ML19246B936
| ML19246B936 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/12/1979 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7907190222 | |
| Download: ML19246B936 (27) | |
Text
BALTI M O R E G AS AN D E LECTRIC CO M PANY GAS AN D CLECTRIC SUILDING B ALTl M O R E, M A RYLA N D 21203 ARTHUR C. LuN ovALL.J R.
July 12, 1979 Vic g Pa t te O E ** f s o..o Director Region I, U. S. Nuclear Rerulatory Commission Office of Inspection and Faforcenent 631 Park Avenue King of Prussia, PA 19406
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos. 1 & 2, Docket Nos. 50-317 & 50-316 Report of Chances, Tests and Exreriments Gentlemen:
As required by 10 CTR Part 50 Para rath 50.59, attached is a report of all chsnges, tests and experiments made on Calve:-- Cliffs Units 1 and/or 2 under the trovisions of that Part and coverinc the period from our last such report throuch December 31, 1978.
Items in the attached are referred to by " Facility Change Request (FCR)" number.
Very truly you
/
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'g a _s 4 cc: Director of Insrection and Enforcement (39 copies)
U. S. Nuclear Reculatory Co=insion Washington, D. C.
20555 J. A. Biddisen, Esquire G. F. Trowbridge, Esquire 343 059 7907190N #
Attachment to Lundvall letter of July 2, 1979 Page 1 of 26 Changes. Tests and Experiments Made In Accordance With 10 CFR 50 59 for Calvert Cliffs Units 1 and/or 2 Th-10 The auxiliary switch linkage and rollers on the h.16 kV circuit breakers were modified as directed by General Electric to correct a binding problem. The safety analysis concluded that this modif-ication did not constitute an unreviewed safety question because the change was made to make the h kV breakers function as criginally intended.
Th-21 This FCR added a local pressure indicator and an existing tap on the vaste gas system. This analysis concluded that this was not an unreviewed safety question, because the piping that was involved was not safety related.
Th-27 This FCR deleted a valve in the diesel air starting system. A safety analysis concluded that this was not an unreviewed safety question, because this valve, which only provides a method of a local starting of the diesel generator, is not relied upon in any of the safety analyses performed in the FSAR.
Th h2 This FCR changed the control band over which the temperature of the concentrated boric acid storage tanks is maintained. This was done to prevent spurious alarms. Since the mid point of the new range was unchanged, since the ecutrol band was made smaller, it was concluded that this change did not constitute an unreviewed safety question.
Tk-kh This FCR raised the low-level set point for the degasifier. The safety analysis concluded that since the set point was not safety-related the FCR did not constitute an unreviewed safety question.
74-53 Originally-installed cable trays and instrument tubing adjacent to the reactor head laydown area in the containment interfered with the laydown of the reactor vessel head and the cavity seal ring.
This FCR relieved this interference problem. The only portion of the FCR that was safety-related was the relocation of the tubing.
The safety analysis concluded that since the tubing was relocated and reinstalled to criteria consistent with the original instal-lation, that this change did not constitute an unreviewed safety question.
Th-56 This FCR added moisture traps upstream and downstream of the condenser vacuu= pumn discharge radiation monitor. The safety analysis for the FCR concluded that it tus not an unreviewed safety question, because the condenser vacuum pump discharge radiation monitor and the associated piping are not safety related.
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, Th-71 As originally installed, the reactor coolant pump vapor seal leak-off line was connected to the reactor coolant drain tank. Valve leakage into this tank caused a steam pressure to accumulate in the tank, and as a result, steam was being discharged to th* contain-ment atmosphere by backflow through the vapor seal leak-off lines.
This FCR was to temporarily disconnect the leak-off lines from the drain tank and run them to the containment sump. As such, this safety analysis concluded that this FCR was not an unreviewed safety question.
Th-73 Added a canopy seal to valves 1-SI-215, 225, 235, 2h5 in the safety injection system to eliminate leakage through the valve cover. The safety analysis concluded that no pressure retaining boundary was compromised, and no change in valve operability resulted, and that, therefore, no unreviewed safety question was involved.
Th-82 Revised drawings of main stea= instrument taps to reflect as-built and corrected a previous drawing error. This did not constitute an unreviewed safety question since it was a drawing change only to reflect as-built conditions. Non-safety related, but described in the FSAR.
74-83 The purification filters are equipped with a lifting eye, used in cartridge removal. The existing eye was damaged. The FCR was written to modify the lifting eye with one of a stronger design.
The safety analysis concluded that this was not an unreviewed safety question, as the pressure boundary was not violated. In addition, a pressure test was to be performed to ensure that the boundary was intact.
TL-8k Modifications to solid vaste cystem: Evaporator bottom fill line to cement mixer, resin discharge piping from meter, add piping to receive resin decant water in order to provide interim means of handling solid radioactive vaste until the permanent system can be redesigned. This did not constitute an unreviewed safety question since the lines are non-safety related, although they are described in the FSAR.
Th-95 Revise drawings of main steam turbine bypass valve, to show added instrument taps. 7ais did not constitute an unreviewed safety question since tbt taps were normally cupped and on non-instrument lines. The '. Anes are non-safety related but are described in the FSAR.
74-96 Modified set points for the Radiation Monitoring System alarms.
Safety Analysis concluded there was no unreviewed safety question because the change was to the setpoint log to make it agree with the FSAR and Technical Specifications; changes were to lover, acre conservative set points.
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. Th-101 Originally installed piping for the reactor coolant pump seal vent and the reactor coolant pump cavity drain was terminated immediately following a root valve. This FCR extended the piping to the con-tainment su=p.
The safety analysis concluded that this change did not constitute an unreviewed safety question, as the piping design was consistent with original design criteria for similar piping.
Th-110 Provided additional valves on the auxiliary steam header between the turbine building supply isolation valves and the vaste evaporators to elimir. ate vnterhammer in this piping. The safety analysis concluded that no safety related system or equipment was affected by this change.
Th-119 Changed set point of the containment sump level switch to agree with its redundant level switch. This corrects a drawing error.
The safety analysis concluded there was no unrevieved safety question because this new lover set point provides the intended redundancy.
Th-123 Relocated instrument sensing lines on the water box vacuum tank.
Safety analysis concluded no unreviewed safety question because instruments involved and their sensing lines do not interface with any safety function.
Th-127 Changed scale on low pressure safety injection (LPSI) flow indicator to agree with actual flov. The safety analysis concluded there was no unreviewed safety question because no actual change was made to the LPSI flow or to any other system.
Th-130 Installed mechanical seals on condensate booster pumps Nos.11,12 and 13 and provided service water cooling to their respective heat exchangers to replace packing glands which have resulted in excessive leakage. The safety analysis concluded that since service water was not required when the pu=ps are cut off, that service water requirements vere not increased during accident conditons and no increase in the consequences or probability of an accident would result.
Th-136 Added protective covers over the 6T Power Calculator and Teold Calculator potentiometers. The safety analysis concluded there was no unreviewed safety question because no safety functions were being modified. The change prevented accidental adjustment of these Reactor Protective System parameters.
