EVAL.t!ATION St3tMARY: This MMOD represented a change to the facility as (
described in the UFSAR. Figure 9.2 2, Sh. 2, required revision to reflect that service water valves i 1-SW-Vl9 and 1-SW-V20 are preset and used for throttling. Resizing of the thermal overload heater for ;
l-SW-Vl9 required a change to UFSAR Table 16.3-9, Motor Operated Valves With Thermal Overload Protection Devices Operable At All Times. The safety evaluation for this design modification concluded l that this did not involve an unreviewed safety question. ;
UFCR 94-032 !
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l UPDATED FINAL SAFETY ANALYSIS REPORT CHANGE REQUESTS (UFCRs)
The following UFCRs, not related to DCRs or MMODs,were incorporat 'd into Revision 3 of the UFSAR. l A 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, UPDATED FINAL SAFETY ANAIXSIS REPORT CilANGE REQtTsr (UFCR) NtisinER: 88-062 TI11.E: Boration Flow Path UFSAR Change Request Evaluation St31stARY DESCRIPTION ann Pt'RPGsE: This change revised the UFSAR to describe a third boration flow path used within the procedures of the plant but not previously described in the UFSAR.
This boration flow path utilizes the cold leg injection line when the charging pump is aligned to the RWST.
I SAFETY EYAl.lfATION St:31%IARY: The UFCR made changes in the procedures as described ;
in the UFSAR. The revisions affected UFSAPs Section 9.3.4.3. The margin of safety as defined in the basis for Technical Specifications is not reduced. Use of Safety injection (SI) Valves as a boration flow path provides an additional means to rapidly borate as required by Technical Specification 3/4.1.1, Shutdown Margin. Single functional capability regarding flowpaths per Technical Specification 3/4.1.2, Boration Systems is assured. Flow into the RCS (Cold overpressure concern per Technical Specification 3/4.4.9) already considers charging flow through either of these Si valves, so a higher flowrate path is not being considered. The safety evaluation determined that this change did not involve an unreviewed safety question.
UiDATED FINAL SAFETY ANAIASis REPORT CIIANGE Rent *EsT (UFCR) Nii3tHER: 93-011 L Till.E: Clarification of the Design Basis for Safety-Related Roof Loads !
St:ststARY DESCRIPTION AND Pt'RPOSE: Section 2.4.2 of the UFSAR discusses the design basis for roofs of safety related buildings. In particular, pages 2 4-8 and 2,4-9 address rain and snow loads, as applied to these buildings. The UFSAR change clarifies the existing basis with respect to how it was actually applied during the design phase.
SAFETY EVAlt1ATION St31%1ARY: The UFCR changes are editorial in nature, clarifying how the design basis for safety-related building Wf loads was applied during the design phase. The design basis and design safety factors are not at'tected. The safety evaluation determined that this change did not i involve an unreviewed safety question.
l UPDATED FINAL SAFETY ANAL.Ysis REPORT CllANGE REQt'EST (UFCR) NL'%IBER: 93-014 f f
TITI.E: Secondary Chemistry Program Changes - UFSAR See. 10.3.5,9.3.2.2.9.4, and 10.4.8.3.g St3tNIARY DESC RIPTION AND Pt'RPGsE: The Westinghouse Chemistry Manual presently referenced in UFSAR Section 10.3.5 was prepared in 1986. Since that time, Westinghouse has joined EPRI along ,
with other NSSS vendors and a consortium of 28 utilities to write the EPRI PWR Secondary Water Guidelines. These guidelines are recognized by the NRC and INPO as the controlling document for secondary chemistry control at US nuclear plants. The issuance of Rev. 03 in April 1993 makes changes to Action Level parameters for contaminant ingress, pil ranges for pl.mt specific situations, and approves enhanced amines as pli additive chemicals. The UFSAR change provides the appropriate references to i the ERPI Guidelines. l l
SAFE 1Y EVAEUATION StoisitRY: The Action Level changes and revised pil ranges reflect l more conservative values and enhanced treatment ranges to reduce the potential for secondary side !
corrosion attack and reducing met:.1 transport in secondary systems. These changes are based on current i industry experience and will enhance secondary system corrosion resistance. The safety evaluation determined that this change did not represent an unreviewed safety question.
UPonED FINA1. SAFETY ANAEYSIS REPORT CIIANGE REQt'EST (UFCR) Nt3tBER: 93-015 TITEE: Diesel Generator Fuel Oil Surveillance Requirements StatstAuY DESCRIPTION AND Pt'RPOSE: A Request for Engineering Services (RES) identified two :
inconsistencies between North Atlantic's commitments to Regulatory Guide 1.137 and Seabrook Station Technical Specifications regarding testing requirements for new and stored fuel oil. Specifically, Technical Specification Surveillance 4.8.1.1.2d(l)(d) requires initial testing for "A clear and bright appearance with proper color when tested in accordance with ASTM-D4176-82", versus the Regulatory Guide recommendation of testing for water and sediment. In addition, the Technical Specifications require i
testing in accordance with ASTM-D975-81 within 30 days versus the Regulatory Guide requirement to complete this testing within two weeks. This UFCR revises UFSAR Section 9.5.4.4 and 1.8 to take i exception to the above Regulatory Guide recommendations to make its commitments to Regulatory Guide ;
1.137 consistent with the Technical Specification Surveillance Requirements.
SAFE 1Y EVAL,UATION St31stARY: The UFCR made changes to procedural commitments i defined in the UFSAR. The safety evaluation concluded that the Technical Specification Surveillance requirements for fuel oil meet or exceed those identified by Regulatory Guide 1.137 and therefore this .
change does not represent an unreviewed safety question. l UPDATED FINAE SAFETY ANAEYsts REPORT CilANGE REQL EST (UFCR) NtainER: 93-020 :
TITEE: Clarification of Text in UFSAR Section 9.4.8.1 St31stARY DESCRIPilON AND Pl'RPOSE: Section 9.4.8.1 of the UFSAR stated that the fans and dampers were the only safety class components in the Diesel Generator Building 11 eating and Ventilating System (DAll). Contrary to this statement, UFSAR Table 3.2-2 lists safety class ductwork, in addition ;
to the fans and dampers that were identified in the text for Section 9.4.8.1. The discrepancy was corrected in Section 9.4.8.1. The actual safety classification of components remains unchanged. !
SArETY EVAEt!ATION StatstruY: The UFCR revised the existing UFSAR text for !
clarification purposes only and the system design basis and design characteristics were not affected. The safety evaluation determined that this change did not represent an unreviewed safety question.
UPDATED FINAE SAFETY ANAEwis REPORT CllANGE Rent EST (UFCR) Nt3tBER: 93-026 TITEE: Battery Charger Alarms StatstARY DESCRIPTION AND Pt'itPOsE: UFSAR Chapter 8.3 was revised to properly describe the installed conSguration of the safety-related battery charger output current indications and alarms. Loss I of battery charger output current from each battery charger is monitored by an electronic circuit internal l to the charger. A relay contact driven by this circuit provides a signal to the Main Plant Computer System (MPCS) when battery charger output current decreases below a preset level. In the original design, this signal would trigger a printout on the MPCS Control Room data logger and an alarm on the Video Annunciator System (VAS).
Frequent bLttery charger failure alarms were received in the control room. It was determined that two of the four DC buses are lightly loaded and caused the frequent alarms which were not indicative of battery charger failure. Because the charger relay is not sensitive enough to sense the low trickle charge current involved, the setpoint could not be reduced sufDciently low to eliminate the false alarm. The station battery current digital ammeters also provide Control Room alarms. These digital ammeters reliably monitor battery charging current which is equivalent to monitoring charger output and therefore, are suitable indicators to replace the function ofIwtery charger failure alarm. Therefore the alann function was climinated for each battery charger by an approved revision to the MPCS data base.
