ML20008E717

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Annual Operating Repts for 1980.
ML20008E717
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 02/28/1981
From:
GEORGIA POWER CO.
To:
Shared Package
ML20008E713 List:
References
NUDOCS 8103090508
Download: ML20008E717 (51)


Text

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O a TABLE OF CONTENTS PAGE i

Introduction i Design Changes and Tests or Experiments Plant Design Changes 1 Test or Experiment Requests 37 SRV Challenges for 1980 39 Data Tabulations and Unique Reporting Requirements Occupational Personnel Radiation Exposure 40 Reactor Coolant Chemistry Summary 43 8103 09 0 tgc) g

INTRODUCTION Edwin I. Ilatch Nuclear Plant Unie 1 it a light water reactor of 764.3 MWc net maximuc dependable capucity. Unit 2 is also a light viater reactor of 772.7 MNe act MDC.

Ownership of the plant is fifty and one tenth percent (50.1%)

Georgia Power Company, seventeen and seven tenths percent

( 17. 7 i, ) Municipal Electric Authority of Georgia, two 7nd two '

tenths percent (2.2%) rity of Dalton, and thirty aercent (30%)

Oglethorpe Electric 14cmbership Corporation. T1e plant is located at a site approximately clevea miles north of P axley, GA, on US H;ghway 1 on the Altamaha Elver. General Electric Company furnished the boiling water reactor nuclear stew sep-ply system and the turbine generator. The plant was designed by Southern Conpany Services, Inc. with assistance provided by Bechtel Power Corporation. The condenser cooling method employs forced dra f t cooling towers and circulating water sys-tems. Normal mak :up is drawn from the Mtamaha River. Unit 1 is subject ta licer se DPR-57 issued 8-i-74, pursuaM to Docket

  1. 50-321; Unit 2 to license NPT-5 issued 6-13-78, Fu saant to -

Docket #50-3(i6. Unit 1 achieved initial criticality on 9 74, Unit 2 cc 7-4-78, and 9-22-78, respectively. Unit I was declared comac cial on 12-31-75. Unit 2 was ic clared commer-cial on 9-5-79. Georgia Power Company has sole respcnsibility foi overall planning, design, construction, operation, main-tenance, and disposal of the plant.

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r Georgia Power Company l Plant E. I. Ilatch r Baxicy, GA 31513 i

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t Design Change Requests 1 i

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t Curtis L. Coggin i Supt. Plt. Eng. Serv.

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2-78-300,R1 Paired up pump overload annunciators with feeder breaker lockouts for the PSW, RilR , and core spray pumps by jumpering some switchgcar termin-als. This was to inform the control room of a remote tripped lockout which could make a pump unavailable without operator knowledge.

The possibility of an accident or malfunction of a different type analyzed in the FSAR does not result from this change because only internal wiring additions are made which do rot affect the automatic logic of the equipment.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change adds supplementary information on the availability of the equipment to perform its

. intended func. on. Before this change the condition descrt 'A could exist without operator knowledge.

2-78-302 Insured valec closu.x 'ollowing PSW pump start by drilling out the ex 'ng valve " cup" holes from four each 1/4" holt to four each 1/2" holes.

The possi'oility of an accident o. ,1F" > tion of a different type analyzed in the 1SAR does not result from this change because the changa enhances the probability of the valve closing not effecting the pressure boundry.

The margin of safety as defined in Tech Specs is not reduced due to this change because Tech Specs are not affected.78-201,R1 Added a synchro-acceptor type 587C886G01 relay to each dicsc1 to provide a permissive to close the dicsc1 output breaker when testing a dics-cl. Added a 1211GA11A52F auxiliary relay to switch synch voltage on and off to the synchro-aceptor relay.

The possibility of an accident or malfunction of a different type analyzed in the FSAR does not result from this change as a failure of this additional circuitry will not affect the diesel except in the TEST mode, the most probable fail-ure being inability to close the dicsc1 breaker manually. In any case no new failure could occur which would prevent operation in the AUTO mode.

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i The margin of safety as defined in Tech Specs is  !

not reduced due to this change in no way affects I operation of the diesci to perform its function l in the AUTO mode. '78-113 Change diesel annunciators to provide better information to the control room operators as to the operational status of each diesel generator.

The possibility of an accident or malfunction of l

a different type than analyzed in the FSAR does  !

not result from this change since no functional l change is involved and no difference in equip-  !

ment is being introduced; annunciation is !

improved.

The margin of safety as defined in Tech Specs is  !

. not reduced due to this change because safety limits are unaffected. ,

r 78-295, R2 Replaced obsolete temperature switches on diesel generators 1A, 1B, and 1C (oil temp high shut-down, oil temp high alarm, coolant temp high shutdown, coolant temp high alarm) with new Allen-Bradicy modc1 837-V3 series A.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does -

not result from this change because the change does not introduce any new or differcnt modes of failure since the replacement switch meets the ,

same specifications as the original switch.  ;

i The margin of safety as defined in Tech Specs is  ;

not reduced due to this change because the set-  !

points are not changed.  !78-325 Improved diesel ger erators start-stop logic to I climinate a potential relay hangup in emergency start mode which could result under a combina-tion of circumstances. -

i The possibility of an accident or malfunction of I a difforent type than analyzed in the FSAR does not r.tsult from this change because no new modes of failure or malfunction are introduced and no t hardware or circuit design is introduced which I is different from those aircady analyzed in the i FSAR. +

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r i The margin of safety as defined in Tech Specs is not reduced due to this change because the change improves reliability and integrity of tic diesel generator systems. Therefore, the margin ,

of safety is not reduced. l 78-411, R1 Unstopped reactor primary coolant water smapic line by cutting and reconnecting using st:agelock fittings. ,

r The possibility of an accident or malfunction of a different type than analyzed in the FSAR does .

not result from this change because the sampling  ;

line to be altered is located downstream of the second isolation valve and does not affeet the safety of the reactor.

, The margin of safety as defined in Tech Specs is not reduced due to this change because there are no new safety limits associated with the samp- i ling system nor does it affect any system that does have a safety limit.  :

79-19 Modified specific hangers in the PSN system so as to bring the allowabic building settlement to values both GPCo and the NRC will find accepta-ble.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because this change i will neither affect old mocas of operation or failure nor will it cause new ones because all it tends to a is add some support to the pipe where building settlement could have affected it in the past.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change does not affect any of the modes of oper-ation. In fact. this change makes the . system i safer in the aspect that the building settlement effect in the pipes is Icssened. i 79-201 Provided capability of transferring water between the two CSTs by installing a cross ,

connect line and using the existing transfer '

pumps.

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced as a result of this change.

The margin of safety as defined in Tech Specs is not reduced due to this change because it will be increased due to added redundancy of cooling water availabic to either unit as a result of this cross connect line between the two CSTs.79-402 Provided a secondary containment syste"1 which will prevent containment violations, assure prompt ingress, and unimpeded egress, and satis-fy fire protection requirements.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no system operation is changed. The system being defined as "no more than one door of an airlock shall be permitted to be opened at a time".

The margin of safety as defined in Tech Specs is not reduced due to this change because system operation as defined above is not affected.79-495 Replaced the bolts which join the PSW pump stages together with studs of an equivalent material and diameter because bolts are not available.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the replace-mont material is equivalent to the original material. Any failure modes should follow the original postulated modes in the FSAR.

The margin of safety as defined in Tech Specs is not reduced due to this change because the material is equivalent to the original material and, therefore, safety factors have not been reduced.

80-66 Allowed the use of 410 SS, 416 SS, or 316 SS as PSW pump shaft material because significant time delays were encountered in purchasing the design specificd shaft material (410 SS).

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because since the vendor reviewed the physical properties of each of the types of material and found them accepta-ble no new modes of failure will be introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because no Tech Specs limits will be affected.80-127 Removed internals of pressure control valve P41-D107 in order to render the valve inactive as a pressure control valve. This will prevent isolation of PSW and RilR SW motor cooler supply water due to potential failure of pressure regulating valve.

The possibility of an accident or malfunction of i a different type than analyzed in the FSAR does not result from this change because this change does not introduce any new modes of failure.

This change does, however, remove the existing potential mode of failure involving closure of the valve. Closing or restricting of the flow path of cooling water to the motor coolers will be climinated.