Th-137 Removed 1/2 inch of thread from one 2-inch diameter socket cap screw on the reactor head lifting rig because of damage to the threads.
It was determined that this change did not constitute an unreviewed safety question because more than sufficient thread engagement remained following the change to allow the screv to perform its safety function.
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-h-Th-lh2 When the evaporators are shutdown, nitrogen is used as a blanketing gas. Unn startup the nitrogen must be pumped from the evaporators.
As ori,">.lly installed, the nitrogen was pumped to the vaste gas decay tanks. This nitrozen is of a relatively large volume and lov activity compared to what is present in the tanks. As such, it was desireable to put a bypass around the decay tanks to avoid filling the tanks with this gas containing little radioactivity.
As part of the safety analysis, detailed dose calculations were performed and it was concluded that the additional activity which vodid be released as a result of this modification was negligible when compared to the releases as shown in section 11 of the FSAR.
It was, therefore, concluded that this change was not an unreviewed safety question.
7h-1020 During initial plant operations, it was found that the steam generator feedpump recirculating line to the condenser was vibrating.
It was desireable to add pressure taps in this line to evaluate the cause of vibration. While not safety-related, this change affected one of the figures shown in the FSAR. The safety analysis concluded that this change was not an unreviewed safety question.
Th-1026 Added drain traps to sample lines of the main vent, spent fuel pool area, and containment radiation monitoring system monitors.
The safety analysis concluded there was no unreviewed safety question because this change in no way affected any safety related eouipment nor added any new systems or components.
7h-1032 Added sodium analyzers to condensate and feedvater se=pling system.
The safety analysis concluded there was no unreviewed safety question because change does not affect any safety related equipment.
75-6 To eliminate inverter problems caused by grounds occurring on the public address system, the co= mon neutrals of the Dusses were isolated. This does not constitute an ur. reviewed safety question since this is non-safety related, but is described in the FSAR.
75-2h Added ladder and lighting in pipe gallery of vest penetration room for cperator convenience and safety. There is safety related piping in the area and the ladder was installed as seismic I, and this did not constitute an unreviewed safety question.
75-28 The changes made under this FCR are similar to the changes performed under FCR Th-101. The safety analysis for Th-101 was also applicable for this FCR.
75-30 In part, this FCR added level controls and a relief valve to the steam generator blowdown tank. The intent of this design change was to increase the blevdown capacity while venting the blevdown tank to the main condenser. It was concluded that this change was not an unreviewed safety question, as the blovdown tank design pressure exceeded the operating pressure with tne higher blovdown, and that the failure of the level controls vould not affect the overall safety of the plant.
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. 75 h8 Revised drawing to show relocation of service vater collection to provide a more representative sample of service water at a conven-ient location. This did not constitute an unreviewed safety question, since no safety-related equipment was changed or function altered.
75-51 Relocated sensing tap for diesel generator (DG) starting air pressure svitches. The safety analysis (Designed under FCR 76-23) concluded there was no unreviewed safety question because original design criteria is being maintained. Chance ensures that starting air co= pressors vill not bleed down.
75-80 Modified 1-CV-5170 and 1-CV-51T1 position indication viring.
Valve position indication was found to be interchanged between these two control valves. The safety analysis concluded that this change corrects a design error. Position indication is as originally intended. Correction provides the operator with proper information to help safely operate the plant. Therefore, the change does not constitute an unreviewed safety question.
75-86 FCR was to update dravings to as-built conditions of the h kV switchgear of the air conditioning, condenser fanc, isolation, dampers and compressors. This change did not constitue an unreviewed safety question, since it was a drawing update only.
75-88 Added alarms to condenser vacuum pu=p seal vater system. The safety analysis concluded there was no unreviewed safety question because the system modified is non-safety related, and the equip-ment added does not affect any safety " elated systems or equipment.75-122 Add a " line to provide demineralized water to the air / vater separator on the miscellaneous vaste and reactor coolant vaste evaporators. This change does not affect any safety-related function or system and the health and safety of the public is not affected by this addition.75-137 Added recorder point identification numbers to FSAR, Fig. 9-11A.
This was a drawing change only, and as such, the safety analysis concluded there was no unrevieved safety question.75-138 Initially the relief valve associated with the vaste gas discharge filter was installed with the wrong lift pressure. This FCR reduced the set pressure to the correct one.
It was concluded that since the design pressure was being reduced to below the design pressure of the vaste gas filter, this FCR did not constitute an unrevieved safety question.
343 064
. 75-lh6 Replaced potentiometer R-26 to improve resoltuion of a linear a=plifier card of nuclear instrumentation. Specifications of the new potentiometer are better then the original specifications, and the change was deemed not to be an unreviewed safety question.75-150 This FCR was one of a series of changes that modified the packing for the charging pu=ps.
The purpose of all of these modifications was to extend the packing life. As such, the modifications to the packing had no effect on normal pump operation, and therefore, it was concluded that this was not an unreviewed safety question.75-165 Moved two nuclear instrumentation cables fro, penetration 1 ZWE 1-3 to penetration 1 ZWE l-lh because internal vire had opened. The safety analysis concluded that the desiFn basis of the cables had not changed, and therefore, there was no increase in the probability or consequences of an accident and no unreviewed safety question.75-182 Conducted a test with a modified charging pump packing arrangement to increase the life of the packing and the reliability of the pumps. The safety analysis concluded that since the function of the pumps was not changed, the probability of occurrence or the consequences of an accident previously evaluated in the FSAR vas not increased, ner had the possibility of an accident different from that described in the FSAR been created.75-185 Replaced present pulsation da=peners for the flow and pressure transrltters on the charging pu=ps' discharge line with more efficient ones. The safety analysis concluded that this modifica-tion did not constitute an unreviewed safety question, and vill improve the performance of the instruments rather than degrade them.75-188 Changed operating configuration of Wide Range Nuclear Instrumen-tation Recorders channel selector switches to a " break-before-rake" operation. The safety analysis concluded there was no unreviewed safety question because this is a change to improve component operation and is not representative of an addition or deletion of systems, components, or capabilities.75-199 Install steam heating coils in the ultrasonic cleaner and rinse tank to facilitate high temperature pre-treatmant of components to be decontaminated. No safety-related equipment or function was altered by this modification.75-200 Deleted control valves CV-5150 and CV-5153 (salt water to and from service water heat exchanger) from logic table LD-58A. The safety analysis concluded there was no unrevieved safety question because this modified design has the proper salt water valves receiving the appropriate Engineered Safety Features Actuation System signals as described in the FSAR and other governing design documents.
