ML20112F857

Interim Annual Operating Rept for 1977

ML20112F857
Person / Time
Site:	Hatch
Issue date:	12/31/1977
From:	Manry M GEORGIA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8501160067
Download: ML20112F857 (56)

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l V) TABLE OF C0tTTENTS PAGE INTIODUCTION 1 OPERATING SIFhARY 2 DESIGI CHANGES, TESTS OR EXPERIMENTS, AND SAFEIY-REIATED $AINTENANCE Plant Design Changes 6 Test Or Experiment Requests 17 Safety-Iblated Maintenance 19 DMA TABILATICNS AND UNIQUE REPORTING REQUIREMENTS Occupational Personnel Radiation Exposure 42 leactor Coolant Chemistry Sumary 46 l

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8501160067 771231

-PDR ADOCK 05000321 R_ _ PDR I h k

INTRODUCTION Edwin I. Hatch Nuc1 car Plant Unit 1 is a Light Water Reactor of 700 MWe Net Maximum Dependable Capacity.

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

Georgia Power Company, seventeen and seven tenths percent (17.7%)

. Municipal Electric Authority of Georgia, two and two tenths percent (2.2%) City of Dalton, and thirty percent (30%) Oglethorpe Electric Membership Corporation. The plant is located at a site approximately eleven miles north of Baxley, Georgia on U.S. Highway 1 on the Altamaha river. General Electric Company furnished the Boiling Water Reactor Nuclear Steam Supply System and , the Turbine-Generator. The plant was designed by Southern Company Services Inc. with assistance provided by Bechtel Power corporation. The condenser cooling method employs forced draft cooling towers and circulating water system. Normal makeup is drawn from the Altamaha river. The plant is subject to license DPR-57, issued August 6, 1974 pursuant to Docket Number 50-321. This unit

! , achi.eved initial criticality on September 12, 1974 and initial generator synchronization on. November 11, 1974. The unit .was declared commercial on December 31, 1975. Georgia Power Company has sole responsibility for overall planning, design, construction, operation, maintenance and disposal of the plant.

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SUMMARY

l977 January 3 The generator came off the line due to a SRV bellows failure alarm at 1656. Possible leakage was not confirmed; a pressure switch was replaced, and the unit tied back to the line on 1-4 at 0634 after preconditioning.

January 6 Load was dropped to 55% to check feed pump gears and the shaft driven oil pump.

Preconditioning was begun and load was steadily increased.

January 9 The unit scrammed at 0524 due to SRV opening. Rust and corrosion was found in the pilot and second stage area of one valve which was replaced with a spare. The outage was extended due to computer prob 1. ems, RSCS, and condensate conductivity. The unit tied back to the line on 1-10 at 1943.

January 15 A control valve test was successfully

, performed while power was reduced for feed pump maintenance for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Steady state

was reached the same day at 1050.

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l January 21 Power was reduced to 55% to pull rods for a pattern improvement. Turbine .and control valve tests were performed while reducing power. Steady state was reached on 1-26 at 0050 after preconditioning.

February 1 The reactor scrammed at 0430 when SRV "E" opened. The valve would not seat properly so the pilot was replaced. The unit tied l back, to the line on 2-2 at 1324 after preconditioning.

r February 4 ~The reactor scrammed at 0013 due to. SRV's L

opening. The valves were sent to Wyle Labs j- for tests and ' repair. SRV repair was completed on 2-11. Saddles were discovered to have been left off on some safety system piping; the outage was extended for the installation of these. The unit tied back l

to the line on 2-15 at 0420.- The SRV's were tested and the unit was brought back down for. saddle repair on 2-15 at 2225. Steady 2-22 after tying to the c

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r'N state was reached on line on 2-19 at 1947 and preconditioning.

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February 27 The reactor scrammed at 1230 because of circulation pump trip and loss of condenser vacuum due to a ruptured disc. The disc was replaced and the generator-was tied to the line on 3-1 at 2230 and reached steady state on 3-3 after preconditioning.

March 11 Power was reduced for the refueling outage at 1950. Refueling operations were completed by 5-7, but the outage was extended to 5-18 in order to complete _1ocal leak rate testing per Technical Specifications. While preparing to bring the unit on the line numerous leaks were found in the recirculation system and e repaired. The unit tied back to the line on 5-22 at 0346 Turbine and relief valve tests were run, and the unit scrammed while the to the line on 0923.

ty generator at Theing unithouse was tied load to back the same. day at 2326.

May 24 The reactor. scrammed at 0741 due to a condensate pump trip due to an error- in valve alignment. The unit was_ tied the line at 2030 and preparation for sequence exchange continued.

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i June 2 An on-line sequence exchange from "B" to. "A"~

was started at 1900. The unit reached steady state on.6-11 after preconditioning.

[ June 17 Power was reduced due to drywell leakage, and the unit came off line on 6-18 .at 0411.

After repairs, the unit was tied back to the line on 6-20 at 1114 and reached full power on 6-23 at 1540 after preconditioning.

! ' July 3 The reactor scrammed at 1435 because 'of.

bypass (valve opening. The uni t' was tied back to the line on 7-4 at 0325 'and

. preconditioning was' started.

July;6 While preconditioning, a leak was found' the above seat drain line_ flange on. the control valves.. The unit was brought off-line at 1422. After repairs the unit was. tied back

• -to the 'line on 7-7 at '0715' and preconditioning was started.

July 10 yThe reactor Iscrammed: at 1017 because of '

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bypass valve Jopening. :The__ unit .was' tied back-to the line on the same day at 2100 and -

reached steady state on 7-13 after preconditioning. .

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/N July 30 A power reduction was started at 0100 for an

('# l on-line sequence exchange: steady state was cached again on 8-4 after preconditioning.

August 9 .ne reactor scrammed at 1428 because of a broken lead on turbine hearing sensor number

4. After repair the unit was tied back to the line on 8-10 at 1452, and preconditioning was begun.

August 13 The unit was brought down and off-line at 0211 after leaks were found on the inner shell manhole in the low pressure turbine.

Repairs were completed, and the unit was tied back to the line on 8-15 at 0833.

Preconditioning was started, and the reactor reached full power on 8-18.

August 27 Power was reduced at 2100 for a rod pattern adjustment. Steady state was reached on 9-1 after preconditioning.

September 8 Power was reduced to 35% at 0050 to cican clogged filters on circulation pumps.

Preconditioning was slow due to computer

, being out of service.

September 9 The reactor scrammed at 1005, while still preconditioning, due to a high water level in reactor caused by A and B RFPT run out.

The outage was extended due to a turbine over excitation problem. The unit was tied to the line on 9-11 at 0620, and preconditioning was begun.

September 12 The reactor scrammed at 1355 when bypass-valves opened. The unit was tied to the line on the same day at 2208, and preconditioning was started.

September 14 Load was reduced in order to change rod pattern in preconditioning ramp from bypass valv# scram. In addition repairs were amde to MSR "C". Preconditioning was then resumed.

September 17 A power reduction was begun at 2250 for a rod -pattern change. Steady state was i reached on 9-19 after preconditioning.

September 30 Power was-reduced.at 2235 for an on-line rod sequence exchange which was completed on

(/T) 9-31. Preconditioning was started.

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October 6 The reactor scrammed at 1031 when personnel b

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,s failed to follow procedure correctl y. SRV

( ) problems developed and the decision was made i/ to stay down while SRV's were sent to Wyl e Labs for tests and repairs. The outage was extended an additional day to repair steam elaks on 1A SJAE. The unit was tied to the line on 10-18 9 1112, and preconditioning was begun.

October 21 While still preconditioning from SRV repair, the reactor scrammed at 0523 from an inboard MSIV partial closure due to drywell pneumatics low pressure when nitrogen supply ran out because of a sticking gage pointer.

The outage was extended by problems with a RWCU isolation valve and RSCS. The unit was tied to the line on 10-22 0 0545, and precnoditioning was started.

October 25 The reactor scrammed at 1352 from a high APRM flux when bypass valves opened. The unit was tied to the line on 10-26 at 0832, and steady state was reached on 10-30 after precon.ditioning.

December 1 A power reduction was started at 0302 in order to fix icaks in the turbine building, drywell, and MSR's, but at 0607 the reactor scrammed when high flux was read by IRM's.

The reactor was put in cold shutdown, the repairs were completed, and the reactor was brought to critical at 0329, but at 0820 leaks were discovered on SRV's and HPCI so the reactor was placed in cold shutdown again at 1250. When repairs were completed the unit was tied to the line on 12-6 at 0319, and reached steady state on 12-8 after preconditioning.

December 12 A power reduction was started at 1900 for an on-line sequence exchange which was completed on 12-13. Preconditioning was begun, and steady state was reached.

December 17 The reactor scrammed at 2225 from high APRM flux due to bypass valves opening. The outage was extended with problems in RSCS and Icaks in condensate minimum fl ow line which became evident on 12-18. After repairs the unit was tied to the line on 12-19 at 2218. Steady state was reached on i e- 12-24 after preconditioning.

\ December 28 The ractor scrammed at 0957 when hypass valves opened causing high APRM flux. The i unit was tied back to the line on 12-29 at 0131 and preconditioning was begun.

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O DESIGN CHANGES TEST OR EXPERIMENTS '

AND SAFETY RELATED MAINTENANCE l

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x/ t.74-119 More stringent limits on torus temperatures necessitated the replacement of the Foxboro Multipoint Recorder, which was difficult to read, with a Speedomax M Mark III Recorder. Other associated changes included the addition of a Century 479 temperature-millivolt transmitter. Provisions were made to measure both torus water and air temperatures. The safe operation of the system was not affected since this change improved measurement accuracy.

2. 75-48 Area radiation monitor number 7 was moved from its close proximity to the RHR lines to a point in the N.E.

corner of the reactor building to prevent spurious alarming. The probability of an accident was not increased and the margin of safety was not decreased because the function of the monitor was not changed.

The reliability was improved by eliminating spurious responses.

3. 75-64 The overload jumpers were removed from the RHR service water valves E11-F068A 6 B and the drive motors were changed from 15 minute duty cycle to continuous duty cycle. Changing the drive motor to one with a continuous duty rating improved its reliability. The safety of the system was not decreased, the

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and probability of an accident was not increased because

, E11-F068 A 6 B was not required to open at the time of an accident.

4.75-246 The second stage area of the Model 7367F Target Rock Safety Relief Valves was modified by cutting off the stem insert (P/N 83) in an effort to minimize bending of the second stage stem. 'This change upgraded the valves to the equivalent of the Model 7467F. Since the modification resulted from bench testing and improved valve reliability, the probability of an accident was

not increased and the margin of safety was not l

decreased.

5,75-252 This change added an todine and noble gas sample line purge switch on panel H11-P600 per FDT submitted by GE so that purging could be initiated from the control room. The probability of an accident or safety related malfunction was not increased since the system's function was not changed. The operability and convenience was extended by permitting purge initiation from control room.

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3. 76-23 A test connection was installed on the bottom of RilR minimum flow line ("B" Loop) in order to allow 4"

the volume of pipe between valves E11-F007B and E11-F046 B 60 to be completely drained for Local Leak Rate Testing. Thus the reliability of the test to determine the integrity of isolation valve E11-F007 was increased. The probability of an accident or a safety system malfunction was not increased and the margin of safety was not decreased by this change.

7. 76-24 A test connection was installed on the bottom of RHR 4" minimum flow line ("A" Loop) in order to allow the volume of pipe between valves E11-F007A and E11-F046 A 4C to be compl etely drained for Local Leak Rate Testing. Thus the reliability of the test to determine the integrity of isolation val ve E11-F007A was increased. The probability of an accident or a safety system malfunction was not increased, and the margin of safety was not decreased by this change.

8. 76-25 Vent valves were added on the RCIC turbine side of check valve E51-F021 and the position of valves E51-F057 6 F058 was changed so that the test connection would protrude from the bottom of the volume between valves E51-F019 6 F021 The entire volume could then be drained to facilitate the Local Leak Rate Testing.

These changes increased the safety of the system

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because the reliability of the test to determine the integrity of.the valves was increased.

9. 76-58 A Vent-Drain Connection was added to the RWCH pump suction from the recirculation system line to allow for complete drainage of the volume on the inboard side of valve G31-F001 and Local Leak Rate Testing of same.

This addition improved overall plant safety by allowing more reliable tests of isolation valve integrity.

Therefore, the probability of an accident or safety system failure was not increased and the margin of safety was increased.

10.-76-63 The vendor's change in specification of the D11/n21 G-M

tubes in the Process and Area Radiation vonitors l necessitated the replacement. of electrical components l

in the quenching circuit of the sensors to insure that

! the G-M tubes would quench properly. The change increased the reliability of the radiation monitors l byinsuring proper quenching of spikes. The margin of L safety was therefore increased.

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The Torus to Drywell Vacuum breaker Limit Switches, T48-F0131 5 K were single pole Licon 65-430095. After failure they were replaced with a double pole Licon 65-430125 in which the spare contacts were wired in parallel for increased reliability. Since the switch functions in the same manner as the old switch, no new modes of failure were introduced so the probability of an accident was not increas-d and the margin of safety was not decreased.

12. 76-72 In order to remedy possible faulty contact operation in the APRM and IRM bypass switches.at the 90 degree - 270 degree positions, GE submitted FDI-RJHO, which changed the switches and other necessary hardware to avoid simultaneous operation of adjacent modes as formerly possible. The change eliminated a possible mode of switch failure and therefore decreased the possibility of an accident and increased the margin of safety.

13. 76-79 HPCI minimum flow switch, E41-N006, was a Harton Model 289A with an element range of 0"-12". An exact replacement was not available when it failed, so this temporary change allowed substitution of a Barton 289 with 0"-11.2" element range at the same flowrate.

Switch settings are set in inches of water instead of scale readings, which are in fl ow rate, so setpoints were unaffected. The probability of an accident was

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not increased because the same model number instrument was used, and the margin of safety was not reduced since flow switch settings are in inches of water and not based on scale readings.

14.76-109 RWCU pump seals were subject to failure since at zero flow in RBCCW the temperature switches coul d not trip the pumps on high termperature. To obtain positive indication of RBCCW isolation valve position to the RWCU pumps, the non-rising stem gate valves were replaced with ball valves. This change increased the scif-protection of the system and thus decreased the probability of an accident and increased the margin of safety.