The margin of safety as ilefined in Tech Specs is not reduced due to this change because this change removes a potential failure mode which would hvc adverse effects on the operability of PSW and RIIR SW pumps.80-129 Provided divisional cooling water for PSW and RilR SW pumps to preclude single failure condi-tion. A crosstie between Div. I and II dis-s charge piping was climinated and additional piping was routed.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because since the additional piping will be instal]~1 by require-ments at least as conservative as those associ-ated with the original piping, no new modes of failure are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because no Tech Specs limits are affected.

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80-132 Changed the diesel generator 2B auto shutdown logic so that the feeder breaker to the 2F bus

, will trip when the dicsc1 generator receives a shutdown signal.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does l not result from this change because no new modes of failure or malfunction are introduced and no hardware or circuit design is introduced which is different from those already analyzed i r. the FSAR.

The margin of safety as defined in Tech Specs is

. not reduced due to this change because the change improves the reliability of the system.80-208 Changed the timing cam to allow the 112 -02 analyzer to go through the purge cycle every twenty minutes instead of every sixty minutes.

This alleviated the problem of water building up in analyzers.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure have been introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because the margin of safety will increase since the change will allow for better drainage of 112 - 0 2 analyzer.80-216 Added snubbers to PSW discharge pressure gages to climinate pressure transients which make premature calibration necessary. This will also give more accurate data during ISI testing.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this chaige because the addition of snubbers does not introduce any new modes of failure.

The margin of safety as defined in Tech Specs is not reduced due to this change because no Tech Specs limits are affected.

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'a . .80-291 Added new pipe support and modified existing support associated with 4" piping that tees off 8" DWL cooling system supply piping, This was donc to make piping meet scismic stress qualif-ications.

The possibility of an accident or malfunt. tion of a different type than analyzed in the FSAR does

, not result from this change because the function of the piping system has not changed.

The margin of safety as defined in Tech Specs is not reduced due to this change because this

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change improves the margin of safety.80-315 Allowed the PSW pump bowls to be fitted with wear rings to reduce pump rebuilding time.

The possibility of an accident or malfunction of

', a different type than analy:cd in the FSAR does not result from this change because the wear rings do not increase the likelihood of pump failure. While wear rings do add another mode of pump failure, pump failure is anelyzed in the FSAR.

The margin of scfety as defined in Tech Specs is not reduced due to this change because wear rings do not adv e rs ely affect pump reliability; pump flow characteristics are unchanged so the margin of safety is unaffected.80-342 Added or removed pipe supports on the PSW supply line to the SBGT filter train deluge system to resolve stresses which exceeded code allowables.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the function of the piping system will be improved.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change improves the margin of safety.80-407 Bored standby SW pump bowls to accomodate fabri-cated wear rings. This will extend the life of the pump bowl assembly. ,

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The possibility of an accident cr malfunction of a different type than analyzed in the FSAR does l not result from this change because the ve:idor l (Johnston Pump Co. ) has specified limiti, on the  !

size of wear rings allowed so that a new mole of l failure will not be it.troduced. }

The margin of safety as defined in Tech Specs is  ;

not reduced due to this change beccuse no Tech Specs limits are affected. l t

76-198 In order to resolve oscillation problem in the d/w to torus dP system as to allow for automatic operation of dP pum change the location of the high (d/w side) pspressure

, taps cf the T48-N048, N081, N082, N083 from downstream of T4 8-F203 to teeing into T48-N022A sensing line with

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SS tubing. Replace T48-DPS-N081 with static ,

ring switch of lower dead band. The process  !

line isolation valve at d/w tap for T48-DPS-N081 should be closed and its tubing capped off. I Change T48-PS-N080 setpoint to 1.70 psig increasing, T48-PS-N083 setpoint to 1.64 pdis increasing.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change since no new modes  !

of failure have been added. The new instrument to replace the existing T48-N081 is of the same f spec as the original but has a more adjustable r deadband.  ;

The margin of safety as defined in Tech Specs is  ;

not reduced due to this change since a drywell to torus diff. pressure of 1.50 psid and a dry- ,

well pressure of less than 2.0 psig will still l be maintained in this change.

r 76-200 In order to accept the as built condition, the

  • RHR minimum flow line restraint was counted with 7 anchor bolts instead of 8.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does  ;

not result from this change because pipe support  :

failures have been analy:cd in the FSAR. I:

The margin of safety as defined in Tech Specs is l not reduced due to this change because the sug-gested changes does not affect any safety set- ,

t points, and, therefore, no safety margin as i defined in Tech Specs. [

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,. t C 77-151 Installed Unit 2 high rad trip to trip Unit 1 ,

refucing floor and reactor building ventila-tion. [

Likewise, Unit I was designed to provide  ;

a high rad trip for other units, refueling .

floor, and reactor building ventilation systems.  !

r The possibility of an accident ot malfunction of f a different type than analyzed in the FSAR does i o not result from this change since the change  ;

does not result in a different type of failure  ;

or change in system operation than analyzed.  ;

The additional trips are a required mode of

, operation of the systems.

l The margin of safety as defined in Tech Specs is  !

not reduced due to this change since the system  :

affects no margin of safety concerning safety i

! shutdown of the reactor. The additional trip is l required to correctly isolate the refueling l

, floor and Unit i reactor building on high radia- (

tion on either Unit 1 or Unit 2 refueling floor.77-213 Change the RIIR heat exchanger outlet valves l (E11-F008ASB) from scaling in on opening and i closing into a throttic valve. This valve can then be used in the shutdown cooling mode to  !

control heat rejection in the heat exchanger. [

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does L not result from this change because no new modes  ;

of failure are introduced as the valve does not  !

have a containment isolation function. The only [

time F003A(B) will be in a position other than  ;

open will be during the shutdown cooling mode.  ;

In the unlikely event that LPCI was needed while the shutdown cooling mode was in service the ,

LPCI flow could bypass the heat exchanger and l

, the throttled IIx out1ct valve F003A(B), thru  !

F048 after it auto opens.

The margin of safety as defined in Tech Specs is l not reduced due to this change because no safety limits, such as closure time, are affected.  ;77-229 Countermeasure to prevent intergranular 3 tress  !

corrosion cracking (IGSCC) of susceptibic aus-  !

tenitic stain 1 css steel piping of the core spray t system. t i

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The possibility of an accident or malfunction of f a different type than analy:cd in the FSAR does not result from this change because there are no new modes of failure introduced due to this change. -

r The margin of safety as defined in Tech Specs is not reduced due to this change because there are no safety limits affected by this change.  ;

2-78-41 In the ADS the time delay relay function of the 2B21-K5A, K5B relays has a tendency to increase '

after long periods in a dcenergi:cd state.

Replacement of these with Agastat 125 VDC time delay relay parts #164C5257P010 will resolve the prob 1cm. Agastat relays were installed. -

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The possibility of an accident or malfunction of a different . type than analy:cd in the FSAR does ,

not result from this change since the function of the new relay replaces the time delay func-tion of the CR2820 relay. Failure modes are the same. l i

i The margin of safety as defined in Tech Specs is '

not reduced due to this change because the  ;

system will function as it did before the  !

change. The margin of safety of the system will

  • be increased by installing the new relay; it ,

will provide a more reliabic time delay function  :

than did the CR2820 relay.

2-78-187 Remove the remote operators from the holding pump suction valves 2G31-F066A/G; replaced with local handles.

The possibility of an accident or malfunction of a different type than analy:cd in the FSAR does not result from this change because normal valve ,

lincup is not affected.

The margin of safety as defined in Tech Specs is  !

not reduced due to this change because system I design is not changed.  !

2-78-282 l Outboard system timer (2E32-N604) was replaced ,

with a longer timer to make the system wcrk l properly. FDDR llT2-368 '

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the system still performs its intended function with the original equipment intended a' analyzed for failure modes.

The margin of safety as defined in Tech Specs is f not reduced due to this change because the equipment is not changing; blowdown occurs in a longer period of time than originally calculated but has been recalculated and the margin of safety reanalyzed ,ithw no compromise to the margin of safety found.78-194 To correct the scale of 2G31-R601 to correspond with 2P33-CITS-N022 having 18% nidscale; also changing 2P33-CITS-N021 to be same type as 2P33-CITS-N022 allowing dual purpose of 2G31-R601 The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change since no new modes of failure are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change since no setpoint changes were made.78-202 Changed out a feedwater sparger with dual piston type spargers and removed cladding. This res-olved cracking problems and incorporated FDI 142/12000.