343 065
.75-205 Relocated PT-h056 to downstream of MSIV to permit continued pressure analog information to be transmitted to TBV/SD control circuitry with one MSIV shut. This is an improved capability that enhances operation and thus, did not constitute an unreviewed saf ty question.75-206 Added piping to the outlet of reliev valve 2-RV h68 on shutdown cooling systen such that the outlet of 2-RV h68 is piped to the floor drain system, thereby preventing contamination of equipnent in other areas of the auxiliary building. The safety analysis concluded that no safety-related equipment or function was altered by this addition.75-211 Modified the trim of letdown valves to provide stable control at lov flows. The safety analysis concluded there was no unreviewed safety question because the safety-related function of the valve (to serve as pressure boundary but not isolation boundary) was not affected by this change, since pressure retaining components were not changed, nor were any new systems nor components added.75-216 Installed manual drain valves in the four upper blank flanges associated with the spent fuel pool cooling spool nieces to pencit draining of the spent fuel cooling lines above the flanges prior to removing them. The safety analysis concluded that the integrity of the spent fuel pool cooling lines was not reduced by this modification and, therefore, no unreviewed safety question was involved.75-22h Installed piping and a valve to allow each charging punp to be vented to prevent pumps from beine gas bound after packing change. The safety analysis concluded that this modification does not alter the function of the pump or the system and the modification would not affect the capability of the pumn to perform its safety-related function. This change does not increase the probability or conse-quences of an accident, and does not represent an unreviewed safety question.75-230 Installed filters and relocated sample point of the miscellaneous vaste system to avoid clogging of the lines. This change did not constitute an unreviewed safety question since Non-safety related filters were added to a non-safety related system. However, the system is described in the FSAR.75-233 Revised specification M-209 to increase air quant ty handled by Access Control Area Exhaust Filter No. 12 to reflect the as-built conditions. Since no safety related function was altered, this change does not constitute an unreviewed safety question.75-237 Added cable stress relief devices to the NI (Nuclear Instrumentation) cables. The safety analysis concluded there was no unrevieved safety question because no changes were made to the Nuclear Instrum-entation signals nor their signal path, and no structural chances were made to the Reactor Protective System equipment.
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. 75-2hh Mounted accoustical booths on the side panels of ICh3 and 2Ch3 for page and C&P Telephone to isolate phone and page communications from surrounding noises during auxiliary shutdown. The safety analysis concluded that the modification did not constitute an unreviewed safety question. The change only moves the phone closer to the area of attention with the addition of sound proofing.75-266 Electrical drawings were updated to shov the existing shielding arrangement, indicating lights and power supplies to the vattmeter and temperature readout.of the hydrogen recombiners. The safety analysis concluded that this change did not increase the probability of occurrence or the consequences of an accident or malfunction previously evaluated in the FSAR, and did not constitute an unreviewed safety question.
75-1002 FCR Th-1020 was to permit pressure taus to be added to the steam generator feedpump recirculation line to monitor vibration of this line. This FCR vas an attemnt to provide temporary modifications to the line to reduce the effects of vibration. There vere many vents and drains installed with double valve isolation. The heavy mass associated with this combination of valves tended to accentuate the uroblem. This FCR removed a double valve and left a single valve installed. Since the single valve was adequate isolation, and since only minor piping changes in non-safety related areas were involved, it was concluded that this FCR did not constitute an unreviewed safety question.
75-1012 This FCR installed shielding material behind the reactor cavity access door. This shielding was necessary to reduce the overall neutron radiation in containment. Since this shielding was behind the existing access door, the door protected the shielding material from the pressure wave associated with the postulated loss of coolant accident. It vas, therefore, concluded that this FCR was not an unreviewed safety question.
75-1018 Revised FSAR, Fig. 9-6, to refleet proper instrument tag numbers.
The safety analysis concluded there was no unreviewed safety cuestion because this was a document change only; no physical change was made to the plant.
75-1022 Changed the type of pressurizer level transmitter root valves.
The safety analysis concluded there was no unreviewed safety question because replacement valves meet the same design criteria as original valves, and as such are capable of performing the required safety related function.
75-1023 Ch(nged the return line check valves and common tie line manual isolation valve on the H2 and 02 analyzing system. The safety analssis concluded there was no unreviewed safety question because replacement valves met original design criteria and as such, are espable of performing their safety related fu--tion.
t' 06l 75-1025 This FCE modified the feedvater pipe encapsulation by the addition of a drain. This drain had been installed in the field but was not shown on the drawing. The safety analysis concluded that since the description of the encapsulation as stated in the FSAR and original design criteria were unchanged, this change did not constitute an unreviewed safety question.
75-1026 Corrected drafting error on P&ID M-78 in the FSAR. This did not constitute an unreviewed safety question since the change was a drawing change to relfect as-built only, is-1032 Provided instrument installation detail for te=perature well on reactor coolant drain tank. The safety analysis concluded there was no unreviewed safety queution because this was a document change only. The te=perature well was installed and inspected per appropriate pipe class.
75-1035 Updated the Piping class sur=ary (M-601) and Piping Analysis (M-601B) to remove conflicts and bring these documents into acreement. Systems and components whose design parameters had increased were analyzed and it was verified ;hst they were suitable for the nev design values; apuropriate notes were added to M-601 to document the analysis and results. The safety analysis concluded that this change did not constitute an unreviewed safety question.
75-1036 Revised specification 6750-M-51 to correct revision not properly noted originally. No change was made at the facility, and thus there was no unreviewed safety question.
75-10hh specification for containment coole rs was revised. The revision was for clarification and was of ar editorial nature. This had no effect on the facility and thus did not constitute an unreviewed safety question.
75-10h9 Relocated discharge from relief valve 3h5 from steam generator blowdown tank to the reactor coolant vaste receiver tank. Since the discharge line is non-safety related, but is described in the FSAR, the change vas determined not to be an unreviewed safety question.
75-1051 This FCR added valve position indication to the P&ID associated with the salt vater system. This installation had been installed but was not shown on the drawing, it was concluded that this change did not constitute an unreviewed safety question.
75-lc56 Performed a reactor start-up after several days of shutdown without the use of the start-up proportional counters. These start-up detectors had all failed and vere not available for use.
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. The procedure used was essentially the same as that used for the initial approach to criticality except that the proportional counters vere not available for indication of very lov power levels.
At power levels producing less then 0.2 counts per second on the fission chambers the following procedure was followed:
1.
The necessary cold shut-down boron concentration was determined. This concentration was based on the cold shut-down temperature, no Xenon build-up, and all rods out. An additienal margin of 1% to 11/2% of this cold shut-down concentration was then added.
2.
Boron concentration dilution proceeded at a rate of one-half the rate of the dilution rate for the initial approach to criticality (0.5 pps/ minute versus 1.0 pps/
minute). Dilution began after all rods were out.
Above a fission chamber ecunt rate of 0.2 counts per second, the same procedure as used for the initial approach to criticality was used.
The safety analysis concluded that there was no unreviewed safety ouestion, because:
I.
The boron concentration prior to withdrawing any con-trol rods is deemed to be safe because this concentration was determined assuming:
a.
cold shut-down temperatures and coolant is actually at hot shut-down temperature; b.
no Xenon build-up and there vill be some build-up; and, c.
all rods out and the rods vill actually be in.
These three actual conditions used above vill all add negative reactivity thus making the plant even more safe than with just the start-up boron concentration.