15.76-113 During startup and shutdown conditions, 4KV busses 1C, ID, 1E, IF, and 1G are normally supplied power. from startup transformer ID. Initial short circuit anal ysi s of this configuration under maximum loading conditions, along with one diesel generator being tested, slightly exceeded the interrupting ' capacity of the 4 KV breakers. Therefore, . permissive diesel test relays ,

were incorporated to prevent diesel testing ~in this  ;

configuration. A final short circuit analysis q utilizing final vendor data showed that the switchgear

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g has a fault duty margin of 2.3% excluding cable

.!O impedences. The diesel permissive test relay was thus removed to permit testing in this con fi gura t i on . To insure that D/G breaker interrupting capacity is not exceeded procedural changes were made which require removal of certain loads from the affected busses prior

! to testing. The circuit breakers are adequately protected and the reliablity and availability of the 1 diesel generators and emergency busses are unaffected.

16.76-119 In order-to provide a greater margin on the drywell to torus differential pressure control the differential J

pressure was raised to 1.68 psid to stop the compressor and 1.50 to start the compressor. This change was the L result of a change in NRC setpoint requirements and was l permanently incorporated after several small incremental changes in dP were accomplished with temporary design changes. The probability of an accident was not increased because the dP was made more conservative and the margin of safety was not decreased since the dP is in excess of the 1.0 psid committed to.

17.76-124 This change improved the performance of the 20 volt power supply of the power range monitor by eliminating 4

a potentially unsafe condition. In the event of a failure of the 20 volt power supply in one channel and t

a misadjustment of the 20 volt power supply in the redundant channel oscillation occurred in the trip circuit of the failure channel that appears in the opposite redundant. channel. This oscillation could j have caused the signal level of- the redundant channel to read low and not trip as required. The probabil ity -

of an accident is not increased because- the- change reduced the possibility of a failure to trip.

18.76-128 The HPCI exhaust drain valve, E41-F053, required greater than 5 psi pilot pressure to open, and sufficient head was unavailable preventing proper HPCI

turbine drainage. A plunger type valve was substituted.

which did' not have the. pressure problem. The-probability of an accident was not increased since a drainage problem was solved and _the -margin of safety was not decreased since the _ mode lo f operation and availability of the system were not-altered.

, 19.76-146 -This1 change removed the administrative requirement for the presence of' two operators- for control of _ group notching'from:50% rod density to 30% power and replaced  ;

. It with a-hardwired group notch mode of reactor - manual control so thati the operator- can only withdraw a-control. rod one notch at a time. This . change - also eliminates the ' possibility of getting a particular f -

O group out of step during:the CRD settle cycle if. the t-(9) .

i fN operator flicks the CRD movement

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was increased switch to insert The probability of an accident not because hardwired

, enforcement of identical rod patterns is more dependable. The margin of safety is increased because of the elimination of human error in withdrawals.

20.76-150 This change corrected a drawing error made in FDI-RJER concerning recorder connections (D11-R622A f, B) in the fission product monitoring system. The correction was made prior to installation of the new monitoring system. The probability of an accident or safety system failure is not increased because the operation of the equipment is not altered by the correction of the drawing error.

21.76-152 Incorporation of FDI-RJER provided a means of detection of fission products in the drywell which escape from the reactor through valves or piping. Tho monitoring i- system provides the opera, tor with local indication and an alarm but has no tripping function. The probability of an accident is not increased because the fission product monitoring has no tripping functions. The margin of safety was increased because this system allows detection of fission product gasses.

22.76-159 This change involved the installation of a logic card and interconnection in panel 615 for use with the group y . notch control portion of the RSCS. . It prevents- out of sequence rod movement due to operator error at power -

levels less than 30%. The possibility of an accident or safety equipment malfunction was not increased because the RSCS does not af, ct ability of reactor to respond to the RPS. The margin of safety was not decreased because safety setpoints were unaffected and new-hardware quality was comparable to that of a safety system.

23,76-160 This change removed administrative restriction of a second licensed operator during minor rod group I

movement prior to 30% power by installation of i additional hardwired group notch control in the RSCS as

! per FDI-RJGX. The possibility of an accident was not l .

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increased because the RSCS does not affect the ability g of the reactor to respond to the RPS. The margin of L _

safety was not decreased because safety setpoints were unaffected and new hardware quality was comparable to that of a safety system.

24.76-163 This change to Group Notch Control implemented FDT-RJHAf which was to install socket and relay C11A-K62 which prevented an out of sequence rod movement if the power supply varies from the specified operating range. The probability of an accident was not increased because the change prevents damage to equipment due to operation under low voltage conditions. The margin of safety was increased because the safety setpoints were increased.

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-25.76-164 Excessive vibration of the Plant Service Water and RHR Service Water Pumps had caused repeated failure of the Fisher Type 4160 Wizard II Pressure Controllers and hence inoperability of the pump minimum fl ow valves.

l The controllers and regulators (P41-F208A-D and E11-F200 A-D) were relocated further from the pumps to eliminate vibration. The probability of an accident

, was not increased because the safety function of -the relays was unaffected, and the increased - safety _

setpoints improve the margin of safety.

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26.76-173 Texas instruments Recorder T41-R620 was requiring

, excessive maintenance and showed a lack of mechanical

! consistency eventhough the electronics were properly-It- was ~ replaced .with the more durable calibrated.

Taylor Instruments Model Number 2142 JA 381042, and all existing alarm connections on' the HVAC system were transferred to it. The probability of an accident ~ was decreased because the replacement recorders. were more-reliable, and all existing alarms were' retained. The-4 margin of safety was not ~ decreased because the

recorders serve no safety related. function.

27.76-174 Texas Instrument Recorder T47-R611 and T47-R612 on the ContainmentJAtmospheric Control System were replaced beccuse of excessive wear rate with Taylor- Instruments Model. Number 2142-JA 381042. The probabil.ity of _an accident is decreased because the replacement recorders were .more -reliable and all. existing- alarms were retained.- The margin of safety was _not decreased because the recorders serve no safety related function.

28.- 76-177 New thermocouples and thermowells, recommended by GE as having better resistance to vibrati.on due to high steam

flow during MS.SRV opening, were welded:into sockets on

./ downcoming pipes. The probability of an accident - or is safety system malfunction was not . increased s

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( more reliabic thermocouples. The margin or sa rety was k not reduced because the thermocuoles provide no s'quals i to safety systems.

29. 77-16 Core Spray Sparger Differential Pressure uonitors, E21-N004 A 6 B, had an insufficient range. 91nce normal plant operation could result in a dP or -3.7 psid, the existing dPIS were replaced with Rarton Model 288A with a 0-5 psid range. The probability of an accident or safety system mal function was not increased by this change because the trip settings remained the same and instrument accuracy was improved. ,The margin of safety was improved due to the expansion of instrument scale.

30. 77-14 In GE's updated analysis, "Edwin I. Ilatch Nuclear Plant linit 1 Channel Inspection and Safety Anal ys i s with Bypass Holes Plugged" (NEDO 21124-1 Supplement 11, a change was proposed to the RBM high flux trip setting.

To maintain fuel cladding integtrity conservatism consistent with exposure dependent MCPR the block of the RBM was changed to 0.66 W + 39% from 0.66 4 + 40%.

The probability of an accident was not increased because of this change since, by extensive analysis,

, the value specified for the RBM represents a limit which might be approached only under the most severe circumstances. The margin of safety was not reduced

. and unsafe reactor operation was prohibited within the scope of these changes.

31. 77-17 The old mode switch on the TIP system's fl ux prohe monitor drawer was not able to withstand continuous operation so a new mode switch (44M45-06-1-5N) replaced the GE Part (135B9756 P001). The probability of an accident is not increased because the system function was not altered by the switch replacement. The margin of safety was not decreased because the system does not activate any safety systems.

.32. 77-28 The reactor vessel low pressure isolation signal setpoint was reduced from 908 + 5 psig to 863 + 15 psig

. on switches B21-N015 A-D to avoid spurious scrams and isolations on low pressure transients. A large pressure differential at such high pressures would cause only a small difference in saturated temperature; the Technical Specifications limit was changed along with the actuating setpoint allowing the safety margin to remain constant. The probability of an accident was not increased because the. pressure setpoint change yielded a very small temperature differential.

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.(_J3. 77-31 The Safety Relief Valves were experiencing pilot seat leakage and second . stage seat scuffing because of foreign particles entering the pilot assembly through the sensing line. Filters which would not clog were thus placed in the sensing lines of valves B21 - F013 A,B,C,D,F,H,J,K,L. The probability of an accident was decreased because the filters prevent foreign material from entering the valve pilots; no new modes of failure have been introduced because Target Rock determined that the filters cannot reduce pressure sensing capability flow. The margin of safety was not decreased because the valves have been made much more reliabic.

34. 77-36 A greater (CFM) capacity isokinetic probe (D11-N001) was installed in the main stack in order to accurately monitor the additional discharge resulting from unit two's addition to the system. The probability of an accident was not increased because the new probe operates identically but with greater flow capacity.

The margin of safety was not reduced since the change enables monitoring of both units.

35.77-131 The reaction source holders and sources (B11-D1141 were

- removed from the reactor vessel, not to be reinstalled, because of four previous failures of the holders in operating BWR's. In addition, the sources are not needed after an average core exposure of 8000 MWD /T per GE SIL 215. The probability of an accident was decreased by this change because a possible mode of failure was eliminated by removal of the source reduced because holders. The margin of safety was not the irradiated fuel supplies a detectabic neutron population to the SRMs.

36.77-147 The CRD return line piping was rerouted to the RWCU system downstream of the last . motor-operated isolation valve as recommended in GE SIL 200. Both return lines and vessel nozzles were found to have cracks in a number of GE/BWRs. The major factors contri.buting to l the phenomena included corrosion and fatique cracking due to thermal ' gradients end thermal cycling. The probability of an accident was not increased due to this change be:ause a crack in the CRD return line will not affect the normal, safe shutdown of the reactor.

The margin of safety was not decreased because the rerouting of this piping did not affect any safety systems.

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( )7.-77-154 The original junction box feedwater spargers were replaced with the new- forged tee design believed to help eliminate sparger cracking and nozzle clad cracking. The new forged tee with fl ow holes eliminates bypass fl ow around the sparger thermal sleeve which is believed to be the mechanism for nozzle clad cracking. The probability of an accident was not increased by this change since failure analysis has dictated the use of the new spargers. The margin of safety was not reduced because the systems function was unaltered; the equipment was replaced with that of higher quality.

38.77-158 The rerouting of the CRD return lines for fatique resistance per DCR 77-147 increased the back pressure which necessitated the addition of a second cooling water line and pressure control station to regulate CRD hydraulic system pressure and CRD cooling water pressure. The probability of an accident was not increased by this change because the replacement switch serves the same function. The margin of safety was not reduced since the regulation was necessary for proper operation of the system.

,-39.77-167 The temporary replacement of the G31-N020 Mercold

. Temperature Switch (100 to 200 degrees FI with an equivalent Fenwall Temperature Switch (-100 to 400

. degrees F) was made because the existing switch broke and no replacement was available on site for this RWCU alarm actuator. The probability of an accident was not increased by this change because the replacement switch serves the same function. The margin of safety was not reduced because the switch only activates an al. arm and does not initiate any safety systems.

40.77-168 This change improved the calibration accuracy of the

, WRM-MSV chassis by decreasing the spray capacitance in the test fixture per FDI-RJHR, which reduced the inaccuracles caused during the high frequency portion i of the alignment procedure. The probability of an L accident was not increased because the change did not

alter the safety function of the IRM but increased the accuracy of calibration. The margin of safety was not reduced since the IRM's safety function remained unaltered.

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(qG1.77-169 A relay and two position switch were incorporated in

\- / the Fission Products Monitor panels H11 - P600 and H11-P604 per FDI-RJHZ. The change permited normal or rapid advance of particulate filter paper and provided relay contacts for use by A.E. The probability of an accident was not increased since the normal system functions remained with flexibility added. The margin of safety was not reduced since no safety system activation was prevented by the change.

42.77-179 A union was installed on the discharge side of RHR Service Water Cooler Coil (E11-C001A) beyond the 90 degree elbow going to the discharge header to make cleaning of the cooler pipe easier. The probability of an accident was not increased because the operation of the discharge cooler coil was unaffected by the change. The margin of safety was not reduced since maintenance case has a direct bearing on cooler pipe efficiency.

43.77-195 The GE Type "HG" Recorder B21-R614, Relief Valve Tailpipe Temperature recorder, was replaced by an equivalent L 6 N recorder in an effort to increase instrument reliability; the old recorder had worn out prematurely. The probability of an accident was not increased since points being monitored were unchanged.

The margin of safety was not reduced because the new, more reliable recorder provides no control functions.

44.77-207 Fission Products Monitor Particulate Pump D11-P011 was connected to 208 VAC instead of 120 VAC to decrease aump current by changing R20-S001 from a single pole '

3reaker to a doubic pole breaker. The probability of an accident was not increased due to this change because the operation of the fission products monitor was unaffected. The nargin of safety was not reduced since no changes were made which degraded the operation of any safety system.

45.'77-209 A 0-60 psig pressure gage was installed at the test port, close to the temperature sensor, on the cylinder and jacket coolng header outlet of Diesel generator IC.

This change provided an indication of jacket coolant pressure and allowed verification of the coolant pressure low switch setpoint. The probability of an accident was not increased by this change because the operation of the diesels in an emergency is not affected. The margin of safety was increased since verification of CPLS setpoint is possibic.

(vb (15)

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6.77-222 The results of TER 77-7 indicated that fuel injector leakage on the diesel generators was caused by insufficient head on the return lines to the day tanks. Existing lines were removed and capped; five gallon clean oil gravity drain tanks were positioned at the skids' bases to provide suffucient head. The probability of an accident was reduced because a potential fire hazard was remedied. The margin of safety was no changed because the emergency operation of the diesels was unaffected.