The possibility of an accident or malfunction of a different type than analynd in the FSAR does not result from this change because no new modes of failure are introduced since the new design i

will reestablish a 1cyc1 of safety consistent with the original design requirements.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits are affected.

[ 78-271 The drywell high pressure switch logic was changed to permit proper operation of the torus drainage and purification system valves.

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s The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the original system design is not changed.

The margin of safety as defined in Tech Specs is not reduced due to this change because isolation capability of the 2G51-F011,, F012, F013 valves s is unchanged.78-284 Reliability was improved in the reactor manual control system by improving the continuity e monitoring circuit.

The possibility of an accident or malfunction of i a diff: rent type than analyzed in the PSAR does

' not result from this change because this change does not increase the chance of any malfunction or accident.

The margin of safety as defincd in Tech Specs is not reduced due to this change because this change does not affect any circuit which would decrease the margin of safety.78-330 i!PCI and RCIC; existing Robertshaw model 82938-11 1cyc1 switches on steam line drain pots have a history of failure at high temp the p r e s en't configuration allows the (300oF);hing switc mechanism to overheat causing switch faili.5c ,

resulting in false alarm on high 1cycls; provided substitute switches and cables.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because there are not any new modes of failure introduced as a result of this design change.

The margin of sa.'ety as dwined in Tech Specs is not reduced due to this change because there are not any safety limits affw J by this change.78-353 A pressure switch was replaced with one of a different reset pressure on the control rod drive system to make the switch reset differen-tial compatible with the scram pilot air header pressure fluctuations.

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't The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the mode of operation of the neu narrow reset differential switch is the same as that of the wide reset switch.78-354 Replaced switch T46-N007B with one that has a 2

range of .05 to 1.0 in WC to make range of switch cover the setpoint (.07 in WC). This change was needed to cicar up MR 78-807.

3 The possibility of an accident or malfunction of a different type than analy:cd in the FSAR does mt rce ult from this change because the mode of cc oration of the new wider range switch is the

, same us that of the narrow range switch.

t 78-416 T23 A pi'lov block bearing was added to Unit I r airlocks chain sprocket to prevent a support shaft from bending when excessive force is appired. This allows correct timing.

The pc.:ibility of an accident or malfunction of a diff erent type than analyzed in the FSAR doc t not result from this change because the door opening mechar. ism is not changed.

The margin of safety as defined in Tech Specs is ,

not reduced duc 'o this change because safety limits are not afi:cted.79-419 Added class I E, sei smically qualified equipment, capable of deenerg :ing the reactor protection system power supply when its output voltage f exceeds or falls below specified points.

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, The possibility of an accident or malfunction of I a different type than analyzed in the FSAR does l not result from this change because no new fail-ure modes are introduced that have different results from existing failure modes. The modification reduces the possibility that the RPS MG set would not deenergize the RPS distrib-

, ution cabinet during a scismic event if the voltage or frequency exceeded specified limits.

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The margin of safety as defined in Tech Specs is not reduced due to this change because the ,

breaker installation has no effect on any margin ~

of safety. It does improve the reliability of the RPS system because of the redundancy and resistance to seismic events that is provided by the additional circuit breaker.78-483 2B31-G003B cut off 1/2" of restraint to provide required clearance between the "B" loop c1 bow pipe and the recire piping. -

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the change will provide the necessary gap (1/2") to lessen the chances of some type of stress cracking occurring in the line at a later date.

The margin of safety as defined in Tech Specs is not reduced due to this change because it will [

remain the same since the restraint would func-tion as it was originally intended.

79-36 2E32 MSIV Icakage control. Move transmitters to torus catwalk area to make transmitters work as intended.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced by this relocation of the transmitters to a location where they will function as originally intended.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits or setpoints will by changed by this change. .

79-54 Add valves F304 F305, F308, and caps so scram discharge level switch (2C11-N013EGF) can be calibrated and surveillance can be run o n. i switches when unit is on line. This allows each r switch to be tested instrument isolation for t test conditions.

The possibility of an accident or malfunction of  :

a different type than analyzed in the FSAR does '

not result from this change because the mode of operation of the system is unchanged.

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3 The margin of safety as defined in Tech Specs is not reduced due to this change because no chang-es are made to setpoints on the icvel switches.

79-88 Same -modification as 79-89 cxcept incorporated into 2E41-K615 (HPCI).

The possibility of an accident or malfunction of 4' a different type than analyzed in the FSAR does not result from this change because method and operation of the system remains unchanged.

a The margin of safety as defined in Tech Specs 11 not reduced due to this change because llPCI sys-tem operation remains unchanged as a result of the modification.

i 79-89 GE FDDR-HT2-385, Rev. 1 incorporated into 2E51-4 K615 (RCIC system). In revision 0, the resis-i tors R1 and R2 overloaded the amplifier to Rev.

I will remove these. Install and adjust a limiter to limit controller output to 52 MA.

Recalibrate system flow control loop.

The possibility of an accident or malfuncti n of a different type than analyzed in the FSAR does not result from this change because method and operation of the system r_emains unchanged.

The margin of safety as defined in Tech Specs is not reduced due to this change because RCIC system operation remains unchanged as a result of the modification.

79-92 2T23 Replace pins with welded caps on vent header support column clevis pins and on SRV discharge line rams head support columns pins.

The possibility of an accident or malfunction of

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a different type than analyzed in the FSAR does not result from this change because the modific-ations will add no more modes of failure.

The margin of safety as defined in Tech Specs is not reduced due to this change bec'.use this g

modification will increase the reliauility of the equipment and will not affect any of its safety systems.

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79-94 A thermal power monitor (TPM) was added to the neutron monitoring system reducing the number of scrams due to momentary flux spikes caused by disturbances in the recirculation and for primary pressure systems.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR is  !

not created as no new failure path is introduced. r 79-106 MSL pressure switch; in order to prevent unnec-essary 1/2 group I i sola t ion when performing [

llNP-1-3105-M FTEC install a test valve in the existing " Tee" connection of each sensing line  !

isolating the switch.

The possibility of an accident or malfunction of ,

a different type than analyzed in the FSAR does +

not result from this change because no new modes I of failure are introduced.

The margin of safety as defined in Tech Specs is .

not reduced due to this change because safety l' limits are not affected, and no Tech Specs lim-its are violated.79-110 Install a new redundant hook fuel grapple head (2F15-E003) to prevent the possibility of bundle drops.

t The possibility of an accident or malfunction of .

a different type than analyzed in the FSAR does  !

not result from this change because this change does not affect the standby gas treatment system nor secondary containment.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change does not modify nor obviate these requirements.79-120 2B21-F037 Ilinge pin bushings on the main steam relief valve pipe vacuum breakers were replaced with bushing of stronger material to prevent bending when valve slams open and closed.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the opera-tion of the valves is not affected or changed. l i

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The margin of safety as defined in Tech Specs is not reduced due to this change because it is increased by the use of stronger materials.79-138 The SRVs F013 A thru M on Unit 2 were relapped on the pilot seats to a less steep angle, and the blowdown orifice size was increased. This allows the valves to hold within 1% of setpoints and resolves chattering problems.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced by this change.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change does not change the setpoint or safety limits of the safety relief valves. It makes compliance to the safety relief valves safety limits more reliable.79-158 The high dT isolation signal to the RCIC system was removed. This will prevent spurious isola-tion of the system due to RCIC equipment room vent air high dT isolation signals.

The possibility of an accident or malfunction of a different type than anilly ze d in the FSAR does not result from this change because the remain-ing isolation signals are suf ficiently redundant ,

and diverse by themselves to cause isolation of the llPCI steam line.

The margin of safety as defined in Tech Specs is not reduced due to this change because the remaining isolation signals are sufficiently redundant and diverse by themselves to cause isolation.of the RCIC steam line.79-159 The high dT isolation signal to the llPCI system was removed. This will prevent spurious isola-tion of the system due to llPCI equipment room vent air high dT isolation signals.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the remain-

ing isolation signals are sufficiently redundant and diverse by themselves to cause isolation of the llPCI steam line.

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i The margin of safety as defined in Tech Specs is not reduced due to this change because the remaining isolation signals are sufficiently redundant and diverse by themselves to cause isolation of the HPCI steam line.79-183 B21 SIL #74 was implemented to increase the reliability of Atwood 6 Morrill main steam i isolation valves.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does 3 not result from this change because no new modes of failure are introduced by this change.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits or setpoints are affected by this change.