At the time of the removal of the battery charger failure alarm, the UFSAR was not reviewed. During the May 1993 Electrical Distribution System Functional Inspection performed by the NRC, the discrepancy with UFSAR Section 8.3 was identi6ed. In addition, the discussion provided in response to USNRC Generic Letter 91-06, " Resolution of Generic issue A-30, Adequacy of Safety-Related DC Power Supplies" was incorrect because it was based on the original UFSAR description. UFCR 93-026 provides the required revision to the UFSAR with the necessary evaluations The response to GL 91-06 has since been amended.
SAH:TY EVAI.1% TION Sl31stARY: The UFCR made changes to the alarm descriptions in the UFSAR Sections 8.3.2.1.f.2 and 9 constituted a change to the facility. The presence of the digital ammeters and other system alarms provides the required status indication. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UPinTEn FINAI, sal'ETY ANAEYsis REPORT CIIASGE REQlTsT (UFCR) NtwinER: 93-039 TITI.E: Revision to UFSAR Tables 8.3-1 and 8.3-2 St31stARY DESCRIPTION AND Pt RPGsE: During the 1993 Electrical Distribution System Functional inspection audit performed by the NRC, it was identified that the original Emergency Diesel Generator fuel consumption calculations were based on manufacturer's information instead of actual operational data.
An engineering and operations review of the operating time duration of the diesel loads was performed. ,
Revised diesel generator fuel oil consumption calculations necessitated changes in operating time durations for cenain diesel generator electrical loads. UFSAR Tables 8.3-1 and 8.3-2 were revised to renect those ,
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san:Tv EVAI,1% TION St31% ARY: Review of accident analyses in UFSAR Chapter 15 )
determined that revising the operating time duration of various components will not affect the diesel l generators ability to operate for seven days during a Loss of OfTsite Power (LOP) with or without a Loss l l
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of Coolant Accident (LOCA). The changes in operating times for the individual components does not affect the ability to perform their required safety functions. The safety evaluation concluded that this modification did not involve an unreviewed safety question. ;
l UPnATED FINAL SAFETY ANALYSIS REPORT CIIANGE REQt!EST (UFCR) NtSturR: 93-040 TITI.E: IST Tables Deletion !
i St31%IARY DESCRIPTION AND PL'RPOSE: This change removed the Inservice Testing (IST) program components list and associated references from UFSAR Sections 3.9(B).3.2 and 3.9(B).6 and Tables j 3.9(B)-24 and 3.9(B)-25. This was done in accordance with guidance provided in Generic Letters 89-04 and 91-08 in order to facilitate the IST change process. The IST component lists are now controlled ,
under station procedures and the IST Program Plan.
f SAFETY EYAttfATION S13t%1ARY: The UFCR changed station procedures as described in the '
UFSAR by deleting certain portions of the IST program. Deletion of this information from the UFSAR was performed in accordance with the guidance provided in NRC Generic letters 89-04 and 91-08 in order to facilitate changes to the IST program. The safety evaluation concluded that this change did not involve ;
an unreviewed safety question.
UPnATED FINAL SAFETY ANALYSIS REPORT CilANGE REQUEST (UFCR) NtainER: 93-043 ;
TIII.E: Fire Detection Operational Test Frequency Revision St3t%IARY DESCRIP110N AND Pt*RPGsE: This UFSAR change was issued to revise Technical Requirement 12, Fire Detection Instrumentation operational test frequency. NFPA 72E Standard on i i
Automatic Fire Detection allows for the adjusting of fire detector inspection frequencies based on the following: (1) proven reliability of the detectors, (2) multiple detectors in each fire area, (3) sophistication of the fire detection system and (4) ALARA considerations. The adjusting of detector incoections is -
intended to optimize resources and does not reduce the reliability or the ability of the fire detection system to detect a fire.
SAFETY EVALUATION St31% ARY: The safety evaluation concluded that the UFCR represented j a change to the surveillance requirements in procedures described in the UFSAR. The safety evaluation .
concluded that this change did not involve an unreviewed safety question.
UPnATEn FINAL SAFETY ANALYSIS REPORT CHANGE REQt'EST (UFCR) Nt31sER: 93-044 TITLE: Ceramic Cooling Tower Cold Weather Operations S13t%IARY DESCRIPTION AND PURPOSE: This change revised the description of cooling tower operations during cold weather conditions to more accurately reflect the operational limitations. t References to outside air temperatures in Section 9.2.5.2b were changed to wet bulb temperatures. This change allows increased fiexibility for cooling tower operation while providing adequate protection of the ,
cooling tower components against ice formation. Figure 9.2 14 was added to provide guidance on cooling tower spray and fan operation during cold weather. ;
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SAIITY EVALUATION St31%tARY: The additional information added by the UFCR we.,
determined to be a change to the facility as described in the UFSAR. The added informWn on operational limitations provides a more accurate description of cooling tower operations during cold weather and does not alter previous performance analyses. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANALYSIS REPORT CIIANGE REQt'EST (UFCR) Nt3:nER: 93-053 TITLE: Revision to UFSAR Table 9.5-1, p. 2 of 2 St3t%fARY DESCRIPTION AND PL'RPOSE: This change updates UFSAR Table 9.5-1, to adopt the 1992 version of NFPA 80, Standard for Fire Doors and Windows, in place of the 1983 edition of this standard. The reason for this change is to provide the necessary clearance tolerances between a fire door and frame, thus providing an acceptance range for inspections that was not addressed in the earlier version of the standard.
SAFETY EVALUATION St31stARY: The addition ofinformation by the UFCR changed the facility as described in UFSAR Table 9.5-1. The safety evaluation concluded that this change did not involve an unreviewed safety question.
UPD ATED FINAL SAFETY ANALYSIS REPORT CIIANGE REQt'EST (UFCR) NtainER: 93-057 TITLE: Associated Circuit UFSAR Criteria StatstARY DESCRIPTION AND Pt'RPOSE: This UFSAR cha.nge revised the criteria for Associated Circuits contained in Section 8.3.1.4. Following an NRC Electrical Distribution System Functional Inspection audit, it was determined that the criteria defining associated circuits and related testing / inspection and procurement criteria was not implemented as intended. As part of the corrective action, Section 8.3.1.4 was revised to incorporate the concept of directly and indirectly interfacing associated circuits. This concept defined those non-Class 1E protective devices that directly interface with and have the potential to degrade Class 1E circuits as Protective Devices With Associated Circuit Requirements (PDWACR). The PDWACRs are subjected to special design, nrocurement and testing requirements similar to those applied to Class lE protective devices. No specia! requirements were applied to protective devices for indirectly interfacing associated circuits since their failure can not degrade Class lE circuits.
SAFETY EVAll'ATION St31stARY: The UFSAR change revised the description and classification, the procurement, maintenance and test procedures associated with these devices, :and established additional test requirements not previously included in the UFSAR description. The revised criteria for Associated Circuits remains in compliance with IEEE Std 384-1974 and Regulatory Guide l.75, Rev. 2. The safety evaluation concluded that this change did not involve an unreviewed safety question.
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UPDATFD FINAE SAFETY ANAEYSIS REPORT CIIANGE REQUEST (UFCR) Nt3tHER: 93-057 TITEE: Associated Circuit UFSAR Criteria St31stARY DESCRIPTION AND Pt RPOSE: This UFCR corrects the analysis for power cables outside the Nuclear Island to reflect as-built conditions. UFSAR Section 8.3.1.4 analyzes associated circuits that have their protective devices located in the Nuclear Island and that transverse the Nuclear Island boundary with a direct interface with Class 1E circuits. The analysis noted that 13.8 kV and 4.16 kV power cables were of the armored construction such that any raceway failure would cause the cable to be grounded before it would come into contact with a lower voltage cable. However there are some 4.16 kV power cables that are not of armored construction, but are either routed in embedded or exposed conduit. This construction provides the same degree of protection to the cable as does armor relative to the conduit causing the cable to ground. The grounding will prevent interaction with lower voltage cables during a raceway failure. This UFCR provides changes to reflect this non-armored construction.