The possibility of a boron dilution incident is not increased because the dilution rate at count rates below the range of the fission chambers vill proceed at one-half the dilution rate proven safe during the initial apporach to criticality.
At these lov counting levels the operators vill still have the boronometer and make-up flov alarms available to alert them of any problems. The analyses in FSAR section 14.3.3.2 and 1h.3.3.3 still apply, and the parameters of these analyses are not degraded by not having these proportional counters; and, II.
The FSAR does not take credit for the presence of these proportional counters in its evaluation of the safety of the plant.
fik)
. To protect against a dilution accident the operator still has available the boronometer and the make-up flow alarms to varn of an excessive dilution rate.
75-106h Replaced existing selinium rectifiers in each battery charger as surge suppressors with metal oxide varistors (nov) in order to increase reliability and personnel safety. The sa'ety analysis concluded that the modification did not constituts an unreviewed safety question. The change to mov's vill only provide a better voltage surge protection to the SCR's of each battery charger.
75-1067 This FCR changed the fire protection P&ID to refleet the as-built configuration of the plant. There was no sienificant affect on the system design or function, and as such, the FCR did net constitute an unreviewed safety question.
75-1071 Provided a uressure indicator to the pressurizer system. The safety analysis concluded there was no unreviewed safety question because the change did not affect the Reactor Protective System nor Engineered Safety Features Actuation System and the pressure indicator was installed per original desien criteria for this pioing class.
75-1072 This FCR revised the PiID for the reactor cavity cooling syster,
to reflect the as-built canditions. It was concluded that this FCR did not constitute an unreviewed safety question, as the desien intent of the system was not altered, nor was the change of a safety-related nature.
75-1073 This FCR revised the P&ID for the fuel system, to refleet the actual as-built configuration. It was concluded that this FCR did not constitute an unreviewed safety question because the safety-related portion of the system vas not affected by the change.
75-107h This FCR correcte( the P&ID for the diesel generator cooling vater system to reflect the as-built conditions. It was concluded that this FCR did act constitute an unreviewed safety question because there were no changes to any equipment as presently installed and described in the FSAR, and furthermore, the function of the system and equipment was unchanged.
75-1080 This FCR revised the fuel pool cooling system P&ID in accordance with the as-built configuration. It was concluded that this FCR did not constitute an unreviewed safety question because there was no change to safety-related equipment, and furthermore, the function and the design intent was not changed.
75-1082 This FCR revised the P&ID for the Chemical and Volume control systems to reflect the as-built conditions. It was concluded that this FCR did not constitute an unreviewed safety-related question because no major equipment nor system function was altered.
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. 75-1092 Enlarged orifices in Unit 1 steam generator surface and bottom blev down lines to allow for 25 gpm flov through each orifice.
This is not an unreviewed safety question since the orifices are installed to meet the requirements for high energy ruptures and the increased blowdown flow meets the same requirements.
75-1109 This FCR modified the dimensions of one in-core instrument guide tube flange to eliminate interference between the thermal sleeve attached to the reactor vessel head and the guide tube. Since all design requirements including mechanical and material properties remained the same, it was concluded that this FCR did not constitute and unreviewed safety question.
75-1113 This FCR corrected a drafting error to the Penetration Room Exhaust P&ID. It was concluded that there vere no safety impliertions to this change, and therefore this change did not constitute an unreviewed safety question.
75-1116 The design temperature for EB-lk, Steam Generator Blovdown Pene-0 tration Piping, vas increased from 500 F to 525 F.
It was verified that all the components of this system were suitable for the new design conditions. The nameplate "NA" was changed but it is located on a raised bracket so the pipe boundary was not affected. The safety analysis therefore concluded that this change did not con-stitute an unreviewed safet/ question.
75-1120 Revised the English description of eight Engineered Safety Features Actuation Syste= outputs. The safety analysis concluded there was no unreviewed safety question because this was a document change only, with no change to the plant.
75-1122 Revise P&ID M-77, " Reactor Coolant Waste Processing System - Units Nos.1 and 2" to reflect the as-built condition of the plant. The safety analysis concluded that no safety related system function was affected nor was integrity of any safety related system com-promised. This is not an unreviewed safety question.
75-1125 Trip settings and heater sizes of motor control centers 10hR and llhR vere modified. These changes were made to insure that the motor controllers vill not trip unnecessarily and that the, vill trip when required to prevent a fault from spreading. The safety analysis concluded that the modification was a design in-provement and did not constitute an unreviewed safety question.
75-1127 Revised drawings to indicate that valves on the safety injection tank test connections were globe valves and not gate valves. The safety analysis concluded that the gystem operation was not affected by this change. The probability or consequences of an accident vere not increased, and no unreviewed safety question was involved.
75-1128 Revised drawings to change line numbers of piping, remove one plant air station, remove a valve from the plant air system and to correct a drawing reference. The safety analysis concluded that no safety related system or equipment was affected by this revision.
34 3 u, / l
. 75-1129 General revision of instrument index. The safety analysis concluded there was no unreviewed safety question by referring to all the other FCR's and their respective safety analyses which concluded no unreviewed safety question existed by the respective change affecting the instrument index.
75-1137 Proviaed breathable air to various locations inside the containment.
This breathable air system vill utilize existing plant air system piping and penetrations. The safety analysis concluded that no safety related system or equipment was affected by this modification.
75-1138 Revised drawings to show diaphragn valves on the spent fuel pool cooling system as normally closed instead of normally open and to revise piping line numbers on reactor coolant vaste piping.
The safety analysis concluded that the function of the spent fuel pool system was not adversely affected by this change. The prob-ability or ceasequences of an accident TTre not increased by this change.
75-11h2 Connected additional h inch line from bottom of level control bridle line to heater drain line. The present bridle appears to indicate false levels in heater lle and causes plant trips. Since no safety replated equipment or function was involved, this change did not constitute an unreviewed safety question.
75-11h7 Revised drawings to show the relocation of 0-PI-1995 on the spent fuel pool cooling system and to make a paper change on two isometric drawings. The safety analysis concluded that the relocation of the instrument did not affect the function of the instrument or the system. This is not an unreviewed safety question. The prob-ability or consequences of an accident or malfunction of equipment is not increased.
75-1152 Revised cravings to add casing vents, drains and bed plate drains as well at seal linkage lines on service vater pumps 11,12 and 13.
The safety analysis concluded that these branch lines did not significantly reduce the service water flow required during accident conditions. This is not an unreviewed safety question. The probability or consequences of an accident is not increased.
75-1155 Revised drawines to correct line numbers for two spent fuel pool cooling lines. The safety analysis concluded that the system is not altered by this pacer change.
75-1160 Revised drawings to change globe valves to gate valves on the auxiliary boiler steam lines. The safety analysis concluded that no safety related systems or equipment vere affected. This is not an unreviewed safety question.
75-1161 Revised P&ID M-39, Condensate and Feedvater System - Unit No.1 to reflect the as-built condition of the plant. The safety analysis concluded that the function or integrity of safety related systems er equipment were not affected by this revision. This is not an unreviewed safety question.