,79-207 B21 SIL #74 was implemented to increase the reliability of Atwood G Morrill main steam isolation valves.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced by this change.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits or setpoints are affected by this change.79-199 B31 An ASCO solenoid valve was replaced with an environmentally qualified one on the reactor sample line per IEB 79-01.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because new modes of

\

failure are not introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because it is increased through the use of environmentally qualified components.79-200 Replaced 2B31-A0V-F019 ASCO solenoid valve (environmentally unqualified) with new c/n NP8320A-135E, 120VDC solenoid which is environ-mentally qualified.

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because it is increased through the use of environmentally qualified components.79-205 The crud trap on the reactor bottom head drain line was removed and two new valves were installed on the line.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety margins are affected.79-215 RHR A transmitter was replaced with a different brand to correct instrument failure and drift of RHR flow indication.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the Rosemont transmitters will perform the exact same func-tion and the Barton transmitters.

The margin of safety as defined in Tech Specs is not reduced due to this change because the new transmitters are more reliable than the Bartons.79-225 Placed blowers on panel 1H21-P151 to reduce excess hea t caused by filter train which causes overheating of electronic equipment mounted in panel and causing erroneous readings of instrum-ents mounted in control room.

The possibility of an accident or malfunction of I a different type than analyzed in the FSAR does not result from this change because no new modes i of failure are introduced that will reduce reli-ability. This change will increase system reli-ability.

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The margin of safety as defined in Tech Specs is i:

not reduced due to this change because no safety '

limits or setpoints changes are a result of this change; however, this should allow for more h,

reliable response to setpoints since this change calls for reduction of heat loads on instrumen-tation. ['79-231 Changed logic of primary containment purge and inerting system so as not to allow opening of 2T48-F338, F339, F340, and F341 valves when a LOCA signal is present without having to manual-ly place normal /open switches in the open or ,

bypass position in order to meet requirements of n IEC 79-19.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new failure modes are added.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits or setpoints are changed.79-252 The position indicating lights on certain T4 8 valves were changed so that both lights are on when the valves are traveling.

ThepossibilityofanaccIdent or malfunction of

~

a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced that would impact or influer<a safety.

The n of safety as defined in Tech Specs is not i .uced due to this change because no set-points or safety limits are changed other than new settings for limit switches which do not affect safety.79-264 Revised t l.e valve isolation signal reset scheme for radwaste sump pump valves to prevent a possible inadvertent discharge from primary containmen; following an accident involving- '

primary cor tainment isolation.

The change is consistent with the FSAR criteria and does not conflict with any Tech Specs  !:

basis. A:.so, no Tech Specs or FSAR change would be neessa"y to implement the proposed change.

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9"79-265 Revised the valve isolation signal reset scheme .

for radwaste sump pump valves to prevent a possibic inadvertent discharge from the primary '

containment following an accident involving primary containment isolation. Objective was to require deliberate operator action to open spec- .

ific valves following receipt of a primary con-tainment isolation signal.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does aat result from this change because the modified logic incorporates a reset feature already anal-y:cd for similar valves in the system. ,

The margin of safety as defined in Tech Specs is not reduced due to this change because the modi-fied logic will actually increase the margin of safety by providing a separate reset circuit.79-271 MSIV Namco limit switches were changed out wth environmentally qualified switches per IEB 79-01B.

The possibility of an accident or malfunction of a different type chan analyzed in the FSAR does not result from this change because no new modes of failure are introduced that are not an improvement in IEEE standards over the old limit  ;

switches.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits or setpoints are affected by this change.79-272 Unit 1 Removed relay noise by removing GE MOV from relays and add resistors, capacitor and diodes to relays in the reactor manual control system. . :

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure to the operation of the relays are added.

The margin of safety as defined in Tech Specs is '

not reduced due to this change because no safety i limits or setnoints are affected by this change.

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79-273 Unit 2 Removed relay noise by removing GE MOV from relays and add resistors, capacitor and diodes to relays in the reactor manual ccatrol system.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure to the operation of the relays are added.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety limits or setpcints are affected by this change.79-274 In order to provide a means of monitoring the "R" recirc generator winding temperature an element was disconnected and a spare was connec-ted to the recorder.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the two elements are exactly alike and perform the same function; thus, no new modes of failure are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because no limits are affected; the elements are alike in function and design.79-290 E41 A new disc was machined off and installed on the HPCI turbine exhaust to torus check valve to make the valve pass LLRT.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced as a result of this change.

The margin of safety as defined in Tech Specs is not reduced due to this change because safety limits are not affected as a result of the modification on the 1E41-F049 valve.79-295 Temporary dP transmitters added to HPCI and RCIC were removed and system is restored to original design.

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r The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the tempor-ary instruments to be installed are isolabic by existing manual valves, and all process lines contain existi ng excess flow check valves; thus, failure mechanisms remain unchanged.

The margin of safety as defined in Tech Specs is not reduced due to this change because the set-points of the instruments paralleled will not be affected. No safety limits involved.79-306 To assure correct selftest operation and improve R B.\1 system safety this activates circuit for lon.c c r period of time. Replaced res.3 tor on signal conditioning cards from 1.6 kohm to 10 kohm per FD1-RJJF.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because basic system operation is unchanged.

The margin of safety as defined in Tech Specs is not reduced due to t..i s change because safety limits are not affected.79-313 Replaced existing steam 1-ine flow dP relays with time delays which prevent isolation of RCIC on high steam line flow for a finite time period after the signal has been received. This will add reliability to the RCIC system for cold auto-start conditions.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the criteria that no singic failure within the RCIC high steam flow isolation configuration shall prevent isolation action is maintained.

The margin of safety as defined in Tech Specs is not reduced due to this change because the Tech Specs surveillance requirements reflect the 13-sec signal delay time described in response to the above first paragraph and, therefore, existing safety margin is not reduced.79-346 By replacing a 1 watt resistor with a 2 watt resistor the probability of failure is reduced which would cause the ICPS to increase from 100 Vdc to greater than 300 Vdc for LPR\ls.

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because system operation is unchanged.

The margin of safety as defhted in Tech Specs is '

not reduced due to this chai. m because safety limits are unaffected. i 79-352 Install stainless steel sleeves on 4 studs 900 apart. Sleeves to be tubing with 3/4" inside diameter, 7/8" OD and 3. 8b , - .06" long. These are to prevent misalignment of valve which could result in the 2B21-F037A-M valves body (vacuum >

breakers) sticking open.

The possibility of an accident or malfunction of a differed type than analyzed in the FSAR does not result from this change because function of equipment will not be changed.

The margin of safety as defined n Tech Specs is not reduced due to this change because it will  ;

be increased due to increased system reliability.79-375 B31 Stiffener plates were added to Recirc pump hangers to give the load a new path away fram potentially weakened structural connections.

  • The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no safety '

related functions of the recirc system are affected, The margin of safety as defined in Tech Specs is not reduced due to this change because this change affects only the recirc pump hanger sup-ports. By reducing the probability of failure of the supports the safety margin is increased.79-386 By using pressure switches 2C71-N002 A/D in lieu of 2T48-R607A/B provision is made for a more reliable circuit than currentiv exists and will -

conform to existing Tech Specs' (tabic 3.6.3.1).

Providing physical separation, upgrading compon-ents from non"Q" to "Q" revising the control circuitry per above ~s tatement and changing of ~

the auxiliary relays or MSIV trip will provide a ,'

more reliable means of' isolating the torus upon actuation of an isolation signal than presently exists.

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The possibility af an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the modified logic incorporates auto isolation of penetra-tions in a manner consistent with existing anal-yzed circuirty.79-394 To prevent valve damage due to rapid post-LOCA closure on the primary containment purge and inerting valves a jack screw was installed in evalve actuator an! set so as to limit valve f travel to 50 degrec'.

l f The possibility of an accident or ralfunction of

/ a different type than analy:cd in the FSAR does

,.~ not result from this change because no new failure modes are introduced by this change.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change increased the safety margin.79-401 Unit ~ Raised the setting of the ADS initiation switches to insure ADS initiation under post-LOCA conditions.

The possibility of an accident or malfunction of a different type than analy cd in the FSAR does not result from this c ht.ng e because the new setpoint will still be wc11 telow normal operat-ing values.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change increases margin of safety by increasing probability of timely safeguard initiation.79-402 Unit 2 Raised the setting of the ADS initiation switches to insure ADS initiation under post-LOCA conditions.