SAFETY EVAElfATION St3 DIARY: The addition of the revised analysis for power cables changed the facility as described in UFSAR Section 8.3.1.4. This revised analysis remains in compliance with IEEE Std 384-1974 and Regulatory Guide 1.75, Revision 2. The failure modes are the same for armored versus non-annored cable relative to raceway interactions as analyzed in the UFSAR. The safety evaluation detennined that the UFSAR change did not involve an unreviewed safety question.
UPnATED FINAE SAFETY ANAI.YSIS REPORT CilANGE REQUEST (UFCR) Nt3tHER: 93-064 TITI.0: Updated Rod Ejection Accident Projected Releases and Radiological Consequences St sistARY DESCRIPTION AND Pt RPOSE: In response to a concern identified in Infonnation Notice 91-56, titled " Potential Radioactive Leakage to Tank Vented to Atmosphere", an evaluation was perfonned. The evaluation was based on the UFSAR Rod Ejection Accident Analysis Source Term. A review of the calculations indicated that the 1986 containment release revisions, specifically containment by-pass, design leakage and draw-down time, had not been applied to the Rod Ejection evaluation. The Staff's Safety Evaluation Report (SER), Supplement 4, for this event had been revised to reflect these containment release revisions. The change to UFSAR Chapter 15, updates the current Rod Ejection Accident, radiological release section 15.4.8, Tables 15.4-5,15.4-6, and 15.4-12, to reflect containment release assumptions as given in Chapter 15, Appendix 15B.
SAFETY EVAI.ttATION St3ntARY: The updated information included in the UFCR changed the facility as described in UFSAR Section 15.4.8, Tables 15.4-5,15.4-6, and 15.4-12. The activity releases and radiological consequences are revised due to off-setting revisions in the containment release pathway assumptions. All off-site and control room doses are still well within 10CFR Part 100 off-site dose limits and below GDC 19 control room limits. Plant vital area's and the ability to mitigate the radiological consequences to the general public are not adversely effected. The safety evaluation determined that the change does no involve an unreviewed safety question.
UrnATED FINAI, SAD:TY ANAIXSIS REPORT CIIANGE REQtT.sr (UFCR) NtStBER: 94-001 TITi.E: Fire Rated Assembly Surveillance Requirements StatstAnY DrscnirTION AND PL'RPGsE: This change modifies the Technical Requirements Manual surveillance requirements of TRIl-4.7.9.5.1 and 4.7.9.5.2 that are concerned with fire rate assemblics.
Specifically it takes exception to the inspection of fire rated assemblies that are inaccessible or are otherwise obstructed and can not be practically inspected. The change also removes the containment structure and the containment enclosure structure from the surveillance requirements of TRil-4.7.9.5.1 and removes the containment air locks from the surveillance requirements of TR11-4.7.9.5.2. These components are surveilled according to Technical Specification Surveillance Requirements 4.6.1.2 and 4.6.1.3.
sal'ETY EVAI.tfATION St31stARY: The UFCR changed procedures described in the UFSAR because the Technical Requirements are included in Chapter 16. The safety evaluation concluded that in the cases where fire rated assemblies were inaccessible or obstructed that credit could be taken for the original documented inspection performed prior to the installation of the obstruction. It was also conciuded that fire rated assemblies in high radiation areas should be considered temporarily or permanently inaccessible due to ALARA concerns. The safety evaluation determined that the change did not involve an unreviewed safety question.
UrnATEn FINAL, SAI ETY ANAtJsts REPORT CIIANGE REQtT.sT (UFCR) Nt3tHER: 94-006 Ti t i.E: Technical Requirement 7 Revision St3ntruv DEsentrilON AND Pt nrOsE: This UFCR revises the surveillance requirement for the Fire Suppression Water System that demonstrates the operability of the fire pump diesel engines. The new surveillance will verify that new fuel is diesel and is free of water and paniculates prior to adding the fuel to the storage tanks and thereafter every 92 days. The requirement to verify proper color by the clear bright test,(ASTM-D4176-82), is being deleted because the diesel fuel for non-over-the-road use is dyed to distinguish it from highway taxed fuel. The dyed fuel cannot pass the color test.
SAFETY EVAL.L'ATION St3 DIARY: The UFCR made changes to procedures described in the UFSAR. The safety evaluation concluded that there are no equipment modifications and that the operation, design basis or failure modes of the Fire Protection System are unafTeeted by the UFCR. The safety evaluation determined that the change did not involve an unreviewed safety question.
UFCR 94-006 UrnA1En FINA1, S u ETY ANAt.Ysts REPOur CliANGE REQt'EST (UFCR) Nt3tnEn: 94-008 TITI.E: Spent Fuel Pool Cooling St3ntAny DEsCHirTION AND PL'RPGsE: This UFCR revises the UFSAR to reflect a change in operational philosophy that includes a full core offload as part of a normal refueling outage operation.
The change in operational philosophy is desired to preclude the need for complex, high risk mid-loop operation when steam generator noule dams are installed and removed. The adequacy of the Spent Fuel r
Pool Cooling System to remove the additional decay heat added by the full core ofiload was evaluated arid found to be acceptable.
SAFETY EYALUATION SU31%1ARY: The UFCR made changes to the facility as described in .
UFSAR Section 9.1.3.1. The safety evaluation concluded that the change in operational philosophy to [
perform a full core offload routinely during refueling operation did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANALYSIS REPORT CIIANGE REQUEST (UFCR) NUMBER: 94-009 TITI.E: Met System UFSAR Changes SUM %tARY DESCRIPTION AND PrRPGsE: The UFCR revises the text of the UFSAR that describes the Meteorological Monitoring System. Specifically the text was made more general by deleting references to specific manufacturer names, model numbers and performance specifications with references to generic instrument types and Regulatory Guide 1.97 performance criteria. The change was made to allow for replacing system components with compatible units without requiring a subsequent change to '
the UFSAR.
SAFETY EYALUATION
SUMMARY
- The UFCR made changes to the facility as described in i UFSAR Section 2.3.3.3 and Tables 2.3-37 and 7.5-1. The safety evaluation concluded that the commitments to meet Regulatory Guides 1.23 and 1.97 for meteorological monitoring system criteria are unaffected by this change and that the efTectiveness of the meteorological monitoring system was not l compromised. The safety evaluation determined that the change does not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANALYSIS REPORT CllANGE REQUEST (UFCR) NUMBER: 94-010 TITt E: MSIV Instrument Valve Tagging
SUMMARY
DESCRIPTION AND PrRPOSE: This administrative drawing change relocates the instrument air supply valves for the Main Steam Isolation Valves (MSIV) from the associated MSIV loop drawings to the corresponding lustrument Air System P&lDs. The modification enhances the level of detail on the Instrument Air drawings but does not involve any change to the facility as described in the UFSAR text.