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- 1h -
75-116h Revised FSAR, Fig. 9-20 and 9-21, to shov existing pressure gauges. The safety analysis concluded there was no unreviewed safety question because no physical change to the plant was made.
Equipment was installed in accordance with original desien criteria.
75-1168 Installed motor operators on six air control dampers in the Control Room and Cable Screading Room smoke removal system.
The installation allovs operation of selected sets of da=pers and the smoke removal fan from a panel immediately outside of the Control Room instad of by chain wheel da=ner operators in the Elevation 69' Equipment Room. The safety analysis indicates that no change was made in the function of the dampers. Addition of the motor operators was made to reduce response time in activiating the smoke removal system. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased.
75-1171 Added valve position limit svitches to emergency air lock to conform to specifications. The change does not constitute an unreviewed safety question since it only further reduces the possibility of leakage through the air lock.
75-1177 Revised drawings to detail a change in nomenclature on the Unit No. 1 compressed air system. The safety analysis concluded that no safety ralated equirment or system has been changed as a result of this revicion.
75-1178 Revised dravings to correct the instrument numbers for three instruments on the chemical and volume control system. The safety analysis concluded that no safety related system or equip-ment was affected by this revision. This is not an unreviewed safety question.
75-1179 Revised drawings of plant chilled water and air service to reflect as-built conditions. This is not an unreviewed safety question since no safety-related function or equipment is altered.
75-1181 Revise the drawings to include the installation of a back draft damper in the vall between the pipe penetration room and the main steam penetration room to relieve pressure in the main steam penetration room in the event of a line break. The safety analysis concluded that there was no change to safety related equipment or functions. This is not an unreviewed safety question.
76-3 Modified velder qualification requirements to be in accordance with applicable section of ASME code. There was no impact on safety or technical specifications.
76 4 Relocate the steam generator blevdown throttle valve to a location adjacent to the blowdown tank, and remove existing isolation valves to eliminate erosion in the blevdown piping. The safety analysis concluded that this design is consistent with the original design criteria. The probability of a high energy pipe rupture is not increased. This is not an unreviewed safety question.
76-8 This FCR involved the removal of a drai:. path from the auxiliary boiler fuel oil heaters to the condensate collection tank. There was a remote possibility that an oil leak in the heaters could find its way into the condenser.
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{[j
. No safety related equipment was affected by this change and no new accident conditions were created.
76-23 Relocated diesel generator starting air pressure switches from their skid mounting to adjacent vall mounting. The safety analysis concluded there was no unreviewed safety question because neither Reactor Protective System nor Engineered Safety Features Actuation S;' stem functioning is affected by the change, and becuase the relocation is in accordance with the original design criteria for materials and installation.
76-29 Added dust covers to the open type relays in the battery chargers in order to eliminate dust that can easily disable the relay circuits. The safety analysis concluded that the modification did not create an unreviewed safety question. The covers vill not interfere with the physical or electrical functions.
76-33 Changed the lifting pads on the pool seal ring of the refueling pool to a better design since the present pads bent in handling.
This change did not constitute an unreviewed safety question because the new lifiting pad is stronger then the original.
76 kh Addition of new chemical addition piping from the chemistry addition station to the condensate system to allow a more complete control of the secondary system chemistry. No safety related syste= or function is affected by this modification.
76-62 Cut 16 inch diamater circular sections from the te=porary shield platform to allow access to ex-core detectors. The structural integrity of the platform was maintained and thus this change did not constitute an unreviewed safety question.
76-66 Interlocked Unit 1 service water supply and return valves as a set with Unit 2 service water supply and return valves for #12 diesel generator & coolir.g systems. The safety analysis concluded that this modification did not constitute an unreviewed safety question and the pessibility for a different type of accident other than that previously evaluated does not exist.76-100 Modified the upper guide structure lift rig to accomodate the new expansion compensating ring and shim ring to increase the hold-down force. The safety analysic concluded that the lifting pin is not altered because of this modification and that no change in the function of the co=nonent vould result. This is not an unreviewed safety question.76-110 Modified the core barrel lift rig lifting pin to allow the pin to rotate in the plate assemblies preventing the shearing of the locking plate cap screws. The safety analysis concluded that the modification does not violate or compromise the design, performance or lifting capacity of the lift rig. The probability or consequences of an accident are not increased.
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.76-116 Changed the coefficient modules on the axial power calculator to enable setting of the axial tilt trip and pre-trip alarm points that account for the actual shape annealing factor of the fuel.
The safety analysis concluded that this change did not constitute an unreviewed sdfety question, since no new functions are being added or deleted and Technical Specification figure 3 k vill remain in effect.76-120 This FCR vas to install an injection point to allow the injection of sodium hypochloride into the salt vater system to test the effects of the biocide failing of the service water heat exchanger.
A safety analysis concluded that since flows through the salt water system and the pressure boundary of the salt water system vere both unaffected, this test did not constitute and unreviewed safety question.76-13h Allowed repair of an ISIV bonnet back seat, to return to original configuration. The cause of the back seat distortion was later found, and FCR's 76-1051 and 77-1006 were issued to correct the problem. The safety analysis concluded that this modification did not constitute an unreviewed safety question,76-135 Removed standpipes from steam generator 21 & 22 feedvater rings because the standpipes do not prevent a water ha==er and may fail in service. This is not an unreviewed safety question because the design is still in accordance with orginal design criteria.76-137 Installed permanent storage racks for two nitrogen bottles used for changing pu=p desurger. This change vac not an unreviewed safety question since the racks were siesnically mounted against the changing room vall.
76-lh2 Unions were installed directly above pump casing on the discharge line to the mechanical seal No. 11 and No. 12 spent fuel pool cooling pump in place of velded fittings to allov for removal of pump casing. The safety analysis concluded that this modification did not constitute an unreviewed safety question since the struc-tural integrity of the line was not co= promised by the modification.76-157 Revised drawings to add a drain line on the outlet piping from reactor coolant drain tank 21 which vill facilitate easier hydrostatic testing of this piping. The safety analysis concluded that this modification does not change the function or integrity of this system. The probability or consequences of an accident are not increased.76-158 Installed accelerometers on CEDM nozzles to obtain data on head and CEDM acceleration during non critical operation. This is not an unreviewed safety question because the addition was found not to affect any evaluated accidents. The possibility of an accident or
=alfunction not described in the FSAR is not increased because the accelerometers are removed prior to critical operation. Accelerometers that remain vould not effect any safety related equipment or function.