47.77-237 DCR 77-114 called for disconnection of H21-P237-AD088 4 AV093 cables to redundant al arm at H11-P654 4 P657 panels. This change disconnects core spray level switch alarms on back panels only so E21-N010A 6 B will still actuate and alarm on low level at the more observable H11-P601 panel. The probability of an accident was not increased by this change because E21-N010 A 4 B are still available on core spray loops. The margin of safety was not reduced since the function of the system was unaffected by the change.

48.77-242 A flexible hose was installed between the rigid radwaste drain header line- and the non-rigid level switch-vent valve assembly (E11-N040) because RHR line movement caused weld cracks at the level switch root valves. This flexible connection of ' rigid and

. non-rigid piping was installed beyond the pressure boundary (double isolation valves) of'the RHR system.

The probability of an accident was not increased by1 this change since the flexible connection reduced the probability of line failure. .The margin of safety was not reduced because the operation of the' high point-leve1~ switch and vent was unchanged.

49.77-260 A relay was added to the Day Tank Moisture Detector's-Internals (R43-N516) of the IB Diesel. Generator to allow indication lights to be used at the local panel.

The detector still alarms both Unit I and Unit 2. The probability of an accident was' not increased because-the moisture detector still alarmed if moisture was present,'and the new relay was mounted inside the explosion proof moisture detector case. The margin o f.

safety was not reduced since the- diesel generator's-operability was unaffected.

50.77-275 A protective' plexiglass cover was added to the RPS MG set selector switch C71-S1, to shield it from accidental. actuation (asfrom'danglingtest leads) 'and still allow visua1' verification. The probability of an accident was not increased by this change because the O

RPS MG set system.and its operation was unchanged.

margin of safety was not reduced because safety limits The were not affected.

8 (16)

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[d1. 77-1 TEST OR EXPERIMENT REQUESTS (TER)

This test demonstrated that all reactor building crane logic and interlocks function as designed. The restricted area interlocks and bypass switches were tested. The 125% load test was performed on the monorail and auxiliary hoists, and the brakes on the monorail hoist were tested at rated load.

This test was successful, and the monorail and auxiliary hoists and brakes were proven for normal limits of operation.

2. 77-2 This test was intended to verify the actual water tabic elevation through the installation of four additional piezometers in Y28. (Yard Drainage Investigation)

3. 77-3 This test provided GE with turbine coastdown dsta by connecting a multipoint recorder to turbine alarm / trip panel.

4. 77-4 This experiment checked the Rosemont Flowmeter's measurement of offgas flow which directly affects radioactive release determination. The check was made by biceding air into the condenser during startup through a Dwyer Flowmeter and comparing the reading to that on the Rosemont.

No definite conclusions could be drawn from this experiment.

5. 77-5 This experiment tested a dispersant and inhibitor in plant service water to determine which additines could help prevent rust and sludge buildup. The station air compressors were the injection points.

This experiment is still under study and a final conclusion has not bcen drawn.

6. 77-6 This test verified the proper operation of the the Unit two SUT 2D and AUTO BANK Transformer's protective l relaying and to check PCB 179540 breaker failure scheme.

i All steps of the test were successfully completed.

! 7. 77-7 This experiment checked for proper flow through fuel oil gravity drain lines from injectors of the diesel-generators. Oil cans were mounted lower than day tank to increase head on drain lines. The injectors were monitored to determine effect of drainage on injector's rs leakage problem. The probability of an accident was (17)

-g

4 not increased by this test because the clean fuel oil was routed to an oil safety can secured from overturning and located away from possible ignition sources. The margin of safety was not reduced because the operation of the diesels was unaffected and no safety limits were changed.

Regular surveillance is still underway.

8. 77-8 This test involved precoating condensate demins A and B using Ecocote as an overlay to determine if it will extend run length of condensate demin vessels.

The new coating is still under' evaluation.

9. 77-9 This test involved addition of Nalco #7348 to the circulating water system to evaluate potential condenser cooling efficiency improvements through 4

removal of scale and slime deposits.

Testing is still underway.

10. 77-11 This test measured the structural response of the Mark I Torus and its supports when subjected to SRV discharge loads in order to supplement and calibrate the structural-analytical models to evaluate the

~

existing design. The probability of an accident was not increacd by this test because it repeated only normal operations that are contemplated in the -FSAR, and the added instrumentation did not cause a reduction in torus wall thickness below the required minimum.

The margin of safety was not reduced since no plant protective trips or set points were affected.

Preliminary results- from Wyle reveal satisfactory response of the torus and supporting structure to test i

loads.

11. 77-13 This test involved the installation of an eccentrically

< weighted, variable speed, DC motor on D plant service water pump in an effort to account for high maintenance records through vibration analysis. The probability of an accident was not increased by.this test because the pump was removed from service for the test, and it. was subjected to a vendor specified~3 mil vibration which could not damage the pump. The margin of safety was-not reduced because no safety limits were affected.

' Vibration analysis revealed that- resonant frequencies occurred at a speed sufficiently far away from g operating speed to be a major factor.

t

(

(18)

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'%) # DATE CAUSE OF tW fljNCTION' EFF. OM 'L^FE e . (Q*

ACTION TO PRE \6 u i- INITIAIED COMPONENT OPER. OF RX.- REPETITION 4305 12-S- 75i : P41' DCR 75-239 i 4463 1-2-76 D11 DCR~75-25d 1

5059 3 N FSI-RCIC Piping , DCR 76-25, 5124 4-4-76 G31-FOO1 & FOO4 DCR 76-58 -

^

5237 12 D11/021 DCR 76-6.3

,- 5275 4-16-76 CSI-Replace APRM & IRM DCR 76-72 Byrans Enttch 5351 4-23-76 E41-FOO2: Valve Lechs at packing Tighted Paching 5455 5-4-76 E41-NOO6 DCR 76-79 56 6 5-27-76 X41-D/C *18' 011 Rm. Fans will not run with Rebuilt Damper Motor

~

. Fans -

Sw. in "RtJN" Position 5665 6-1-76 C11-FOS 7 CRD Hydraulic Water cak dt'Cland Hut Tishtened Cland Nut Control System 5667 6-1-76 831-COO 2 Snub. "A*on Oil Level Low Serviced Snubber with oil

'Pecirc Loop Discharge 5863 6-23-76 C31-ROOI Regenative F016ts Valve Leaks Pact Replaced Valve m Heat Exchange Vent Seat _i a

8 6091 7-22-76 T98-DPS-tO81 DCR 76-119 620t 8-4-76 Hil-P603 DCR 76-124

~

6319 8-19-76 C71-51-RPS Bus Power Repate RP8 Bus Power Replaced Damaged Stop

• Selector Switch Select Suitch to climinate Plate and tected. Test the estra posittonc past catt factory.

Alt. A and Alt. B Ref. HrF-1 - 1E.E.6 6323 8-23-76 U45, T45 Tornado Vents DCR 76-136 6337 8-24-76 P70-COO 18 Drywell Compressor is not pumping Replaced Compressor air

. -6344 8-25-is B31-FOf2 & F063 Reactor DCR 76-13 Recirc Paping 6379 8-30-76 - Ell-F904 a RHR Service Valve has multiple lesh'c Tishtened Lines Water Air Release V1v.

6410 9-2-76 C11-0013 (50-19) Cont.

. Rods. Control Rod GO-19) Erh l High Temp. Continually. Fluched CRO Module (50-19) h replaced 3 filters with new

/ O' Rings. As pec, HrP-1-1431.

~

' ACTION TO PRtNENT

~

pWt O , DATE CtmPONENT CAIEiE OF MALFUNCTION EFF. ON MAFE- "

E OPERg OR R X . REPETITION ' O *

/"N INITIATED * .

~

( I f ) *

( 23 9-3-76 C11-ROO91 CRD Press. Cauge Indacates too High' Installed New C Q '  ?

Cause 6434 '9-13-76 T49-tE O-R4 Drywell to DCR 76-119 .

Torus Ocita P Wstem 6 6770 10-17-76 E11-DOO2f1 RHR Service ~ Top Sical Leatcs Tashtened Strainer Head Kiter Strainer Bolts E11-DOO3A RHR Service Head Bel te not f.uf fic. Re-tightened Head Belts 6771 10-17-76 -

W tir Strainer Tight C'318 11-1-76 E11-FOG 1 Heat Each. Solenoid Valve Malfunc. Inctalled New solenoid H Valve Valve .

7033 11-9-76 N12-tJOO1; Circulating DCR 76-41 Hater Flume 7060 11-11-76 EF1-F054 Steam Line Leaking Air Line Replaced air line Drain Pot Trap Bypassed

• Viv. Air Operated 7103 11-17-76 T41-R620 Rx. 81ds. DCR 76-173 HVAC Recorder r

7104 11-17-76 T47-R611- & R612 DCR 76-174 Cont. Atmos. Cont. Sys.

to Repacked Viv. Gland ESI-FOOB RCIC Outboard Leah at Cland Nut C

'S 7240 12-2-76 Isolation Valve ,

7237 12-8-76 B21-N602A Feedwater Transmitter cannot bc Replaced Transmitter d Temp. Transmitter calibrated 7298 12-8-76 C31-HOO1A: RWCW Regen. Leakc Steam Head use scaled -(

Heat _ Exchanger Ell-FO31-B HPCI-Steam Valve Paciting Leal:ing Replaced Prescure Scal

• 7300 12-8 and rcpacited Viv.

V1v. to PHR Hz.

7361 12-13-76 831-R621A Recarc. Pump Loose Hire Connectienc Tzshtened Harc on Controller "A* Connections 7371 12-13-76 Fil-f-Oca A & B RHR DCR 75-E.4 Service Water Bellnus Lealtage Pone,sh te- One Rs. Fe e l s e + Replaced prcccure Ewitch 7372 12-13-76 B21-FOl3K Rs. Relief Valve Not Confsrmed V!v. con 0:Ccred

- Inop, 7373 12-14-76 CSI-JOOSC Tip Machine Te .t Clutd.e on Tip Clutches Tc ted Sat.

"C" th hine 7402 12-16-76 CSI-tJOO3C Tip Machine Tip Detectnr Bir$ds Replaced tubing. See "C"

MR 77-25

. Steam Supply Line Valve Adjusted Cland Nut

'7462 12-23-76 .E41-F037 HPCI Steam L a n<* Trap Leahs at Paching C 1.::n d

.R43-SOO!A D/C, Fuel Injectors L.ccit ' Replaced Com Roller -

7468 '12-29-76 an jec tor: M6&7 Scarans:

g ,, e oa v -

, MR DATE COMPOBENT CAUSE OF MALFUNCTION EFF. ON SAFE ACTION TD PREA

) * ' ~

INITIATED

• OPER. Oc RX. REPETITION 175 12-30-76 Oll-FCO3D Main Steam Differential Amp Replaced Differ tal

) Line Rad. Monitor Defective Amp 77-2 1-3-77 CSI-APHN *A" Ou t of Calibration ^

.PRM Channe *A" Calibra ted C51-R603A h

"A" Inup t 77-8 1-3-77 ESI-ROO2 RCIC Pump Zero out of adjuctment Erronecu, Indica. Calibrated Instrument F,ut t ion Prect. Cauge on Instrument 77-34 1-3-77 Bdl-FOl3E Rs. Relief Pot.cible bellows Icahave One Rs . Helsef Prect. nac releaced at ,

Valvo not conftemed Valve inap. precc. cwitch. Switch usc reinstalled.

77-39 1-4-77 CSI-HColE IRM "E" Signal Connector ' coce

. IRM "E" Inop. Adjucted Connector &

functionally tested.

77-41 1-4-77 CSI-APRM *A* Upecale alarm-cetpoint Upccale alarm cet A3RM channel "A* calib. (

found wrong at wrong cetpotnt and functionally tested.

77-45 1-5-77 B21-R606 Rs. Vessel Selector W itch contact: Recorder Inop. Repaired Recceder . (

Temp. Mul ti P t. Rec. dirty

-

• 77-60 1-6-77 E41-R60S RHR Water' Set screw loose on Print Recorder Inop. Tightened cet screw on (

temp. & HPCI pump and Bar Mechanism. Prin t Bar Mechantcm Turbine Recorder D (

m 77-62 1-E-77 C11-06-31 CRD/HCU Loose Air Line Fitting Atr Leahs Tightened Fittings N, Solenoid Valve A v (

77-70 1-6-77 T48-F024 & FO25 Drywell DCR 76-192 to Toruc Diff. System

(

77-74 1-7-77 N62-NOO3 A & B Off Gas Vaccum pumps Warn None Replaced Vacuum pump *B" H2 Analyzer No Malf. was found on "A*

Pump (

77-81 1-9-77 B21-F013G Rx. Relief Corrosion found in Pilot Relief Viv. blew Replaced with space v1v.

Valve & Second Stage Area Rs. Precc. to t

. approx. ISO pcas 77-82 1-9-77 Bal-F013K Rs. Relief There was no problem with N/A Rr. in S.D. Replace Bace Sections t Valve this valve .t thic time.

The base section was replaced because of prob.

with bellows leahage alarm in Pact.

77-84 1-9-77 B31-FO91 A & B Recirc Valve Stems Lached Lubrc. Lubricated Viv. Stems Pump Disch. Viv.77-103 1-12-77 831-R625 Recirc Drive Slide Ware *Dtrty Cleaned Slide Ware Ternp . Recorder 77-113 1-12-77 821-FO!3 A,B,C,D E.F. Remove Valvec & inctall Valvec Removed, Blanhc G H I,J K,L Safety blanks anctalled Relief Valvec 77-115 1-12-77 TAS-F33SA Drywell Vent Limi t Swi tch ou t of Adj. , VI.. Pocation Adjuc ted Limit Suttch Vlv. .indicattng itshts

. - Erreneou: -

g. -

'l

. . ,~s .

. /_N

• j' 7 0,' DATE COMPONENT CAUSE OF MALFUNCTION EFF. ON M.^FK ACTION TO PREY '

k' l\ INITIATED OPER. ON RX. REPE1IIION \m/ -

!, N11-NO42 ASB Main Steam Relocate tiensors per DCR 77-118 1-12-77 Relocated Eencorc h-I e Pressure Sencors A & 8 76-157 .

l- 77-138 1-13-77 Ell-NOO2 A & B Dtff. Transma tter ou t of Calib. Recalibrated Transmitters Pressure Transmitter l

!77-182 1-14-77 E41-F011 Motor Operated When Mo t tu operated Viv. Had a Cruund on the Tightened Hire on Viv. (HPCI & RCIC) is operated to open posi. MOV Elec. Syc. reversing relay calib.