The possibility of an accident or malfunction of a different ty; than analv:cd in the FSAR does not result from this change because the new setpoint will still be vell below normal operat-ing values.

The margin of safety as defined in Tech Specs is not reduced due to this change because this change increases margin of safety by increasing probability of timely safeguard initiation.

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79-421 Due to high humidity and/or moisture the motor of MOV 2E41-F041 failed. Keeping the shunt field energized keeps the motor internals dry ,

improving the system reliability.79-431 2C71 LER commitment 79-111. Primary contain- I ment high/ low alarm was separated electrically and physically by this change. Procedure was aircady correct so the only change was that there are two annunciator windows, one for the high alarm and one for the low alarm (one on top of the other). j The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced; ths change only separates the existing alarm so that they can no longer be confused for each other.

The margin of safety as defined in Tech Specs is not reduced due to this change because the -

change will not have any affect upon the margins ,

set in the Tech Specs.79-447 Changed the existing containment isolation valve i logic so that the requirements of "NUREG-0578- -

TMI-2 lessons learned task 2.1.4, position 4" could be met. Changed the valve oper. logic for the primary containment isolation valves such that upon resetting the isolation signal, the valves will not automatically reopen. '

The possibility of an accident or malfunction of a different type than analy ed in the FSAR does not result from this change because the isola-tion function of the primary containment isola-tion system remains the same; only the reset logic is changed to allow the operator to reopen the isolation valves when he feels plant condi-tions warrant it. ,

The margin of safety as defined in Tech Specs is '

not reduced due to this change because the mar- .

gin is actually increased because of the reasons mentioned above.

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79-448 Changed the existing containment isolation valve logic so that requirements of "NUREG-0578- TMI-2 lessons learned task 2.1.4, position 4" could be met. Changed the valve oper. logic for the primary containment isolation valves such that upon resetting the isolation signal, the valves will not automatically reopen.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the isola-tion function of the primary containment isola-tion system remains the same; only the reset logic is changed to allow the operator to reopen the isolation valves when he feels plant condi-tions warrant it.

The margin of safety as defined in Tech Specs is not reduced due to this change because the mar-gin is actually increased because of the reasons mentioned above.79-461 The setpoints of dP switches on 2B21 were changed from 115 psid to 100 psid to prevent unnecessary deviations from Tech Specs limita-tions on main steam flow.

The possibility of an r :cident or malfunction of a different type than .nalyzed in the FSAR does not result from this change because no new failure modes are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because it is increased due to added conservatism.79-463 HPCI flow transmitter was broken and replaced with a Rosemount transmitter. This replacement will ensure availability of spare parts at all times.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are created due to this change.

The margin of safety as defined in Tech Specs is not reduced due to this, change because no safety r.arg a3 are affected.

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y. _ -- - 79-479 Installed pipe supports on head vent line to provide the RPV head vent line with seismically qualified supports.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the function of the system and the pipe supports have not changed. ,

The margin of safety as defined in Tech Specs is not reduced due to this change because these changes reduce the pipe stresses.79-499 A crossmember was added to the downcomers in the torus and drywell to provide adequate support to the vent header downcomers.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because this change provides more support for this equipment making any type of malfunction less probable.

The margin of safety as defined in Tech Specs is ,

not reduced due to this change because the margin of safety is increased due to additional supports being added. .79-500 T23 The DW interior barrier plate was cut to allow a 3" cicarance between the SRV "D" line and the plate to prevent stresses on the SRV line following heatup.

The possibility of an accide.tt or malfunction of a different type than anal'; zed in the FSAR does not result from this change because only the barrier plate is being modified. The acciA.it of concern is a pipe break.

The margin of safety as defined in Tech Specs is '

not reduced due to this change because the barrier plate is stili provided in the area where it would be needed for the design accid-ent, and the additional clearance will return ,

the piping system to the analyzed condition. '79-502 B21 Support added to primary steam equalizing line per IEB 79-14.

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the function of this support does not change.

The margin of safety as defined in Tech Specs is not reduced due to this changa because the support capacity i.5 increased.79-503 RHR drain line wat secured to the bonnet of RHR valves.

The possibility of an accident or malfunction of a different type then analyzed in the FS \R does not result from tl'is change because the weld will perform the s r.m e function as the threaded pipe to bonnet connection.

The margin of safety as defined in Tech Specs is not reduced due to this change because the valve will still function the same as before the change.79-504 A snubber was removed from the "A" feedwater line in the drywell because it was locked up and damaged. The remaining snubber is sufficient for necessary protection per Behtel letter B-GP-6346 (8-28-79). .

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because mode of piping damping is not affected by removal of snubber. The second snubber on device B21-FDH-20 provides the necessary protection against piping movement during any adverse condition.

The margin of safety as defined in Tech Specs is not reduced due to this change because safety limits are not affected.

80-3 Installed a 3/4" 600011 socket weld ASTM A-105 GR II threaded coupling into packing leak offline from MOV B21-F016 to allow easy removal of packing leak of line.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of failure are introduced.

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The margin of safety as defined in Tech Specs is not reduced due to this change because the coup-ling strength will be equal to or greater than that of the existing line. Therefore, the safety margin will not be decreased.

80-4 Change setpoint of IIPCI steam line low pressure switches to comply with Tech Specs paragraph 3.5.d.1 and table 3.2.2 item 10. Change from 125 psig to 106.5 psig.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the setpoint ~

is conservative and within Tech Specs limit and r ,

no nc: modes of failure are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because during n orr.ia l operation with reactor pressure greater than 113 psig this switch does not affect any safety margin. The change allows compliance with Tech Specs when reactor pressure is at or near 113 psig and ensures safety margins are maintained.

80-18 The high dT isolation signal to the llPCI system was removed. This will prevent spurious isola-tion of the system due ~to llPCI equipment room vent air high dT isolation signals. Unit 2.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the remain-ing isolation signals are sufficiently redundant and diverse by themselves to cause isolation of r the IIPCI steam line.

The margin of safety as defined in Tech Specs is not reduced due to this change because the remaining isolation signals are sufficiently redundant and diverse by themselves to cause isolation of the llPCI steam line.  ;

i 80-39 Two (2) padeyes were welded to two beams above ,

the north equipment hatch in the 130' floor of i the reactor building to provide a means of ,

removing the hatch from the floor. i i

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new fail-ure modes are introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because safety factors associated with this equipment will not be reduced.

80-93 Add a shim plate to E11-F004 RIIR valve disc guide to allow valve to seat better and pass LLRT. .

The possibility of an accident or mal function of a different type than analyzed in the FSAR does not result from this change because the shim will not introduce any effects upon the operation of the valve other than allowing t .ic calve to seat better than it is presently.  !

The margin of safety as defined in Tech Specs is not reduced due to this change because the valve ,

will still be abic to meet its cycling limits  !

and the RIIR system flow limits will not he r affected.80-105 E11.-F015ASB Allows a harder material to be used as an option on the disc facing of the valve.

liarder material should preven + the valve discs l from galling to the seating surfaces. ,

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does  ;

not result from this change because the valve is ,

not changed from the deaign in the FSAR. A  !

harder facing on the disc will not adversely affect the valve disc function.

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The margin of safety as defined in Tech Specs is not reduced due to this change because the valve  :

discs function is not affected.80-109 Cut off the cor, of restraints' I-beam and stiffener plate to achieve at least a 2" gap between downcomers and restraints for RIIR test  :

line to prevent damage to these restraints and '

line during vent header di charge.

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The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the modified restraint will be capabic of supporting the return line while not interfering with the func-tions of the downcomer.

The margin of safety as defined in Tech Specs is not reduced due to this change because Tech Specs margins are not affected by the change.80-114 Installed an antipumping circuit in valve motor control crcuitry to prevent valve motor from pumping af ter valve closes fully. RCIC outboard steam isolation valve.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new unan-alyzed failure modes are created.

The margin of safety as defined in Tech Specs is not reduced due to this change because no safety margins are affected since the ability of the valve to close on an isolation signal is not affected.80-118 The standby gas treatment filter heaters had undersized cables. The~ cables wure replaced with larger cables.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the new cable performs the same function as the old.

The margin of safety as defined in Tech Specs is not reduced due to this change because no limits are changed.80-126 Replaced 1" check valves that were damaged during removal for rcpair with 1 1/2" check valves on the *;C valve air supply accumulator.