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.76-16h Changed the reactor coolant pumn controlled bleed-off flov indicator from a local indication (rotometer) to a transmitting tyne of rotometer with remove flow indication. The safety analysis concluded there was no unreviewed safety question because chance did not affect Reactor Protective System nor Engineered Safety Features Actuation System and no new systems were being added. Installation was in accordance with original design criteria.76-170 Instrument index change to correct an erroneous service description of two motor operated valves of the boric acid system. No physical changes to the plant are involved. The safety analysis, therefore, concluded that the change does not constitute an unreviewed safety question since no changes to safety related equipment was involved, and no new systems or operating methods are being added.76-172 Windows were cut out of upper end of corner envity to make it oossible to observe the grapple, the fuel assembly and the CEA when the mast is rotated other thna 00 The safety analysis eencluded that this modificatian did not constitute an unreviewed safety question. Neither the oyeration nor the structural integrity of the equipment vill be affected by the modification.76-196 This change involved a design document clarification of the 120 VAC vital power system. No field modifications were required.76-199 The MSIV coupling actuator ring assembly was redesigned to be more rigid to preclude minor veld cracking. This assembly is external to the valve and not pressure retaining; its function is to actuate MSIV position indicating svitehes. Safet: analysis concluded that this modification did not constitute an unreviewed safety question.76-207 Installed 800 resistors in series with the over-voltage relay coils on the 125 VDC battery chargers in order to adjust the relays to within the trip range as specified by the relay setting sheets.
This FCR does not constitute an unreviewed safety question. The addition of the resistors has increased charger operation reliability, since they eliminated the spurious trips caused by the normal charger operation with the original relay circuit. Resistor failure, which may or may not trip the charger, vould not de-energize or render inoperable the d.c. bus. The margin of safety as defined on the basis for technical specification 3.8.2.3. is not reduced since each d.e. battery is backed up by a redundant charger, fully capable of recharging a fully discharged battery while at the same time supplying the steady state power requirements of the system.76-211 Rubber lining of Comoonent Cooling Heat Exchanger manvay covers was allowed to compensate for excessive corrosion of the epoxy lining. This change did not affect the design function of the heat exchangers. The safety analysis concluded that this modification did not result in an unreviewed safety question.
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.76-220 Change fuse size from 30 amn to 6 amp at panel 1D13 breaker 22, panel 1D17 breaker 22, panel 2D13 breaker 22 and panel 2D17 breaker 22.
The safety analysis concluded that this did not constitute an unrevieved safety question. The total electrical load on each of these circuits is on the order of 1-2 amps.
It is important for equipment protection to have a fuse on a circuit to be rated slightly higher than the full load current. A 30 a=p fuse does not protect satisfactorily.
76-1001 Revised drawings to add the following: a) a vent and drain from the miscellaneous vaste processing heat exchanger, b) reducers on the lines connecting the reactor coolant ion exchangers to the solid vaste system, c) vents on the reactor coolant vaste monitor tankt.-
pining, d)
- e. reducer on the drain pining leading to the nos. 11 &
21 ECCS pump ' room sump, e) a flanged connection adjacent to duplex sumu nump no.,11, f) flances on the discharee piping from boric acid pump no.(12. The safety analysis concluded that the function of the systerp and equipment was not altered by these modifications.
The probability or consequences of an cecident were not increased.
T6-100h Correct drawings to shov penetration 51 as " spare" and penetration 50 as ILRT Containment Pressurization".
"'he safety analysis concluded that the relabeling of the drawing did not constitute a change to any safety related function or equipment. This is not an unreviewed safety question.
76-1005 Install an er?ansion co=pensating ring and shim ring to resist axial unvard movement of the reactor internals. The safety analysis reviewed the effects of excessive holddown, fuel rod growth and the hydraulie overturnine moments. The t.nalysis concluded that this modification vould sufficiently hold down the upner guide structure and core support barrel without adversely affecting the internals. This is not an unreviewed srfety question.
76-1012 Modified the air supply to CV-517, CV-518 and CV-519 ( Auxiliary Spray and Charging Lines Containment Isolation Valves) to insure their operability after an accident so as to provide a means of preventing boron precinitation in the reactor vessel after an accident.
This chance added an air accumulator to the valve air supply, added a valve to isolate the non-seismic from the seismic air system in the containment, and provided a means of overriding Containment Isolation Signal (CIS) to containment air supply isolation valve (MOV-2080) in order to allov iperation of CV-517, CV-518 and CV-519 after an accident.
The safety analysis concluded there was no unreviewed safety question because:
I.
The design vill not prevent the operation of RPS or ESFAS.
The CIS to MOV-2080 Override Handsvitch vill be key operated and alarmed on override operation. Tech Specs vill restrict 343 077
. operation of this override function to insure containment integrity.
New piping vill be Seismic Category I.
Prior to this change the implied operation of CV-517, 518, and 519 during and after a seismically-accompanied accident is for CV-518 and 519 to fail open and for CV-517 to fail closed, because the non-seismic air supply to the valves vould be lost. The new seismic air supply and isolating capabilities allows positioning the valves in other than failed position following an accident.
Having CV-518 and 519 positioned closed (rather than f.iled open) does not prevent the charging pump injection of concentrated boric acid because the check valve bypassing CV-519 is still available to allow this flow. Having CV-517 positioned open (rather than failed closed) during an accident merely means an additional flow path fer charging pump injection of concentrated boric acid. The positive displacement charging pumps vill maintain a constant flow rate, by the nature of their desigt.
The new valve (CV-2085) which isolates the seismic from the non-seismic portions of the containment instrument air supply will not, should it fail, cause the loss of any safety functions becaur.e all valves required for safety downstream of CV-2085 are designed to assume their safe position on loss of air; II.
No new systems are being added nor are any existing systems being made to enerate differently; and, III. The margin of safety as defined on the basis for technical specification 3.6 is not reduced. Justification: The CIS override switch operation vill be alarmed in the control room, so the operators will be aware when this containment isolation valve is being held open.
76-1 m8 General revision of instrument index. The safety analysis concluded there was no unreviewed safety question by referencing all the other FCR's and their respective safety analyses which concluded no unreviewed safety question existed by the respective change affecting the instrument index.
76-1029 Revised drawings to add and delete various drains and v :nts on the condensate and feedvater line. The safety analysis concluded that no safety related systems or equipment vere affected. This is not an unreviewed safety cuestion.
76-1030 Revised drawings to a) correct line numbers of piping to and from No. 12 RC Waste Processing Tank, b) relocate instrument o-FDI-2199 and o-SX-6k95 downstream of miscellaneous vaste ion exchancer no.
11, c) relocate check valves from Unit no.1 reactor coolant system ion exchangers. The safety analysis concluded that these changes did not affect the integrity or function of the systems involved.
This is not an unreviewed safety question.
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. 76-1031 Revise P&ID M-Th, Safe'.y Injection and Containment Spray System -
Unit No.1, to reflect the as-built condition of the plant. The safety analysis concluded that the integrity of the safety related systems affected by this revision was not compromised. This is not an unreviewed safety question.
76-1053 This FCR issues a new set of drawings in a slightly different format with different information. Desien information is based on existing P&ID's.
This was not an unreviewed safety question because no design or equipment changes were made.
76-105h Add dual set point protection to PORV's for MPT protection. This change is to decrease the chance of RV over-pressurization at lov temneratures. This FCR does not constitute an unreviewed safety question because the change involves provisions to prevent inadvertent lifting of the RV's with any higher probability than currently exists.