A IS M.A. Cround ic ind. -

& alarm sounds77-241 1-17-77 E%1-FO73 Enhaus t Drain Steam Lealt at Viv. Packing Added Pacting Material .

Trap I s ol.e t ! on & adjusted Cland Nut *

[

L 77-242 1-17-77 E21-NOO4 A & B Core DCR 77-6

. Spray Differential F Press. Monitors (ERI-

! NOO4 A & B) -

F 77-223 1-19-77 xq3,P41,Z41-DOO4 A & B DCR 76-209

• Fare Prot. & Plt.

Service Hater Piping

[

77-293 1-20-77 R42-SO30 IB Station Brolten and Dirty Equali:ing Repaired and Cleaned Service Battery Charger Charge Time. Brchen & equli:ing charge timer 3^ IE dirty equali:cr adjusting Repaared and C1 caned E

w Rheostat. Brohen printed equalisce adjusting l circuit board. Module B & D 7 Rheostate. Repaared Loose wiring on output of printed circutt board:

air circuit becaher Module B & D. Tightened utring on ou tput of air ctrcutt becalcer 77-302 1-20-77 831-NO14C rectrculating Flow trans.mttter out of Calibrated the trans.

flow transmitter A & B calibration in acccedance with r? f3- 1 -52S3.77-309 1-20-77 R43-SOO1A: Diesel Cen. Water Leak between bottom Replaced Cachet IA: Water Espansion Th. Plate & Casket 77-317 1-21-77 C21 Flow Unit D Comparator Inoperattvc ReplacCd LCabing Zenon Dscdc 77-332 1-22-77 R43-SOOIC: Diesel Cen. Pana! arm Unit was broken, Peplaced Panalarm tJns t IC Inboard Beartng Cave false alarm !c set the alarm unit at 180 degrecc F.77-342 1-24-77 E41-F036-HPCI Steam Valve packing blows steam Repacized valve and tested Inne draavi pot trap profuscir for Icah , - tested

[ , anlet asolation.viv. ,aticfactory.77-368 1-25 D11-K614 Carbon Bed CM Tube failed & incorrect Replaced CM Type &

V.nuit Rad ution R3 reststor installed

• installed recactor of j Octector correc t value 77-377 1-25-71 N21-7001A Condensate Pacio n9 ad Jus t a ng nut A1;u.ted valve stem demin manual isol. needs adjustment . paching adjustment nut valve 1A .

fW _ DATE COMPONENT CAUSE,CC MALFUNCTION. EFf , CN h^FE ACTEDM TO PRE'. .

, )

INITIATED

• OPER. OR HX. REPt: TION (

,-405 1-26-77 C11-DOW A CRD Dicch. Hith Otff. Pests. acrrss Rem ved cleaned cA-F 1ter filters installed filter 77-409 1-26-77 T43-R602, N2 Make up Red pen drivet upscale Repatred Recorder f l ove recorder needs upscale 77-410 1-26-77 C11-1040 DCR 76-159 77-431 1-28-77 P*l-C001C Plant Serv. DCR 76-171, R1 ,

Water Pump 77-434 1-23-77 021-REOO ARM Recorder The recorder gives Calibrated recorcer per *

- crroneous readings HNP-1-5261 .

• 77-443 1-23-77 T4?-P620 torus vent Hlack pen is driving Repaired power supply e x haus t of low recorder downscale 77-453 1-31-77 Bll-AOO2 Remove head for refuel Removed and replaced head ,

i Dryuell Head outage .

O 77-454 1-31-77 B11-0081 Reactor Remove for refueling Removed Plust Cavity shield plugs , (a 77-476 1-31-77 R43-S')O1-A Diccel Cen. Drain Valve Handle Broken Replaced handle on drain

) Otrty Fuc1 Tank Valve A 77-477 1-31-77 R43-R753A Diecc1 Cen. Pyrometers Inop. up to Replaced Thermacouple

) $ 1A Cylinder Pyrometers 400 degrees F. - 450 F. o 77-451 1-31-77 R43-N/54A Coolant Faulty Circuit Card Replaced Circuit Card i Level Alarm @

77-487 2-1-77 B21-R614 Safety Relief Recorder Driving downscale Replaced thermocouples &

t .

V1v. Temp. Recorder reconnec ted t:rchen Icads @

77-497 2-1-77 821-F013E Auto Safety / Valve Blew down Replaced Palet Acccmbly Relief Valve l f 77-499 2-1-77 T43-F3:2C Solenoid Viv. Solenoid Cover Screw came Installed Screu &

for Torus /Drywell loose, cover fell off replaced cover vacuum breaker C.77-500 2-1-77 C71-K13A Refueling Relay Chatters AcJusted Contact Spring Ins trument Relay Tencion.77-501 2-1-77 E41-F114 Test Lane Test Line Cap fell off Retn:talled Test Lane Cap 77-503 2-1-7 OSI-42-15 Rod Pocitton Rod Blockage Acced Temp. Jumper from Indicating System PI-V to P2-W. File 3, S!=t 15 S completed Step

• E' of HN 1002 77-504 2-2-77 R24-SO12 Notor Control DCR 77-50 Center 77-509 2-2-77 821-RE.06-Reactor Vessel Dirty Contac t on Stepping - Clea ird Stepping Switch Temp. Recorder Switch Centact:

77-511 2-2-77 E41-F051-HPCI Torus Air Leak in fica rbic air * *' Replaced Circuit Card Suc. Atc Operated Viv. line between regulator, ,

and v31ve.opeentne k

m __

tRe DATE CCMP&ENT CAUSE*

OF MALFUNCTION EFF. &JtsA!-E ACTI&a TO PRE \ .

• 2

• It41TIATED OPER. OR RX. REPFTITI&1 O .

X 1a 2-2-7/ H9 3-S001% B,C, Die:c t DCR 76-113

)

i Cencrator e

77-518 2-2-77 Pc'd-9003 & 4 Fmer. Bus DCR 76-10.2 )

Undervo l tage- Relays77-519 2-2-77 D11-POOt, PO11 DCR 76-152 77-522 2-3-77 C11-D002 "Y" Cate Suc. Exce:Cive Pec cure Cleaned

-*a and re-installed.

9tratner for CRO Pump Drop acronc straincr* 'aner:

77-524 2-3-77 Pdd-SMi , 5, 6 Emer. DCR 76-1E2 '

But tJndervoltage Relay 77-523 2-3-77 D11-1020 DCR 77-529 77-531 2-3-77 Ett-FG248 Motor Handuheel bacame loose Tightened Handuheel and .

Operated Valve repisced hardware 77-551 2-3-77 T96-N007A Flow Switch Eustch out of calibration Celsbrated f!cu cuitch' 1 .77-552 2-4-77 R42-SOO1A Battery Cround Detection System Repaired Crcunded Bruch i System en "A" 125/250'.' Batteries has a ground on positive

) stdc.

2 77-556 2-4-77 C51-H600A SRM Channel Retrac t permit da d not Cal:brated ins trumen t

]I 8 "A" clear 77-557 2-4-77 221-FO13K Rr. Relief Cause not determined Bicu Rs. pre::ure Removed bc e :::cebly valve dcun cent tc Hyle Lab fcr repatr and steam tetting 3 77-558 2-4-77 B21-FO13S cafety Abnormal crening and Reecved p : 1ct <:sth c:r relief valve would not teat crerator, cent to Myle Lab to be recet, reinstalled ptiot w/cir

- cperator cnd test 0; per Hv3 3931.77-562 2-4-77 C11 Rod Potation Probe Repair failed potation Repicced RPIS probe indication switch 77-563 2-4'-77 R relief valves DCR 75-246 R21-F013 A.D.C,D,F.H.L DCR 77-31 77-566 2-4-77 Eq1-COO 2 HPCI Shoch Dil Leve! low Servated suppressors with

'uppressors

. ca1 77-570 2-5-77 T49-ADF-3230 vaccum Hill not operate when ROpaired Oir line b r eal:er te,t puchbutton ::

depre::cd 77-575 2-7-77 C11-Rv378 CRD stabi- Internal filter on B Cle:ned fziter end lazing valve stabit:ing valve chect.ed va!ve for I calce .

Te:t est: fcctory.77-602 2-8-7i E21-F011R manual feed- Valve teat:0 at pac t::n g Re-pacited vc!ved water isclation valve

. , MR t DA rt-_ COMPtNENT CatEE OF Wy_FLNCTION FFF. ON S.aFE ACTION TO PREE *

) INITIATED 0%R. OF HX. REPE T IL*1 y o .

1-613 2-lf-7 7 Cll-F126 CPD hydraulic Bonnet and flange l eal:ing Ttchtened flJnSc DZltt drive unst d 77-641 2-10-77 Bit-Dlot PPIS probe Replace probe on rod at-27 H::p !:ce prebe, c

77-642 Eti-COO 1 RHR ptping No malfunction-caddict In0talled 0 ddles were lett off dueing cunt truc t, ion 77-643 2-10-77 E 0-COO 1 - HPCI man In.tallatirn of reinforce- Installed reinforcement -

flou I tne reinf orcemen t ment mate tal on HPCI-flow sacdles caddict 1:ne was omtttco duriny cons truc t t un .77-644 2-10-77 E21-COO 1 - Core Spray Reinforcement caddice In.talled reinforcement man flow line rein- omitted du r i n g plant caddle forcement construction 77-6E.O 2-11-77 ped Discharse flow DCR 75-8

)77-661 recorder * '77-662 2-11-77 821-NOO4 LtL9 reitef Thermocouples defective Removed defective thermo-

) . valve thermocouple coupleO and replaced them '

utth new ones.

)77-673 2-11-77 NJ1-r3OO1 A-C DCR 77-64 d J

Qu,77-692 2-13-77 cst-APRM-C neutron monitoring system Tete alarm was received erroneously Calibrated the instrument ,

y recorder

)77-693 2-13-77 E91-F036 HPCI Inlet Lealt at the Pactring Cland Rep: cited the Valve Cland (

Steam Trap Icol. Vlv.

D 77-694 2-13-77 Ell-COOID RHR Service Lectcing - Scal Ma t er Tube Replaced Seal Icter Tube Water Pump IB 77-6 % 2-13-77 CSI-APRM-D Monitoring Upccale Trip comes on at Calibrated the Recorder '

. Recorder 11.5%

77-708 2-14-77 Ell-FO 71-A-RHR Pump Unable to close valve InstcIled nut and Suctten "A" Drain Vlv. (Stem Nut Unscrewed) tightened cc :e 77-703 2-14-77 Ell-FOISH PHR Inboard Valve need r epacic ing Repsct:cd Valve Injection Valve 77-710 2-14-77 CSI-E00-2 Traveltns DCR 77-17 Incore System 77-719 2-14-77 146-RE.09-A B l acit Pen Blact: Pen docc not respond Replaced rect 0 tort in (Hz. B. to outside DP) to changes in outside DP AM'M FIER Performed on recorder test. Test Saticfactory 7 -722 2-14-77 B21-NO15 A,8,C,D Main DCR 77-6f Steam Line Prect. Sw.77-723 2-15-77 CSI-r.PRM-B Neutron Mon. Trtp Alarm wa: received Calibrated the Instrument System erroneously

____77-726 2-15-77 Pol-COOI Plant Service No malfunction - caddle Installed Saddles ,.

) Water Piping were Irft o. i t encing r n e. + ,

OU LGAJ COMPLM}fT CAUSE* OF MALFLNCTION EFF . f.N SN-E

, . . INIT!ATED

• AC T!ON TO PRh'.'EN *

• O'3ER . OF RX. REPh1 ION

~

730 2-16-77 FIS-EC')3 Hefuelin? OCR 77-H Brad 3e Crapple Mae.t 77-73S 2-1t.-77 Cil-Dodo CPD tu ter Eu cctive Otff. Prcet. .

F Iter "B" t19 PSIC) Cleaned and re-installed F t ! t er".77-769 2-16-77 Elt-COOL RHR Service No Malfunctson-Saddle tu t er Piping Installed Saddle Installed were not larse enough 77-770 2-17-77 R43-S001C-!C Dic cl Would not start Generator Heplaced Bechen Cable Terminal Les77-774 2-18-77 B21-N004-M ThermocouPlc for RV-K T.C. Signal Lead Anchoring Device Massing Replaced Connecter Screw .77-785 2-18-77 P41-COOL-D Plt. Sec. Pun.p Seal Leak -

tbter Pump ID

• Changed Mechantec1 Seal I in 10 Servicc Pump Tc ted f or Leat:0 Test Satafactory 77-S02 2-21-77 CSI-ID-APRM Upecale Alarm is not receivang

.^

Alarm Repaired flou centrol c per HNP-t-3054 Trtp Reference Cced &

Chectied Te rp ce tp o tnt: O 77-E40 2-2d-77 N71-COO! A & 8 No Seal tuter Supply Carculating Water Pump Removed Fcreisn Ub,;cct frem Occin Outlet O 77-ES2 2-23-77 edl-R604-A Reactor Indicator Reading about Q

cn tu ter Level (Yarway) IS* Difference from all Pcinter decssing escinct Face. Repa tre'd pointer.

w other level O 77-864 2-24-77 E11-F046 A & B 4" RHR Weld Reinforcement Pad.

Steam L ane Melded Pae: O on Lane 77-874 2-29-77 Oll-K-E.03-8 Main Steam Recordans readtns of Line Radiation Monitor Replaced Par to an Monitor O Monitor doc not comp ly "B" with other monitor reading:

and Calibrated 77-876 2-24-77 821-PX)l7-A.8,C, & D Scram Barton Level Indic.

Scram Barton Level Ind, are readans approx. 5 in. Perf ern.ed Tc t and Calib.

difference. Ret. Procd.  : Peccedure SdCd & $003 5202, 3003 77-E84 2-25-77 CSI-LPRM Det. String: Replace String that might Rep!Oced Etrans:

• fail 77-894 8 c as-77 E51-F054-Aar operator Steam Leahans Bottom of Tishtened Pachins.