Also adapters were installed to accommodate the large valves.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new failure modes are introduced.

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The margin of safety as defined in Tech Specs is not reduced due to this change because the larger valves will retain accumulator pressure as well as the original valves.80-130 The corner of a stiffner plate was cut to allow P70-F056E valve to fully open.

The possibility of an accident or malfunction of ,

a different type than analyzed in the FSAR does "

not result from this change because the snubber  :

capability is unchanged.

The margin of safety as defined in Tech Specs is not reduced due to this change because the snub-ber will not be subjected to a degraded condi-tion. '80-131 In d/w pneumatic system (P70) an autonitrogen backup to the instrument air supply to the ADS valves should be supplied an' operators with a carlier warning of low air supply trouble. To resolve, remove clic ck valve internals 2P7 0-F016. Reset 2P70-PS-N006 to actuate at 85 psig decreasing. Reset 2P70-PS-N003 to actuate at 80 psig decreasing. '

The possibility of an accident or malfunction of f a different type than analyzed in the FSAR does not result from this change because no new failure modes are being introduced.

The margin of safety as defined in Tech Specs is not reduced due to this change because safety is increased by the addition of an automatic air supply backup the the ADS valves.80-178 Replaced a snubber on the RHR system which was locked up with a rigid restraint.

The possibility of an accident or malfunctica of a different type than analyzed in the FSAR does not result from this change because the design i rating is still well within bounds. Since the '

subber will be removed, the snubber lockup fail-ure mode is climinated. No additional failure modes are produced.

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The margin of safety as defined in Tech Specs is not reduced due to this change because mechanic-al snubbers are not in Tech Specs and the mech-anical snubbers are within safe limitations.

Allowable stresses due to thermal loading are not increased above allowable with the rigid strut. No margins of safety are affected.80-179 Replaced a snubber on te RHR sytem which was

'ocked up with a rigid restraint per Bechtel's recommendations.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the design rating is still well within bounds. Since the subber will be removed, the snubber lockup f ail-ure mode is climinated. No additional failure modes are produced.

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The margin of safety as defined in Tech Specs is not reduced due to this change because mechanic-al snubbers are not in Tech Specs and the mech-anical snubbers are within safe limitations.

Allowabic stresses due to thermal loading ar2 not increased above allowabic with the rigid strut. No margins of safety are affected.

l'80-181 Replaced mechanical snubber with a 4" stroke with a snubber having a 2" stroke. The original snubber was locked up.

The margin of safety as defined in Tech Specs is not reduced due to this change because mechanic-al snubbers are not in Tech Specs and the mech-anical snubbers are within safe limitations.

Allowabic stresses due to thermal loading are not increased above allowable with the rigid strut. No margins of safety are affected.80-181 Replaced mechanical snubber with a 4" stroke with a snubber having a 2" stroke. The original snubber was locked up.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the design rating is still well within bounds. Since the snubber will be removed and the snubber will be replaced with one that still has same load range no additional failure modes are produced.

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The margin of safety as defined in Tech Specs is not reduced due to this change because the margin of safety is not affected since the replacement snubber is within the same load range. Allowable stresses are not increased.80-222 RHR supports modified to reduce the chances of failing due to design basis carthquake.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the new supports will provide for the proper safety ,

factors within their design for meeting the requirements of the DBE loading.

The margin of safety as defined in Tech Specs is not reduced due to this change because no Tech Specs safety margins will be affected.80-403 2T48 Valve steams at the nitrogen storage tanks are being replaced as they go bad with a new material because the material presently used is no longer available. 1 The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result fcom this change because therc are no new failure modes introdu~ced by the new material.

The margin of safety as defined in Tech Specs is not reduced due to this change because new stem ,

material will still assure proper system operation.80-413 B21 Revised setpoints of SRV temperature recorders from 2000F tm 2500F. Temp is  ;

slightly higher than 2000F during normal oper-ation so this change will eliminate false alarms.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the opera- ,

tion of the SRVs and that of the SRV temp recorder is not changed.

The margin of safety as defined in Tech Specs is ,

not reduced due to this change because a small  !

amount of seat leakage may not be detected buy any type of steam Icak releasing a substantial amount of steam would be detected.

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78-332 To provide reliable operation of a radwaste valve a solenoid was replaced with a different brand. No safety systems were affected.

79-20 Removed a hanger on the radwaste system to bring the building settlement to acceptable values.

No safety system were affected.79-286 A cable pulley and brass plug spacer were machined and installed on the radwaste capping machine to allow for double cabic arrangement to the boom arm. No safety systems were affected.  ;79-328 A valve was replaced with a different brand for more reliabic operation. No safety systems were ,

affected.  ;79-341 The wiring was changed for the program computer so that the logic for a radwaste valve will be consistent with other valves.

i 79-351 A centrifuge radwaste valve was replaced with a di ff erent brand for more reliabic operation. No safety systems were affected.

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Georgia Power Company Plant E. I. Hatch Baxley, GA 31513 i

I Test or Experiement Requests  !

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Curtis L. Coggin Supt. Plt. Eng. Serv. ,

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The following tests or experiments were completed in 1980.

75-12 RCIC electronic overspeed trip was disabled for .

1 quick start in order to determine peak speed in worst drain down condition (EGR supply line intentionally drained). Peak speed was found to be 5200-5500 rpm.

80-4 Precoat vessel "D" and with the holding pump running remove the vessel cover. The intent of this test is to be assured that the vessels are being precoated properly and to locate any fouled positions of the vessel's elements. The conclusions drawn were that the initial precoat '

was good enough but could be bettered by slowing the rate of precoat application.

80-2 With the Rx mode switch in startup/ hot standby all control rods were withdrawn to "48" and inserted to position "0" individually and continuously. SRh! readings for all operable SR31s and coo-dinates of rods pulled were record- ,

ed. This te.t was used to verify subcriticality per IEB 79-26 step 3-a.

The probability of occurrence and the consequen-ces of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR due to this change because equipment reliability is unchanged.

The possibility of an accident of a malfunction of a different type analyzed in the FSAR does not result from this change because system operation is unchanged.

The margin of safety as defined in Tech Specs is .

not reduced due to this change because safety  ;

limits are not affected.

  • 80-8 Exploration and engineering evaluation of soil backfill in the area of the intake was done in ,

order to evaluate depressions in the asphalt '

pavement and apparent settlement of backfill immediately south of the intake structure.

The probability of occurrence and the consequen- i ces of an accident or malfunction of equipment important to safety are not increased above  ;

those analy cd in the ESAR due to this TER because:

Page 37

1. No significant amount of backfill will be removed to degrade the piping system in the event of.an accident or malfunction.
2. The location of the pipes hat ' been surveyed and marked in order to prevent inadvertently destroying a pipe.
3. Test pits will be dug with caution and under the supervision of Law Engineering and will not exceed the length allowed by analysis for maximum length of pipe that may be uncovered.
4. Test pits will be backfilled as soon as practical.

The possibility of an accident or malfunction of a different type than that analyzed in the FSAR does not result from this TER because:

1. No significant amount of backfill will be removed to degrade the piping system in the event of an accident or malfunction.
2. The location of the pipes have been surveyed and marked in order to prevent inadvertently destroying a pipe.
3. Test pits will be dug with caution and under the supervision of Law Engineering and will not exceed the length allowed by analysis for maximum length of pipe that may be uncovered.

i 4. Test pits will be backfilled as soon as practical.

The margin safety as defined in Tech Specs is l not reduced due to this TER because:

1. No significant amount of backfill will be removed to degrade the piping system in the event of an accident or malfunction.
2. The location of the pipes have been surveyed and marked in order to prevent inadvertently destroying a pipe. .
3. Test pits will be dug with caution and under the supervision of Law En gineer in g and will not exceed the length allowed by analysis
for maximum length of pipe that may be uncovered.
4. Test pits will be backfilled as soon as practical.

80-14 Core flow and recirc drive flow were measured at various levels of flow to determine single loop and two loop operating data. This test was used to provide data in order to submit a Tech Specs change to allow for singic loop operation.