SAFETY EYALUATION
SUMMARY
- The UFCR was issued to provide additional detail to '
Figure 9.3-6 that only reflects the original design and does not constitute a change in the facility or procedures as described in the UFSAR nor does it involve tests or experiments not described in the UFSAR. The safety evaluation determined that this change did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANALYSIS REPORT CilANGE REQUEST (UFCR) NUMtiER: 94 015 TITI.E: Cycle 4 Boron Dilution Analysis SrMMARY DESCRIPFION AND Pt RPGsE: This UFCR modifies the UFSAR to reflect the results of the Cycle 4 boron dilution analysis. The current description of the boron dilution analysis in the UFSAR
i r describes the results of the Cycle 3 analysis. The Cycle 4 analysis determined that throttling of the Reactor Makeup Water (RMW) flow rate is not necessary during Mode 6 and also reflects a change in the assumed rod position from an All Rods Out (ARO) condition to an All Rods In less the highest wonh assembly (ARI-Stuck) condition. I SAFETY EVALUATION StatstARY: The UFCR changed the facility as described in UFSAR Section 15.4-6 and Table 15.4-1. Funher, the UFCR changed refueling procedures that are described in the UFSAR. The safety evaluation determined that the deletion of a throttling valve rcquirement in the ;
non-safety related RMW system and the prohibition of control rod " shuffling" in the reactor vessel during l refueling operations were necessary to support certain assumptions made in the boron dilution analysis for Cycle 4 but that these changes in operation did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANAIJslS REPORT CIIANGE REQt EST (UFCR) NIStBER: 94-021 TITLE: Reactor Coolant Chemistry Update to UFSAR StatstARY DESCRIPTION AND 1*l RPOSE: This UFCR updates the UFSAR to reflect the adoption of the EPRI chemistry program in place ,f the Westinghouse chemistry program. The EPRI program is more current than the Westinghouse program and incorporates input from a consortium of utilities as well as vendors including Westinghouse. Changes in parameter analysis and operating limits have occurred in response to information gained through operating experience. New methods and levels of detection have been deveioped and sample types, location, and purpose have been revised to reflect current practices.
StrETY EVAtt!ATION StatstARY: The inclusion of additional chemistry programs changed procedures described in the UFSAR. The safety evaluation concluded that updating the UFSAR chemistry program to reflect practices endorsed by EPRI allows the station to predict situations that involve potential changes to chemistry conditions in various systems. The update represents improvements that provide greater protection from chemistry upset to equipment important to safety. The safety evaluation determined that the UFCR change did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANAIXSis REPORT CIIANGE REQt EST (UFCR) NtatBER: 94-023 TITLE: Accumulator Water Level and Pressure Instrument Test Interval Extension StatstARY DESCRIPTION AND Pt'RPOSE: This UFCR and Technical Requirements change extends the test frequency from monthly to quanerly for the eight level transmitters and eight pressure transmitters associated with the stre ty injection accumulator tanks. The change is consistent with the industry recognition that operabilit/ of accumulator instrumentation is not directly related to the capability of the accumulators to perform their safety function. The surveillance testing requirement was recently removed from Technical Specifications and placed in the Technical Requirements Manual by License Amendment No. 30 (submitted to the USNRC as LAR 93-14).
SAFETY EVAL.t!AllON St31stARY: The UFCR changed procedures described in UFSAR Chapter 16, Technical Requirement 17 and the Technical Requirements Manual, Technical Requirement 17 necessitating a change to the test frequency for the analog channel operational test (ACOT) of the accumulator level and pressure channels. The safety evaluation concluded that this change is acceptable because of the high reliability of the instruments that has been verified over years of operating experience
1 P and because the instruments are not necessary for the accumulator tanks to perform their safety function.
The safety evaluation determined that the change did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANALYSIS REPORT CilANGE REQUEST (UFCR) NU5tBER: 94-033 TITLE: UFSAR Change Request for OIR 94-080 i
SU3IStARY DESCRIPTION AND PURPOSE: Certain statements contained in UFSAR Section 6.3, ;
Emergency Core Cooling System (ECCS) have been identified as being ambiguous. Operational Information Report (OIR)94-080 identified an apparent restriction in performing an integrated ECCS test ;
which introduces flow into the Reactor Coolant System. The evaluation determined that this interpretation was incorrect but that the associated ambiguity should be removed. !
SAFETY EYALUATION SUststARY: The UFCR made changes to procedures described in the l UFSAR. The safety evaluation concluded that the revisions being made eliminated ambiguities in the UFSAR description of ECCS actuation testing. No functional requirements of the Emergency Core ,
Cooling System were affected by the UFSAR revisions made by UFCR 94-033. The safety evaluation i determined that the change did not involve an unreviewed safety question. ,
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UPDATED FINAL SAFETY ANALYSIS REPORT CilANGE REQUEST (UFCR) NU5tBER: 94-035 j TITLE: Remote Safe Shutdown Equipment i SU313tARY DFSCRIPTION AND Pi RPGsE: Change to UFSAR Table 7.4-1, Equipment Required For ;
Safe Shutdown, corrects inconsistencies between the UFSAR and operating procedures OS1200.02, l
OS1200.02A and OS1200.02B. Specific changes include the addition of local CST level instrument [
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1-CO-LIS-4052, Spent Fuel Pool Cooling Pumps 1-SF-P-10A and B, Gravity Feed Boration Valves 1-CS-V-410,416, and 1207, Thermal Barrier Cooling Pumps 1-CC-P-322A at.d B to Table 7.4-1 and the deletion of Safety Injection Pumps 1-SI-P-6A and B from Table 7.4-1. This change also corrects a minor numbering problem for SSPS Train B Output Panel.
SAFETY EYALUADON SUststARY: This represents a change to the Remote Safe Shutdown l system as described in the UFSAR. The updated information corrects identified inconsistencies between l UFSAR Table 7.4-1 and the current remote safe shutdown operating procedures. The safety evaluation I concluded that this change did not involve an unreviewed safety question. j i
l UrDATED FINAL SAFETY ANALYSIS REPORT CilANGE REQt EST (UFCR) NU3tHER: 94-039 TITLE: Delete Specific Coating Product identification From UFSAR SUststARY DESCRIPTION AND PURPOSE: The UFSAR lists applicable ANSI standards for coatings (paints). Additionally, it identifies specific coatings (paints) by manufacturer and product number. The specific manufacturer and product number information is not necessary as part of the design basis. A commitment to such specifics limits flexibility in using new or different products without having to repeatedly revise the UFSAR. The design basis requires that coatings meet specific ANSI standards, in support of Regulatory Guide 1.54, and therefore the UFSAR was revised to only include that information.
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SAFETY EVAttfATION S131%IARY: He 10CFR50.59 evaluation of this change determined that this represented a change to the facility and procedures as described in the UFSAR. Specific manufacturer and product information as well as specifications of Dry Film Thickness or final coating thickness were !
deleted from UFSAR Sections 1.8,3.8.1.6, and 6.l(B).2. The applicable ANSI standards are maintained ,
and station procedures will continue to identify Dry Film Thickness for each product. The safety ,
evaluation determined that this change was editorial in nature and did not involve an unreviewed safety !
question.
UPDAnn FINAL SAFETY ANALYSIS REPORT CIIANGE REQt'EST (UFCR) Nt3tBER: 94-040 TITLE: Primary Chemistry Control Program l St3t%iARY DESCRIPTION AND Pl'RPOSE: This change revises the chemistry specifications for the Reactor Makeup Water System, allowing for the specific conductivity limit to exceed 0.3 MicroMhos/cm.
at 25 C. The specific conductivity limit of 0.3 MicroMhos/cm. at 25 C is difficult to maintain due to carbon dioxide absorption. Current industry guidance does not include conductivity as a guideline value for the reactor makeup water. Analysis ofindividual contaminants is used under current methods, rather ,
than gross measurements for conductivity, in determining the acceptability of reactor makeup water. !