76-1065 This FCR made minor modifications to tube routings for two pressure transmitters in the safety injection system, found to be necessary during system startup due to thermal movements of piping. The change was found not to constitute an unreviewed safety question, since the design was done in accordance with original desien requirements.
76-1068 This FCR made a modification to a shim at the fixed point of attachment of a snubber on the auxiliary pressurizer spray piping.
It was found not to be an unreviewed safety question, since the change merely " fine-tuned" the snubber so that snubber and system would operate as designed.
76-1060 Update Unit 2 on drawings to conform with the latest revisions of corresconding P&ID's.
This is not an unreviewed safety question because it is only a transfer of information and involves no design work.
77-1 Renlaced h inch RC-16-200h sch.10 pipe with seh. h0 h inch pipe cf the same type material because the existing seh 10 pipe leaked at the branch connection veld. This change does not constitue an unreviewed safety question since schedule h0 pipe has additional thickness, compared to schedule 10, to reduce the stress level at the branch location.
77-11 Cut damaged threads from the end of one cap screv securing the access cover plate to the drain tank assembly of #12 SG.
The failure of the access cover plate screvs vould not affect any SR function of the SG and the integrity of the cover plate and screws is not a factor in any accidents. Thus, this change does not constitute an unreviewed safety question.
77-25 Revise connection diagrams of deisel generators 11,12, and 21 control circuitry to reflect as-built. This is not an unreviewed safety question since this is a drawing change only of a satis-factorily operating system. Original intent is not affected.
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. 77-29 Fevise a drawing to renumber valve 1-SI h31 on the containment spray system as 1-SI h71. The safety analysis concluded that no safety related function or equipment had been modified.
77-31 Modified the diesel air vent fan circuitry to insure starting of fan on an under voltage condition. The safety analysis concluded that this modification did not constitute an unreviewed safety question. The probability of a malfunction vill not increase since this modification improves the reliability of the diesel air vent fan.
77-37 This FCR relocated one of the remote snubber reservoirs associated with the piping to the quench tank. As originally installed, this reservoir was belov the level of the snubber.
It was concluded that the relocation of the snubber reservoir did not constitute an unreviewed safety question, as the tubing was routed and installed in accordance with existing criteria applicable to this type of tubing.
77-38 A salt vater pu=p shaft was " cut down" to remove damaged areas, then built up to original dimensions with metal spray. Corrosive /
erosive effects of salt water vere accelerating wear. The repair did not affect pump operation. Safety analysis concluded that an unreviewed safety question did not exist.
77 h5 Installed a flow restricting orifice in the service water outlet line from blovdown recovery heat exchangers 12 and 22 to throttle service water flov belov design flow of heat exchanger with valves completely open. The safety analysis concluded tnat the modification vill prevent damage to the valves and vill otherwise not effect the system. The probability or consequences of an accident are not increased.
77-51 Two drain and two vent lines were added on the bypass connecting the shutdown cooling and safety injection systems to remove water and air from these lines. The safety analysis concluded that this modificatian did not constitute an unreviewed safety question.
Neither the design parameters nor the operation of the shutdown cooling or safety injection system were affected.
77-68 Threads of the yoke bushing on #22 Auxiliary Feed Pump Steam Supply Throttle Trip Valve experienced normal year to the extent that trouble was experienced latching the trip valve. Machining of the bushing by.125" maximum was allowed to compensate for the wear and allow trip valve latching until a spare yoke bushing could be sent from the manufacturer. This repair allovad the trip valve to continue to perform as intended and no pressure boundaries were affected. No unreviewed safety questions were found to exist.
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. 77-71 Revised drawine rSK-MP-160 Rev 1 to reflect as-built change from 3/h" half coupling to 2" x 3/h" bushing on 8 inch HC h-2005 pipe.
The veld on 3/h" half coupling had a crack and repairing enlarged the opening requiring an oversized plug to be used. This change did not constitute an unreviewed safety question since t'2e piping code allows the use of the reulaced coupling on the 8 inch diameter piping.
77-72 Added closure assist springs in charcoal filter dousing valves.
The safety analysis concluded no unrevieved safety question because change did not affect Reactor Protective System nor Engineered Safety Features Actuation System; does not affect opening of valves; original design criteria still applies; and, no new systems nor connonents are being added.
77-82 Replace valve 1-SI h52 shown on drawing OM-7h which was removed by error. This change did not constitute an unreviewed safety question since this was a drawing change only and the valve was in the system.
77-86 Remove up to 0.125 inch from the yoke bushing to allow latching of trip throttle per manufacturer's reco=mendation. This is not an unreviewed safety question because the modification allows the design intent to be met.
77-91 Add instrument tubing to the drain on the suction of one charging rump to measure suction pressure. This was a test and was removed upon completion. This test did not constitute an unreviewed safety question since this was a temocrary setup, and operators were available to isolate any portion as necessary to assure the integrity of the system.
77-95 Installed permanent rack stovage for two 300 cubic feed nitrogen bottles in each charging pump room. The racks were seismically mounted against the vall. The safety analysis concluded that the seismic mounting of the racks did not constitute an unreviewed safety question.77-118 Update drawings to show existing thermocouple vells on hot reheat piping. This was a drawing change and did not affect ai y safety related systems and thus was not an unreviewed safety question.77-121 Temporarily repaired No.12 steam generator blowdown line using bolted clamshell sleeve of sch.h0 pipe and furmanite seal. This was not an unreviewed saf*+y uastion since the weight of the repair material was found not to affect existing pipe stresses, and the repair is very close (2 ft) from an existing hanger and thus is supported properly.77-133 This FCR added flanges to the releif valve in the safety injection system to facilitate removal of the valves for maintenance. The bI b
. stress analysis was reviewed to determine that the addition of flanges would have no effect, and furthermore, the flanges were installed to criteria consistent with the original piping instal-lation. It was concluded that this FCR did not constitute an unreviewed safety question.77-137 Installed flances aeroes safety injection line relief valve RV h09, to facilitate removal and mainter.ance of the valve. The safety analysis concluded that this modification did not constitute an unreviewed safety question and met all applicable criteria.
77-lbl and Severe vear had occurred in the stuffing box area of a salt water 77-lh8 nump. New shaft sleeves were made from monel, and the lantern ring replaced with a ring of packing. No seal or flush water was ever used for these pumps so the lante.n ring served no purpose.
Safety analysis concluded that these modifications did not constitute an unreviewed safety question.
77-lh5 Installed flanges across uafety injection leakoff header relief valve RV h07, to facilitate removal and maintenance of the valve.
The safety analysis con luded that this modification did not con-stitute an unreviewed safety question and met all applicable criteria.77-150 Installed flanges across shutdown cooling return header relief valve RV h69, to facilitate removal and maintenance of the valve.