Page 38

c Georgia Power Company ,

Plant E. I. Hatch Baxley, GA 31513 t f

f i

SRV Challenges for 1980  ;

l s

i b

Curtis L. Coggin  :

Supt. Plt. Eng. Serv. ,

U 1

0

SRV Challenges for 1980 Unit 1 Date Valves Actuated 5-13-80 J,H,D,E,C,K 6-26-80 C,D,E,H,J,K, Valves H and J opened a total of 4 times each 11-10-80 B21-F013C was opened manually Unit 2 Date Valves Actuated ETIT80 All relief valves 9-8-80 A,E,C,M,G Page 39

- a,u. .

OCCUPATIONAL PERSONNEL RADIATION EXPOSURE I

OCCUPATION PERSONNEL RADIATION EXPOSURE This section has been compiled to satisfy the requirements of E. I.

Hatch Unit I Technical Specifications Section 6.0.H.l.b (3) and to assure compliance with the Code of Federal Regulations as set forth in the pertinent sections of Title 10. Special attention was afforded to the methods prescribed by the Commission in Regulation Guide 1.16 in order that the intent as well as the letter of these laws might be fulfilled while providing meaningful information as to the degree and circumstances of all exposures of personnel at this facility. An indication of the effectiveness of the plant radiation safety program may be inferred from the large number of personnel with no measureable exposure of minimal dose.

The time period covered by this tabulation extended from 1 January, 1980 through 31 December 1980. All monitored personnel were included in survey as provided under 10 CFR 20.407 (b) (1) (i). Individual exposures as indicated by selfreading pocket ion chambers were recorded daily with the use of a programmable calculator and stored in the associated mass memory disc system. These exposures were tabulated and printed in hard copy on a weekly basis and then required, along with the difference between these readings and the most restrictive exposure limit. The corresponding ion chamber results as reccrded on the disc dosimetry files were supplanted by thermo-luminescent dosimeter measurements made over a period of approximately one month as the TLD data became available from a vendor.

Each person listed in the dosimetry disc files was assigned a usual job category based on his expected daily activities. There are six job categories of this nature and are identified in the following table. Running totals of dose acquired in each of these categories were maintained for each person in his dosimetry file.

This data is accumulated through two processes:

1. Each daily dosimeter reading, in addition to being rethined for individual exposure record, is added to the total representing the cumulative dose in his usually job category.
2. In order to account for exposure in job categories other than the usual category, the job category dictated by the circumstances of ,

the covered exposure is indicated on each radiation work permit.

This data is input via mark-sense cards to the calculator, which substracts the covered exposure from the usual job category total (to which the exposure was added in the daily inputs) and adds this dose to the job category as indicated by the radiation work permits.

The implicit assumption involved in this method of accounting for exposure in different tasks is that all exposure acquired in job categories other than the usual will be documented by a radiation work permit. This circumstance should prevail in all significant Cases.

Page 40 L-----__ __

1980 PLANT E. I. IIATCII STATISTICAL

SUMMARY

RADIATION EXPOSURE REPORT (10 CFR 20.407)

EXPOSURE RANGE (REM) NO. OF INDIVIDUALS N.M.E. 1286

< .1 1039 0.1 - 0.25 396 0.25 - 0.5 258 0.5 - 0.75 98 0.75 - 1.00 73 1-2 61 2-3 4 3-4 0 4-5 1 No exposures greater than 5 REM This report is submitted in accordance with paragraph (b) (1) (i) of 10 CFR 20.407.

Page 41 q., ..f_

__ 1 __ _

/,,, 1980

r. . PLANT E. I. HATCH PERSONNEL EXPOSURE BY TASK AND BY JOB (PER REGULATORY GUIDE 1.16)
  1. Personnel ( >100 rn r e rn .s Total fi n n - P e ra W o r t. n Job Function 5 t at i on l Ut i 11 t u l Cont rc t St at i on l Ut i 11 t 'l Cent rc t ROUTItiE OPERAT10t45 t SURVEILLAhCE M ai nt e n anc e o Con 2truction 14 0 3 5 0 0 Operation 2 139 3 0 95 1 0 Heal t h Physic s & L ab 44 2 41 30 1 20 Supervizory & Of fice St af f 35 15 2 8 4 1 Engineering Staff 30 3 6 7 1 2 POUTItlE PLAtiT li A l tit E tintiC E Maint enanc e & Cons truc t ion 188 , s6 88 2 13 Operations 60 0 0 28 0 0 Health Phys ics & Lab 9 0 2 6 0 0 Supervisorv & Office Staff 6 1 0 1 0 0 Engineering Staff 24 2 10 4 0 4 It4 SERVICE It45PECT I Ori Haintenance L Construction 0 0 6 0 0 1 Operations 0 0 0 0 0 0 Health Phy2ics a Lab O O O O O 0, Supervisory & Office St af f 0 0 0 0 0 0 Engineering Staff 1 1 2 0 0 0 SPECIAL PL At1T fir 1 I t4 T Ell A tic E 11 ai nt e n anc e a Construction 102 22 424 47 5 124 Operationi 25 0 0 5 0 0 He-alth Phy2ics 0- L ab 0 0 41 0 0 11 Supervisory & Office St af f 0 2 8 0 0 2 Engineering St af f 10 __ 8 66 3 2 21 UASTE PROCESSIt4G Mai nt e n anc e & Construction 8 0 1 2 0 0 Operations 21 0 0 4 0 0 Health Physics ? Lab 0 0 0 0 0 0 Supervisory L Office Staff 0 0 0 0 0 0 Engine ering St af f 0 0 0 0 0 0 RE F UEL IllG llai nt en anc e O Con;?ruction 0 0 0 0 0 0 Operations 1 0 0 0 0 0 He al t h Phy2ics S L ab 0 0 0 0 0 0 Supervisory a Office St af f 0 0 0 0 0 0 Engineering St af f 0 1 0 0 0 0 TOTALS M ai nt e n anc t Construction 204 26 4 51 147 7 149 Ope r at i ona 182 3 0 137 1 0 He al t h Physics A L ab 48 2 75 37 1 34 Supervisory & Office 5.t a r i 42 1 :2 10 10 5 2 Engineering Staff 56 , 13 80 16 4 30 Page 42

6 ee o REACTOR COOLANT CllDfISTRY SUM 3fARY i

i l l t

i i

I i

l l

l

e .i .

REACTOR COOLANT CHEMISTRY Tabulations on a monthly basis of values of SJAE Isotopics ar.d Reactor Coolant system parameters as required by Section 4.6.2.1 of the Unit I Technical Specifications found in the following tables.

Unit II values as also shown, although it is not required that they be reported.

t i

UNIT 11 SJAE ISCTOPICS I UCi/SEC lDATE 1980 MWT ixe-133 Kr-87 ,Kr-is kr-85M xe-135 xe-133 iAR=41 iN=l3  ;($1X)

'JAN 16 j2367 l 1.45 ; 4.26 l 2.70 i 1.88 9.99  ; 2.92 j 1.73 4.22 3.02 i i l E3 1 E2 8 E2 1 E2 E2 . E2 I El E3 E3 FEB 12 3.42 1 d.02 i 5.39 l 3.03 1.42 ) 4.59 l 1.60 3.42 6.94 l2186 I lt E3 I E2 I E2 l E2  ! E3 f E2 1 El E3 E3 MAR 18 2391 7.08 ; 1.27 7.53 } 3.75 2.16 7.70 l< 5.15 2.u6 g 1.24 E3 I E3 . E2 E2 E3 lE2 I E0 E3 1 E3  ;

APRIL 15 2415 i 1.90 iI 4.45 g E3 2.06 j 1.00 1 7.16 1.77 g5 2.98 g4.33 i 3.60 i E4 E3 i E3 I E3 E3

  • El E3
  • E4 r MAY 13 2430 5.14 1.11 i 8.63 4.15 1.98 5.48 4 1.50 1.83 1.01, lE4 '

l E3 l '

E3 8 E2 E2 El E2 El E3 JUNE 17 2359 2.11 l 4.50 2.73 1.03 4.90 1.40 < 2.66 3.60 3.57 l E4 I E3 k E3 f E3 l E3 I E3 ' El l E1  ! E4 !

JULY 15 2276 1.37 E4 3.07 l E3 g 2.14 E3 r

i E2 9.25 i 5.50 I E3 d.40 E2 5 1.44 El l 1.54 i E3 l2.if

. E4 ,

AUG 12 2407 2.96 G.45 3.95 '

1.88 < 9.10 . 2.12 s' 3.13 4.61 j4.78 E4 Q l E3 l E3 El i E3 El E3 E4 SEPT 16 2410 4.35 l 6 76 1I4.57 15 2.46 l 1.10 - 4.17 5 3.63 l 4.13 g 6.90 i E4 1 E3 . E3 I E2 I E4 I E3 El I E3

  • E4 OCT 14 l1792 1 5.16 j 8.Id [ 5.30 'j I E4 2.06 j 1.02 e 3.41 g 5 3.76 i 7.46 I E3 g 8.07.