SAFETY EVAltfATION St31',tARY: This change affects the chemistry requirements for the i Reactor Makeup Water System specified in UFFAR Table 9.2-17, and constitutes a change to the station chemistry program and procedures. Because a7alysis ofother parameters specified under station chemistry procedures is performed to current analytical limits and effectively bounds the water quality within the +
NSSS vendor requirements, the use of generat measurements for conductivity is no longer a determining factor for acceptability in all cases. The safety -valuation concluded that this change did not involve an ,
unreviewed safety question. {
UPDATEn FINAL SAFETY ANALYSIS REPORT CIIANGE REQL EST (UFCR) NtatiiER: 94-041 TITLE: Temperature Requirement for CGCS Tubing IIcat Tracing i
St31%1ARY DESCRIPTION AND Pt'RPOSE: This UFCR reflects a change in the required CGCS l hydrogen sample line temperature requirement from a nominal 300"F to the required greater than or equal <
to 278'F. This 278*F temperature will maintain any possible steam content of the sample in a slightly l superheated condition which will preclude any condensate formation. j SAFETY EVAlliATION St31%lARY: The UFCR changed UFSAR Section 6.2.5.2. The safety j evaluation concluded that the change only clarifies the design basis requirement for the sample tubing heat 1 tracing and that the systems ability to monitor hydrogen gas concentrations will not be affected. The heat tracing will continue to operate at a nominal temperature of 300 F. The safety evaluation determined that '
the change did not involve an unreviewed safety question.
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UPDATED FINAL SAFETY ANALYSIS REPORT CIIANGE REQtTST (UFCR) NUslBER: 94-043 TITLE: Station Blackout '
St31%IARY DESCRIPTION AND PURPOSE: This UFCR incorporates station blackout information per Regulatory Guide 1.155. North Atlantic has submitted information to the NRC documentating compliance with 10CFR50.63, " Loss of All Attemating Current Power". The NRC reviewed and issued a Safety Evaluation Report on this subject.
SAFETY EVALUATION SU%1%IARY: The UFCR changed UFSAR Sections 8.4 and 15.9 and Figure 15.0-12 and also incorporated new station blackout procedures. The safety evaluation concluded that since this administrative change does not involve any hardware, the operation of the plant is unaffected. The safety evaluation determined that the change did not involve an unreviewed safety ,
question.
UPDATED FINAL SAlElY ANA!.YSIS REPORT CIIANGE REQUEST (UFCR) NU3tBER: 94-044 TITLE: Revision of the Tornado Protection Status of Three Seismic Category 1 Structures St31.%IARY DESCRIPTION AND PrRPOSE: This UFCR revised certain tornado design criteria. The site specific tornado design criteria was deleted and the tornado protection status of three Seismic Category i i structures was changed from "open" to " closed".
SAFETY EVAL UATION Sl31%IARY: The UFCR changed UFSAR Sections 1.8, 2.2, 2.3, and 3.3. The safety evaluation concluded that all safety-related structures and components were reevaluated and shown to meet the original design basis tornado criteria and that the design or function of any safety-related system, structure or component was not changed. The safety evaluation determined that the change did not involve an unreviewed safety question.
UPDATED FINAL SAFETY ANALYSIS REPORT CilANGE REQUEST (UFCR) NUhlBER: 94-047 TITLE: UFSAR Change Request in Response to ESAR 94-012 StantARY DESCRIPTION ann PrRPOSE: This UFCR corrects invalid valve positions and clarifies potential leak paths associated with certain containment isolation valves. Specifically this UFCR brings the UFSAR into agreement with the design changes made by DCR 90-032. That DCR did not change the UFSAR to reflect the change in containment isolation valves on the steam driven emergency feedwater pump from hts-V127 and h1S-V128 to hiS-V393 and hiS-V394.
SAFETY EVAL.UATION S131NIARY: The UFCR changed UFSAR Section 6.2.4.2 and Table 6.2-83. The safety evaluation concluded that the changes merely incorporate the normal operating position of the subject containment isolation valves and also determined that any leakage path through these valves is bounded by the steam generator tube rupture accident analysis. The safety evaluation determined that the change did not involve an unreviewed safety question.
UPnATEt> FINAL SAFETY ANALYSIS REPORT CIIANGE REQt EsT (UFCR) NtisinEn: 94-062 Tm.E: Revisions to UFSAR Chapters 13 and 17 i
St!ht3fARY DESCRIPTION AND PL'RPosE: This UFCR incorporates recent changes made to the North .
Atlantic Energy Service Company (North Atlantic) organization that are aimed at improving efficiencies and communications as well as eliminate redundant functions. The change also reflects recent NRC approval to eliminate certain required biennial procedure reviews.
SAFETY EVAI.tfATION SUst%IARY: The UFCl changed UFSAR Sections l 3.1 and 17.2, Table 17B-1, and Figures 13.1-2 and 17-2. The safety evaluation concluded that the organizational changes and the change in procedure review policy do not change the design, function, or method of performing the function of any plant component, system or structure. The change does not reduce the knowledge of the i organization, or qualifications or skills of the workers and does not effect review and suppon functions currently in place. The safety evaluation determined that the change did not involve an unreviewed safety question. i a
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January 31,1995 i l
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i ENCLOSURE 2 TO NYN-95010 i i
Summaries of the Remaining 10CFR50.59 Safety Evaluations ;
Performed for Temporary Modifications, Procedure Changes, Commitment Changes, and Miscellaneous Changes ;
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TEMPORARY MODIFICATIONS (TMODs) ,
ne 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 modification. Each safety evaluation concluded that the TMOD did not involve an unreviewed safety question. Summaries of these TMODS and their safety Evaluations are provided below.
TENIPORARY MODirlCATION (TMOD) NU3tBER: 93-022 Tm E: Plugging of Floor Drains 226 and 267-Service Water Slot l
SU3131ARY DESCRIPTION AND Pt RPOSE: his temporary modification installed two floor drain plugs l in the floor drains of the service water slot on elevation 53' of the Primary Auxiliary Building (PAB).
It was identified that these floor drains have the potential to provide an unmonitored release path should i leakage occur from Containment Building Spray (CBS) components, CBS-V-129,133 and CBS-LT-2338.
A permanent design modification (MMOD 94-547) has been approved and is planned for future l installation. !
SAFETY EVALUATION SU3t%IARY: The TMOD made changes in the facility as described in the UFSAR. The drains afTected by this temporary modification are not designed to contain a liigh Energy Line Break (IIELB) or any large line break. The plugged drains will not allow any significant j water buildup on the 53' elevation of the service water slot, since there is an open grate to the 25' l elevation service water slot. An water cascading down to the 25' elevation would flow into the normal l plant drain system and would be transported to the Waste Liquid Drain (WLD) system for processing. ]
The safety evaluation determined that the change did not involve an unreviewed safety question.
i TE%IPORARY MODIFICATION (TMOD) NU3tnER: 93-038 l
TITI.E: Condenser Waterbox Level Indication SUststARY DESCRIPTION AND Pt RPGsE: This temporary modification installed tygon tubing on the ;
three condenser waterboxes to measure waterbox level. The tygon tubing is only used when the waterbox !
is out of service. During normal operation, the tygon tubing is valved out of service. The tygon tubing ;
was installed to assist station personnel in locating a leak in the condenser. '
SAFETY EYAl.UATION SU313tARY: The TMOD made changes in the facility as described in !
the UFSAR. The Circulating Water System is not a safety related system. Should a leak occur in the tygon tubing, valves are available to isolate the tubing. The safety evaluation determined that this modification did not involve an unreviewed safety question.
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TEsIPORARY MODIFICATION (TMOD) Nt:stBER: 94-008 Tiit.E: BTRS Jumper Installation St:ststARY DESCRIPTION AND Pl'RPGsE: This TMOD installed threejumpers in the control circuits of the Boron Thermal Regeneration System (BTRS) to allow for system operation in the dilute mode.
Thesejumpers eliminate the need to operate the associated BTRS chiller unit but pennit operation of an associated heat exchanger that will effect letdown stream cooling and consequent boron dilution. The TMOD will become permanent at a later date when MMOD 94-564 is implemented.
SArETY EVAEtfATION StisistARY: The TMOD made changes to the facility as described in the UFSAR. The UFSAR includes discussion regarding the use of the chiller unit to cool the letdown stream but this TMOD precludes use of the described chiller. The safety evaluation concluded that the TMOD only affects operation of the BTRS system which performs no safety function and is not used during post accident recovery. The safety evaluation also concluded that the operation of the system in the Dilute mode would have no impact on any boron dilution accident addressed in Technical Specification 3.1.2.7. The safety evaluation determined that the TMOD did not involve an unreviewed safety question.