Vatve; for Test lechs. Test tatt factory Steam Trap B yp a c e. Viv. Valve S ter 77-899 2-2d-77 821-F0138 Reisef Viv. Abnormal openin's and would on MSL not Seat Hem =ved Ptict with Air Operater, tent t Hyle 1 ab . Tc be rccet.

Heinstalled Pilot W/ Ate Op era tar and test as per Ht &*- t -3 %Q I m _____,____.77-926 2-23-77 U21-F013-C.E,C R Rel.

Valve Air Operators In talled A/D of C-SM 'os ' -ted for lects test OK and sent E-SN-146 to Hyle __

~'

. i  ; -

t

, t1R tt DATE COMPONENT

)

INir!ATED CA0SE OF k.LFtfNCTION EW. O*!teFE AC T!t.W TD PR -

WEM . Oc R ?. . REPE ! ! rlt:4

'77-927 2-d8-77 Ell-F079 & Ell-FOBO No finu in tu t:i ng near Ell-a RHR-H-l.one Sample FOSO Targe t Norf Valve on Cut tubing cleaned tubi 63 Line and Valvec and ecstored flow.

Dictharge Sanple Line

= 77-935 3-1-77 P42-F09eA Heat Exch. Valve Leah at eaching Dutlet Valve Tig?.tened Pac!ang c 77-937 3-t-77 E21-COOMA Core Spray Pump Motor Overheate & ~

Jo(bey Pump Trips Circui t Brealice Installed New Motor

- 77-942 3-1-77 Ell ** Pipe Snubbers DCR 77-49 -

t 77-954 3-1-77 T46-COO! A?.B S8CT Fanc AdJu t Fan Pitch

' Adjusted Pitch 77-964 3-4-77 H11-P654 Refueling Bellows Assy. Pupture Ind:cate Excesesve Leat: Drained Alarm Cleared 5

Setpoint for Alarm In-Et dacates cacessive leak

• 77-966 3-4-77

" N31-HOOlA tiaru C Turb. Perform DCH 77-65 Ict Stage Norzle Bolt 6 Cover Plate

(77-972 3-4-77 Ell-F0918; HPCI Steam Valve Motor Torques out

{ Supply Rctet Torque before it cloces77-976 3-4-77 C31-NOOi; RWCU Fitting Cracked E. [j s-Conductivity Cell Replaced Conductivity p- Cell 77-983 3-5-77 C51-K-605-Ad-21 IB Broken Wire on bottom 02-Rod bloci: Monitor 19 underneath Matria Board Repatred wire and b conf 2rmed cat. test 77-998 3-7-77 P41-F208-A PSW Pump Packing on Valve Leching v Taghtened pacf:ing g 1A - Min. Flon Valve Chec!:cc f cr Ldatic - lest Ea t i c f ac tor y 77-1013 P41-F119,120,121,122

- DCR 76-214 PSW to fire protection P Intertte Valves i 77-1041 3-10-77 E: Cll-X46 & Y19 Control Rod Pocition Indicating Rod DILplay Matrix Light; that Rod H46-19 Chect:cd Problem, does not csitt it full-out and full-in

" 77-1095 3-10-77 Cll-DOO3-CRD "B" Dicc.

1 Filter Falter Ucito P ic Hrsh Cleaned and replaced Filters as per HNP-1-1431 E

77-1066 3-12-77 821-FOl3 *A* Safety / Install Valve with Higher Relief Valve Setpoint Installed Valve EN E9

t. hose cetpotn t a t 1100 77-1067 3-12-77 821-N004A-L Safety DCR 76-177 Relief Viv. Thermo.

77-1071 3-21-77 N21-COO 1; install re- DCR 77-123

' enforcing pads on branch connections

[ *

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_ a

_ _ _ _ ___7 _ __ _ _

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. (_sXi -

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DATE COMPorelT CAUSE O2 MALFUNCTION EFF. Of S.^FE ACT!e! TO PRE \"J., #

l INITIATED. OPER. Oc RX. REPETI0** c l

r 77-1118 3-14-77. 141-8003-0 HHR North-' . Lou alarm on Cooler Suitch Cleaned Pcto Tube

• East Diasonal Cooler A Swa tc h MN3-8 .

' 77-1125 3-14-77 - ES t -K+H HPC I E s h. DCR 76-li'd Drain valve *

~

! 77-1159 3-17-77 Bd t -HM2A MS IV Hill not pass LRT Cicaned Limit Switch

77-11E.6 3-17-7 7 C11-06-15 Rod Display Full in Indicator does not Chect

ed all lights Maten . Work - Laght lit ~,

77-1167 3-17-77 921-F019 MSL Drain Viv. Hill not pass LRT Adjusted close torque

^

7

;. 77-1179 3-18-77 821-F013 Safety / Relief Calibrate Press. Switches Calibrated ostches Valves I

( .

, ' 77-1191 3-18-77 CS7-SOO1 SRM & TRM Det. Chech Stroke Setting of Chect:ed Steche & cettins *

! Ortves Limit Switches h

b 77-1193 3-18-77 Cll-DOOIA CRO Discharge High Delta P C1cened Filter Falter

. 77-1195 3-19-77 ESI-FOO1 & F040 RCIC Hill not pass LRT L pped Valve Seats

^ Turbane Exhaust

. N i co . @

l.v '77-11,96 3-19-77 E41-F021 & F029 HPCI Will not pass LRT Replaced Seat Rings

' Turbine Enhaust I h

, 77-1197 3-19-77 F-15-EOO3-A Refueling Refueling Platform moves Replaced Defective Switch Platform unusally slow in reverse position h 77-1198 3-19-77 Ell-FOSIB RFR *B* Loop No Valve Position Indic. Replaced Two (2) SA Fuscs Inboard Injection Valve in Centrol Circuits p l

77-1193 3-19-77 831-COO 18 D.C. Dil Pump on IB Recirc MG Set l 77-1204 3-21-77 Ell-FCCTA RHR Pump Min.. Will not pass LRT Lapped Seat

. Flow Valve t

77-1209 3-21-77 E11-F0170 RHR *B" Inj. Valve gives no indic. in Rep; aced Faulty Brecher Valve (Throttic) Control Room 77-1210 3-21-77 F15-FOO3

• Bundle an Light will not I l lum in.a t e Replaced fissnette Read Hook Shirt

• Light Sua tch 77-1212 3-22-77 811-Dd33 & D231 Rs. Perform Inspection per H P- In*.pectton Completed

. Vessel Jet Pump 1-10314 L 77-1214 3-c:2-77 821-F019 Main Steam Hall not pass LRT Replaced Sect & Cleaned

, Line Draan Valve . Seal Ring a

77-1215 3-22-77 CSI-BOO 1-F APRM-F Ccn not bypass this APRM . Replaced M-17 in *S*

77-1216 3-22-77 'CSI-BOO 1-D APRM-D Cart not bypass this APHM , '

Replaced M-17 in *8*

i

. . . , gs * .

,/,mT tt DATE COMP &JENT CAUSE OF PW_HJNCTION EFF. Cet 8.^FE ACT!&t TO PEYE } ~

\v/ 'INITIAIED C ER. CF HX. REPtTION C/ .

1217 3-22-7/ CSI-ROOl-Ft APRM-B Bypact Light on Barh of Replaced K-17 *B" Pinel will not light when .

"B" is bypassed 77-1233 3-22-// B31-COOL-Arc Striltre Arc 'strittes Pemoved Arc Strifies I on 12" Recirc Line i

i 77-1238 3-22-71 Cll RPIS Proble 06-15 PlaceTem)oraryJumperon Installed Temporary

[ ,

Full In Wire Jumper -

I. 77-1242 3-23-7/ Dil-J013; Post Treat. Pump inefficient; cause Rc=oved & chect:ed pump j O mple Pump ,

Control Room Alarm reinstalled pump .

77-1243 3-23-71 C71-06-IS Positive Sw. Defective Rod Installed Neu Rod l 77-1257 3-24-7/ .

Eq1-F02S & F029 HPCI Will not pass Leat Rate Lcpped Valve Seat $ &

Steam Drain Valves Te .t replaced Ca:Itets 77-1261 3-24-77 C41-FOOiH SELC Replace Valve after perfor. Replaced Valve & changed Emplosive Valve of Ht'F-1-3703 Accumuistor * (

77-1267 3-25-77 N22-D500 A & B SJAE Plus one tube in each Plugged Tubes -

A&B Condenter (

77-1269 3-25-77 C32-R604 A & B Feed- Indicates Flow when no Calibrated Tecn:mitter m water Flow Ind. A & B flow exists (i ro

• $ 77-1276 3-25-7/

N62-C530 Chemical Sump Pump in WCT Building Sump needs Cleaning Cleaned Sump l Q

'77-1277 3-25-77 E51-FOO3; RCIC Torus Air Line brotte of f Replaced A P Line and Suction Valve Nipple (

77-1281 3-26-77 F15-EOO3 Refueling Bridge saill not drive in Realigned Cece Bos &

Platform Forward or Reverse Motor .:oupling -(

77-1282 3-26-77 D11-M606 RBCCW Problem Repair or replact: high Replaced High Voltage Radiation Monitor voltage power supply Pcuer Supply )

77-1284 3-26-77 P11-V512, NS13 Div. I. Inoperattve Switches Replaced & Cs11brated

& Div. II Service Watee Switches Press. Suttch 77-1287 3-27-7/ 141-R620 'ulti Point Stamps Erraticly Cleaned Suitch Potnts &

Recorder synchrony:ed Recorder 77-1289 3-27 '77' B31-SOOle MG Set Drive Heaters Crounded C1 cared Cround Notor Heater 77-1230 3-27-77 C41-FOOiA SELC Expl.V1v. Valve failed to fire Installed New Valve

~

77-1231 3-28-71 E21-FO31A & F010A Core Will not pass LRT Cleaned Seats Spy. Pm. Man. Flow V!v.

77-1292 3-28-77 Ell-COO 2A RFH Supply Inspection Due Incrected Brestace Breal:ce "A" ,

p 77-1301 3-28-77 P24-SO26 Motor Control Change Time Settings I Times Setting: Changed F

Center 1B OCR 77-30, *

. ....rn .

..L-.?

9 .

CDMPCNENT CAUSE OC MN_FLNCTION EFF. OM 5J.FE ACTION TD PREVEN u DATE REPET!ON CaER. C'- R:!.

INITIATED ,

77-1302 3-28-77 831-COOI Rs. Rectrc. DCR 77-12't ,

Piping P41-E208D Plant Service Faulty Line Replaced 1.ine 77-1305 3-29-77 Man. Flou V1v. Leaps a t Coup l a n2 77-1306 3-23-77 N6b NO10 H2 Analyzer Perform DCR 77-55 C3?-H+.048 Feedwater Instrument indicates a f1cu Calibrated Transmitter .

77-1307 3-29-77 Flow Indicator but no flow cuits 77-1317 3-23-77 831-H616 Rs. Recirc Syc. DCR 76-118 i MilliJmPc DigitJ1 Ind.

Will not pace LRT Replaced Cachets and j 77-1331 3-31-77 E51-FORS Drain Valve Lapped Scate

• T47- DOO18; Prefilter High Delta P Repaired Falters l 77-1337 4-1-77 .

h

- Train l

Tightened Bennet Bolts j l 77-1342 4-1-77 P21-FS72 Valve Valve Leahc Recorder ac up Scale & Repatred Stezed Bearan95 77-1344 4-1-77 C32-PE.09 Reactor Water Level Recorder will not move i

k

'u 831-COO 1 Reactor Recirc DCR 77-127

,O 77-1345 4-1-77 Pump Dicc. Viv. Bypass t q

Line 77-1346 4-1-77 B31-F032 A & H R s. Perform DCR 77-127 Cceplete Recirc Pump Dicch. V1v. {

C11-N059 Waste Sludge Recorder needs calib. Calibrated Recorder 77-1349 4-1-77 i Tana Level Indicator 77-1350 4-1-77 C11-ROO6A Spent Resin Tank overflowe at 90% on Caltt: rated Recorder (A) Tank Level Ind.. Recorder Broken Cable ReplaccJ Calit. and 77-1360 4-1-77 Cll-DOS 7 Remote Cont. Roller (B) Drum Carper Light Inoperative Replaced scappleitsh 77-1360 4-1-77 F15-E003 Refueling plastic Floor Bridge Crapple F13-EOO3 Refueling Crapple Micter Raitch Peplaced Crapple Macter 77-1366 4-3-77 f:'u: tch a rep laced a cc-Ortdge Condle Detective fective wire an the

• centrcl caule C11-RO71 Chemical Waste Stugs Dropping at 4% Caltbrated Recceder 4

77-1373 4-4-77

• 8 Level Recorder Indicator util not give Adjusted Microcwitch

• 77-1386 4-4-77 Cll-Rods Floor Drain Collector Tank Level High Level Alarm Indacator

m DATE COMPONFNT CAUSE INITIATED MALFUrtCITON EFF. ON St.FE AClION TO PREVEN "

C'2LH . u- HX. HEPETILN 77-1399 t,-5-77 F21-F0919 & FOIOR Core Wall not pats LPT Spray Pump Min. Flcw Lapped Valve Seatt .

e Bypass Valves 77-1403 4-5-77 F15-hC03A Refueling Platform Installed ners Contro! Replaced Cables Cables 77-1407 4-6-77 B 31 -F05 7A & F058A Add l' Coe.tp l ing in line Excess Flow Check between Bdl-F057A & Added Coupling

• Valve FOSHA 77-1425 4-7-77 M-F439 2" Torus Ven t ~

Switch out of AdJuct. Replaced and adjusted Relief Valve Limit Sw. -

Stntch 77-1432 4-9-77 T46-COOlA SBCTS 1A Fan r*

Prefilter Differential Replaced Filters Pressure High 77-1436 4-9-77 B21-F022 Filter Filter Dicty 77-1437 Inctalled New Filter 4-9-77 Fll-EOOI Fuel Prep Holst Motor Inop.