I f E4 I E3 l E3 I E4 I E3 El - E4 NOV 12 1721 1.15 i 4.77 2.79 l 1.48 2.76 E4 1 E3 i E3  ! 1.29.l 5.89 E3 E3 l1.36 E3 .< 2.38 El . E3 E4 DEC 16 1939 2.24 0.17 3.26 1.51 6.90 1.42 3.03

  • 4.17 E4 E3 E3 E3 E3 "E3 l<2.59 El E3 l E4 REAC"'CW CFEMISTRY FOWER ) ICDINES UCi/ML DATE MWT I-131 i I-132 eI-133 tI-134 i I-135 DEI 131 JAN 16 j2378 2.d23 4.136 l1.163 l4.2d/ 6.690 6.8411 l E-3 E-3  ! E-2 IE-3 E-3 E-3 , ,

FE8 12 2196 l 1.020 2.341 j1.514 l."-2

1. '.13 1.395 l1.6502 IE-2 E-2 IE-2 E-2 IE-2  !

MAR 16 2403 tl.479 1 3.867 l 4.1 M 2.961 j 3.427 [ 3.0666 lE-2 3 E-2 !E-2 E-2 1 E-2 tE-2 APRII.15 2414 l 1.833 t 5.243 3.961 4.323 3.162 l 3.4303 1 E-2 i E-2 E-2 E-2 E-2 IE-2 ,

HAY 13 2417

  • 1.193 j 3.923 2.934 3.609 1.690 a2.3302 lE-2 I E-2 E-2 E-2 E-2 lE-2 .

JUNE 17 2326 l1.143 j 3.009 i7.323 4.728 6.170 1 3.8284 IE-2 1 E-2 IE-2 E-2 E-2 lE-2 JULY 15 2276 1.279 l 2.172 6.056 2.745 J.778 lJ.3566 .

E-2 I E-2 E-2 E-2 E-2 IE-2 AUG 12 2405 2.602 4.020 1.917 4.691 5.3801 E-2 E-2 l8.111

.E-2 E-2 E-2 lE-2 SEPT 16 2625 8.762 1.326 j2.515 1.050 1 1.968 1.8040 E-2 E-1 1 E-1 E-1 E-1 i E-1 OCT 14 1792 d.077 1.687 d.296 ,3.176 4.824 g1.13d3 E-2 E-1 E-2 .E-2 E-2  ! E-1 NOV 12 1915 1.245 l 2.513 1.200 6.730 l o.986 g1.7298 E-2 I E-2 E-2 E-3 1 E-3 E-2 PEC 16 1939 2.038 6 4.220 l3.410 2.334 l 2.700 i 3.37ea I E-2 3 E-2 IE-2 E-2 f. E-2 f.E-2 1

Page 43

. . - - - - - - . . - , . - . .- . . . _ - _ _ - _ = _ _ _ . - ._ - ~ _ . . . . . . - . _ . .

s e.o4 I

i T

i

. I i

j I i i i

i l

UNIT $2 SJAE ISOTOPICS I

' uC1/SEC

CATE IPWT Xa 139 i Kr-d7 Ikr-ss Kr-d5M Xe-l35 Xa-L33 AP-4L N-L3 L (SIX) '

j JAN 16 2411 2.89 2.J3 1.19 51.62 1.20 5.96 3.06

<3.13 3.36 E2 El El El El EO EO E3 i E2 FEB 13 2418 2.72 2.71 5 8.53 <2.57 8.95 . s6.d9 5.21 2.80 J.06 l

E2 El E0 El EO EO - EO E3 E2 MAR 12 0 .51.20 42.71 < 2.99 f s8.30 7.06 42.42 < 2.37 < 4.95 7.0b i E-1 E-2 E-2 E-2 E-2 E-2 E-2 E-2 E-2  !

APRIL 16 0 [< 9. 42 (2.47 ,5 2.67 '<7.71 < 1.11 s2.39 < 1.49 < 3.39 0 ,

i E-2 E-2 E-2 E-2 E-2 E-2 E-2 E-2 MAY 21 2419 3.02 [

3.34 j < 1. 2 4 s3.80 1.12 5 d.19 < 1.47 4.34 3.47  ;

n E2 El l El El El EO E0 E3 E2 1

JUNE IS 2421 2.99 3.01 ;< 7. 41 s2.24 1.18 5 4.22 < 1.08 3.55 3.41  ;

E2 El l_ E0 El El EO E0 E3 E2

.i JULY 16 2366 2.34 i<u.06 g< 1.19 53.50 1.55 5 7.40 7.79 L

3.30 l 2.49i t 1 E2 '

EO I El El EO E3 El EO i E2 l j

! AUG 13 2421 2.4b a 2.30 *<E-1 5.731i<2.28 l 1.84 is3.65 5. 9 4 . l 1.83 1 2.88j El i EO  !

E0 l En I E-1 i

E-1 8 E2 I El i SEPT 17 2420 3.14 <1.23 g< 1.76El 155.10 j< 6.79 l<1.77 'i.59 3.14i  !

OCT 15 E2 E1 .

I El f EO El EO l 3.25 E3 l E2 l '

2303 l 3.53 l 3.24 is 5.73 <1.73 i 1.37 is3.25 4.54 2.54 1 3.99

  • NOV 12 I E2 t El I EO El I El l E0 i EO g 'E3 i E2 I ,

0 P 1.15 l E-1

<4.15 E-2 i< 4.06 l*8.03 l E-2

< 1.86 <3.58 is 2.97 r< 4.77 1 0 I. E-2 E-2 E-2 I E-2 I E-2 I

}

DEC 17 0 s2.02 54.70 < 4.92 <1.46 2.19 E' 1 E-2 s4.08 < 1.75 6.67 0 [

E-2 E-1 E-2 E-2 E-2 E-2

,i ~

4 POWER k IODINES UCi/M1 CATE K4T I-131 I-132 i I-133 I-134

  • I-135 l
  • DEI 131 JAN 16 g432 1.799 4.577 3.201 1.145 4.751 1.a027 j f E-5 E-4 E-4 E-3 E-4

. t FEa 13 2427 3.090 6.667 3.134 1.712 E-4 , '!

5.689 2.1641 l E-5 E-4 E-4 E-3 1 E-4 E-4 MAR 12 0 4.468 1.499 < 3.784 1.439 (< 3.725 5.0078 h E-6 E-5 E-6 E-6 I E-7 E-6 APRIL 15 0 1.871 1.297 l 6.853 < 1. 2 3 8 5.238 2.0608 [

E-5 E-7 I E-6 E-6 E-7 E-5 t'

HAY 21 2420 9.736 4.766 l 1.85d 1.100 I

E-5 5.595 6.8176 [

E-4 1 E-3 E-3 E-4 E-4 JUNE id 2421 2.156 4.915 3.244 2. 0" 5.556 2.0903 {

1 Il E-5 E-4 E-4 E-3 E-4  !

i E-4 - '

JULY 16l2333 l4.335 1.050 6.446 2.253 1.006 3.7815

+

t i I E-5 E-3 E-4 E-3 E-3 E-4 I

AUG 13 1417 2 1.219 9.497 8.945 1.196 E-4 1.565 5.2460 -

l E-4 E-4 E-3 E-3 E-4 l i

SEPT 17 9430 4.217 a.555 3.871 1.91; 7.610 .2.7390 I E-5 E-4 E-4 E-3 E-4 E-4 OCT 15 2303 1.711 2.d16 < 1.957 7.385 3.071 6.5605 t E-5 E-4 E-4. E-4 E-4 E-5

!4V 12 0 :1.949 4.548 < 3.845 2.643 < 7.170 a

E-6 E-6 2.1573 i E-6 E-6 E-7 E-6 DEC 11 0 2.261 1.645 3.538 <5.031 51.166 2.2872 E-7 E-8 E-7 E-7 .

E-7 (-7 -

i j i i

r i I l

Page 44 i i

I

! i I

r 2 .i. .-***# -.s..d- - - - + - -