TEstPORARY MODIFICATION (TMOD) NitsinER: 94-019 TITI.E: Steam Generator Blowdown - Lead Cation Demineralizer SttsistARY DESCRIPTION AND Pt'RPGsE: This TMOD converted Steam Generator Blowdown (SB) mixed bed demineralizer SB-DM-28A to a lead cation demineralizer and provided a flow path from SB-DM-28A to SB-DM-28B/C. The change was implemented to enhance blowdown reclaim and reduce the frequency of mixed bed regenerations caused by the use of Ethanolamine (ETA).
SAFETY EVAEt'ATION St'ststARY: The TMOD made changes to the facility as described in the UFSAR since Figure 10.4-13 was affected. The safety evaluation concluded that the affected portion of the blowdown system has no safety function, nor is its performance necessary or required during or after an accident. The new configuration of the SB system extends mixed bed service runs and compensates for cation depletion attributed to ETA addition. The modification enhances the system's ability to remove impurities from the plant secondary water system and to maintain the secondary water chemistry within existing specification, thereby maximizing the service life of the steam generators. The safety evaluation detemiined that the TMOD did not involve an unreviewed safety question.
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COMMITMENT CHANGE REQUESTS (CCRs)
The following CCRs, not related to UFCRs, DCRs or MMODs, were approved. A safety evaluation was perfonned for each CCR. Each safety evaluation concluded that the CCR did not involve an unreviewed safety question. Summaries of these CCRs and their safety evaluations are provided below.
COststIDIENT CIIANGE REQt'EST Nt3tBEn: 94-01 Tm.E: Periodic Verification of Auxiliary Operator Rounds Si31stAny DEsenIPilON AND Pt nrosE: The commitment made to verify proper performance of roving Nuclear System Operator (NSO) [formerly Auxiliary Operators] rounds on a daily basis was a conservative short term measure. Afler conducting the surveillance procedure on a daily basis for approximately eight months, no discrepancies were identified with Primary NSO rounds and two satisfactory explained discrepancies were found with roving NSO rounds. Since November 1992, this surveillance has been performed bi-weekly for seventeen months with no discrepancies noted. After performing a safety evaluation this commitment was reduced to perform the surveillance quarterly.
SAirTY EYAI.t!ATION Sl3tstAnY: The CCR did not make changes in the facility as described in the UFSAR. The probability or consequences of an accident previously evaluated in the UFSAR will not be increased since this change does not directly affect plant design or equipment configuration. This change does not affect the manner in which an NSO operates and monitors plant equipment. No accident evaluated in the UFSAR explicitly depends on the frequency of verifying Roving NSO performance of rounds and log keeping. The safety evaluation concluded that the commitment change did not involve an unreviewed safety question.
Costsiinti:NT CIIANGE REQt EsT Nt3tBER: 94-02 Tirl.E: Electrical Cable Insulation Resistance Testing Requirements St31stARY DESCRIPTION AND Pt'nrosE: Seabrook Station previously committed to perform megger insulation testing on a number of cable systems. Based on EPRI Report NP '/485s it has been determined that this is not the most effective method fbr determining detenoration of cable insulation. Based on a safety evaluation Seabrook Station modified the cable insulation monitoring program to supplement and/or replac- meggering with visual inspections on most cable systems.
SWETY EYAI tfATION St31stAny: The CCR did not make changes in the facility as described in the UFSAR. The probability or consequences of an accident previously evaluated in the UFSAR will not be increased. The change does not efTect the design, function, or method of performing the function of any plant component, system, or structure as described in the UFSAR. The incorporation of visual cable inspection, in addition to the cable meggering performed with selective loads, will increase the re iability of cable operability. The EPRI NP-7485s Report provided several conclusions which supported the elimination of " cable megger testing" in determining cable operability. The safety evaluation concluded that the commitment change did not involve an unreviewed safety question.
CostMITMENT CilANGE REQt'EST Ntaintu: 94-04 TITI.E: Receipt of Technical Information From NSSS Vendor StatMAny DESCRIPTION AND Pt'RPOSE: North Atlantic made a commitment to the NRC in response to Generic Letter 90-03 to establish contact with Westinghouse on an annual basis in order to verify the continued receipt of applicable technical information. The basis of this commitment is a statement in Generic Letter 90-03 that an adequate vendor interface program should include provision for assuring receipt by the licensee of all technical information provided by the NSSS vendor. Subsequent to this commitment, North Atlantic determined that annually requesting updated 1:chnical information from Westinghouse is unnecessary since Westinghouse has stated that all information necessary for the proper and safe installation, operation, maintenance or repair of Westinghouse supplied equipment or parts in ,
nuclear applications is provided in periodic Technical Bulletins. Moreover, these Technical Bulletins are controlled documents and are accompanied by a return receipt. Based on this information, North Atlantic has determined that proper internal administrative control of these Technical Bulletins makes annual contact with Westinghouse for the purpose of verifying the receipt of technical information redundant and unnecessary.
SAFETY EVAL t!ATION StatMARY: The CCR did not make changes in the facility as described in the UFSAR. Revising the commitment to establish annual contact with Westinghouse for the purpose of verifying receipt does not increase the probability of any accident evaluated in the UFSAR or a malfunction of equipment important to safety. The source of the commitment is a statement in Generic Letter 90 03 that an adequate vendor interface program should include provision for assuring receipt by the licensee of all technical information provided by the NSSS vendor. Revising this commitment is based on a statement by Westinghouse that all necessary information for the proper and safe installation, operation maintenance or repair of Westinghouse supplied equipment or parts in nuclear applications is provided in periodic Technical Bulletins, and these Technical Bulletins are controlled documents are accompanied by return receipt. The safety evaluation concluded that the commitment 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 10CFR 50.59 Report. A safety evaluation as defhed in the requirements for 10CFR50.59, was not required but in each case 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.
PROGRAst CilANGE:
TITEE: Use of Ethanolamine and Morpholine for Secondary System Chemistry Control StiststARY DESCRIPTION AND Pt RPGst: The change to the secondary system chemistry involves the use of Ethanolamine and Morpholine for pl-1 and wet layup control resp. .ely. Ethanolamine and Morpholine are both amines approved by EPRI PWR Guidelines, Rev. 3, which is the basis for the secondary chemistry control program.
SAFETY EVAIFATION St!ststARY: The safety evaluation determined that the addition of Ethanolamine in the feedwater system and Morpholine in the steam generators for wet layup did not involve an unreviewed safety question. The use of these amines will increase the life and efficiency of the steam generators by reducing both secondary system iron transport and erosion / corrosion.
ENGINEERING EVAIFATION: 93-021 TITEE: Compensatory Ventilation Plans StatstARY DESCIOPTION AND Pt'RPOSE: The purpose of this evaluation was to determine compensatory actions that could be taken to provide alternate methods of building cooling and ventilating when supporting safety-related IIVAC components are not functional. Each plan was analyzed and qualified using the design basis cooling load associated with its corresponding environmental zone during normal, abnormal and accident conditions. Whenever implementation of compensatory ventilation actions necessitates breaching plant barriers, appropriate administrative actions will be taken. In addition, the analysis established the heat-up rate for each room assuming maximum design basis cooling load and a complete loss of ventilation.
SArETY EVAixATION St:ststARY: This engineering evaluation was performed to identify compensatory actions that could be taken to provide alternate cooling when the supporting safety-related IIVAC components are unavailable. The review concluded that compensatory ventilation actions will maintain building room temperatures below the limiting equipment qualification temperatures. The safety i evaluation determined that compensatory ventilation actions could be taken and an unreviewed safety question did not exist.