Machine Replaced Hoist Motor O

77-1444 4-11-77 Fll-EOO1 Fuel Prep Change the Air Motor on Machine Changed Air Motor the West Fuel Prep Mach. C 77-1445 4-11-77 D11-PCO2 Sample Pump Pump will not start Replaced Carbon Vancs Q 77-1499 4-11-77 Dil-KE.04 Radwatte O

Out of acceptance per HNP-3 Discharge Monitor 1-7404 Cheched Monitor & found te be acceptable 77-1952 4-11-77 O C11-RO35 Demin Tank Recalibrate Recorder Level Recorder Recalibrated Recorder 77-1454 4-11-77 Gil-N061 Calibrate Instrument Instrument out of Calib* Calibrated Instrument 77-1469 4-11-77 T48-NOO3 A & B Torus Out of Calibration Drywell Press. Trans. Recahbrated Tran:mitters 77-1483 4-12-77 T41-ft620 Temp. Recorder Will not operate Replaced Reccccer 77-1486 4-12-77 Tel-EOO4 Ref. Fir. Crane Cont.'oi Cable Mal. Replaced Copntrol Cabic '

77-148B 4-13-77 811-AOO3 RPV Arc :3trike on Cladding RemcVed Arc Strific 77-3499 4-14-77 CS/LPHM Replaced LPRM's - Damaged Replaced LPhM's by CRO Work 77-1505 4-14-77 ESt-ROO2 HCIC

, Suct. Press. Ind. Indicator needs Calib. Calibrated Indicater 77-1527 4-8-77 G31-R601 RWCU Inlet Conductivity Recorder Clutch Burned Out Repaared Clutch 77-1528 4-18-77 C11-R065 Sample Tank Chemical "B"

War.te Tank Overflows at 99% Replaced Red Pen Serve Recd.

( Motor 77-1534 4-18-77 811-AOOI CRO Return Perform Incpection IAW -

B1cnd Radius HNP-1-lO926 M/A

_. .- sm

- .- .- j-. .

o;[ s}O

( i DATE- COMPCNENT s -

P- \ . INITIATED- CAUSE OF MALFtJICT!ON EFF. ON SAFC /

d'. OPER. OF RX.

^'* TI&t TO PREVE. .r' '

HSPETlel 77-Ir.A5 4-20 RP2-SOO6:4IEOV Bus IF c

DCR 7 T-ISO DCR 77-150

• 77-1547 4-20-77 P41-COOL H & D PSW .

Pumps Failed to Auto Start' on Replaced Ewatch Low Pressure 77-1555 4-21-77 eM 4.4 Fire Prot. Hosc- DCR 77-164 reel 77-1557 4-21-77 C71-NOOSAE9 Press. Sw.

Needs Hecalibration 77-1562 4-23-77 Calibrated Switch C71-NOOSCtLD Press. Ew. Needs Recalzbration Calibrated Switch

~

77-1565 4-23 C11-NOO3 Drywe11 F1cor .

DCR 77-155 Drain Stimp Flow XMTR 77-1571 4-23-77 Ell-FOlfA Upper Cont.

Spray Valve Motor does not cperate valve Replaced Motor Shaft 77~1574 4-25-77 .*

P41-RfC2 C/R Serv. Cauge Brohen Water Press. Cauge Calibrated Press. Cauge

• 77-1579 4-25-77

• G31-F0618 Vessel Isol. Knocker Assy. Binds

, Drain Valve Tightened Set Screw

.77-1581 4-25-77  %

C11-RE.05 Semple TankChemical Waste Tank Overflows at 907.

"B" Reed. Calibrated Recorder 77-1585 4-25-77 .E51-NO12 A-D Press. Sw. L Switches need Calib.77-15SS 4-25-77 Calabrated Sustches v E41-FORS HuC1 Supply Relay Sw. has brotten 1.ine Drain Mount Screw Replaced brchen Screws 77-1587 4-25-77 E11-R603A RHR Loop Flow Indicates flow-No flow (

Indicator presant .Calib. Sq. Root Indc.

• 77-1583 4-25-77 F15-FOO3 Ref. Bridge Repair first two sections of Fuel Crapple Repatred Crapple Repatred Crapple 77-1592 4-26-77 E11-FOO78 RHR Pump Min. Will not pass LRT Flow Valve '

Installed New Cate 77-1597 4-27-77 T47-R612 Temp. Recd. Recorder Arm Swings erratically R tk H Switch Heplaced 77-1603 4-27-77 C31-ROO3 Cauge on Pump Suct. Calibrate Cause Calibrated Cause

. 77-1612 4-27-77 Cll-H607 Pressure Cont. Install Pressure Cont.

DCR 77-158 77-1616 4-27-77 C32-COO!

"A" Feedwater Line. Cracks in wcld metal

~

Cr=und & tested wcld

=ctal 77-1617 4-27-77 .C11 CRD Cooling Water . ,

DCR 77-1555

• 77-1618 4-23-77 Ell-F0178 RHR Return Will not p.2cc LRT Valve 'J Cround Valve Scot e .

E .

)_ . .

'\ IQ' DATE COMPGNEMr CAUSE OF MALFUNC110N EFF. CM EAFE ACT!ON iO PRLV D~ - INITIATED OPER. L5 HX. REWl!ON C11-PXM Con trol Hod Valve Stem.Hent Hepicted Valve Stem -

77-1621- 4-28-71

Drive Mater.Prescure Control Valve 4-29-77 FP1-F001 A & B Motorc give ovrrload starr Replaced Motcrc p 77-1629 I

2Dll-FE-NOO! Isokenetic ' Replace Probe eith one cf Replaced Prote 77-1638 4-29-77' -

Probe Higher Volt 5-2-77 Ell-FOO48 RHR Pump Ad fuct Torque Switch Ad;ucted Tcrque Switch

. 77-1643 Suct.. Valve . .

77-1645. 5-2-77' C11-DOO3B "H" CRO High Delta P Installed Clean Filter i

Diccharge Filter Ell-FOO98 RHR Pump Will not pace LRT Lopped Seat Ransc 77-1647 5-2-77 1 .Suct. Valve ,

B11-D141 Control Rod Switches Defecttve R placed Peche 77-1650 5-2-77

,)

10-11 .

I Rebuilt & re-installed l 77-1655 2-77 Pol-COO 1A Plant Sec. Pump Icahs at scal Seal - Accy

) Hater Pump. j l

l 77-1E.60 5-5-77 Cll-NO23 Condensate Out of Calibration Calibrated Indicator i

j) Backwash Press. Ind.

I Freed Meter Movement

!)' W C 77-1(>76 5-8-77 H11-P651 Battery Ground Alarm Present, but Alarm condition does not exist w

P44-COOlA Primary Ou+ Leaks at Packing Added Pachang i 77-1691 5-9-77 i

] Water Recirc Pump C51-JOO4C Ball Valve' Valve Defective Replaced VJ1ve -

77-1702 5-9-77 77-1710 5-9-77 Ell-COOlA RHR Service 77-179 Water Pump 1A 77-1711 5-9-77 821-NOO2 Vessel Head Calibrate Instrument Calibrated Instrumcast "O" ring Leak Detect.

Instrument-77-1715 5-10-77 C11-RO71 Waste / Floor Tank Overflows at 91% Re-calibrated Recorder Drain Level Recorder 77-1716 5-10-77 Ell-COOIC Pump. Seal Water Line Lecits Installed New Hardware on Hater Lane

- '77-1717 5-10-77 Ell-COO 1A Pump- Bearing Running Hot Cleaned Cooler

77-1721 5-10-77 N71-COOlB Circulating Sig'ht Class Leaks Ot1 Repl:Ccd Cachet Hater Pump T47-RE.Il Multipoint' Recorder gives spurious Repaired Binding Arm 77-1726 5-10-77 Temp. Recorder alarm .

77-1729 5-10-77 .H31-F031 A & B Recirc Jos Circuit Inop. Repaired Jeg Timer j "

f Pump Discharge Valves .

}

e' of . - . . ,

(b jO DAIE . Corm rCNi CAtFE LF MALFLNCl ltN EFF. (N &^FE AC f !U"J TO PREVi j *

• h.

INITIATED, OPER. OF RX. HEPEl!OfJ ll 77-1731 5-11-77 .D11-NO N A,H,C,0 Post Crounci Cunduit Condui t Crcunded .

) LOCA Detectort, t 77-1732 5-11-77 E41-FOS 9 & F029 HPCI Limit Swi tches need Adiuct. Adjusted tswitches Valvec 77-1743 5-12-77 E41-FOS 9 Lube Oil Gears brolev in scar be Replaced Cearc Cooling W. iter Viv.

• i

~

77-1747 5-13-77 HW-1-POOIA Diesel Cen. Alarms Inop. Power Supply Heplaced Fuse Annune. ia t or Cabinet- Fute Blows

• l l

77-1748 5-13-77 R43-POOlF1 Diesel Cen. Alarms Inop. Replaced Fuse in Power Annunc:ator Cabinet SuppIy (

! 77-1750 5-13-77 ESI-FIOS Recirc Vacuum Valve will not open with Reutred Drop Out Relay .

7 Breaf er MtN Switch , f l - 77-1752 5-13-77 H31-COO 18 Recirc Pump Seals Leak Replaced Shaft Seals D

Seal (

, 77-1756 5-13-77 G31-R7S2 Flow Recorder Entremoir out of Calib. Calibrated Recorder D. for 2A Rs. Water Cleanup (

77-1758 .5-13-77 Ell-FOBOA Valve Packir.g Lect:5 Water Tightened Poching b . (

77-1559 b-13-77 Bal-FOllA Feedwater Water Leak at Valve Bonnet Tightened Ecnnet jg Isolation Valve Fa* (

7~-1763 5-13-77 R43-POOIA D.G. Annun. Lights were out of Service Replaced Fuses Panel

) . , &

l 77-1764 5-13-77 E11-F126B Crosstic V1v. Defective Stem Replaced Stem and l .

Pcliched Seat 77-1766 5-14-77 ' F4:1-FOO3 HPCI Steam Valve causes ground on IB Heplaced Valve Operatcr Line 1s.olation Valve Station Batterico Mater 77-1767 5-14-77 B21-F022 Filters Filter Diety Installed New Falter i

77-1768 5-14-77 BPI-F022A Main Steam Valve Cloces too fact Ad;ucted Clocang Speed Isolation Valve

(. 77-1769 5-15-77 F11-F017B RHR Return Ad jus t Torque to allow Viv. Increa cd Tcrque Switch Valve to pass LRT. Setting i 77-1716 5-15-77 CSI ,1f00 C & D Tip C & D Tip Machine will not Connec ted lutsted Tubing Machine Drive an Indence 77-1781 5-16-77 Oll-POO1 Vacuum Pump Pump Motor Trips after 10 Ad;usted Overload Min. Operation l

l 77-1782- 5-16-77~ EI1-FOl7H RHR Uuiboard Mator Ovrrheated In: tailed New Rotor and injecitun Valve . Htndang:

77-1784 5-17-77 Ell-COO 1A 1A RHR SW Hner Icatm at flange on . Installed New Casket Pumps Minimum Flou Line /

C ..J iI O- DATE _ . COMPONENT CAUSE OF MALHJNCTirN EFF. (PJ SAHi ACt!t?J TO PREV.;p)- .

- A

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)- INITIATED DPER. OF HX. RFPh1 ION 77-1786 5-17-77 N/1-COOlA Circulating Water Lealts nn Top of Pump Unplugged Scaled Hater hr Water Pump Lance q l.

E 1794 5-18-77 M?l-COO! A Condenter Flow Indtcater doc % not Repaired Meter Pump indicate a Hater Flen 77-1800 5-18-77' Cil-PO71 Chemical Hastr Tants overVlows at Ei% T:shtened and re-Tanit Level Hecorder calibrated Recordce ,

77-1805 5-18-77 HL1-P650 1 *B* RFP Detective Annunctator Card Replaced Card Beartn3 011 Precs. ,

Alarm 77-1816 5-18-77 T48-R776 A & B Sento Meterc show no Responce Replaced ccmbustable sa 02 Monitor detectors reactivated 02 cencor cell & replaced -

b. battery pacts (

77-1920 5-19-77 P33-R706 RHCU Conduct. String (Drive) Bretten Replaced Drive Card i Recorder f 77-1821 5-19-77 E41-N004 HPCI System HPCI Syctem 1solates Repaired Barten Switch

) ( Al- Turbine reache: 1200 RPM $

t i 77-1821 5-19-77 C11-DO538 Centrifuge Belts loose Tishtened Belts b (B) (i

. ,, 77-1826 5-20-77 B31-C0018. Reactor Pump Seals Leat: Replaced Seals p ca Recirculating Pump .y l cn I ' 77-1827 5-20-77 B21-F013C Rx. Relief Pilot Filter Leal:0 Replaced Falter Housing Valve Sec1 Q' l .

l 77-1841 5-20-77 C31-F056B Effluent Handwheel will not turn Installed ucodruff Mcy 3 Valve Manual Isol. Valve, -9 I

l--

77-1847 5-20-77 821-R0048 Reactor Needle Disconnected from Repisced Needic & Calib.

Prcsture Cause Stem Cause i 77-1853 5-23-77 R43-9001 A,8, & C Replace Fuel Cam Roller: Replaced Rc11ers i

Diesel Cencrator l

(

77-1855 5-23-77 H11-P602 Cenerator 'A' Interval Air Temp.

System Alarming but Calibrated Switch M331-condition does not exist PE 71 A l High Alarm 77-1881 5-24-77 N21-D001A, B, & C Cond. Straincrc Clogged Cleaned Stratners Pump Suc tion Strainers i

! 77-1900 5-24-77 Dil-RA06 Standby Cas & Pen Driving Oowntcale Cleaned Drave Mater Drywell Vent Recorder Clutch & Calzb. Recorder

, 77-1913 5-26-77 C11-POS6 Car Conveyor Transverse Retrzevins Changed Actuator Position Inop.

77-1924 5-27 C11-DOS 6 Conveyor Main Wires Overheat Relay s Freed Stiching Relay Control Panel. Sticking j Contacts 77-1930.5-27-77 C11-10-07 Scram' Air Lenk Tishtened Connection

y. -

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DATE . ~COMPONFNT CAUSE OF MN FINC1 ION - EFF. ON SAFE ACTilN TD PMX *

- \

Nj LINITIATED, OPER. OF RX.- RE%I I11CN

• 77-2031 6-8-77 R43-R759C 011 Fil ter High Diff. Precc. Changed Filterc' 77-2032'6-8-77 R'G-POOIR Annunciatorc. Lights will not alluminate Secured two loose circuit when tected cards 77-2047 6-9-77 Z41-rX)O3 Purgo Air Filterc are dirty- Changed Filterc Fa t tors .