The safety analysis concluded that this modification did not constitute an unreviewed safety question and met all applicable criteria.77-151 Installed flanges across quench taak relief valve RV-2h2 to facilitate removal and maintenance of this valve. The safety anslysis concluded that this modification did not constitute an unreviewed safety question and met all applicable criteria.77-152 Installed flanges across safety injection tank relief valves RV-211, RV-221, RV-231 and RV-2h1 to facilitate removal and maintenance of these valves. The safety analysis concluded that these modifications did not constitute an unreviavad rafety question and met all applicable criteria.77-153 Installed flanges across reactor coolant pump controlled bleed off relief valve RV-199 to facilitate removal and maintenance of the valve. The safety analysis concluded that the r >dification did not constitute an unreviewed safety question and net all spplicable criteria.77-156 Allowed the use of annealed copper sheet to manufacture stem vashers for small (1/h" and 1/2") Dragen valves it. the MSIV h draulic system. These washers are not pressure re aining and vere much easier to manufacture than purchado, cince they were evergiay com-mercial hardware. The washer material was unchanged. Saft'y analysis concluded that this change did not constitute an unrevieved safety question.
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77-162 This ICR modified the hydrostatic test connection on the charging pump suction header. This modification was necessary to reduce the suseptability of this area to fatigue-type failures. It was concluded that the madification would have a negligible effect on the seismic analysis, and as a result, this FCR does not constitute an unreviewed safety question.77-16h This FCR modified the in-core instrumentation guide tube f1roge and the coupling bracket fastener to delete the necessity for lock viring the tap screws. This FCR vas necessitated because the guide tube thimble contained a stuck in-core instrument and nad to be replaced. An alternate locking method was provided and the safety analysis concluded that since this alteir.ste served the same function as the original, the change was not an unreviewed safety question.77-166 The MSIV hydraulic system flov diagrams were corrected to show a three-way, instead of two-vay sa=ple valve, to reflect the as-built system. No unreviewed safety question existed.77-179 Modified the siphon breaker gooseneck on the spent fuel pool cooling line by changing its mass and length to prevent vibration of the line. The safety analysis concluded that the structural integrity of the line remained unaffected and the modification did not constitute an gnreviewed safety question.
77-1001 Renlaced overload relays in the safety related motor control centers with ambient condition compensated overleed relays. The change did not constitute an unreviewed safety question because the new overload relays meet the original intent of the motor control center specifications.
77-1010 Change drawing M-186 to correct size of the fuel transfer tur -
0-rings. Since this was a drawing change only this did not con-stitute an unreviewed safety question.
77-1018 Repair concrete reactor head laydown piers for unit 1 because of damaged caused by drifting reactor head. This change is not an unreviewed safety question since the system is non safety related, but described in the 7 JAR, and is to restore original conditions.
77-1026 Revised instrument tube clamp and mounting drawings to allow use of cadmium plated, brass, or aluminum tube clamps and ASTM A-193 or A-307 for bolts. Safety analysis concluded no unreviewed safety question because new materials are consistent with criginal design criteria, and because no new systems nor co=ponents were added.
78-1 Allov " Fur =anite" to be injected into the upper stuffing box area of various instrument root, drain, and vent valves that do not isolate normal flov, to act as a packing bar'.-up.
The use of "Furmanite" and the injection location was approved by the valve manufacturer l'.
question prior to implementation and provided a means to reduce packing leakage while remaining in-service. The safety analysis concluded that this change did not constitute an unreviewed safety quest #au.
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. 78-h' Existing pipe hanger was modified from velded to bolted construction to allow temporary removal for rigging S/G hot manway scaffolding.
The safety analysis concluded that the modification did not constitute an unreviewed safety question. The structural integrity of the hanger was not compromised by the change.
78-5 Existing pipe hanger was modified from velded bolted construction to allov te=porary removal for rigging S/G hot manway scaffolding.
The safety analysis concluded that the modification did not constitute an unreviewed safety question. The structural integrity of the hanger was not compromised by the change.
78-6 This FCR was for the injection of Furmanite into the gland leak-off into the pressurizer root valves. Fur =anite is a cornpound which has been used to successfully stop leakage. At the time of the injection, the primary system leak rate exceeded the allowable technical specification limits, and as such, this FCR vas to reduce this leakage to the point where the plant could continue to operate.
The use of Fur =anite is concidered on a ccco by case basis because of a known level of chlorides associated with this material. In this circu=st'ince, the use of Fur =anite was approved for a specific limited time which was clearly insufficient time for any degradation to the valve. The requirement of the FCR was that the valve be inspected at the subsequent outage.
Consequently, it was concluded that this FCR did not censtitute an unreviewed safety question.
78-9 This FCR changed the t-be plug material for the shutdown heat exchanger from a type 30L stainless rceel to a type 316.
It was concluded that since the only requi-ement for the tube plug was that it be of 300 series stainless steel that thi FCR did not constitute an unreviewed safety question.
78-22 A small stainless bushing was added to the arm /dise asseably of a fire protection system check valve to compensate fue vear in this location and provide good disc / valve sent alignment and better seating. Safety aialysis concluded that this modification did not r:onstitute sn unreviewed safety question.
78-26 This FCR was to install a platform and small crane adjacent to the spent fuel pool to allow sleeving of the fuel assembly guide tubes during the refueling outage. The design met the necessary seismic criteria, and since installativu :n-treated as safety related, it was concluded that all design criteria was consistent with what vould have been required during the original plant desiCn, snd that this FCR did not constitute an unreviewed safety question.
78-32 This FCR modified the fuel transfer tube b ing flange to enlarge the groove for the 0-ring.
This was necessary to inprove the seal of the flange. Stress analysis associated vi+h the flange was found to be unaffected by this change, and since the fur.ttion of the flance was unchanged, it was concluded that this FCR nid not constitute an unreviewed safety question.
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. 78-k6 Drawing change only to service water NSR piping. The function of the system var not affected.
78-53 A sliding-type support was added to an existing hanger on the Unit No. 2 main steam line. Although the piping was NSR, the FCR was treated as SR because the change occurred to hanger that was included in the main steam line seismic stress analysis. The added support did not attach to the pipe pressure boundary nor alter the original stress analysis, so no unreviewed safety question existed.
78-lh 3 This FCR reduced the number of anchor bolts associated with a pipe hanger on the charging pump suction. It was found that one bolt had pulled loose. Calculations vere performed to show that the remaining bolts provided adequate strength, and as a result it was concluded that this FCR did not constitute an unreviewed safety question.
78-1005 Update the seisnic response curves for h kV switchgear 6750-E-5, h80 V load center 6750-E-6, and h80 V msse 6750-E-7 (E-7G).
Original curves did not reflect the true requirements. This change did not constitute an unreviewed safety question since it only corrected a previous error.
78-1003 This FCR was necessary to allow the necessary nodifications to a spring hanger associated with the main steam line which were necessitated by a failure of the existing hanger. It was concluded that this FCR did not constitute an unreviewed safety question, as the design modifications ensured that the modified hanger was as strong or stronger than the existing hanger.
78-1021 This FCR corrected a drafting error associated with snubbers on a pressurizer surge line.
Th.
aving change had no effect on plant operations, and was for clarification only. It was concluded that this FCR did not constitute an unreviewed safety question, and that the fie1d' installation was correct.
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