TFCIINICAL SI'PPORT EVAttiATION: 93TSEV006 TITI.E: Removal ofInterlock Between Service Water Ocean Pumps and Service Water Cooling Tower Pump Discharge Valves During Maintenance / Testing On Cooling Water Pump Discharge Valve (SW-V-25 or 54)
StT31%lARY DESCRIPTION AND Pl'RPOSE: The design of the control circuits for the Service Water Ocean pumps and Service Water Cooling Tower pumps include an interlock from the associated pump discharge valves. If maintenance activities are necessary on the cooling tower discharge valves, one train of Service Water could be rendered inoperable following a LOP. A Standing Ograting Order (93-015) was issued to prevent this possibility. The operating order requires action to defeat the interlock during maintenance activities to prevent the undesired inoperability condition.
SAFETY EVAL.tIATION St'%t%1ARY: The safety evaluation concluded that the instructions in the Standing Operating Order, when followed, constituted a system configuration that is difTerent than that described in the UFSAR. The safety evaluation concluded the Standing Operating Order configuration ensured that the train related Service Water pump would auto start should a LOP occur during the performance of maintenance / testing activities. Since instructions to return the system configuration to normal are included in the standing order and appropriate Technical Specification Action requirements are followed, it was determined that no compromise in safety resulted. The safety evaluation determined that the change did not involve an unreviewed safety evaluation.
PROCEnt'RE CllANGE: OS1023.68, Rev. 8 TITLE: Containment Air Purge System Operation Stt%1%IARY DESCRIPTION AND PL'RPGsE: Procedure OS1023.68 " Containment Air Purge System Operation" was revised to allow for a change in system operation. The procedure change allowed for running the containment exhaust fans with the associated supply fans isolated. The new system configuration maintains the containment building at a slightly negative atmospheric pressure with the containment equipment hatch removed and the Kelly Enclosure Panel installed by drawing in outside air.
This alignment eliminates the potential for exfiltration from containment during refueling operation with the hatch open while still providing containment environmental controls regarding temperature limits and tritium levels.
SAFETY EVAlt!ATION Sl!%INIARY: The safety evaluation concluded that the procedure change does represent a change to the facility as described in the UFSAR. The safety evaluation concluded that using an alternate supply air path to the non-safety related air handling system did not increase the probability of, or increase the consequences of an accident, nor did it compromise any accident mitigation action. The procedure change included limitations on outside air temperature that could be drawn in so that temperature limitations for equipment located inside containment would not be exceeded. The procedure change did not alter the design function or operation of any safety-related equipment. The safety evaluation determined that the procedure change did not involve an unreviewed safety question. ]
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LICENSEE EVENT REPORT CO% silTstENT CIIANGE:
Tirt.E: Deletion of LER 92-07 Corrective Action Number 8 ,
- St:ststAny DESCRIPTION AND PI'nrosE: Corrective action #8 of LER 92-07 specified that a Technical Clarification would be developed listing all equipment required to be OPERABLE on a given train when the opposite train Emergency Diesel Generator (EDG) was inoperable. Further evaluation of this proposed action determined that no benefit would be derived from this clarification since it would only reiterate information that is already available in Technical Specifications and the UFSAR.
Duplicating guidance already provided introduces the rek that guidance necessary for specific plant ;
conditions will not be included. Additionally, such a clarification would require constant review to reflect any future design changes which is presently outside the scope of the station design control process.
SAFETY EVA1.tIATION St!ststAny: The safety evaluation concluded that the rescinding of an LER corrective action did not represent a change to the facility as described in the UFSAR. The proposed Technical Clarification was identified as an enhancement at the time the corrective actions were identified in LER 92-007. However it has been determined that the Technical Clarification is no longer necded.
The safety evaluation concluded that this revision did not involve an unreviewed safety question.
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North Atlantic January 31,1995 ENCLOSURE 3 TO NYN-95010 Listing of 10CFR50.59 Safety Evaluations Completed But Not Required Pursuant to 10CFR50.59
DESIGN COORDINATION RF, PORTS (DCRs):
Design modifications described in the following Design Coordination Reports (DCRs) were installed during the period covered by this 10CFR50.59 report. These DCR's did not meet the requirements for performance of a safety evaluation as specified in 10CFR50.59, but 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 on-site for review.
NtminER: TITII:
86 DCR 041 Water Treatment Silica Analyzer 86 DCR 140 Fire Pump ilouse Donkey Boiler 86 DCR 504 Dual Bar Locks Replacement with Overlee Locks 86 DCR 523 Rotate Snubber End Brackets 90 Degrees for (29) Snubbers 86 DCR 620 GSC-CP-0195 Generator Temperature Scanner, Spare Parts Substitution 87 DCR 409 Scaling of Pipe Sleeves Di8-1 and D257-1 88 DCR 021 Spray Additive Tank Instrument Isolation Valves 88 DCR 023 Access Ladders for Various Roof Areas 88 DCR 135 Upgrade Service Water Screen Wash Pump 88 DCR 136 Reset Turning Gear Relay TDR-1 89 DCR 069 Remove Unistruts Between Critical Areas of Plant 89 DCR 082 P.epair/ Replacement of Piano Type Door Ilinges 90 DCR 008 Service Water "A" Train Supply Buried Pipe Access for Inspection 90 DCR 02? Trim Change for Level Control Valves 90 DCR 033 Level Gauge Glass Replacement 91 DCR 016 Improve Indication of St Test Line Flow 91 DCR 041 Timber Swamp Direct Transfer Trip Dual Channel Receiving Terminal 92 DCR 038 Veritrak to Rosemount Pressure Transmitter Replacement 92 DCR 044 East Air Intake Opacity Monitor 92 DCR 045 Emergency Operating Procedure Access Problems 92 DCR 048 Piano flinge Replacement Doors C101, C201, EM408 92 DCR 057 Modification of SW Pump ilouse Roof Plugs 92 DCR 064 Condenser Boot Access Platforms 92 DCR 066 New Power Panelin Admin Building 92 DCR 068 Phones at Spent Fuel Pool / Manipulator Crane
% DCR 008 Asphalt and Caustic Tank Building Monorail 93 DCR 019 Removal of Exhaust Duct for Feedpump Turbine 32A 93 DCR 024 Generator Stator Coolaut Pressure Switch Replacement 93 DCR 025 Turbine Generator EllC Signal isolation 93 DCR 026 Turbine Generator Vibration Monitoring 93 DCR 027 Fish Count House Platform 93 DCR 028 ErosiW^ nosion Program Piping Component Repiacement e .
93 DCR 031 Safety Valve Replacement on Feedwater. Condensate and Heater Drain Systems 93 DCR 032 Sewage Lagoon Oxygen Aeration 93 DCR 033 Reactor Coolant Pump Oil Collection System 93 DCR 042 Replacement of Valve MS-PV-3067 Internals 93 DCR 047 DRPI Power Supply Replacement 93 DCR OSI Very liigh Radiation Areas Barriers 93 DCR 057 EAll-DP-25A/B Damper Modifications 94 DCR 001 Reheater Drain Tank Level Connections Weld Repair 94 DCR 008 GE IIEA Lockout Relay Replacement 94 DCR 009 GE Alterex Exciter Oil Deflector Rings Replacement 94 DCR 017 RCP TVS Design 94 DCR 018 RCP Motor Removal Interferences MINOR MODIFICATIONS (MMODs):
Design modificatiou described in the following Minor Modifications (MMODs) w ere installed during the period covered by this 10CFR50.59 report. These MMOD's did not meet the requirements for performance of a safety evaluation a specified in 10CFR50.59 but safety evaluations were performed for conservatism. Each safety evaluation concluded that the MMOD did not involve an unreviewe.1 safety question. The documentation for each MMOD listed below is available on-site for review.