77-2048 6-9-77 R43-AOO2A D/C 1A Main Vent was classed with ruct Cleaned Pipe -

Fuel Ot1 Tan!< Vent & ccale .

'77-2060 6-12-77 ES I -8 MO L HRCf lurbine Steam Leais at one inch viv. Ttshtened Psching -

Steam Supply Line.

77-2063 6-13-77 E51-NO?E8 RCIC Diff. Thermocouple Defective Replaced Thermocouple Terne. lhermocouple

• 77-2075 6-14 77 Cll-DOO38 CHD Drive. High Differ. Preccure Removed, Cleaned & Re ,

Water Filter installed Filter 77-2118 6-18-77 821-FOl3 8 & C Rs. Tail Pipe Temp. for these N/A Relief Valvec tuo valvec were high, changed valvec out at a pre-caution

'77-2120 6-18-77 B21-FOl39-L SWS Replaced Switchec 77-2124 6-18-77 Ell-FOSOS RHR Tectabic Bonnet Casket Lect: at Replaced Cactret

.Om Check Valve Flange 77-2125 6-18-77 Ell-F060A Losts at Stem Tightened Pachins 77-2151 6-22-77 831-R614 Recirc Loop Blacf Pen Clutch Elipc Tishtened Pochirjs Flow Hecorder 77-2181 6-24-77 B21-RS15 Rs. Vescel Recorder wall not advance Replaced Drive Cear & Hex

, Level Recorder Properly Ecceu

,g - 77-218S 6-26-77 Cll-D0039 CPD Dicch. Filter Dirty Cleaned and Re-inctalled

., Falter- Filter 77-2209 6-27-77 C11-DOO3A 1A CRD Dicch. High Diff. Preccure Clraned & Replaced Strainer Stratner 77-2220 6-23-77' E41-F029 HPCI Steam Had CJcl:ct ReplOcCd Cac!!Ctc Supply Drain Pot Valve to Main Ccndenter 77-2261 6-30-77 E51-A-M RCIC_ Turbine Relay Ccntacts Dirty Cleaned Centacts Trip Relay 77-2278 7-1-77 Tel-BOOIA CRD Pump Room Peto Tube, not in line Ad;ucted Peto Tube

Cooler correctly caucing Icu flow alarm 77-2291 7-4-77 _E41-F028 HPCI'Stm. Line Cround on Limit Suitchec ,

Rep laced Limi t Switches -

Drain.to Main Condenser .

77-2322 7-5 Cll-06-31,Co.ntro.l Rod Probe Malfunction Replaced Probe

n. . : ,

>- }

. . p- . . .

'l i 0- DATE. C(WIYFHT CAUSE OF MALF-LIClION FFt . t?! EW-E ACT![?! TO Pitt( / - .

)- \_ / INITIATED , OPER. tF RX. RtEPhl !110N 77-2328 7-7-71 B41-F0318 Recirc Pump Hlown Fuse'in Jeg Circuit Removed Wire EP-7 fecm Ort. charge Valve Term:na! A-73 to A-20 77-2333 7-7-77 Eil-NOIH Level Switch Repaired Switch will not gave alarm 77-2349 7-10-77 E51-1 & T RCIC Turbine When the*RCIC Turbine is Cleaned Contacts on Trip Trip & Thenttic Valve tespped, the turbine trip Coil ,

valve will no t close .

77-2356 7-11-77 FIS-E003A refueling DCR 77-21ct ,

Platform

'77-2447 7-20-77 E11-FOl68 Lower Cont. Won't Seal off Set Tcrqac Ewatch Isol. Valve

)' 77-2462 7-21-77 T46-RSOOA SBCT Filter . Bulbs blown in alarm Replaced Bulbs "A" Press. Drop Bulbs Blown in alarm .

) 77-2468 7-21-77 C51-H605-AR42 Rod Block Bad Card in Monitor Replaced Card

. Monitor "A"

)- 77-2487 7-24-77 C51-RE.05A 1A RBM Faulty Second Level Multi- Replaced Component Plener CalibrJted

,) 77-2553 7-27-77 E51-COO 2 RCIC Turbine -Dirty contacts on limit Cleaned Centacts & Tested Trip & Throttling V1v. Switches

)Q 77-2511 7-28-77 CSI-MED5 APRM Channel LPRM Card Bad Replaced LPRM Card Ooun-73 E-LPRM 4C-20-21 scale & upscale trips checited

)

77-2617 8-1-77 N2 Valve 111 on CRD Hardened stem packing Replaced Pactring Accumulator 26-03 causing Icaks

)-

77-2732 8-8-77 R43-SOO18 18 diesel Worn Casket Replaced Casitet Gen. Jacket Coolant Solenoid Valve 77-2740 8-9-77 Ell-F0518 Air Line Copper Tubing Broken Replace lubing for Steam V1v. from Cause Unknown HPCI to RHH 77-2803 8-12-77 R42-SO29 10 Battery Float Voltage too High; Reset Timer Charger for 10 Statiott Timer had to he reset Service Battertes 77-2806 8-12-77 Rel3-SOOIA 1A diesel. Diode's Defective Replace Dacdes in Diesel Gen. Voltage Reg. Cen. V:ltage Regulator 77-2818 8-13-77 E11-R6048 RHR Heat Ell-NOOSB Level Trans. RHR Hz *B" Level Calibrated Ell-NOOSB re-Euch. 8 Level Cont. out of calib. E11-R6018 c en t . w:.;u l d no t paired Ell-R60iB had defective parts cperate 77-2824 8-14-77 E41-F036 HPCI'Isol. Valve Paching Lealt Etcam Leal: ct Viv. l Repact:cd the Val.e

! Viv. for Steam Trap - Ste=

77-2825 8-14-77 E11-NO40 level switch Wold was crocited Hater Lea!! age Retnstalled Line

. isol. viv. weld 4 rem craetre

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.DATE- COM!*GTENT CAtJSE OF M.^LH.?tCl !&t EF F . t?! u ^' * - ar'TITa TO PFbAT.N[/

4 INITIATED. ,

LPEH. 19 HX. . Hi-PP.l ! ! ITJ 77-2828 E-15-77 E41-F011 HPCI Test . Motor was luce.e on /tv. Itshtened Motor Valve to CHT uper. caucing breaf ter to trip 77-2845 8-16-71 C61-H605A Rod Block Signal Condition an need Megatred Stsnal Cond.

Monstur of repate 77-2849 H-17-7/ Hdt-P614 SMety/ Relief 'Sinde Wire Utrty Cicaned Sitde Wire Valve lemp. Recorder EOOV breat:er was closed 77-2E58 8-17-77 P42-8086 1A 125/250 EOOV AC urcaher was cpen volt hattrey charger 77-2870 8-17-77 T4S-HE.8 & HSS Relays Relays Defective Replaced Relays on Drywell and Torus Vent Enh. V1v. T48--

F3348, T48-F3368

. 77-2879 8-18-77 B11-D146 RP1S Control Malfunction in indicator Heplaced Probe

.) Rod Indicator for CR probe 10-31

) 77-2899 8-19-77 R43-SOO18 18 Diccel Inboard Bearing Horn IB Diccel Inop. Replaced Ecaring Generator 3- 77-2900 8-19-77 821-R614 Safety Relief Contacts on Selector Su. Cleaned Cent' acts

_. Valve Temp. Recorder

.W i$ 77-2906 8-19-77 E11-COO 19 RHR Service Mech. Seal Blown Peplaced Seal Water Pump 18 77-2907 8-20-77 U51-NIO18 thru t>61- Several Sw. found out of Calib. all Suitches H1160 Temp. Sw. in tolerance giving spuriuuc Turb. Building traps in the 81 Croup 1 Icolation 77-2908 8-20-77 831-R601 Recirc. Pump Rotor Su. Contacts dirty Cleaned retor switch temp. recorder clide wire defective centacts replaced slide utre contact

. 77-2318 8-21-77' E41-PfCOS RHR Temp. Horn Pctnt Hheel geart &, Replaced Pr:nt Wheel Cear Recorder brushings and *>uchings 77-2962 S-26-71 Cll-ROIS control rod Drzve Card bruhen point Replaced de:ve card - re-drive temp. recorder mechanism hung up pa: red paint mechanism and oil the gears 77-2976 8-29-77 R22-SOO5 AKV Emergency DCR 77-Itd. R1 Bus IE 77-2381 8-23-77 E21-F0698 Jockey Pump Lsmit Sustch Matt. Replaced open limit tw.

99.tton inboard V1v.

Indicating 1.ights A/O

^

77-2988 8-29-77 'P41-COO 10 Plant Service Seal Leahing, Seal Dirty,' Sect was dicas:embled.

- Water Pump D Carbon and Metal Scale uct:c cleaned, repaired carben ,

worn- and metal ceals

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• Lw'l O DATE COMPONENT CAUSE OF MN_FUNC1 ION EFF. O*! SAFE AC11CN TO PREY' M 1 INITIATED OaER. L'- RX. REPhlil(UN 77-3017 8-30-77 N2 Blact: V!v. 111 Accum. Pact:tns ! catting (hardened) Replaced Pacleing & 0-Ring -

14-3S

'77-3060.9-6-71 N2 Hlacle Viv. 111 Accum. 0-Rins brolsen & Pact:ing Replaced pact:ing & 0-Ftins 5' 18-15 har dened caucir"3 leatic around ctem 77-3073 9-7-77 C51-ME.OS ARS1 APRM *E" Aum.' Card & VR3 Zener '

Aua. Card & VR3 Zence Diode Bad Dscde replaced 77-3074 9-7-77 C51-HHM A & U Rod Blocle DCR 77-14, R1 Monitor 77-3075 9-7-77 ~R43-SOO1A-C D/C Fuc1 Dil DCR 77-22d .

Cravaty Drain Tantic -

77-3103 9-12-77 E51-COO 2

• 77-3135 9-15-77 Pol-COO!A; PSW Pump Remove & Repair oc nec. Performed S/R Insp.

77-3177 9-19-77 ESI-F%3 RCIC Test conn.' Leat:c Recurfaced Seat

) 77-3206 9-22-77 CSI-HEOS-AR21 IB Rod Had Trancistor an occil. Replaced tranc. in occil.

Block Monitor circuit circuit 77-3207 9-22-77 E41-COO 2 RCIC turbine Bruch Spring in matcr T ghtened all electrical trip & throttle valve loose connections 77-3254 9-29-77 Ell-NO40 RHR high point DCR 77-24d Icvel switch 77-3262 9-29-77 N2 UlacIt Valve 111 on Pac t:ing Hardened Replaced pact:ing &

, accumulator 10-43 0-Range 77-3289 10-3-77 C11-22-43 Control Rod Probe Malfunction Control Rod Pocit. Replaced Probe Poci. Ind. Switch not indicated 77-3300 10-4-77 C51-H605 AH31 APRM Instrument out of Calib. Calibrated APRM Channel "A" 77-3309 10-4-77 EiPt-F0708 air operated Copper Tubing Fitting Taghtened Fatting viv. on Jocitey Pmp.Suc. loose 77-3320 10-7-77 B21-FOl3A-L Safety Checks for Satpoint R & R Pilots Relief Valvec 77-33bl~ 10-7-77 R2d-H F.N 6, 7 4HV DCR 77-235 Sc.c c IE, IF, IC under-voltage relarc 77-3322 10-7-77 H21-P615 Reactor Veccel- Instrument Draft Recalibrated Level Recorder I' 77-3347 10-7-77 T16-H2A Time Delar Relar Chec!:s fur E-tp t. O !strated Relay Checl<c for cetpoint '

j 77-3351 10-7-77 Toa-!+320 A & 8 Precc. Transmitter Trancmatter do not Recalibrated Tranc.

Pee ,e . Te,nemi++rr- - - - ~ -

7

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I

. T (w/l9 .DATE. COMPDFENT ' 'CAUSE OF MALFIE JCT IOf EFF. Of SAFE ACT!ON TO PRtNg' * .

)- INI T! ATF.O ODER. OF RX. REPhl!ON 77-3352 10-7-77 E11 Relays Time Delay .Checle for cetpotnt drift Adjusted as necessary ,

? Relay 77-3358 10-8-7/ E21-COO 2A A :licy Pump Tripe Replaced defective heartng 77-3361 10-8-77 .C51-k601B IRM "H" Read: High Perf ormed HP.9-1-3052 &

5' found no malfunctton .

77-3387 10-11-77 NP HIacic Valve 111 P.ac !:ing hardened causing Replaced pactring !!: 0-ring '

Accumulator 22-35 Icalic .

77-3398 10-12-77 Safety Relief V1v. Base Rody Coused Instal'ed l New Base

'77-3424 10-15-77 T48-R60S Torus Precs. Recorder needs Calib. . Calib. made en recorder Recorder -

77-3425 10-15-77 Te7-R612 Drywell Temp. Calibrate Recorder Recceder eclibrated -

toruc air & torus water recorder .

77-2436 10-15-77 T48-Rf.07R drywell press. Calibrate Recorder Calibrated Recorder

& water Icvel recorder 77-3427 10-15-77 T48-R631B Drywell Torus Calibrate Recorder Calibrated Recorder Recorder 77-3469 10-19-77 C11-DOO3B CRD "B" Water High Dtff. Precs. Cleaned Falter m Filter A

8 77-3474 10-20-77 C51-H605 APRM Channel A Dut of limite Changed Transistor 77-3491 10-20-77 T47-R611 Primary Cont. Some Points indicate high Synchroni:cd Points Recorder 77-1493 10-20-77 T48-F1128 Control Valve Erroneous Posit. Ind. Erron. Post. In. Adjusted Ltmit Switch Lights Stay On 77-3494 10-20-77 T48-F334A Isola, tion V1v. Lisht: Stay On AdJutted Limit Switch

. 77-34 % 10-20-77 T48-RE.02 Drywell N2 Chart W/N Advance Replaced Drive Motor Mal <eup Flow Recorder 77-h518 10-20-77 C11-HCU-14-43 Hyd. Cont. Solenoid Leal:s Air Tightened Scienoid Rod Drive Unit 77-3523 10-20-77 C31-FOO1 RWCU Icol. V1v. Spurious Indication Replaced Switch 77-3542 10-24-77 T46-R60aB Diff. Press. Penc read High Ma repair ccquired Recorder 77-3S^.5 10-E5-77 Bc>1-ROO4 A & B R x . Replace Gauses Replaced Causec

} Press. Cause 77-3547 10-25-77 T48-COO 1 T48' Piping Ledles at Joint Helded up Leal 77-3605 10-31-77. P41-COOIC PSW Pump Seals Leak Replaced Seal r

77-3694 11-1-77 . install Vibration Rio  ?, +,i t re p.1 +

t , n . . n . .