NtNnEn: TITt.E:
90 MMOD 513 DM Flush Vent and Sample Line 90 MMOD 534 Turbine Building Sump 1 A Modification 90 MMOD 651 liigh Rad Area Door Padlocks 90 MMOD 675 Door EM-409 and P-415 Lockset Replacement 91 MMOD 516 SS-CP-166B Drain Line Re-Route 91 MMOD 533 Valve 1-CBS-V-006,010,016,024 Modifications 91 MMOD 562 AB Stack Drain Flange Additions 91 MMOD 573 Sanitary Lift Station #5 Relay Wiring Change 91 MMOD 589 Silencing of Fire Alarm llorn in SAS 91 MMOD 603 Lube Oil System Sample Points 91 MMOD 619 Miscellaneous Emergency Lights 91 MMOD 624 Spray Additive Tank Recire Equipment Storage 91 MMOD 643 Guard flouse Elevator Fusible Disconnect Switch Installation 92 MMOD 509 Purge Line Isolation Details for Radiation Monitoring Skids 1-RM-SKD-83, 84,85,86 and 87 92 MMOD 511 Bypass Inoperable Indication for MS-V-127 and MS-V-128 92 MMOD 515 Emergency Feedwater Pumphouse Plug Fire Seals 92 MMOD 538 Cire Water / Service Water Travelling Screens Cathodic Protection 92 MMOD 548 Type C LLRT Relief Valve Discharge Pipe Couplings 92 MMOD 570 Bus E5 and E6 Replacement Lockout Relays 92 MMOD 571 Selected Cryofit Testing 92 MMOD 580 Main Feedpump Governor System Power Supplies e ,
92 MMOD 582 Fire Detection Control Panels - Unsupervised Power 92 MMOD 583 Pressurizer Enclosure Platform Modification 92 MMOD 588 SB System Caustic / Acid Piping Replacement 93 MMOD 504 Iso-Phase Bus Duct Cooling Unit Dampers 93 MMOD 505 Revise the Moisture Separator Removal Reheat Steam Low Load Valve Limit Switch Wiring 93 MMOD 506 Atmospheric Steam Dump Valves Bailey Positioner - Assembly Substitution from Model AP21210C to Model AVil2100 93 MMOD 509 Vibration Reduction of Miscellaneous Plant Systems 93 MMOD 511 T-G Seal Oil Filter Drain Isolation Valve 93 MMOD 514 GFI Circuit Breaker Installation in CW Pump !!ouse 93 MMOD 515 Add Connection to PAB Roof Drain for SW Strainer Draining 93 MMOD 519 Eiger Static Transfer Switch Logic Board Revisions 93 MMOD 527 CRD Unlatching Tool llose Connection Mods and Shoulder Bolt Replacement 93 MMOD 530 Telephone Near Eyewash Station (SGBD) 93 MMOD $31 125 VDC Switchgear Bus 1IC Alternate Supply Breaker Setpoint Change 93 MMOD 534 Safety Related UPS and Static Transfer Switch Setpoints 93 MMOD 541 LO Storage Bldg lleater Trap 1-ASC-r312 Orifice Change 93 MMOD 543 Sersice Water Pump ilouse Associated Circuit Protective Devices 93 MMOD 546 Splice Box for flydrogen Gas Alarm Cab'e 93 MMOD 549 Relief Line Modifications for FW lleaten. FW-E-26A&B 93 MMOD 552 Instrument iloist for Service Water Cooling Tower 93 MMOD 556 Ilot Leg Recirculation Throttle Valve Adjustment 93 MMOD 558 Welded Eye Rod Replacement on Pipe Supports MS-SV-3 and MS-SV-10 93 MMOD 560 Snubber Removal on Support 81-RM 33 94 MMOD 502 TG EllC Filter Isolation Valve 94 MMOD 507 MSIV Fluid Reservoir 94 MMOD 508 Startup Feed Pump Low Suction Pressure Protection Switch Replacement 94 MMOD 517 Resize Circuit Protective Devices for CAS-CP-556 l 94 MMOD 513 Equipment llatch Shield Wall Tensioning Rods !
94 MMOD 519 DM-V517 Valve Replacement ;
94 MMOD 520 Polar Crane Bolting j 94 MMOD 521 Nuclear instrumentation Audio Count Rateffimer Scaler Replacement i 94 MMOD 523 Resin Sluice Piping and Support Modifications 94 MMOD 527 Feedwater Isolation Valve Pressure Switch Setpoint Change 94 MMOD 528 Primary Component Cooling Water Channel licad Flow Straightener 94 MMOD 529 Main Generator Out-of-Step Protective Relay Wiring Change 94 MMOD 531 Emergency Air Cleaning Unit liigh lleater Temperature Setpoint Change 94 MMOD 533 Comroi Panel Separation Corrections 94 MMOD 539 RAT Backup Relay Contact Wiring Discrepancy 94 MMOD 541 OTDT Uncertainty Considerations 94 MMOD 542 Main Turbine Generator Emergency Hearing Oil Pump Timer Setpoint Change 3-
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RESTORED TEMPORARY MODIFICATIONS (TMODs):
The following Temporary Modifications (TMODs) were installed during the period covered by this 10CFR50.59 Report, and have since been removed. The affected equipment has been restored to its normal configuration. In each case, a safety evaluation was performed. Each safety evaluation concluded that the TMOD did not involve an unreviewed safety question. The documentation for each TMOD listed below is available on-site for review, NtminER: TartI:
93 TMOD 004 Install Clamp and Pump With Sealant to Repair Leak on SB-V9 93 TMOD 013 Provide Alternate Suction and Discharge Paths for Jockey Pumps to Maintain Pressure During Piping Replacement 93 TMOD 014 Install Temporary Relief at Fire flydrant #1 93 TMOD 018 Temporary Electrical Power to Main Control Board ;
93 TMOD 019 Removing Roughing Filters from llousing and from Containment 93 TMOD 023 Add a Flanged Outage " Fixture" to the Spare Penetration (E-29) 93 TMOD 025 Replace Defectivo Rev K Logic Drive Card with an Old Rev E Logic Drive Card ,
93 TMOD 029 Install Jumper on Relay Housing 27D-1 From Terminal 11 to 12 Node A73 on 1-EDE-SWG-6 93 TMOD 035 Install Pressure Sensing Line to Provide a System ileader Pressure Signal !
to the Temporary Compressors 93 TMOD 039 Install Connection to llookup Backup Air Compressor to SA-V5 93 TMOD 042 Temporary Source of Power for Load Center 3 During the Bus 4 Outage i 94 TMOD 001 Temporary Monitor System While the Main Plant Computer is Being ;
Replaced 1 94 TMOD 006 Supply WPB and PAB Demin Water Demands Using the RWM System l 94 TMOD 009 Fabricate and Install a Temporary Enclosure inside Double Doors C325 94 TMOD 010 Temporary Electrical Power for ED-PP-122A and ED-PP-121 A ,
94 TMOD 012 Temporary Electrical Power for 480V Power During Unit Sub 27 Outage !
94 TMOD 014 Install Blind Flanges at the SW Train B Supply and Discharge ficaders -
to Allow Isolation of the DG B IIX for Pipe Replacement r 94 TMOD 017 Install Replacement Timer-Scaler Drawer in the N1 Cabinet 94 TMOD 018 Install Necessary liardware to Provide Temporary Cooling Water from the Demin !!cader 94 TMOD 020 Supply WPB, PAB and Containment Demin Water Demands Using the RMW System l 94 TMOD 022 Temporary Cooling Towers to Facilitate the Parallel Inspection and Possible Retubing of the PCCW IIcat Exchangers (1-CC-E-17A&B) 94 TMOD 024 Temporary liardware Provides Temporary Cooling Water From the Demin IIcader !
94 TMOD 033 Jumper Ground Cell 27 in Battery 1-ED-B-2B Due to Jar Leaking in Cell 27 ;
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