/ 1 0 DATE COFPOFEN T CAUSE OF MALFUNCTION EFF. ON SN-l. ACTION TO PREY j k-( ,r! INITIATED OPER. OF RX. REPETITION (_/

77-3707 11-7-77 R43-N516 D/C IB Day Tant DCR 77-260 -

4 Moisture Detector ,

77-3716 11-8-77 ESI-FOS 2 RCIC Test Valve Leak ,

Recurfaced Valve Seat Connection E51-FOS 4 Recirc A/D Viv. Leaft at Stem Adjusted Pacleing 77-3718 11-8-77 77-3725 11-9-77 B21-NO26A Yarway Ind. Water Leatsing from Case Tishtened Scaling Plus .

F15-EOO3A Refueling Repair Urnhen tag on Repaired the Bracl<ct 77-3756 11-16-77 .

Platform line brattet on troller .

cabic rail C51-K605 APRM "A" Upscale alarm comes on at Replaced DAI on "A*

77-3822 11-23-77 trip I 107.5 quadrant of quad card & recct setpoint.

P70-COO 1A Orywell Pne- Compressor not-pumping Replaced diaphram & 0- -

77-3828 11-23-77 Ring matic Compre:cor ,

T47-R611 & R612 Mul ti- Alarm Point have drifted Calibrated & cet the

^

77-3859 11-28-77 Octpoint 1AH HNP-i.5314 point temp. recorder ,

E41-FOO2 HPCI Steam Line Pressure Seal Leales Replaced Prc cure Seals 77-3911 12-2-77

'- Isol. Valve .

B31-F051H Recirc pump Packing Lealc Repacited Valve 77-3912 12-2-77

( b "B" Suction Line Drain Performed HNP-1-5111 to d

77-3916 12-2-77 Z41-R613A Control Room Alarms at .5 MR bring upscale

" OctPt., to 7 HVAC Disc. Rad. Monitor tolerance 77-3924 12-2-77 E41-F029 HPCI Steam Donnet Ca:Icet Lealcing Replaced Ca let D -

Line Drain .

77-3929 12-3-77 T48-R607A Drywell Prest. Recorder gives high press. Checlied setpoints found Recorder alarm to be OK 77-3933 12-4-77 821-F013A-C-K-C Safety Bonnet & 1-ilter Cachet Replaced Cacicct:

Relief Valve Leal 77-3934 12-4-77 E41-FOO2 Add Paching to Stem Added Pactring 77-3338 12-5-77 T47-R611-Multipoint Some Point read upscate tightened Loose Wire Temp. Recorder Connectten 77-3964 12-6-77 Cll-DOO3A CRD Disch. Falter has high Diff. Pec5. . Cleaned Filter:

- Falter 'A' 77-3986 12-9-77 T48;F3348 Drywell Vent Doubic ligh indication Adjus ted Limit Switche Enhaust 2* 100. V1v. When Open

~

77-3562 12-9-77 E41-F029 HPCI Steam Line Valve has double ind. lightd Replaced limit twitche:

Drain Valve 1 adjusted them

.e P70-COOL A Drywell Penu. ' Dil Lealc 'at Oil Line Replaced Copper lubing 7.7-4005 12-10-77 Comp.

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DATA TABULATIONS 6 UNIQUE REPORTING REQUIREMENTS O

s 4

6 4

9

^ ~ - - ' ' " - ---- . . _ _ _ _ , ,, _ ._

OCCUPATIONAL PERSONNEL RADIATION EXPOSIIRE O

l l

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, _ . . _ , _ _ ,. _ _ _ _ - - - - - - - - - - - - - - ~ - - - ~ ~ ~ - ' - ~ ' ' ~ " ' ~ ~ ' ' ' ' ' ~ ' " ' ..E

O OCCUPATIONAL PERSONNET, RADIATION EXPOSIIRE This section has been compiled to satisfy the requirements of E.

I. Hatch Unit 1 Technical specifications section 6.0.H.1.b(3) and to assure compliance with the Code of Federal Regul a t i ons as set forth in the pertinent sections of Title 10. Special attention was afforded to the methods prescribed by the Commission in Regulatory Guide 1.16 in order that the intent as well as the letter of these laws might be ful fill ed while i 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, 1977 through 31 December 1977. All monitored personnel were-included in survey as provided under 10 CFR 20'.407 (b) (1)

(1). 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 when required, along with the difference- between

, these readings and the most restrictive exposure limit. The corresponding ion chamber results as recorded 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 file- was assigned a usual job category based on his expected daily activities. There are six job categories of this nature and are ident i fied . in the following table. Running totals of dose acquired in- each of i

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 3- retained for. individual exposure- record, is- ad<'3d- to the total representing -the cumulative dose in- his usualy job category.

j. (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 radiatin work permit. This data is input via mark-sense cards to'the calculator, which

. subtracts 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 g -indicated by the radiation work permit.

J* (42) ,

/s,)

'y _

The implicit assumption' involved in this method of accounting for exposure in different tasks is that all exposure acquired in iob

categories other than the usual will be documented by a radiation i work permit. This circumstance should prevail in all significant Cases.

, Futher delineation as to the number of persons and amount of 4

exposure of people in different job categories by various personnel categories is indicated by the standard reporting

. format of Regulatory Guide 1.16. Each personnel dosimetry disc file contains the personnel category information required to accomplish this compliation. The individual running dose totals for each job were used by the calculator to compute the number of man-rem indicated in each group. Backup disc files were '

I maintained for redunancy in the case of destruction or temporary

inaccessability suffered by the main files. Hard copy records as i.

printed by the calculator were also maintained.

By the use of a programmable calculator with disc mass storage, personnel dosimetry information has been complied, retained and i tabulated in such a manner as to satisfy the pertinent Federal' Regulations and Plant Technical Specifications. The system has ,

been organized to provide this information in the format specified by these requirements and the suggestions of the Regulatory Guides.-

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. -(43) ,

REGULATORY GUIDE 1.16 INFORMATION

, r id NUMBER OF PERSONNEL

(> 100 MREM) NUMBER OF MAN-REM STATION UTILITY CONTRACT STATION UTILITY C0: TRACT ROUTINE SURVEILLANCE & INSPECTION MAINTENANCE & CONSTRUCTION 3 9 0 0 3 0 OPERATIONS 102 0 0 53 0 0 HEALTH PHYSICS & LAB 28 0 0 15 0 0 SUPERVISORY & OFFICE STAFF 0 0 0 0 0 0 ENGINEERING STAFF 12 0 35 5 0 13 ROUTINE PLANT MAINTENANCE MAINTENANCE & CONSTRUCTION 92 0 0 70 0 0 OPERATIONS 17 0 0 18 0 0 HEALTH PHYSICS & LAB 0 0 0 0 0 0 SUPERVISORY & OFFICE STAFF 0 0 0 0 0 0 ENGINEERING STAFF 4 0 0 0 0 0 SPECIAL. PLANT MAINTENANCE & TESTS McINTENANCE & CONSTRUCTION 62 21 0 28 14 0 0FERATIONS 21 0 0 14 0 0

' HEALTH PHYSICS & LAB 0 0 0 0 0 0 SU'ERVISORY & 0FFICE STAFF 0 0 0 0 0 0 o ENlINEERING STAFF 0 0 221 0 0 97 FUELING OPERATIONS MAINTENANCE & CONSTRUCTION 11 0 0 7 0 0 OPERATIONS 3 0 0 0 0 0 HEALTH PHYSICS & LAB 0 0 0 0 0 0 SUPERVISORY & OFFICE STAFF 0 0 0 0 0 0 ENGINEERING STAFF 0 0 48 0 0 27 RADWASTE OPERATIONS MAINTENANCE & CONSTRUCTION 0 0 0 0 0 0 OPERATIONS 0 0 0 0 0 0 HEALTH PHYSICS & LAB 0 0 0 0 0 0 SUPERVISORY & OFFICE STAFF 0 0 0 0 0 0 ENGINEERING STAFF 0 0 0 0 0 0 IN-SERVICE INSPECTION MAINTENANCE & CONSTRUCTION 0 0 0 0 0 0 OPERATIONS 0 0 0 0 0 0 HEALTH PHYSICS & LAB 0 0 0 0 0 0 SUPERVISORY & 0FFICE STAFF 0 0 0 0 0 0 ENGINEERING STAFF 0 0 94 0 0 67 INTENANCE & CONSTRUCTION 156 25 0 105 17 0 PERATIONS 334 0 0 86 0 0 o H ALTH PHYSICS & LAB 78 0 0 26 0 0 SUPERVISORY & OFFICE STAFF 0 0 0 0 0 0 ENGINEERING STAFF 45 0 310 6 0 204 g

(44)

-- . - . . - _ ~ . - . . . .

. . . . . .. ,,s

• STATISTICAL SLPHARY RADIATION EXPOSURE REPORT

4. (

( 10 CFR 20.407 )

i Exposure Range (RD4) No. Of Individuals N.M.E 320 4

<.1 515 0.1-0.25 327

^

. 0.25-0.5 180 0.5 - 0.75 100 3~

0.75 - 1.00 61 1-2 103 2-3 15 3-4 2 4-5 0

.I i No exposures greater than 5 RDi 4

'Ihis report is submitted in accordance with paragraph (b) (1) (i) of i 10 CFR 20.407.

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, REACTOR COOLANT CIIBfISTRY silhMARY f

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,,_ .,_..__.~ __....,, _ .,= ...-.... .__ ._...,,_ __ ,_,_ _ _ _,.___ _. __ _ _ _ __.__,_.. ____-- 1_. 1 M __

~ ~ '

• REACTOR COOLANT CHEMISTRY c -

, ~x .taA at oni on a monthly basis of values of SJAE Isotopics and Reactor Coolant ubl

/ System parameters as required by Section 4.6.F.1 of the Technical Specifications L ,j;re found in the following tables.

SJAE IS0 TOPICS uCi/sec DATE MWT Xe-13R Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Ar-41 N-13 E (six) 1-7-77 1455 431 50.7 40.2 24.4 93.2 48.6 9.0 815 688.1 2-22-77 2127 658 128 112 76.3 157 52.2 8.7 1670 1183.6 3-8-77 2111 501.2 88.7 72.6 43 144 128 5.8 1840 977.3 4-12-77 0 0 0 0 0 0 0 0 0 __0 5-12-77 0 0 0 0 0 0 0 0 0 0 6-7-77 1765 48.1 4.2 .8 3.7 1.2 .2 1.1 2150 58.3 7-19-77 2353 37 3 .6 7.2 2.2 .7 .5 1590 51.0 8-25-77 2372 99 6.8 2.1 1.8 2.7 28 .5 3770_ 139.4 9-14-77 2023 1300 484 381 234 896 266 2.0 3390 3561 10-27-77 1834 411 155 185 119 373 140 .8 2300 1383 11-22-77 2335 246 144 153 95.8 469 256 .5 2380 1364 12-20-77 1698 7-8 34.2 60.2 29.7 49.2 1530 1.4 2650 1801 REACTOR COOLANT CHEMISTRY POWER 10 DINES (pCi/ml)

DATE I-135 D.E.I-131 o MWT __ I-131 1-132 I-133 I-134 1/11 3.32 8.00 1.01 4.10 1.70 3.64

, 1977 1444 E-3 E-4 E-3 E-4 E-4 E-3 2/8 9.94 8.47 1.86 5.87 4.15 1.04 1977 0 E-4 E-6 E-4 E-8 E-7 E-3 3/8 4.55 3.87 1.07 5.65 5.19 8.11 1977 2111 E-4 E-4 E-3 E-4 E-4 E-4 4/8 8.65 <2.26 4.16 <l.35 <6.99 8.65 1977 0 E-5 E-7 E-12 E-6 E-7 E-5 5/18 1.05 3.22 2.35 4.74 2.19 1.96 1977 0 E-6 E-7 E-6 E-6 E-6 E-5 6/14 1.01 4.35 1.39 3.73 1.81 8.48 1577 2362 E-5 E-4 E-4 E-4 E-4 E-5 7/12 1.14 2.53 1.68 5.84 2.50 9.68 1977 2111 E-5 E-4 E-4 E-4 E-4 E-5 8/16 7.82 1.41 8.20 3.58 1.99 2.57 1977 1740 E-6 E-4 E-4 E-4 E-4 E-4 9/13 1.57 3.76 2.43 <9.19 3.40 1.38 1977 1316 E-5 E-4 E-4 E-4 E-4 E-4 1 10/11 1.86 7.57 2.84 1.19 1.21 1.87 1977 0 E-2 E-5 E-4 E-4 E-7 E-2 11/15 1.83 4.35 2.23 8.06 3.40 1.56 1977 2355 E-5 E-4 E-4 E-4 E-4 E-4 12/14 5.27 2.78 1.65 4.92 2.15 1.37 1977 1775 E-5 E-4 E-4 E-4 E-4 E-4

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February 13, 1978 pll( i. h)r.;JK

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Mr. James P. O'Reilly dYA "d '@SM"*"

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Q U.S. NRC  !

Office of Inspection 6 Enforcement -

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y Region II, Suite 1217 /

230 Peachtree Street, N.W.

! Atlanta, Ga. 30303

Dear Mr. O'Reilly,

Pursuant to Sections 6.9.1.b. and 4.6.F.1 of the Plant Edwin T. Hatch Operating License, please find attached the interim Annual Operating Report for 1977 as requested in the NRC letter of September 22, 1977.

- Sincerely yours,

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